ML20149G316
| ML20149G316 | |
| Person / Time | |
|---|---|
| Issue date: | 06/30/1997 |
| From: | NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | |
| Shared Package | |
| ML20149G302 | List: |
| References | |
| REF-GTECI-MI, REF-GTECI-SC NUDOCS 9707230139 | |
| Download: ML20149G316 (89) | |
Text
,. _.... _ _ _ _...... _. _. _. _.. _ _ _
s.
4 4
i-1 4.
i.
i
'1 1-l f
1 i.
1-ATTACHMENI j
l e-4 l:
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM j
SECOND QUARTER FY-97 UPDATE j
g.
I L
g u
(j.
OFFICE OF NUCLEAR REGULATORY RESEARCH JUNE 1997.
l l
1 1
i
.i 8
9707230139 970714 PDR GTECI GMISC PDR
f V
33 4
' TABLE OF CONTENTS (a)
Generic Issue Management Control System (1)
Description (2)
Legend (3)
Data Elements (b) ' Table 1 -
Generic Safety Issues Scheduled for Resolution, Issues Resolved, and Issues Integrated (FY-83 Through 2nd Quarter FY-97)
(c)
Table 1 A - Summary of Generic Safety Issues Scheduled for Resolution, Issues Resolved, and Issues Integrated (FY-83 Through 2nd Quarter FY-97)
(d)
Table 2 -
Number of Generic Safety Issues Resolved by Fiscal Year (FY-83 Through 2nd Quarter FY-97)
(e)
. Table 3 -
Generic Safety Issues Resolved (by Fiscal Year)-
I 4
f]
(f)
Table 4 -
15-Generic Safety Issues Scheduled for Resolution (by Fiscal Year) 1 (g)
Table 4A - Generic Safety Issues Scheduled for Resolution (by Priority)
(h)
Table 5 -
Number of Generic Issues Prioritized from FY-83 Through the 2nd Quarter of FY-97 (i)
Table 6 -
Generic Issues Prioritized (as of 2nd 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 Gereric Activities (q)
Index of Issues - (With Work Scope & Schedules for Generic Issues and Related Generic Activities)
O
7 IV) iii 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 through the stages of prioritization and resolution (development of new criteria, management review and approval, public comments, and incorporation into the regulations, as appropriate). The A
priority evaluation for each issue listed in this report is contained in
?V)
NUREG-0933, "A Prioritization of Generic Safety Issues." The Procedures for Identification, Prioritization, Resolution, and Tracking of Generic Issues is outlined in RES Office Letter No. 7, dated February 16 1996, which superseded 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 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.
i i
Some prioritized generic issues may not have resources allocated for resolution; these issues are listed in GIMCS as inactive issues. Generally, 1
these will be MEDIUll-priority issues that have no safety deficiency demanding High-priority attention, but have the potential for safety improvements or i
reduction in uncertainty of analysis that may be substantial and worthwhile.
I Efforts for the resolution of these issues will be planned over the next several years, but on a basis that will not interfere with work on the resolution of HIGH-priority generic issues or other High-priority work. Thus, some (MEDIUM-priority) generic issues may be inactive until such time as resources become available to resolve them. The detailed schedule for resolving generic issues is monitored by GIMCS.
p]
\\v
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 1/II DRPM -
Division of Reactor Program Managerr. ant 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 GL Generic letter GSI Generic Safety Is' sue 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 11-3 PD31 -
Project Directorate 111-1 PDND -
Non-Power Reactor and Decommissioning Project Directorate Emergency Preparedness and Radiation Protection Branch PERB 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
v
)
LEGEND (Cont.)
l 50W Statement of Work SPLB -
Plant Systems Branch SRP Standard Review Plan SRXB -
Reactor Systems Branch STS Standard Technical Specification T/A Technical Assistance TAP Task Action Plan TBD To be Determined TI Temporary Instruction TS Technical Specification USI Unresolved Safety issue i
l J
l 1
s I
i k
vi DATA ELEMENTS Management and control indicators used in GIMCS are defined as follows:
1, Issue No.
- Generic Issue Number 2.
Iith
- 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.
Tvoe
- Generic Safety (GSI), Licensing (LI), or Regulatory Imp'act (RI) 6.
Priority
- High (H) or Medium (M) 7.
lask 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 !Lq requirements);
5 - (Licensing or Regulatory impact issue that has been assigned resources for completion) 11.
TAC Number
- Task Action Control (TAC) number assigned to the issue l
l l
A. O (N
vii 12.
Resolut' ion Date
- Scheduled resolution date for the issue 13.
Work Authorization
- Who or what authorized work to be done on the issue 14.
EJB Financial identification number assigned to contract (if any) for technical assistan :
15.
Contractor
- Contractor name 16.
Contract Title
- Contract Title (if contract issue) 17.
Work Scoce
- describes briefly the work ne essary 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 40.
Problem / Resolution
- Identifies problem areas and describes what actions are necessary to resolve them
(
21.
Milestones
- Selected significant milestones:
A (a) the " original" scheduled dates reflect the original Task Action Plan plus additional milestone dates added during task resolution; (b) changes in the original scheduled dates are listed under " Current";
(c). actual completion dates are listed under " Actual" MU i
,/--~
.,]
Y Y
TABLE 1 GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION.
ISSUES RESOLVED AND ISSUES INTEGRATED FY-83 THROUGH FY-97(2ND OUARTER)
FY-83 FY-84 FY-85 ISSUE GSIs New GSIs GSIs New GSIs GSIs New GSIs TYPE Start +
Issues - Resalved - End Start +
Issues - Resolved = End Start +
Issues - Resolved - End USI 16 0
2 14 14 0
2 12 12 0
0 12 HIGH 24 2
0 26 26 1
1 26 22*
41 6
57 MEGIUM 31 2
0 33 33 4
3 34 28*
1 10 19 NR 20 3
4 19 19 5
9 15 15 11 7
19 TOTAL:
91 7
6 92~~
92 10 15 87 77 53 23 107 FY-86 FY-87 ISSUE GSIs New GSIs ISSUE GSIs New GIs GSIs TYPE Start +
Issues - Resolved - End TYPE Start F 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 1
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
- Extensive revisions to Human Factors issues resulted in priority changes.
T1-1 As of 2nd Quarter FY-97
TABLE I (Continued)
GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION.
ISSUES RESOLVED AND ISSUES INTEGRATED FY-83 THROUGH FY-97(2ND OUARTER)
FY-88 FY-89 ISSUE GSIs New GSIs GSIs ISSUE GSIs New GSIs GSIs TYPE Start + Issues
~ Resolved - Integrated - End TYPE Start + Issues - Resolved - Integrated - End USI 9
0 5
0 4
USI 4
0 4
0 0
HIGH 32 1
6 3
24 HIGH 24 1
9 0
16 MEDIUM 16 2
2 3
13 MEDIUM 13 1
3 1
10 NR 11 1
3 0
9 NR 9
0 2
0 7
TOTAL:
68 4
16 6
50 TOTAL:
50 2
18 1
33 FY-90 FY-91 ISSUE GSIs New GS!s GSIs ISSUE GSIs New GSIs GSIs TYPE Start + Issues - Resolved - Integrated = End TYPE Start + Issues - Resolved - Integrated - End HIGH 16 0
2 0
14 HIGH 14 2
2 0
14 MEDIUM 10 1
2 0
9 MEDIUM 9
3 1
0 11 NR 7
0 3
0 4
NR 4
1 1
0 4
TOTAL:
33 1
7 0
27 TOTAL:
27 6
4 0
29 FY-92 FY-93 ISSUE GSIs New GSIs GSIs ISSUE GSIs New GSIs GSIs TYPE Start + Issues - Resolved - Integrated - End TYPE Start + Issues - Resolved - Integrated = End HIGH 14 0
4 0
10 HIGH 10 0
7 0
3 MEDIUM 11 1
2 0
10 MEDIUM 10 0
3 0
7 NR 4
2 1
0 5
NR 5
2 0
0 7
TOTAL:
29 3
7 0
25 TOTAL:
25 2
10 0
17 TI-2 As of 2nd Quarter FY-97 O
O O
O O
O TABLE I (Continued)
GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION.
ISSUES RESOLVED AND ISSUES INTEGRATED FY-83 THROUGH FY-97(2ND OUARTER)
FY-94 FY-95 ISSUE GSIs New GSIs GSIs
_ _ _ ISSUE GSIs New GSIs GSIs 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 FY-96 FY-97 ISSUE GSIs New GSIs GSIs ISSUE GSIs New GSIs-GSIs TYPE Start + Issues - Resolved - Integrated = End TYPE Start + Issues - Resolved - Integrated = End HIGH 4
~0 1
0 3
HIG!!
3 1
0 0
.4-MEDIUM 6
0 1
0 5
MEDIUM 5
0 1
0 4
NR 5
5 1
0 9
NR 9
0 2
0 7
TOTAL:
15 5
3 0
17 TOTAL:
17 1
3 0
15 I
T1-3 As-of 2nd Quarter FY-97
.. =
Table IA
SUMMARY
OF GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION.
ISSUES RESOLVED. AND ISSUES INTEGRATED CUMULATIVE TOTALS FY-83 THROUGH FY-97(2ND OUARTER)
~
TYPE Start + Issues - Sub-lotal - Resolved -
Integrated" - Remainder USI 16 0
16 16 0
0 HIGH 24 35*
59 45 10 4
MEDIUM 31 18 49 36 9
4 NR 20 28*
48 40 1
7 TOTAL:
91 81 172 137 20 15
- Extensive revisions to Human Factors issues resulted in priority changes in FY-85 and FY-86.
" GSIs Intearated FY-87:
Issues 48, 49, and A-30 into Issue 128 Total (13)
Issue 65 into Issue 23 Issues 68; 122.1.a; 122.1.b; 122.1.c; and 125.II.1.b into Issue 124 Issues I.B.I.l(6) and I.B.I.l(7) into Issue 75 Issue B-6 into Issue 119.1 Issue 67.7 into 135 FY-88:
Issue 77 into A-17 Total (6)
Issues I.D.5(5), II.B.5(1), II.B.5(2), II.B.5(3), and II.F.5 were integrated into the Research Activities Program and were reclassified as Licensing Issues.
FY-89:
Total (1)
Issue 131 was integrated into the External Events IPE Program.
T1-4 As of 2nd Quarter FY-97 O
O O
O O
O TABLE 2-NUMBER OF GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR FY-83 THROUGH FY-97 (2ND OVARTER)
PRIORITY FY-83 -FY FY-85 FY-86. FY-87 FY-88' FY-89 FY-90 FY-91 FY-92 FY-93 FY-94 TOTAL.
USI 2
2 0-1 2
5 4
0 0
0 0
0 16
.HIGH 0
1 6
3 3
6-9 2
2-4 7'
1 44 MEDIUM 0
3 10 2
4 2
3 2
1 2
3
'2 34
.NR 4
9 7
3 1
3 2
3 1-
'l 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-97l TOTAL USI 16 0
0 0
16 HIGH 44 0
1 0
45 MEDIUM 34 0
1 1
-36 NR 36 1
1 2
40 Total:
130 1
3 3
137 T2-1 As of 2nd Quarter FY-97
~..
~. ~..
-~
TABLE 3 GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR lssue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved LYS A-11 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-OP 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 II.E.5.1 (B&W) Design Evaluation NR No. Req.
NRR-OP FY83 0?/21/83 IV.C.1 Extend Lessons Learned From NR No. Req.
NRR-0P FY83 04/15/83 TMI to Other NRC Programs FY-84 12 BWR Jet Pump Integrity Medium No. Req.
NRR-0P FY83 09/25/84 20 Effects of Electromagnetic NR NUREG/
NRR-0P 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 T3-1 t
FY-97 e
e Asof2ndQuar6
CJ j\\
~
s G
n 1
TABLE 3 (Continued) l GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue' Resolution Date Approved Date Number Title Priority Product..
for Resolution Resolved
~FY-84 (Cont.)
t 50 Reactor Vessel Level NR
.MPA F-26 07/28/83 09/06/84-
. Instrumentation in BWRs 69 Make-Up Nozzle Cracking in NR MPA B-43 12/06/83 09/27/84 B&W Plants 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.1.4 Long-Term Upgrading of-NR New Rule NRR-OP FY83 01/01/84 f
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 NURPi-0667 NRR-0P FY83 09/28/84 Response Task Force III.D.2.5 Offsite Dose Calculation Manual NR
.NUREG/
NRR-0P FY83 01/17/84 CR-3332 j
i T3-2 As of 2nd Quarter' FY-97 i
TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-85 22 Inadvertent Boron Dilution NR GL 85-05 11/05/82 10/15/84 Events A-41 Long Term Seismic Program Medium ~
No Req.
NRR-OP FY83 10/10/84 B-19 Thermal-Hydraulic Stability NR GL 01/03/85 05/21/85 B-54 Ice Condenser Containments Medium NUREG/
NRR-0P FY83 10/22/84 CR-4001 B-58 Passive Mechanical Failures Medium No Req.
NRR-OP FY83 07/09/85 C-11 Assessment of Failure and Medium No Req.
NRR-0P FY83 07/09/85 Reliability of Pumps and Valves 1.A.2.2 Training and Qualifications High Policy NRR-0P FY83 06/24/80 of Operating Personnel Statement (No Req.)
I.A.2.6(4)
Operator Workshops Medium No Req.
NRR-OP FY83 09/25/85 I.A.2.7 Accreditation of Training Medium Policy NRR-0P FY83 06/24/85 Institutions Statement (No Req.)
I.A.3.4 Licensing of Additional Medium Policy NRR-0P FY83 02/12/85 Operations Personnel Statement (No Req.)
I.G.2 Scope of Test Program Medium No Req.
NRR-0P FY83 10/05/84 T3-3 As of 2nd Quarter FY-97 G
O O
~ _ - _ -.
O O
C TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date.
Number Title Priority Product for Resolution Resolved FY-85 (Cont.)
1 II.B.6 Risk Reduction For Operating High.
No Req.
NRR-0P FY83 09/25/85 Reactors at Sites With High Population Densities II.B.8 Rulemaking Proceedings on High Degraded Core Accidents (a) Hydrogen Rule Rule /.
NRR-0P FY83 07/19/85 (b) Severe Accidents Policy-NRR-0P FY83 08/12/85 Statement l
II.C.1 Interim Reliability Evaluation High No Req.
NRR-0P FY83 07/09/85 Program e
II.C.2 Continuation of Interim High No Req.
NRR-0P FY83 09/25/85 Reliability Evaluation Program j
II.E.2.2 Research on Small-Break LOCAs Medium No Req.
NRR-OP FY83 07/25/85 and Anomalous Transients
)
III.A.I.3(2)
Maintain Supplies of Thyroid-NR Policy NRR-0P FY83 08/15/85 Blocking Agent for Public Statement l
III.A.3.4 Nuclear Data Link Medium No Req.
NRR-0P FY83 06/26/85 t
III.D.2.3(I)
Develop Procedures to Dis-NR-ESRP NRR-0P FY83-08/28/85 criminate Between Sites / Plants Revision III.D.2.3(2)
Discriminate Between Sites NR ESRP NRR-0P FY83 08/28/85 f
and Plants that Require Revision Consideration of Liquid
)
Pathway Interdiction Techniques i
III.D.2.3(3)
Establish Feasible Method of NR ESRP NRR-0P FY83 08/28/85 Pathway Interdiction Revision.
T3-4 As of 2nd 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-85 (Cont.)
III.D.2.3(4)
Prepare a Summary Assessment NR ESRP NRR-0P FY83 08/28/85 Revision IV.E.5 Assess Currently operating High No Req.
NRR-0P FY83 09/25/85 Plants f.h8,1 3
Setpoint Drift in NR Reg Guide NRR-0P 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 (No Req.)
61 SRV Discharge Line Break Medium No Req.
11/30/83 08/08/86 Inside the Wetwell Airspace of BWR Mark I and Mark II Containments A-43 Containment Emergency USI SRP Revision 01/79 10/85 Sump Performance (Req.)
I.C.9 Long-Term Plan for Upgrading Medium No Req.
NRR-0P FY83 06/07/85 of Procedures III.D.3.1 Radiation Protection Plans High No Req.
NRR-0P FY83 05/19/86 HF1.2 Engineering Expertise on High No Req.
10/01/84 10/28/85 Shift HFl.3 Guidance on Limits and High No Req.
10/01/84 06/26/86 Conditions of Shift Work T3-5 As of 2nd Quarter FY-97 O
O O
s v
V
[V L
TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date. Approved Dat~.
Number Title Priority Product for Resolution Resolved FY-87 91 Main Crankshaft Failures in NR NUREG-1216 07/85 09/87 Transamerica Delaval Diesel (No Req.)
Generators A-46 Seismic' Qualification of.
Equipment in Operating Plants (Req.)
A-49 Pressurized Thermal Shock USI Rule / Reg.
12/81 02/87 Guide'l.154 (Req.)
I.A.2.6(1)
Long-Term Upgrading of High Reg.' Guide 10/82 05/87 Training and Qualifications -
-1.8 (Req.)
Revise Reg. Guide 1.8 I.A.3.3-Requirement for Operator High No Req.
12/82 01/87 Fitness I.A.4.2(1)
Research on Training High Reg. Guide 10/84 05/87 Simulators 1.149, Rev. 1 (Req.)
I.B.l.1 Oraanization and Manaaement Lona-Term Imorovements I.B.I.l(l)
Prepare Draft Criteria Medium No Req.
12/82 01/87 I.B.l.l(2)
Prepare Commission Paper Medium No Req.
12/82 01/87 1.B.1.1(3)
Issue Requirements for the Medium No Req.
12/82 01/87 Upgrading of Management and Technical-Resources I.B.I.l(4)
Review Responses to Determine Medium No Req.
12/82 01/87 Acceptability T3-6 As of 2nd Quarter FY-97
TABLE 3 (ContinuTd)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR issue Resolution Date Approved Date Number Title Priority Product for Resoliition Resolved FY-88 86 Long Range Plan for Dealing NR NUREG-0313, 10/84 01/88 with Stress Corrosion Cracking Rev. 2, in BWR Piping GL 88-01 (Req.)
93 Steam Binding of Auxiliary High GL 88-03 10/84 02/88 Feedwater Pumps (No Req.)
1.D.4 Control Room Design Standard Medium No Req.
NRR-0P FY83 03/88 II.E.4.3 (Containment) Integrity Check High NOREG-1273 NRR-OP FY83 03/88 (No. Req.)
B-5 Ductility of Two-Way Medium No Req.
NRR-0P FY83 04/88 Slabs and Shells and Buckling Behavior of Steel Containments HF8 Maintenance and Surveillance High Policy 03/85 05/88 Program Statement (No Req.)
1.A.4.2(4)
Review Simulators for High Rule NRR-0P FY83 05/88 Con formance (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.)
T3-7 As of 2nd Quarter FY-97 O
O O
O O
O 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.II.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 Integrity USI NUREG-0844 01/79 09/88 (No Req.)-
A-45 Shutdown Decay Heat Removal USI NUREG-1289 02/81 09/88 Requirements (No Req.)
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 -05/06/85 06/89 (Req.)'
T3-8 As of. 2nd 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-89 (Cont.)
115 Enhancement of the Reliability High NUREG-1341 07/07/86 04/89 of Westinghouse Solid State (No Req.)
Protection System 122.2 Initiating Feed-and-Bleed High No Req.
01/86 04/89 124 Auxiliary Feedwater System NR 2 Plant-02/86 01/89 Reliability Specific Backfits (Req.)
125.I.3 SPDS Availability NR GL 89-06 05/06/88 04/89 (No. Req.)
134 Rule on Degree and Experience High Policy 01/86 08/89 Requirements for Senior Statement Operators (No Req.)
A-17 Systems Interaction USI NUREG-ll74 01/79 08/89 (No Req.)
A-40 Seismic Design Criteria USI SRP Revisions 01/79 09/89 (Req.)
A-47 Safety implications of Control USI GL 89-19 02/81 08/89 Systems (Reg.)
A-48 Hydrogen Control Measures and USI Rules (Req.)
02/81 04/89 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 2nd Quarter FY-97 9
9 9
[
~
J 3
T
(
TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL" YEAR Issue-Resolution Date Approved Date
- j Number
~ Title Priority Product ~
for Resolution -Resolved' FY-89 (Cont.)
I HF4.1 Inspection Procedure for High
- IN 86-64 10/01/84 10/88 i
Upgraded Emergency Operating (No Req.)
-Procedures l
1.F.1 Expand QA List High No Req.
NRR-0P FY83
_01/89 f
II.C.4 Reliability Engineering High No Req.
NRR-0P FY83 10/88-
[
II.E.6.1 Test Adequacy Study Medium-GL 89-10 NRR-0P FY83 06/89 l
(Req.)
j FY-90 70 PORV and Block Valve-Medium GL 90-06 05/14/84 06/90 i
Reliability 1
75 Generic Implications of NR Req.
'10/19/83 05/90 ATWS Events at the Salem Nuciear Power Plant L
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 09/04/85 11/89 Maximum Precipitation (Req.)
[
T3-10 As of 2nd Quarter FY-97
--=
TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR lssue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-90 (Cont.)
A-29 Nuclear Power Plant Medium No Req.
NRR-0P FY83 10/S9 Design for the Reduction of Vulnerability to Industrial Sabotage C-8 Main Steam Line High No Req.
NRR-0P FY83 03/90 Isolation Valve Leakage Control Systems FY-91 128 Electrical Power High GL 91-06, 11/28/86 09/91 Reliability GL 91-11 (Req.)
130 Essential Service Water High GL 91-13 03/10/87 09/91 System Failures at (Req.)
Multiplant Sites 135 Steam Generator Medium No Reg.
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.)
[1;;.91 29 Bolting Degradation or High No Req.
NRR-0P FY-83 10/91 Failure in Nuclear Power Plants T3-Il As of 2nd Quarter FY-97 9
9 9
.m..
4,.
. \\g v /-
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.)
P 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 r
87 Failure of HPCI Steam-High No Req.
09/26/85 12/91 Line Without Isolation j
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 i
151
-Reliability of ATWS Medium No Req.
'08/27/91 09/92 Recirculation Pump Trip in BWRs-f.h9.d
- l 105 Interfacing Systems LOCA High
' No Req.
06/11/85 06/93 at LWRs j
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 2nd Quarter FY-97
TABLE 3 (Centinued)
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-0P 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 Monitoring Medium No Req.
NRR-OP FY83 09/93 M
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 Medium No Req.
11/03/87 11/93 Combustible Gases in Vital Areas I.D.5(3)
On-Line Reactor Surveillance NR No Req.
NRR-0P FY83 11/93 Systems T3-13 As of 2nd Quarter FY-97 O
O O
(, - )
y-y s
\\
(
\\
\\,/
\\,_/
\\u/
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 Habiti.'lity NR No Req.
08/--/83 06/96 (NUREG/CR
-5669) fl::E 78 Monitoring of Fatigue Transient Medium No Req.
07/10/92 02/97 Limits for Reactor Coolant System T3-14 As of 2nd 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-57 (Cont.)
166 Adequacy of Fatigue Life NR No Req.
04/01/93 02/97 of Metal Components 173.B Spent Fuel Storage Pool:
NR No Req.
06/24/96 10/96 Permanently Shutdown Facilities T3-15 As of 2nd Quarter FY-97 O
O O
. (,.
U U
U TABLE 4 15 GSIs SCHEDULED FOR RESOLUTION (BY FISCAL YEAR)
PRIORITY FY-97 FY-98 FY-99 FY-00 FY-01 FY-02 TBD TOTAL HIGH 23 165 163 4
171 MEDIUM B-55 158 4
B-61 B-17 NR 145 172 168 7
190 173.A 170 191 TOTAL:
3 6
2 0
0 0
4 15 t
T4-1 As of 2nd Quarter FY-97
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-0P FY83 01/97 07/97 Failures 163 Multiple Steam Generator NRR/DE/EMCB H
01/17/97 NA TBD Tube Leakage 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 158 Performance of Safety-Related RES/ DER /GSIB M
01/26/94 08/97 12/97 Power-Operated Valves Under Design Basis Conditions B-17 Criteria for Safety-Related RES/DSR/HFBR M
03/22/82 06/97 01/98 Operator Actions B-55 Improve Reliability of Target NRR/DE/EMEB M
NRR-0P FY83 08/97 08/97 Rock Safety Relief Valves B-61 Allowable ECCS Equipment Outage RES/DSR/PRAB M
NRR-0P FY83 01/97 04/97 Periods 145 Actions to Reduce Common RES/DSR/PRAB NR 02/11/92 02/97 02/98 Cause Failures 168 Environmental Qualification NRR/DSSA/SPLB NR 04/01/93 TBD TBD of Electrical Equipment T4-2 As of 2nd Quarter FY-97 O
O O
Table 4A (Continued)
GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION i
Date Resolution Current Issue Lead Office /
Approved for Date at end ' Resolution 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 172 Multiple System Responses RES/DSR/PRAB NR 12/07/95 12/98 12/98 Program 173.A Spent Fuel Storage Pool:
NRR/DSSA/SPLB NR 06/24/96 10/98' 10/98 Operating Facilities 190 Fatigue Evaluation of Metal RES/ DER /GSIB NR 08/26/96~
12/97 12/97 Components for 60-Year P1 ant Life 191 Assessment of Debris Accumulation RES/ DER /GSIB NR 09/--/96 TBD TBD on PWR Sump Performance Total:
15
[
i i
T4-3 As of 2nd Quarter FY-97 t
()
'wl TABLE 5 NUMBER OF GENERIC ISSUES PRIORITIZED FROM FY-83 THROUGH THE 2ND OUARTER OF FY-97 ISSUE TYPE FY-83 FY-84 FY-85 FY-86 FY-87 FY-88 FY-89 FY-90 FY-91 FY-92 FY-93 FY-94 Total Issues Identified 56 19 54 45*
6
'3 38 3
29 7
5 1
266 to be Prioritized Issues Identified 19 2
0 1
1 2
0 0
0 0
0 0
25 to be Reprioritized Total:
75 21 54 46 7
5 38 3
29 7
5 1
291 New Issues (Entered into GIMCS)
High 2
1 41 6
4 1
1 0
2 0
0 1
59 Medium 2
4 1
1 1
2 0
1 3
2 0
1 18 Nearly-Resolved 3
5 6
1 0
1 0
0 1
2 2
0 21 Sub-total:
7 10 48 8
5 4
1 1
6 4
2 2
98 Resolved 4
0 1
0 0
1 1
1 0
2 1
0 11 Low 1
4 0
2 1
0 0
2 0
4 3
1 18 Drop 1
4 4
6 13 9
2 8
5 24 6
0 82 RI/LI/El 0
0 4
6 0
2 33 1
1 3
0 0
50 Integrated 8
2 3
6 0
1 1
3 0
5 0
0 29 Total issues 21 20 60 28 19 17 38 16 12 42 12 3
288 Prioritized:
[ Annual Progress]/ [+54
+1
-6
+18
-12
-12 0
-13
+17
-35
-7
-2]
3 Remaining Issues to be Prioritized or Reprioritized:
Extensive Revisions to Human Factors Issues Resulted'in Priority Changes.
'TS-1 As of 2nd Quarter FY-97
l l
TABLE 5 (Continued)
NUMBER OF GENERIC ISSUES PRIORITIZED FROM FY-83 THROUGH THE 2ND OUARTER OF FY-97 l
ISSUE TYPE Total (Bl_Fl FY-95 FY-96 FY-97 Total F
l Issues Identified 266 2
21 0
289 l
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 1
61 Medium 18 0
0 0
18 Nea.'y-Resolved 21 1
5 0
27 Sub-total:
98 2
5 1
106 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 1
308 (Annual Progress]/
Remaining Issues to be Prioritized or Reprioritized:
[
3 0
+7
-1]
9
=
T5-2 As of 2nd Quarter FY-97 O
O O
s
\\
,/7
(
)
L.,)
%J Q,,)
TABLE 5 GENERIC ISSUES PRIORIT! ZED AS OF 2ND OUARTER 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 51 Proposed Requirements for Improving the 09/82 06/83 MEDIUM Reliability of Open Cycle Service Water Systems 52 SSW Flow Blockage by Blue Mussels 09/82 05/83 S(51) 56 Abnormal Transient Operating Guidelines as 09/82 02/83 S(A-45/I.D.1)
Applied to a Steam Generator Overfill Event 58 Inadvertent Containment Flooding 09/82 08/83 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 Natural Convection Cooldown D-1 Advisability of a Seismic Scram 09/82 06/83 LOW IV.E.2 Plan for Early Resolution of Safety Issues 09/82 06/83 RESOLVED T6-1 As of 2nd Quarter FY-97
TABLE 6 (Continued)
G_ENERIC ISSUES PRIORITIZED AS OF 2ND OUARTER FY-97 Action Item /
Identification Date Current Issue No.
Title Date Prioritized Priority f.l.::El 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 09/8:
10/83 S(43) 48 LCO for Class IE Vital Instrument Buses in 09/E 10/83 NR Operating Reactors 49 Interlocks and LCOs for Redundant Class IE 09/SZ 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 Wetwell Airspace 10/82 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 l
Resulting from Turbine-Driven Auxiliary l
Feedwater Pump Steam Supply Line Rupture l
69 Make-up Nozzle Cracking in B&W Plants 06/83 12/83 NR 70 PORV and Block Valve Reliability 06/83 05/84 MEDIUM 75 Generic Implications of ATWS Events at the Salem 06/83 10/83 NR Nuclear Plant 80 Pipe Break Effects on Control Rod Drive Hydrau-06/83 01/84 LOW l
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 l
l T6-2 As of 2nd Quarter FY-97 1
O O
O 1
p
(~
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 2ND OUARTER FY-97 Action Item /
Identification Date Current Issue No.
Title Date Prioritized Prioiity FY-85 37 Steam Generator Overfill and Combined Primary 09/82 05/85 S(A-47) and Secondary Blowdown 54 Valve Operator-Related Events Occurring 09/82 06/85 S(II.E.6.1)
During 1978, 1979, and 1980 55 Failure of Class IE Safety-Related Switchgear 09/82 03/85 DROP Circuit Breakers 59 Technical Specification Requirements for Plant 10/82 02/85 RI Shutdown 67 Steam Generator Staff Actions 06/83 03/85 MEDIUM 81 Potential Safety Problems Associated With Locked 11/83 10/84 DROP Doors and Barriers in Nuclear Power Plants 83
.ontrol 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 r
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 2nd Quarter FY-97 L.-
TABLE 6 (Continued)
GENERIC ISSUES PRV0RITIZED AS OF 2ND OUARTER FY-97 Action item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-85 (Cont.)
B-19 Thermal-Hydraulic Stability 02/83 01/85 NR B-50 Post Operating Basis Earthquake Inspection 02/83 04/85 RI(LOW)
B-59 N-1 Loop Operation in BWRs and PWRs 02/83 06/85 RESOLVED HF-01 Human Factor Program Plan (HFPP with 24 08/83 10/84 HIGH subtasks)
HF-02 Maintenance and Surveillance Program Plan 04/84 03/85 HIGH (MSPP with 10 subtasks)
FY-86 21 Vibration Qualification of Equipment 03/83 06/86 DROP 30 Potential Generator Missiles - Generator Ector 09/82 10/85 DROP Retaining Rings 74 Reactor Coolant Activity Limits for Operating 06/83 05/86 DROP Reactors 97 PWR Reactor Cavity Uncontrolled Exposures 09/84 10/85 S(III.D.3.1) 111 Stress Corrosion Cracking of Pressure Boundary 01/85 11/85 LI Ferritic Steels in Selected Environments 112 Westinghouse RPS Surveillance Frequencies and 01/85 10/85 RI(R)
Out-of-Service Times 114 Seismic-Induced Relay Chatter 03/85 06/86 S(A-46) 115 Reliability of Westinghouse Solid State 04/85 07/86 HIGH fratection System 122.1.a Common Mode Failure of Isolation Valves in 08/85 01/86 HIGH Closed Position 122.1.b Recovery of Auxiliary Feedwater 08/85 01/86 MEDIUM 122.1.c Interruption of Auxiliary Feedwater Flow 08/85 01/86 HIGH 122.2 Initiating Feed-and-Bleed 08/85 01/86 HIGH 122.3 Physical Security System Constraints 08/85 01/86 LOW 124 Auxiliary Feedwater System Reliability 12/85 02/86 NR T6-4 As of 2nd Quarter FY-97 O
O O
gg
/~~h p
(,)
b C
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 2ND OVARTER FY-97 Action Item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-86 (Cont.)
125.I.2.a PORY Reliability - Test Program 11/85 06/86 S(70) 125.I.2.b PORV Reliability - Surveillance 11/85 06/86 S(70) 125.I.2.c Auto Block Valve Closure 11/85 06/86 DROP 125.I.2.d Equipment Qualification for Feed-and-Bleed 11/85 06/86 S(A-45)
Environment 125.II.3 Review Steam / Feed Line Break Mitigation 11/85 08/86 DROP Systems for Single Failure 125.II.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.II.9 Enhance Feed-and-Bleed Capability 11/85 08/86 S(A-45) 125.11.14 Remote 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 LOCA Heat Sources 02/83 06/86 RI(R)
FY-87 113 Dynamic Qualification Testing of Large Bore 03/85 07/87 HIGH 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 2nd Quarter FY-97
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 2ND OUARTER FY-97 Action Item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-87 (Cont.)
125.II.1.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 Improvemer.ts 11/85 10/86 DROP 125.II.1.d AFW Steam and Feedwater Rupture Control 11/85 10/86 DROP System /ICS Interactions in B&W Plants 125.II.2 Adequacy of Existing Maintenance Requirements 11/85 06/87 DROP fos Safety-Related Systems 125.II.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/b5 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 f.h8.8, 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 2nd Quarter FY-97 O
O O
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 2ND OUARTER FY-97 Action Item /
Identification Date Current Issue No.
Title Date Prioritized
-Priority FY-88 (Cont.)
62 Reactor Systems Bolting App!! cations 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 05/38 NR 125.I.6 Valve Torque Limit and Bypass Switch Settings 11/85 12/87 DROP 125.I.7A Recover Failed Equipment 11/85 12/87 DROP 125.II.11 Recovery of Main Feedwater as Alternative to AFW 11/85 06/88 DROP 125.II.13 Operator Job Aids 11/85 03/88 DROP 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 Cryogenic Combustibles on Site C-14 Storm Surge Model for Coastal Sites 02/83 05/88 LI(DROP)
III.D.l.l(2) Review Information on Provisions for Leak 12/82 09/88 DROP Detection III.D.1.l(3) Develop Proposed System Acceptance Criteria 12/82 09/88 DROP FY-89 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 Required by Design Basis Analysis 131 Potential Seismic Interaction Involving the 07/86 07/89 S(IPE)
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 92/83 02/89 LI(DROP)
D-2 ECCS Capability for Future Plants 06/83 10/88 DROP Previous Priority Evaluation Published in NUREG-0933' T6-7 As of 2nd Quarter FY-97
TABLE 6 (Continued)
GENERIC ISSUSS PRIORITIZED AS OF 2ND OUARTER FY-97 Action Item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-90 63 Use of Equipment Not Classified as 10/82 02/90 DROP Essential to Safety in BWR Transient Analysis 71 Failure of Resin Demineralizer Systems and 06/83 02/90 LOW Their Effects on Nuclear Power Plant Safety 81*
Impact of Locked Doors and Barriers on 12/86 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) fh91 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 2nd Quarter FY-97 O
O O
C N
/O l
TABLE 6-(Continued)
GENERIC ISSUES PRIORITIZED AS OF 2ND OVARTER FY-97 Action Item /
Date Prioritized-Priority Identification : Date Current Issue No.
Title FY-91 (Cont.)
-72 Control Ro'd Drive Guide Tube Support Pin 06/83 10/90 DROP Failures 73 Detached Thermal Sleeves 06/83 08/91 NR 100
.Once-Through Steam Generator. Level 09/84 09/91 DROP 120 On-line Testability of Protection Systems 08/85 11/90 MEDIUM 143 Availability of Chilled Water Systemt 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 IIIGH 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 2nd Quarter FY-97
TABLE 6 (Continutd)
GENERIC ISSUES PRIORITIZED AS OF 2ND OUARTER FY-97 ActionItemT Identification Date Current Issue No.
Title Date Prioritized Priority FY-92 (Cont.)
123 Deficiencies in the Regulations 11/85 12/91 DROP Governing DBA and Single Failure Criterion Suggested by the Davis-Besse Incident of June 9,1985 132 RHR Pumps Inside Containment 07/86 03/92 DROP 138 Deinerting of BWRs With MARK I and II 10/86 10/91 LOW Containments During Power Operations Upon Discovery of Reactor Cooling System Leakage or a Train of a Safety System Inoperable 144 Scram Without a Turbine / Generator Trip 03/88 03/92 LOW I45 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 T6-10 As of 2nd Quarter FY-97 O
O O
(~\\
_,)
N O
TABLE 6 (Continuedl GENERIC ISSUES PRIORITIZED AS OF 2ND OUARTER FY-97 Action Item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-92 (Cont.)
156.2.3 Containment Design and Inspection 02/91 05/92 DROP 156.2.4 Seismic Design of Structures, Systems, 02/91 03/92 DROP and Components 156.3.1.1 Shutdown Systems 02/91 03/92 DROP i
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 156.3.3 Ventilation Systems 02/91 09/92 DROP 156.3.4 Isolation of High and Low Pressure 02/91 12/91 DROP Systems 156.3.5 Automatic ECCS Switchover 02/91 11/91 S(24) 156.3.6.1 Emergency AC Power 02/91 02/92 S(B-56) 156.3.8 Shared Systems 02/91 06/92 DROP 156.4.1 RPS and ESFS Isolation 02/91 11/91 S(142) 156.4.2 Testing of the RPS and ESFS 02/91 03/92 S(120) 157 Containment Performance 10/91 02/92 RESOLVED FY-93 146 Support Flexibility of Equipment and Components 01/89 09/93 RESOLVED 149 Adequacy of Fire Barriers 04/89 10/92 LOW 152 Design Basis for Valves That Might Be 03/90 01/93 LOW Subjected to Significant Blowdown Loads 155.3 Improve Design Requirements for Nuclear 02/91 01/93 DROP Facilities 156.3.6.2 Emergency DC Power 02/91 03/93 LOW 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 Restoration of Power 161 Use of Non-Safety-Related Power Supplies in 10/91 03/93 DROP Safety-Related Circuits 162 Inadequate Technical Specifications for Shared 10/91 07/93 DROP Systems at Multiplant Sites When One Unit Is Shut Down 164 Neutron Fluence in Reactor Vessel 10/92 03/93 DROP T6-ll As of 2nd Quarter FY-97
TABLE 6 (Continu'd)
GENERIC ISSUES PRIORITIZED AS OF 2ND OVARTER FY-97 Action item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-93 (Cont.)
156 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-Operated 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-0il in Rosemount Transmitters 02/96 05/96 RESOLVED 177 Vehicle Intrusion at TMI 02/96 05/96 RESOLVED 178 Effect of Hurricane Andrew on Turkey Point 05/96 05/96 LI 179 Core Performance 02/96 05/96 LI 180 Notice of Enforcement Discretion 02/96 05/96 LI (Resolved) 181 Fire Protection 02/96 05/96 LI T6-12 As of 2nd Quarter FY-97 O
O O
'\\
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 2ND OUARTER FY-97 Action-Item /
Identification Date Current Issue No.
Title Date Prioritized Priority'
.l FY-96 (Cont.)
J 182 General Electric Extended Power Uprate 05/96 05/96 RI 4
183 Cycle-Specific Parameter Limits in Technical 02/96' 05/96 RI.
Specifications i
i 184 Endangered Species 05/96
_ 05/96 EI 190 Fatigue Evaluation of Metal Components for 08/96
'08/96 NR 60-Year Plant Life i
l 191 Assessment of Debris Accumulation on PWR 09/96 09/96 NR:
Sump Performance FY-97 lj 163 Multiple Steam Generator Tube Leakage 06/92 01/97 H
\\
f V
?
I L
t P
t t
[
i T6-13 As of 2nd Quarter FY-97
j%,
(3 2
1 TABLE 7
. GENERIC' ISSUES TO BE PRIORITIZED AS OF 2ND OUARTER FY-97 Action Item /.
Identification Current Issue No.
Title Date Schedule i
156.6.1 Pipe Break Effects on Systems and Components 02/91 03/97 169 BWR MSIV Common Mode Failure Due to Loss of Accumulator Pressure.
10/93 02/97 NMSS-0001 Door Interlock Failure Resulting from Faulty MicroSelectron-High 04/96 TBD Dose Rate Remote Afterlooder NMSS-0002 Significant Quantities o'.
Fixed Cor.tamination Remain in Krypton-85 07/96 TBD Leak-Detection Devices After Venting NMSS-0003 Corrosion of Sealed Sources Caused by Sensitization of Stainless 07/96 TBD' Steel Source Capsules During Shipment j
NMSS-0004 Overexposures Caused by Sources Stolen from Facility of Bankrupt 07/96
-TBD Licensee TOTAL: 6 i
L i
i T7-1 As.of 2nd Quarter FY-97
[;
h.
\\
- Q.)
)
TABLE 8 GENERIC IS5 DES TO BE REPRIORITIZED AS OF 2ND OUARTER FY-97 Action Item /
Previous Ident.
. Current Issue No.
.Ti tl e Priority
'Date Schedule 71 Failure of Resin Demineralizer Systems and Their Effects LOW 04/96-09/97-
.on Nuclear Power Plant Safety t
107
LOW 04/96 09/97 l
152' Design Basis for Valves That Might Be Subjected to LOW 04/96 09/97 Significant Blowdown Loads
}
I.F.2(1)
QA - Assure the Independence of the Organization LOW.
04/97 TBD Performing the Checking Function II.D.2 Research on Relief and Safety Valve Test Requirements LOW 04/97
.TBD-
-TOTAL: 5 t
L I
i i
T8-1 As of 2nd Quarter FY-97 f
I t
/-
, - ~.
G a
La TABLE 9 REGULATORY IMPACT ISSUES SCHEDULED FOR RESOLUTION AS OF 2ND OVARTER FY-97 Lead Office /
Issue Division /
Resolution Number Title Branch Date 182 General Electric Extended Power Uprate NRR/DRPW/PD31 TBD TOTAL:
1 T9-1 As of 2nd Quarter FY-97
\\
\\xJ'
,)
x_/
TABLE 10 LICENSING ISSUES SCHEDULED FOR RESOLUTION AS OF 2ND OVARTER 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 TBD 179 Core Performance NRR/DSSA/SRXB 12/97 181 Fire Protection NRR/DSSA/SPLB TBD TOTAL: 4 T10-1 As of 2nd Quarter FY-97
O C
TABLE 11' ENVIRONMENTAL ISSUES SCHEDULED FOR RESOLUTION AS OF 2ND OVARTER FY-97 Lead Office /
Division /
Issue Resolution Number Title Branch Date:
184 Endangered Species' NRR/CRPM/PDND TBD TOTAL: 1
.Tll-1
- As of 2nd Quarter FY-97
.m C
O J
,. TABLE 12 RESOLVED GENERIC ISSUES WITH ONGOING ACTIVITY AS OF 2ND OUARTER FY-97
- Lead Office /.
Issue
' Division /-
' Resolution Number Title Branch 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 2
Controls and Instrumentation
)
II.E.6.1 In-Situ Testing of Valves NRR/DE/EMEB-TBD r
t TOTAL: 4 1
Y I
i 6
1 I
f
.i l
e 1
4
~
t Tll-1 As of 2nd Quarter FY-97:
2
,~
\\,.,
\\,-)
N.-)
TABLE 13 RELATED GENERIC ACTIVITIES AS OF 2ND OVARTER 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-005 RCS Draindown NRR/DSSA/SRXB 04/98 RGA-006 SRP Revision NRR/ DISP /PIPB TBD RGA-007.1.2D PRA Implementation Plan - Graded QA NRR/DRCH/HQMB 04/98 TOTAL: 5 T13-l As of 2nd Quarter FY-97
m.
2._...~.
m._....
..,s_..
~., _. _. _ _.... -. _. _......
3 O
^
O RUN DATE: 05/23/97-D INDEX OF ISSUES I
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM ISSUE NUMBER TITLE
'PAGE I
23 REACTOR COOLANT PUMP SEAL FAILURES 1
f 78
- MONITORING OF FATIGUE TRANSIENT LIMITS FOR REACTOR COOLANT 5
116 ACCIDENT MANAGEMENT 8
145 ACTIONS TO REDUCE COMMON CAUSE FAILURES 10 148 SMcKE CONTROL AND MANUAL FIRE-FIGHTING EFFECTIVENESS 12 I
t 155.1 MORE REALISTIC SOURCE TERM ASSUMPTIONS 14 158 PERF OF SAFETY-RELATED POWER-OPERATED VALVES UNDER DESIGN BASIS CONDIT 18
+
165 SPRING-ACTUATED SAFETY AND RELIEF VALVE RELIABILITY 20 IGS ADEQUACY OF FATIGUE LIFE OF METAL COMPONENTS 23
' ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT 25 i
168 170 REACTIVITY TRANSIENTS AND FUEL DAMAGE CRITERIA FOR HIGH BURNUP FUEL 27' 171 ESF FAILURE FROM LOOP SUBSEQUENT TO LOCA 31
{
172 MULTIPLE SYSTEM RESPONSES PROGRAM 33 l
173.A SPENT FUEL STORAGE POOL: OPERATING FACILITIES 34 173.B SPENT FUEL STORAGE POOL: PERMANENTLY SHUTDOWN FACILITIES 37 178 EFFECT OF HURRICANE ANDREW ON TURKEY POINT 39 179 CORE PERFORMANCE 41 i
I 181 FIRE PROTECTION 44' i
182 GENERAL ELECTRIC EXTENDED POWER UPRATE 47 i
l 184 ENDANGERED SPECIES.
50 190 FATIGUE EVALUATION OF METAL COMPONENTS FOR 60-YEAR PLANT LIFE 52
}
2 l
191 ASSESSMENT OF DEBRIS ACCUMULATION ON PWR SUMP PERFORMANCE
.54 l
I t
I l
9 I
RUN DATE: 05/23/97 INDEX OF ISSUES GENERIC ISSUE MANAGEMENT CONTROL SYSTEN ISSUE NUMBER TITLE PAGE B-17 CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS 56 B-55 IMPROVE RELIABILITY OF TARGET ROCK SAFETY-RELIEF VALVES 59 B-61 ALLOWABLE ECCS EQUIPMENT OUTAGE PERIODS 62 HF 5.2 REV. CRIT. FOR HUMAN FACTORS ASPECTS OF ADV CONTROLS AND INSTRUMENT.
65 II.E.6.1 IN-SITU TESTING OF VALVES 67 RGA 001 BOILING WATER REACTOR INTERNALS 71 RGA 003 DRY CASK STORAGE OF SPENT FUEL 74 RGA 005 RCS DRAINDOWN 77 RGA 006 SRP REVISION 79 RGA 007.1. 2D PRA IMPLEMENTATION PLAN - GRADED QA 81 O
O O
f Ch (w
k v/
/
\\
s/
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
1 ISSUE NUMBER: 23 TITLE: REACTOR COOLANT PUMP SEAL FAILURES IDENTIFICATION DATE: 12/80C' PRIORITIZATION DATE: 04/83C TYPE: GSI PRIORITY: H
-s TASK MANAGER: K. SHAUKAT OFFICE / DIVISION / BRANCH: RES / DER /GSIB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE: 07/97
' WORK AUTHORIZATION: NRR FY-B4 OPERATING PLAN. (APPENDIX G)
FIN CONTRACTOR CONTRACT TITLE A3751 BNL REACTOR COOLANT PUMP (RCP) SEAL INTEGRITY A3771 BNL ASSESS EFFECT OF MECH. MAINT. RCP SEAL f
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. ANALYSIS B3049 ETEC LEAK RATE ANALYSIS OF WESTINGHOUSE RCP D1760 SCIENTECH REG. ANAL. FOR GI-23.' RCP SEAL FAILURES t
W6211 BNL SOLUTIONS TO MAINTAIN RCP SEAL INTEGRITY L
WDRk SC0PE kHk k P kbR kHis iksbk E5 kEVkSkb kb kNbbR kHbbLb T Kb kF NY TbRkbbCkRCPkk F kLbRk kb N PORATE WORK NECESSARY TO COMPLETE GSI 65.
REVIEW ACCEPTABLE LEVEL COMMENSURATE WITH THE POTENTIAL SAFETY PWR RCP SEAL FAILURES CAUSED BY MECHANICAL FAILURES CONSEQUENCES OF SEAL FAILURE. THE PROGRAM CONSISTS OF AND LOSS OF SEAL-COOLING TO ASCERTAIN IF INCREASED NRC THE FOLLOWING MAJOR TASKS:
REQUIREMENTS ARE NECESSARY TO MINIMIZE SEAL FAILURES.
TASK 1 - DETERMINE ACTUAL SEAL FAILURE MECHANISMS.
EVALUATE THE EFFECTS OF SYSTEM DESIGN. MATERIALS.
TASK 2 - EVALUATE RCP SEAL COOLING FOR ALL MODES OF OPERA-
+
OPERATION. TESTING. AND MAINTENANCE ON SEAL FAILURE TION FOR WHICH SEAL COOLING IS REQ *D USING THE MECHANISMS. REVIEW THE RELIAB. OF SEAL COOLING. SYSTEMS RELIABILITY OF TYPICAL RCP SEAL COOLING SYSTEM I
AND IDENTIFY METHOOS TO MINIMIZE THE EFFECTS OF LOSS OF DESIGNS.
SEAL COOLING. PERFORM A RISK ASSESSMENT 0F SEAL FAILURE TASK 3 - REVIEW MECHANICAL AND MAINTENANCE-INDUCED FROM MAINTENANCE AND MECHANICAL EFFECTS.
FAILURE MECHANISMS.
[
THIS PROGRAM WILL DETERMINE WHAT STEPS THE NRC TASK 4-FEASIBILITY STUDY TO IDENTIFY MOST EFFECTIVE FIX.
t STATUS AN NRR GENERIC LETTER FOR INFORMATION ONLY WAS ISSUED REGULATORY GUIDE DG-1008 AND THE DRAFT REGULATORY ANALYSIS.
MAY 2 1991. TO INFORM LICENSEES OF THE POTENTIAL IMPACT NUREG-1401. THE STAFF DECIDED TO PROCEED WITH A RULEMAKING ON $80 ANALYSES. A FEDERAL REGISTER NOTICE WAS PUBLISHED FOR OFF-NORMAL CONDITIONS WHILE THE NORMAL CONDITIONS HAVE i
APRIL 19, 1991 REQUESTING PUBLIC COMMENT ON DRAFT BEEN ADDRESSED BY APPROPRIATE GENERIC COMMUNICATIONS.
L t
AS OF FY97 QUARTER 2 l
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
2 ISSUE NUMBER: 23 TITLE: REACTOR COOLANT PUMP SEAL FAILURES AFFECTED DOCUMENTS PROBLEh/ RESOLUTION (1) THE FOLLOWING REPORTS HAVE BEEN ISSUED:
THE STAFF HAS ACCOMMODATED CRGR COMMENTS. THE STAFF 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 COMMISSION FOR REVIEW AND DURING STATION BLACKOUT" APPROVAL. THE COMMISSION DISAPPROVED ISSUANCE OF THE PRO-NUREG/CR-4643, " EVALUATION OF CORE DAMAGE SEQUENCES POSED RULE FOR PUBLIC COMMENT AND DIRECTED THE STAFF TO INITIATED BY LOSS OF REACTOR COOLANT COMMUNICATE THIS DECISION TO REACTOR LICENSEES.
PUMP SEAL COOLING" AN INFORMATION NOTICE 95-42 WAS ISSUED TO THE LICENSEES NUREG/CR-4400, "THE IMPACT OF MECHANICAL AND MAINTENANCE-ABOUT 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 RELATED 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 MILEST0NES DATE DATE DATE hPIkhbEbFbRbbhkkNT ~ ~~
b4b3
~~
5 b5/b5~~
TAP APPROVED BY DSI DIR 10/83 10/83 ISSUED REQUEST FOR PROPOSAL TO BNL FOR 11/83 11/83 COMPONENT COOLING VATER PRA TRANSFER RESOLUTION REPONSIBILITY FROM DSI TO 06/84 06/84 DE t
TRANSFER RESOLUTION RESPONSIBILTY FROM DE TO 05/85 05/85 DST /GIB AS OF FY97 QUARTER 2 l
l l
1 l
l O
O O
b
\\
V RUN DATE: 05/23/97.
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
3 s.
' ISSUE NUMBER: 23 TITLE: REACTOR COOLANT PUMP' SEAL FAILURES l
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE COMPLETE DOCUMEN. OF BACKGROUND PAST 05/85 12/85 SEAL FAILURES, INCLUDING LER SEARCH,REV 0F INDUST. EXP.& REV.0F BWR SCR.(TASK 1)
EVAL. RCP SEAL COOLING. INCL. DETERM. EFFECT 12/84 08/86 0F LOSS COOLING, EVAL RELIAB. OF COOLING SYS.
AND REV. RCP SEAL CDOLING INSTR. (TASK 2)
EVALUATE MECHANICAL AND 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 5
ACRS REVIEW'0F DTR COMPLETE 11/85 09/90 CONCURRENCE BY OTHER OFFICES 09/85 10/90
[
DTR SENT TO CRGR 10/85 10/90 CRGR REVIEW OF DTR COMPLETE 11/85 03/91
[
FRN OF ISSUANCE OF PROPOSED RESOLUTION FOR 12/85 04/91' FUBLIC COMMENT l
DRAFT PERFORMANCE 07/91 08/91 PUBLIC COMMENT PERIOD ENDS 09/91 11/91 COMPLETE REVIEW AND COMPILATION OF PUBLIC 04/86 02/92 COMMENTS RECEIPT OF GUIDANCE FROM EDO ON RULEMAKING 05/92 11/92 l
t
'AS OF FY97 QUARTER 2 l
f l
i
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
4 ISSUE NUMBER: 23 TITLE: REACTOR COOLANT PUMP SEAL FAILURES
- ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE PkbPbSEbkPPkbbbhbkRkFbkkbkMkbbPEkTbk khbh hhhh PREPARE PROPOSED RULE 09/92 05/93 DIVISION DIRECTOR REVIEW OF PROPOSE 0 RULE 10/92 06/93 COMPLETED CONCURRENCE BY OTMER OFFICES OF PROPOSED 11/92 07/94 RULE LETTER TO NRR FOR BWR SEALS UNDER SB0 05/93 10/93 ACRS AND CRGR REVIEW OF PROPOSE 0 RULE I2/92 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 07/97 AS OF FY97 QUARTER 2 O
O O
- s
/
t L
-RUN DATE:. 05/23/97
~
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
5 t
. MONITORING OF FATIGUE TRANSIENT LIMITS FOR REACTOR COOLANT ISSUE NUMBER: 78 TITLE:
IDENTIFICATION DATE: 05/B3C PRIORITIZATION DATE: 07/92C TYPE:
PRIORITY: M lt
. TASK MANAGER: K. SHAUKAT OFFICE / DIVISION / BRANCH: RES / DER /GSIB.
ACTION LEVEL: ACTIVE
-STATUS: A TAC NUMBERS:
. RESOLUTION DATE: 02/97C l
WORK AUTHORIZATION: 7/10/92 MEM0/8ECKJORD TO MINNERS. " MONITORING OF FATIGUE..."
i 4/1/93 MEMO /BECKJORD TO SNIEZEK, " RESOLUTION OF FATIGUE...**
I FIN CONTRACTOR-CONTRACT TITLE i
W6077 ANL.
STATISTICAL ANALYSIS OF FATIGUE DATA L
i i
WORK
$ COPE i
kbbkVkLbPbbkbkkbkbkPbhkkhfkLhkhibbkbkbkkbkhibkbh bb[Dkkbh[bkPPL[bkkLkhbhhbSkRkkkkkkkbhkkkkbFPLEkh COMPONENT OF THE RCPB FOR ALL OPERATING PLANTS. THIS OPERATION UNDER THE CURRENT 40-YEAR LICENSE.
i i
STATUS t
BECAUSE THE ORIGINA DESIGN BASIS OF THE REACTOR COOLANT THE RISK OF FAILURE OF REACTOR PRIMARY CIRCUIT COMPONENTS TO
-i PRESSURE BOUNDARY (RCPB DID NOT ACCOUNT ADEQUATELY FOR THE BE ACCEPTABLY LOW FOR 40-YEAR PLANTS. THIS WAS INTEGRATED EFFECTS OF THE REACTOR OOLANT HARSH ENVIRONMENTS DURING INTO NRR*S. GENERIC ISSUE 166 ENTITLED " MONITORING OF OPERATION ON THE RCPB FATIGUE RESISTANCE. GENERIC ISSUE 78 FATIGUE TRANSIENT LIMITS FOR REACTOR COOLANT."
WAS ESTABLISHED TO ASSESS THE INCREASE IN RISK DUE TO OPERA-THE OUTCOME OF THE GI-78 AND 166 WORK IS THAT NO TION UNDER THE HARSH ENVIRONMENT.
FATIGUE CONCERNS EXIST FOR 40-YEAR PLANTS AND A 60-YEAR i
A RISK ANALYSIS WAS COMPLETED IN LATE FY'95 THAT SHOWED LICENSED PLANT.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION i
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE l
GI-78 ASSIGNED TO RES/DSIR/EIB 07/92 07/92 i
l
[
AS OF FY97 QUARTER 2_
i I
L
=
m u
w m
w
i RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
6 ISSUE NUMBER: 78 TITLE: MONITORING OF FATIGUE TRANSIENT LIMITS FOR REACTOR C00LAMT ORIGINAL CURRENT ACTUAL MILESTCNES DATE DATE DATE l
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 STUDICS 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 STEEL AND LOW ALLOY 04/94 09/94 STEEL)
ANL COMPLETES STAINLESS AND NICKEL ALLOY 12/94 12/94 STEEL ANALYSIS ANL COMPLETES DRAFT REPORT (STAINLESS AND 01/95 01/95 MICKEL ALLOY STEELS)
ANL COMPLETES FINAL REFORT (STAINLESS AND 04/95 06/95 NICKEL ALLOY STEELS)
CLOSEOUT MEMO AND PRA ANALYSIS (STAINLESS 0S/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 2 O
O O
-.___._._..-_-_.__..,-~.._._.y...____.._.,_.m..____m..
r*
r
't
-- i
.RUN DATE: 05/23/97 Li.\\
~ GENERIC ISSUE MANAGEMENT CONTROL-SYSTEM PAGE:
7 1
ISSUE NUMBER: 78 TITLE: MONITORING OF FATIGUE TRANSIENT LIMITS FOR REACTOR COOLANT 4
ORIGINAL CURRENT ACTUAL-
. MILESTONES DATE.
DATE DATE-
.i CLOSEOUT MEMO TO EDO FROM RES 06/95 02/97-i 6
i AS OF FY97. QUARTER 2 I
-?
i 1
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
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 /DSSA/SCSB ACTION LEVEL: ACTIVE STATUS:
TAO NUMBERS: M91966 M91641 RESOLUTION DATE:
WORK AUTHORIZATION: SECY-88-147, " INTEGRATION PLAN FOR CLOSURE OF SEVERE ACCIDENT ISSUES." 05/25/88 FIN CONTRACTOR CONTRACT TITLE L1697 ORNL TECHNICAL ASSISTANCE IN SUPPORT OF THE REACTCR SYSTEMS BRANCH W0RK SC0PE 5PkbiF[b bhkbkk [kbLbDEb kk kHE /Mkbk[bkPLkkRE[
bbkPLEhE P[Lbh [kkPEbh[ bks kkb FblLbWbP kb(5 bkVElbPkk (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. BASED ON FEEDBACK FROM THE WORKSHOP. THE FORMAL INDUSTRY POSITION ARE BEING IMPLEMENTED, (3) COMPLETE STAFF WILL FINALIZE THE INSPECTION PROCEDURE AND THE THE DRAFT TEMPORARY INSTRUCTION (TI) USING THE INFORMATION APPROACH AND SCHEDULE FOR EVALUATING A/M IMPLEMENTATION FOR AND PERSPECTIVES OBTAINED THROUGH THE SITE VISITS. (4)
THE REMAINING PLANTS.
STATUS SEVERE ACCIDENT MANAGEMENT GUIDELINE DOCUMENTS HAVE BEEN MARCH I.
1996. TO DISCUSS PLANS FOR INSPECTING UTILITY SUBMITTED BY EACH OF THE PWR OWNERS GROUPS AND REVIEWED IMPLEMENTATION OF THE FORMAL INDUSTRY POSITION ON SEVERE BY THE STAFF. THE BWROG SUBMITTED REV. 0 0F THE EMERGENCY ACCIDENT MANAGEMENT AND MAJOR ELEMENTS OF THE DRAFT TI.
THE PROCEDURE AND SEVERE ACCIDENT GUIDELINES (EP/ SAG) AND STAFF AND NEI MET ON DECEMBER 19, 1996. AND JANUARY 24 TECHNICAL BASIS REPORT ON AUGUST 29, 199S. A BWOG 1997. TO DISCUSS AN INDUSTRY PROPOSAL TO ORGANIZE SUBMITTAL ILLUSTRATING EP/ SAG USAGE FOR AN EXAMPLE BWR "0EMONSTRATIONS" 0F COMPLETED A/M IMPLEMENTATION AT SEQUENCE IS EXPECTED IN APRIL 1997. THE STAFF AND OAK RIDGE SELECTED SITES. CURRENT PLANS ARE FOR THE STAFF TO NATIONAL LABORATORY HAVE COMPLETED A HIGH LEVEL REVIEW OF PARTICIPATE IN A/M DEMONSTRATIONS AT 4 SITES IN 1997 FOR THE DOCUMENTS. A MEETING TO DISCUSS SPECIFIC CONCERNS THE PURPOSE OF OBTAINING AN UNDERSTANDING OF HOW THE REGARDING THE BWROG PRODUCTS IS EXPECTED IN APRIL 1997.
VARIOUS ELEMENTS OF THE FORMAL INDUSTRY POSITION ARE BEING LICENSEE TARGET DATES FOR COMPLETING A/M IMPLEMENTATION IMPLEMENTED. STAFF PLANS AND GUIDANCE FOR INSPECTION OF HAVE BEEN SUBMITTED TO NRC, AND A DRAFT TI FOR USE IN THE A/M IMPLEMENTATION WILL BE REASSESSED AND REFOCUSED PILOT INSPECTIONS HAS BEEN COMPLETED. COMMENTS ON THE DRAFT FOLLOWING THE DEMONSTRATIONS.
TI HAVE BEEN RECEIVED FROM THE NRC REGION OFFICES. THE SEE NRR DIRECTOR'S MONTHLY REPORT FOR LATEST STATUS.
STAFF MET WITH INDUSTRY ON FEBRUARY 22, 1996. AND ACRS ON AS OF FY97 QUARTER 2 O
O O
h
'(
J J
b RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
9 ISSUE NUMBER: 116 TITLE: ACCIDENT MANAGEMENT AFFECTED DOCUMENTS PROBLEM / RESOLUTION GL 88-20. SUPPLEMENT 2 -
NONE OPIGINAL CURRENT ACTUAL MILEST02E$
DATE DATE DATE REVIEW SEVERE ACCIDENT TRAINING MATERIALS 06/95 06/95 AND 8WROG PRIORITIZATION METHODOLOGIES INITIAL DRAFT (FOR INTERNAL USE) OF TI FOR 11/95 11/95 l
PILOT INSPECTIONS REVIEW BWROG SEVERE ACCIDENT MANAGEMENT 08/96 07/97 GUIDANCE (SAMG) DOCUMENTS INDUSTRY-SPONSORED A/M DEMONSTRATIONS 11/96 REVISED DRAFT OF TI FOR PILOT INSPECTIONS 12/96 TO NEI AND PUBLIC FINAL TI FOR PILOT INSPECTIONS 03/97 COMPLETE PILOT INSPECTIONS AND FOLLOWUP 12/97 12/97 ISSUE DRAFT REVISED INSPECTION PROCEDURES 03/98 03/98 (IP) i HOLD PUBLIC MEETING / WORKSHOP 05/98 05/98 ISSUE FINAL IP 07/98 07/98 REVIEW REMAINING PLANTS I
r L
+
AS OF FY97 QUARTER 2 i
r i
t i
I
~
n 2
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
10 ISSUE NUMBER: 145 TITLE: ACTIONS TO REDUCE COMMON CAUSE FAILURES IDENTIFICATION DATE: 07/85C PRIORITIZATION DATE: 02/92C TYPE: GSI PRIORITY: M TASK MANAGER: E. CHELLIAH OFFICE / DIVISION / BRANCH: RES / DST /PRAB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS:
RESOLUTION DATE: 02/98 WORK AUTHORIZATION: MEMORANDUM FROM E. S. BECKJORD TG V. MINNERS DATED FEBRUARY 11, 1992 FIN CONTRACTOR CONTRACT TITLE L1125 BNL TECHNICAL SUPPORT ANALYSES L2553 BNL TECHNICAL SUPPORT TO GI-145 W0RK SC0PE THE ACTIONS REQUIRED TO RESOLVE THE ISSUE ARE MINIMAL. THE REPORT THAT WILL BE PLACED IN THE PUBLIC DOCUMENT ROOM.
SCOPE OF THE ISSUE IS ONLY TO COLLECT THE INFORMATION SO AS TO BE READILY AVAILABLE TO LICENSEES.
AVAILABLE ON COMMON MODE FAILURES AND PUBLISH IT IN A STATUS BNL SUBMITTED A FINAL REPORT IN DECEMBER 1993. THE STAFF NEEDED TO RESOLVE THE ISSUE. THIS CONCLUSION WILL BE FFIND THAT NO ADDITIONAL REQUIREMENTS ON THE LICENSEES WERE SUBMITTED TO THE PRAB BRANCH CHIEF IN 07/97.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION POSSIBLE NUREG/CR.
NONE.
ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE COMPLETION OF GI PRIORITIZATION 02/92 02/92 COMPLETION OF TAP 04/92 04/92 AS OF FY97 QUARTER 2-O O
O
..m
..m.
,(n-<
em t
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
11 ISSUE NUMBER: 145 TITLE: ACTIONS TO REDUCE COMMON CAUSE FAILURES ORIGINAL CURRENT ACTUAL I
MILEST0NES DATE DATE DATE IhhbEbbkTkkCllbhb bl/95 04)95 CONTRACTOR'S ORAFT FINDINGS 06/92 10/93 CONTRACTOR'S FINAL FINDINGS 09/92 12/93 STAFF *S DRAFT FINDINGS 10/92 11/93 i
DECISION ON STAFF *S FINDINGS 11/92 12/93 DTR TO NRR FOR COMMENTS 04/9 5 04/95 CONTRACTOR PUBLICATION TO JOURNALS 05/95 05/95 NRR PROVIDES COMMENTS ON BNL*S FINDINGS 02/95
.07/95
- i CONTRACTOR CORRECTIONS TO FINAL TS REPORTS 08/95 09/95 FTR COMPLETE 08/95 11/95 i
FTR TO ACRS 09/96 09/97 PRAB PU3LISH CCF METHODS REPORT 04/96 11/97 t
ISSUE CLOSURE MEMO TO EDO 04/96 02/98-
+
t I-F
?
i t
l t
AS OF FY97 QUARTER 2
~
m w.
2.
-?
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
12 ISSUE NUMBER: 148 TITLE: SMOKE CONTROL AND MANUAL FIRE-FIGHTING EFFECTIVENESS IDENTIFICATION DATE: 04/89C PRIORITIZATION DATE: 08/92C TYPE: LI PRIORITY:
TA5K MANAGER: J. CHEN OFFICE / DIVISION / BRANCH: RES /DSR /PRAB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE:
WORK AUTHORIZATION: MEMORANDUM FROM E. S. BECKJORD TO W. MINNERS DATED AUGUST 26, 1992 FIN CONTRACTOR CONTRACT TITLE W0RK SC0PE TO DEVELOP STAFF GUIDANCE FOR THE REVIEW OF LICENSEES
- MANUAL FIRE-FIGHTING EFFECTIVENESS.
IPEEE SUBMITTALS RELATED TO THE EFFECTS OF SMDKE AND STATUS i 5K kk bb5bkkb hb b ib/hkbhibh b ik Fkbkb kh 5bbb hb ik
[PkkkkbHkbbLk$
BEING PREPARED BY SANDIA.
SCHEDULE CHANGED TO CONFORM TO AFFECTED DOCUMENTS PROBLEM / RESOLUTION POSSIBLE NUREG/CR.
" RAFT REVIEW GUIDANCE PLACED IN CONCURRENCE BY TASK MANAGER uN 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 2 O
O O
.. _ m
.._.m_.
..4..m__
......__..---...._......._._..._._.____._-__..,__..._.~_._.m_..-
4 5
J' RUN DATE: 05/23/97'
. t l
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
13 a
s ISSUE NUMBER: 148 TITLE: SMOKE CONTROL AND MANUAL FIRE-FIGHTING EFFECTIVENESS
- L i
?
ORIGINAL CURRENT' ACTUAL
[
MILEST0NES DATE DATE DATE ISSUE FINAL STAFF REVIEW GUIDANCE 09/93 t
{
' ISSUE CLOSE.00T MEMO 06/95
~ i t
. i i
i t
I t
b 6
. i
. I t
i, I
f i
i I
s i
?
r f
I n,
I d
I i
l A
i j.
[
AS OF FY97. QUARTER 2..
l 1
i i
i
-l l
.. ~.
.. I
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
14 ISSUE NUMBER:
155.1 TITLE: MORE REALISTIC SOURCE TERM ASSUMPTIONS IDENTIFICATION DATE: 03/79 PRIORITIZATICN DATE: 02/92C TYPE: GSI PRIORITY:
TASK MANAGER: A. HUFFERT OFFICE / DIVISION / BRANCH: NRR /DRPM/PERB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS: M895B6 RESOLUTION DATE: G3/95C WORK AUTHORIZATION: MEMD FOR W. MINNERS FROM E. BECKJORD DATED 2/26/92 FIN CONTRACTOR CONTRACT TITLE Bb85k bkkL kbb[kkbbkk[bIbFbkHk 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 TbkkTkFkkVikUEbTbkkRhkhbRKbbbbhkkTkkbPkkPkkb bbkhikk[bk[kkbVkhBkR k bkkbkiBkb ik Th CbkM[kk[bh A COMMISSION PAPER AND DECISION LETTER THAT DESCRIBES A PAPER. THE PLAN IS TD REBASELIME TWO NUREG-al50 PLANTS GENERIC IMPLEMENTATION APPROACH. THE STAFF PRESENTED THE AND THEN REVIEW PILOT PLANT APPLICATIONS AND DETERMINE 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 NEI SUBMITTED ITS GENERIC FRAMEWDRK DOCUMENT IN NOVEMBER 1996 TO UPDATE INDUSTRY ON THE STATUS OF NRC*S RLVIEW OF 1995 FOR NRC REVIEW AND APPROVAL. PILOT PLANT APPLICATIONS THE EENERIC FRAMEVORK 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 ALSO 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 SE 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 2 O
O O
S
'].
/
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
15 t
ISSUE NUNBER: 155.1 TITLE: MORE REALISTIC SOURCE TERM ASSUMPTIONS AFFECTED DOCUMENTS PROBLEM / RESOLUTION R.G. 1.3 1.4, SRP 15.6.5 NONE.
R.G.
1.7 1.25 NUREG-1465 ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE IODINE / TID SCHEDULE TO COMMISSION 04/9 0 05/90 PRA BASED SOURCE TERM PAPER TO COMMISSION 05/90 05/90 FISSION PRODUCT TIMING PAPER TO COMMISSION 07/90
.08/90 REVISED BNL DRAFT REPORT 07/90 08/90 TID REPORT SCHEDULE - IODINE CHEMICAL FORM 12/90 07/91 REPORT ISSUED FOR COMMENT PROPOSED REV. TO TID TO RES DIRECTOR 07/91 09/91 i
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 f
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)
ISSUE REVISED TID FOR COMMENT 02/92 07/92 i
AS OF FY97 QUARTER 2 j
\\
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CCNTROL SYSTEM PAGE:
16 ISSUE NUMBER:
155.1 TITLE: MORE REALISTIC SOURCE TERM ASSUMPTIONS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE ISSUE ORNL IDDINE REPORT AS FINAL 04/92 04/92 SNL REPORT ON POOL DF NUREG/CR ISSUED FOR 08/92 09/92 COMMENT ISSUE IEEL REPORT FINAL 08/92 09/92 END COMMENT PERIOD ON DRAFT 'C.,nCE TEkN 08/92 10/92 NUREG RESPONSE TO SRM ON IMPACT OF INCREASED 00/92 11/92 AMOUNT OF RADIATION (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 TO COMMISSION 11/92 02/93 SNL SPRAY NUREG/CR ISSUED FINAL 11/92 06/93 CRNL NUREG/CR ON MELCOR ISSUED 09/93 09/93 SNL REPORT ON POOL OF NUREG/CR ISSUED FINAL 11/92 11/93 ISSUE BNL REPORT FINAL 06/92 11/93 SNL NUREG/CR ON MELCOR ISSUED 11/93 03/94 NEI LETTER 07/94 07/94 BRIEF ACRS 09/94 09/94 COMMISSION MEMORANDUM 09/94 09/94 NEI RESPONSE 09/94 09/94 NEI/NRC MEETING 10/94 10/94 AS OF FY97 QUARTER 2 O
O O
e.
m RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
17
+
+
ISSUE NUMBER:
155.1 TITLE: MORE REALISTIC SDURCE TERM ASSUMPTIONS ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE i
COMPLETE REVISED SOURCE TERM NUREG 11/92 02/95 PUBLICATION OF NUREG-1465 02/95 02/95 ISSUE CLOSEDUT MEMO (L. SOFFER, PROJECT 12/92 03/95 MANAGER. RES/ DST)
NEI/NRC MEETINGS 06/95 06/95 NEI/NRC MEETINGS 10/95 10/95 i
SUBMITTAL OF GENERIC FRAMEWORK DOCUMENT 11/95 11/95 (FROM NEI)
FIRST PILOT PLANT SUBMITTAL 12/95 12/95 i
NEI/NRC MEETINGS 01/96 01/96 PRESENT COMMISSION PAPER IN E-TEAM BRIEFING 08/96 09/96 BRIEF CRGR ON COMMISSION PAPER 09/96 10/96 BRIEF ACRS ON COMMISSION PAPER 10/96 11/96 SEND COMMISSION PAPER TO EDD/ COMMISSION-10/96 11/96 RESPONSE TO DECISION LETTER 11/96 02/97 BEGIN REBASELIMING 11/96 02/97 COMPLETE REBASELINING I
COMPLETE PILOT PLANT REVIEWS t
6 AS OF FY97 QUARTER 2 b
t m.
e
+ e L
- r
-s
- m w
L
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
18 ISSUE NUMBER: 158 TITLE: PERF OF SAFETY-RELATED POWER-OPERATED VALVES UNDER DESIGN BASIS CONDIT IDENTIFICATION DATE: 09/91C PRIORITIZATION DATE: 01/94C TYPE: GSI PRIORITY: M TASK MANAGER: V. LEUNG OFFICE / DIVISION / BRANCH: RES / DER /GSIB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE: 12/97 WORK AUTHORIZATION: MEMORANDUM FROM E. BECKJORD TO J. MURPHY ON JANUARY 26, 1994 FIN CONTRACTOR CONTRACT TITLE h635k kkEL PbhERbPERETEbhki$VkPERFbRMkCk W0RK SC0PE
~~-------------------------------------------------------------------------------------------------------
AIR-OPERATED VALVES. SOLENOID-OPERATED VALVES, AND PROGRAM WILL DETERMINE IF THERE ARE SAFETY-RELATED HYDRAULIC-OPERATED VALVES HAVE NOT BEEN SUBJECTED TO A PROBLEMS, THE SOLUTION OF THE PROBLEMS, AND WHETHER COMPREHENSIVE RISK EVALUATION: HENCE. THESE VALVES LACK THE IMPLEMENTATION OF THE SOLUTIONS ARE COST BENEFICIAL.
REGULATORY SCRUTINY APPLIED TO THE OTHER EQUIPMENT. THIS STATUS PRELIMINARY DRAFT REPORT WAS SUBMITTED BY THE CONTRACTOR AND REVIEWED BY NRR, AFFECTED DOCUMENTS PROBLEM / RESOLUTION WITH THIS ISSUE. A DECISION HAS BEEN MADE TO ENLIST CONTRACTOR ASSISTANCE TO SORT AND CATEGORIZE THE DATA AND ASSIST IN THE RESOLUTION. DATA ANALYSIS COMPLETED BY INEL.
NRR REVIEWED AND COMMENTED ON INEL DRAFT REPORT.
CONTRACTOR REVISING DRAFT REPORT IN RESPONSE TO NRR COMMENTS. SCHEDULE MAY BE DELETED DUE TO ILLNESS OF CONTRACTOR'S PRINCIPAL INVESTIGATOR.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE QbIbKkEVkkhCbMPLkTk Ok)9k 2-Ok)9k ~
AS OF FY97 QUARTER 2 O
O O
(,
\\
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
'19 i
~ ISSUE NUMBER: 158 TITLE:.PERF OF SAFETY-RELATED POWER-OPERATED VALVES UNDER DESIGN BASIS CONDIT ORIGINAL CURRENT ACTUAL-MILE $ TONES DATE DATE DATE PROGRAM PLAN COMPLETE 05/94 05/94 CONTRACTOR SELECTED 06/94 06/94 PROGRAM ASSUMPTION 06/94 07/94 NRC FORM'189 RECEIVED 08/94 09/94 PROPOSAL ACCEPTED 08/94 09/94 DATA ANALYSIS 11/94 06/95 l
MODEL SELECTION 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 07/97 RESOLUTION PACKAGE FOR ACRS/CRGR REVIEW 02/'.'6 10/97 I
ACRS/CRGR MEETINGS 03/96 11/9/
RESOLUTION MEMORANDUM TO THE EDO 04/96 12/97 4
i AS OF FY97 QUARTER 2 t
9 i
k
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
20 ISSUE NUKBER: 165 TITLE: SPRING-ACTUATED SAFETY AND RELIEF VALVE RELIABILITY IDENTIFICATION DATE: 10/92C PRIORITIZATION DATE: 11/93C TYPE: GSI PRIORI'Y: H TASK MANAGER: O. GORMLEY OFFICE / DIVISION / BRANCH: RES / DER /GSIB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE: 06/98 WORK AUTHORIZATION: NOVEMBER 26, 1993 MEMORANDUM FROM E. BECKJORD TO W. MINNERS FIN CONTRACTOR CONTRACT TITLE TBD TO BE DETE TO BE DETERMINED W0RK SC0PE 1.
SELECT OR LOAD PRA*S FOR ANALYSIS IN SARA VERSIONS 4.0 INCLUDING RELIEF VALVES IN THE PRAS.
OR 5.0.
6.
PERFORM COST / BENEFIT ANALYSES TO DETERMINE THE BEST 2.
DETERMINE WHAT SYSTEMS HAVE SPRING-ACTUATED RELIEF FIX FOR THE PROBLEM AND WHICH VALVES SHOULD BE TESTED.
VALVES AND OTHER IMPORTANT INFORMATION BY REVIEWING P& IDS 7.
PREPARE REGULATORY ANALYSIS.
FROM THE SELECTED PRAS.
8.
RESOLVE GSI-165 WITH EITHER THE IMPLEMENTATION OF THE 3.
PERFORM ANALYSIS TO DETERMINE THE EXTENT OF VALVE BEST FIX OR A CLOSEOUT MEMO IF THE COST / BENEFIT IS FAILURE REQUIRED TO FAIL THE SYSTEM IN WHICH THEY OPERATE.
NEGLIGIBLE.
4.
REVIEW LERS TO MORE ACCURATELY 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 CHANGE IN CORE DAMAGE FREQUENCY FROM LICENSE RENEWAL PERIOD OF 20 YEARS.
STATUS kb hbkkb [k hhk PRkV5bbb RhPbRh [Tbh kbP bbbk PPkbIbk kb ThkhPhikG Tb btbbk bbT hbk bSi ibkBkh3LkkhPkkHb SUGGESTED BY THE CONTRACTOR ALLOWED INVESTIGATION OF MORE BEEN OBTAINED, BUT THERE ARE INSUFFICIENT PROJECT FUNDS PLANTS THAN ORIGINALLY ANTICIPATED. THIS RESULTED IN TO PERFORM THE EVALUATION. CONSEQUENTLY, ALL WORK HAS INVESTIGATION OF TWO TYPES EACH OF WESTINGHOUSE AND GE STOPPED. USE OF CARRYOVER MONEY FOR THIS PURPOSE HAS PLANTS AND ONE CE PLANT, LEAVING ONLY B&W PLANTS BEEN ASSIGNED A HIGH PRIORITY, AND WHEN THE NECESSARY UNEVALUATED. CONSEQUENTLY. IT WAS DECIDED TO OBTAIN A FUNDING BECOMES AVAILABLE, PATED ThAT fun'blN Cr WI( l E THE SCHEDULE WILL BE B&W PLANT PRA AND PERFORM THE REQUIRED EVALUATION PRIOR REEVALUATED.IT IS AMTsc_t APPftoVED DMRINCrTHE SItD QTR. OF FY-9'7.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION AS OF FY97 QUARTER 2 O
O O
..-.w.
- - ~.-..- - -. -..- - -.- - -.-- ~--- -.~.- -.
~--..--~-.~~..~.w RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
21 ISSUE NUMBER:
165.
- TITLE: SPRING-ACTUATED SAFETY AND RELIEF VALVE RELIABILITY.
r
(
ORIGINAL CURRENT ACTUAL M I L E 3 T O N E-S DATE DATE DATE' GSI 165 ASSIGNED TO RES/DSIR/EIB 11/93 11/93 i
I DRAFT TAP TO DSIR DEPUTY DIRECTDR 04/94 04/94 DRAFT TAP APPROVED BY DSIR DIRECTOR AND
-06/94 04/94 FORWARDED TO OTHER RES DIVISION DIRECTORS.
AEOD. AND.MRR FOR COMMENT INCORPORATE COMMENTS IN TAP
'08/94 10/94 I
4 FINAL TAD APPROVED BY DSIR DIRECTOR 11/94 12/94
. SUBTASK 1.1 - SELECT PLANTS 12/94
-12/94 SUBTASK 1.2 - REVIEW P&ID*S 02/95 02/95 I
i SUBTASK 1.3 - REVIEW OPERATING EXPERIENCE 02/95 03/95 i
DATA r
l SUBTASK 1.4 - PERFORM FAILURE ANALYSIS 05/95 08/95 I
t TASK 2.- PERFORM RISK ANALYSIS 08/95 07/96 REVISE TAP 02/97 04/97 I
~
TASK 4 - FINAL CONTRACTOR REPORT 12/95 04/97 i
TASK 5 -' PROPOSE ISSUE RESOLUTION-02/96 04/97 TASK 6 - TRANSMITTAL OF **FOR COMMENT" 04/96 04/97 RES0!_UTION PACKAGE TO DET DIRECTOR FOR CONCURRENCE j
TASK 7 - NRR' INTERFACE WITH LICENSEES AND 04/96 04/97 INDUSTRY GROUPS TASK 8 4 NRR COORDINATION PLAN 04/96 04/97 TASK 9 - AE00 COORDINATION PLAN 04/96' 104/97 b
I l
.AS OF FY97 QUARTER 2 I
I l
r
O 2
R E
T RAUQ 7
7 9
9
/
Y 3
F 2 2
/ 2 F
5 L
O 0
AE UT S
TA A
E E CD T G A
A A D P NUR Y
T T
N I
EE h 7
7 7
7 7
8 8
8 8
8 L
RT h 9
9 9 9 9
9 9
9 9
9 RA
/
/
/ /
/
/
/
/
/
/
UD h I
4 7
9 0 1
1 2
4 6
6 BA C
b 0
0 0
1 1
0 0
0 0
0 I
L E
R E
M V
E L
T A
S V
L Y
A S
F NE 6 6
6 7 7 7
7 7
8 8
8 E
IT h 9
9 9 9 9
9 9
9 9
9 L
I GAf
/
/
/ /
/
/
/
/
/
/
O L
ID 5
8 1
2 5 6
0 2
2 5
6 R
E R
b 0
1 0 0 0
1 1
0 0
0 T
R O
N O-O D
C NA T
N Y
E T
M E
E F
G A
A S
R S
N U U)
S T
A D
LCN R
N M
E bNO C
N N
N N
E T
bOI A
O O
O O
M E
A ECT I
IE I
I E
U U
k A "T
D T
TC T T
N R
S T
RR N
U UN U U
O I
S C
OE NS A L
LE L L
I U
I A
hFD ER O
OR O O
T Q
k I
MC R S
SR S S
U E
C G
ESS MA G E
EU E E
L R
I N
HEN O R
S R RC RR R
C R
I S MCO CD C T
N O
S L
E R
bIC N
N L LO LF L
E A
N P
R N
O E
S FL O T
M N N
NS N
I M
G N kO A FR M
I IR IE I
L F
E b W G E O F FO FC F
A M
E 0 FCE "R
G C
F I
N F
L RN FC A F
F FF FS I
O T
T T
NE O K
I F R 0 C I
O O
C E
O T
sbr Lf A
L N LT L LA F C
E A
P B O AC AC A
O N
S E BEE MS TS S U I
L L HOE IG CN A
II I
IA C S
N S
I IOI SK AM O A S
SE SR A I
E MTL NC UM P
NT NH NG UR U
kE RP SC N R RD RO RC SN RS S EGL T I
E P T
T E T I
NE I
kAC N
C O
OC O
O E
T TN T
T S
5KN O
I 2 CI I
L E
N b A( 1T 2B 3 4E 5E 6ER 7E 8E 9E 0 lP 1U 1U 1
1G 1G 1GR 1G 1G 1C 2 E
L P
A A
AU A
A I
KNC KO K K KK KK KKC KK KK KL K kON SS SR S SC SC SCN SC SC S S
5 kIE AE AO A AA AA AAO AA AA AO A 6
hTR TR TF T TP TP TPC TP TP TT T 1
R O
E BM U
N EU 3
S I
m-
\\
\\
V s
RUN DATE:.05/23/97 6
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
23 ISSUE NUMBER: 166 TITLE: ADEQUACY OF FATIGUE LIFE OF METAL COMPONENTS IDENTIFICATION DATE: 04/93C PRIORITIZATION DATE: 06/93C TYPE: GSI PRIORITY:
j TASK MANAGER: K. SHAUKAT OFFICE / DIVISION / BRANCH: RES / DER /GSIB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS: M86344 RESOLUTION DATE: 02/97C WORK AUTHORIZATION: APRIL 1, 1993, MEMORANDUM FROM T. MURLEY TO J. SNIEZEK FIN CONTRACTOR CONTRACT TITLE J2bEi 5N5L~~~~
55EHkid L~ 5555i kC5 iN 5UPPbRT bF IHE~F iiGUE UIIbN PL N
~ ~ ~ ~ ~ ~
~ '
~ ~
~
~
WORK SCOPE
_______._____~_________ __....______._ _______.____________________..__________________..______.. _...._________________..
EVALUATE FATIGUE ADEQUACY OF OPERATING PLANT COMPONENTS. IN THE RES DIRECTOR, RESOLUTION WILL INCLUDE CONSIDERATION OF ACCORDANCE WITH 5/5/94 MEMORANDUM TO THE NRR DIRECTOR FROM A LICENSE RENEWAL PERIOD OF 20 YEARS.
STATU5 i
FATIGUE ACTION PLAN (FAP ACTIVITIES ARE COMPLETE FOR ISSUED ON SEPTEMSER 25, 1995. RES IS CARRYING OUT THE OPERATING REACTORS DURIN LICENSED OPERATING LIFE.
STAFF RESIDUAL WORK UNDER A NEW GENERIC ISSUE GI-190 (MEMO FROM ACTIVITIES AND CONCLUSIONS ARE DESCRIBED IN SECY-95-245 RES TO NRR 08/26/96).
AFFECTED DOCUMENTS PROBLEM / RESOLUTION NUREG/CR-6260 NONE.
l
[
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE t
fiRSh bEEhiNG W5kb~[NbhShRY (PERkbbkCf ~~ ~~
~b9)hb~~
^=
~ Ohhh5~~
f PROGRAMMATIC REVIEW 12/93 12/93.
(
I INFORM COMMISSION (PERIODIC, 6 MONTHS) 04/94 07/94
~
i b
AS OF FY97 QUARTER 2 i
i s
~
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
24 ISSUE NUMBER: 166 TITLE: ADEQUACY OF FATIGUE LIFE OF-METAL COMPONENTS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE DATA COLLECTION AND ANALYSIS 05/94 07/94 RISK ASSESSMENT 03/94 09/94 TECHNICAL ISSUES 05/94 01/95 COMPLETION OF ACTIVITIES FOR OP. LIFE 06/94 09/95 ISSUE TRANSFERRED FROM NRR TO RES 06/96 06/96 CLOSE00T MEMO TO EDO 11/96 02/97 s
D AS OF FY97 QUARTER 2 O
O O
_. ~. _ _
m __
(m RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
25 t
ISSUE NUMBER: 168 TITLE: ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT IDENTIFICATION DATE: 04/93C
-PRIORITIZATION DATE: 06/93C TYPE: GSI PRIORITY:
f TASK MANAGER: G. HUBBARD OFFICE / DIVISION / BRANCH: NRR /DSSA/SPLB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS: M8564B RESOLUTION DATE:
WORK AUTHORIZATION: APRIL 1, 1993 MEMORANDUM FROM T. MURLEY TO J. SNIEZEK i
FIN CONTRACTOR CONTRACT TITLE i
A2336 ANL RISK IMPACT OF EQ E2097 SCIENTECH EQ FOR OPERATING REACTORS WB169 BNL EQ RESEARCH PROGRAM WORK SCOPE 1.
TO GATHER, REVIEW, AND EVALUATE OPERATING EXPERIENCE
-ASSOCIATED WITH EQ ISSUES.
DATA AND EQUIPMENT REPLACEMENT SCHEDULES FOR NUCLEAR POWER IN ACCORDANCE WITH THE S/S/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 i
STATUS BET [LkbShkTbSkNFbRhkh[bhFbRGi56BHSBEENkbBh[hTEbkb bkN Bb Rkbbbkb kh k RkbblT bb Pb8L[b hkkT[hb HELb kb THE COMMISSION IN A MEMORANDUM DATED NOVEMBER 15, 1996.
DISCUSS THE FINDINGS FROM THE LITERATURE REVIEW. PLANNED THE DRAFT PROGRAM REVIEW REPORT ISSUED IN APRIL 1996 RESEARCH TO INVESTIGATE UNCERTAINTIES WITH ACCELERATED i
IS CURRENTLY UNDER MANAGEMENT REVIEW. FOR DATA AGING AND TO REVIEW PROMISING CABLE CONDITION MONITORING COLLECTION AND ANALYSIS THE REVIEW OF EQ-RELATED METHODS BEGAN IN MAY 1996. WYLE LABORATORY WAS SELECTED 1
PUBLISHED DOCUMENTS AND INDUSTRY REPORTS, REVIEW OF TO PERFORM AGING AND LOSS-OF-COOLANT ACCIDENT TESTING.
i 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 EO TEST REPORTS, RESEARCH TESTS. AND ARE EXPECTED IN FISCAL YEARS 1997 AND 1998. OVER THE NEXT OTHER TEST ACTIVITIES ARE COMPLETED. A DRAFT FINAL REPORT SEVERAL MONTHS, SPLB WILL WORK TO CLOSE OUT CERTAIN ITEMS ON EO 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
~
t AS OF FY97 QUARTER 2
RUQ DATE: 05/23/97 GENER2C ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
26 ISSUE NUMBER: 168 TITLE: ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT AFFECTED DOCUMENTS PROBLEH/ RESOLUTION IN 92-81 AMD 93-33.
NONE.
ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE INFORM COMMISSION 05/93 05/93 DATA COLLECTION AND ANALYSIS 08/94 04/96 STATUS REVIEW 02/95 11/S6 RISK ASSESSMENT 10/94 05/97 PROGRAMMATIC REV'EW 06/94 05/97 TECHNICAL ISSUES 10/94 10/98 OPTIONS FOR RESOLUTION IMPLEMENTATION l
AS OF FY97 QUARTER 2 O
O O
1 i
1 N
2
(
. G R
E
- N E
B-
- IE D
T
- ZV E R
NNFL
- YO V,
A E
IOOL
- LR ES U
T I
I
- AP IM O
Q A
NSTW
- NPLVO N
7 D
OIL
- AAAEI 7
'd IVUS NRT S
9
/
R N TESN RTO C E
Y 3
- N O AREO OOI,A T
F 2 7 Y
I R
RI FNTD A
/ 2 T
T ER T IEH C
F 5
L I
S U POAC DLDVC I
O 0
E R U L O
A ELDIU D
U O T O ONS
.SIAES N
S F
I A S COAY
.UW C
I A
E E R T E I
R LER T G P,
P S R RTDO EFIRO R
A A IAET
.BFT F
N L i
D P N
EMNA-
- ANS O P R
hRIL-DTUIS I
A N
U
. TIAU LS I
T P U
B
- FTG U SSS U
R E
NNBE OCTTA L N H
V IOOR CRINB O O G
I AC NME S
I I
T t
EY T IDE E T H
C B
.B N AELIL R
I A
O A
HH CB-
/ S R
SL TTPCA M O O
E P F
L
- )
ONLR UAT -
L E
. TOIO
- AN P E
C)
IWF I, RYE B Y A
V
- L NA ST
- RSUTC O R I
I E
E AI EAAD ETBIC R A R S L
- U RS VUIE
- TN VA P M E G
- F FS ILRE
- IEFI M
T N
U TAEN
- RDOTN U
I
- O P
,R AVT CI CA R E I
- U M
TEIE
- CSA C P T N
A M
Y C
- R RM, N RH
- MCNEM
. 6 EYCT
- IAORR 9
E E T A Y
- U GA ST
- R I
O
/
T G
T
- B OR EEED
- EYSNF 4
S A
I
.RG RFGN
- TTNO
. 0 Y
M V
E-H PO
- NIE O PAAA.
S A
T"L I
L-G R
- IVTNT I
D T-I EP R A
,D IXO E
L' CE I - H LV
- GDKE
- RTEID N
O L
B AU T-EIE YN RN
- OC 7N R
E S
EF
- R UTV E RILOI FARAU E
T U
P R
T.
O FAI TSEWM EEMO H
N F
/
"P C SF RT P SSU R
- SRHRF T
)
O U
AT PEA UEFSE I
TO C
D R
,N R NTSUPR D DS IT SERFD N
S 4R T ENTNOE NSFHE S AHUNN T
A D
9U N MENROP C IAOTD BTFIA N
/
/B O EMEUCO U-E S
9 C.OOS VPIB(O M
T C S
/H C
T-E N 5 E 1G RLNHT(
G E 9 R 1I PEAGS A-A I
/
H
- MVRIET K-N S
I N
- IETHTS
- D H T-
~
A N O H OR
- D E
R-E CH M
A C
O E YFLT E RCH S-D E A R
N RF DLTOE D-N ART EE BY E
T E A O
- OEI UL
- N EAI
- GS TE U
T R LA CDVYFE W AR SEW AU LED S
Y A B YI OIG U
,E ES
- M LFI S
T D /
I N
TE O CUU DUE RL DI WSO V N O
.I IDALNP E H E
- RR R
R VNELRU MRT.LH LEOTRP C
I O
I I
T I
S JC
- AARAUN
- RE SA
- ETJAA R
C T I
- H TBR OISPNE
- UIAHEL E
A A V ME
- EUFE U
- FLSUOS FRMTLL N
E Z I
- BEOMHB RRENI
- C CI E
R I
D RA I
G EASRTL F LSUW G
T /
FM DVSGIH PESUAL
- OELTN I
E A
- OEINHG ABNI
- HAN S E R C SD RRSI I
R YDIH AAOHE E
M* E T
I F
EL LALDR W TGTS BN 5CP S
=
I R F NE ETAABR
- D INN MOSSRA T
T P O OU
- UANLAG TESHIO U TENP N
IF FDACCI NTN -
I NDNS E
S EPOTMS EESEE M
SD MOIAOS ASDAHS U
IN SDT RU UI TE C
MA SACAFC SCCA H O
M E AI S SOCTFT D
OS R-ST RSI EFAAO CT O-SALETD S
O T D
N T-AHATL SNY EA E
C OE C-TNIU AETGUH T
5 TI A-Y ORS EINST C
9 S
R-TDICED OBVIS E
/
ON TL EET RE T IRID F
I MA N ELLLAC FPIE Z
- STA E F
O R ER O NNNNER AODGDY YACPLT
'A E
MT C.IPBACR SLDANL AHAEAC 7
- Y 6
- EAMAA W ERIE 7
E E 5 YV A
,N RNRPCP 0 T M 2 h REDD A
EO EX 1
m 7 A 1
c ADE D DIEEPE 1
D 9
I N NLEE NTHRS E
R M T ISIEMB UNTA S D
N A
MAFUR E
AI I
- O Z
IWEFOL STGS U
R I
R I
- L D FL ITNRNT G
g E T E S R
- EN FRI AIOII
(
B A G R O 402370
- RADOEW K
,Z T Y
M C A E H N 908890
- PLN P R
YAD R
U I
N B T I
123445
- PAY S OALGE.
O N F A M U F 6666G6
- A CEM WIAIHL T
I M U A WWWWWW
- NRABA
- RNTSA A
E T N
- ROEU R EEASIN L
U N K K
- EITQLG LT ELR U
S E S C R
- TTTELO IIRVBU G
S D A A O
- FCEDIR HRONUO E
I I
T T W
- AALAWF WCFIPJ R
4 l
O 2
R
- O E
- ET S
H T
- C R NC R
- AN VE A
U
- CO 1Y DE O
- II ES 7
- FT UL SE 7
9
- IAELA AR 9
/
- NUBCR B Y
3
- GL NE N
F 2 8
- IATOV.NR
/ 2
- SVOCETOE F
?
L EN SRIT L
O 0
E
- Y NT OT AE 3 4 4 4 4 4
4 4 5 5
5 U
- TSAARPIR UT 9 9 9 9 9 9
9 9 9 9
9 S
F
- EECHOPSE TA / / /
/ /
/
/ / /
/
/
A E E
- FR TFUOG CD 0 3 8 9 0 0
1 1
1 3
9 T G P
- A E SPN A - 1 0 0 0
1 1
1 1
0 0
0 A A U
N SESDE O
D P N
O-HANLSML R
I - WTBABEI N
U TO ARRG U
B UL AAL EN R
L-
.TIIDTI H
O NEARANNT G
S OCDEVAII I
E-N TA A
H R DETI YNW
/ ERNRERAA T
R M SRECBT N
O E AUR SPE EE-F L BCRDTUOL RT- - - -
B-CUEODLI RA- - - -
A O-
,OCSNNEH UD-I RN A IVW C
R P OFEBL E E
- IOH LLDN T
- T TNIA O I
- CY GWIOI R
- ATTI TTT C
IASAN A M
- YLHETAEM E
E
- RITDATVR V
G
- TB DSAO S
A
- SAEO BHF L
Y M
- UBTTLU N A -
S A
- DOA ASYI NE 3 4 4 4 4 4
4 4 5 5
5 D
- NRCDT A IT 9 9 9 9 9 9
9 9 9 9
9 L
- IPIENHME GA / / /
/ /
/
/ / /
/
/
ID 0 3 8 9 0 0
1 1
1 3
9 O
L DT tT L.
R E
- RWNAMIRBS R
- 1 0 0 0
1 1
1 1
0 0
0 T
U
- EOILIWRAT O
N F
- HL ER NLL O
O
- T EREN IU C
D
- RDTRPE AS N
- UNAOXV VE T
A
- FADCEE AR N
E S
M T
E N
G E
A I
N S
A N
M A
R T
R O
O A
N E
T T
T T
E U
C A
I S
Y A
S N
D S
S T
L E G
L I
N I
I
)
E R N
E G
A V
4 U
I U
N N
R C
I 6
F R T
F O
I T
I T
E E
I D
R C
5-4 F T E
P T
I E
E A
9 U A M
U A
V H
N E
ES N W N
T O
T E
R
- E N
R Y
R N
R L
G
(
B A T
B M
OU NR I
U T R
U E
P NE E
0O S
U F
L
- T E
H A U
H C
1 G
T S-T-
S CA G T D
G S O NP A
N I
R D I
T-
- R E IT I
IU T
N-SE R TA H D I
H O L
TN E-
- T OO D R P
ER M-ET Y N N P E
N N O P
EU U-
- E B A O U T
O E F U
MB C-LL NI N
A V
SR O-D OR R R N
R D
E SH D-I - D E I
E U IS E O E
.T TG
- E U TW P BG DN P T I
6E IH E-
- N S MN P HI OI P R I
L L T-I R
GT OT E T 4
AF C-
- R OG N IE CC N T N3 9R IO E-
- E S FN O HE /A O T E3 O C F-
- S T NI I
M E I
E D9 ND ER F-
- U C IC S T LS S L I0 IN PO A-A N S NY US S E SI
- E R EU I
E EG EV V
- S N SN M EF HS M S SR SD NH 0
- S O SN O RA CI O S SU SN SF 7
IN IA CB 1
- 2
- 4 R
6 O
E
- N4 B
- O M
- I0 U
- T54 N
- C 6
- ER-E
- SF4 U
- C9 S
- P S
- R0N I
S1I
p K.
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL' SYSTEM PAGE:
29 ISSUE NUMBER: 170 TITLE: REACTIVITY TRANSIENTS AND FUEL DAMAGE CRITERIA FOR HIGH BURNUP FUEL.
ORIGINAL CURRENT ACTUAL MILES.T0NES DATE DATE DATE REVIEW INDUSTRY MEI RESPONSE 09/9 5 09/95 ASSESS EFFECTS ON DESIGN BASIS ACCIDENTS OF 09/95 09/95 REDUCED FAILURE THRESHOLD FOR HIGH BURNUP FUEL WATER REACTOR SAFETY INFORMATION METING ON 10/95
'10/95 HIGH BURNUP COMMISSION PAPER ON HIGH BURNUP FUEL 03/96 03/96 ACRS BRIEFING BY RES 04/9 6 04/96 CSNI EXPERTS MEETING ON TRANSIENT BEHAVIOR 05/96 05/96 0F HIGH BURNUP FUEL-INITIATE RESEARCH PROGRAM ON LOCA CRITERIA 09/96 09/96 AT HIGH BURNUP WATER REACTOR SAFETY INFORMATION MEETING ON 10/96 10/96 HIGH BURNUP FUEL CORE PERFORMANCE ISSUES WORKSHOP WITH 10/96 10/96 INDUSTRY COMMISSION PAPER ON HIGH BURNUP FUEL 11/96 11/96 ISSUES RIL WITH TECH BASIS FOR INTERIM RIA 12/96 03/97 ACCEPTANCE CRITERIA COMMISSION BRIEFING ON HIGH BURNUP 03/97 03/97 FUEL-DEVELOP INTERIM RIA ACCEPTANCE CRITERIA 12/96 04/97 ISSUE GL TO DEFINE INTERIM RIA CRITERIA AND 02/97 04/97 REQUEST EVALUATION ISSUE LETTER TO NEI. ASSESSING INDUSTRY 09/9 6 04/97 ACTIONS AS OF FY97 QUARTER 2
RUN DATE: 05/23/97
-GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
30 IS$UE NUMBER: 170 TITLE: REACTIVITY TRANSIENTS AND FUEL DAMAGE CRITERIA FOR HIGH BURNUP FUEL ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE MOU WITH EPRI FOR COOPERATION ON LOCA 04/9 7 04/97 CRITERIA HOU WITH DOE FOR COOPERATION ON LOCA 04/97 04/97 CRITERIA ACRS SUBCOM.1ITTEE MEETING ON HIGH BURNUP CS/97 05/97 FUEL SPECIAL ISSUE OF NRC*S NUCLEAR SAFETY 06/97 06/97 JOURNAL ON RIA RESEARCH CLOSEOUT MEMO TO THE EDO AS OF FY97 QUARTER 2 9
O O
f) f%
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT-CONTROL SYSTEM PAGE:
31 ISSUE NUMBER: 171 TITLE: ESF FAILURE FROM LOOP SUBSEQUENT TO LOCA IDENTIFICATION DATE: 02/95C PRIORITIZATION DATE: 06/95C TYPE: GSI PRIORITY: H TASK MANAGER: A. SERKIZ OFFICE / DIVISION / BRANCH: RES / DER /GSIB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE: 12/97 WORK AUTHORIZATION: MEMORANDUM TO L. SHA0 FROM D. MORRISON ON JUNE I6, 1995
-FIN CONTRACTOR CONTRACT TITLE W6617 BNL EVALUATION OF SAFETY ISSUE 171 PRIORITIZATION ASSUMPTIONS W0RK SC0PE INITIAL SAFETY ISSUE EVALUATIONS RESULTED IN RANKING THE PRIMARY DBJECTIVE OF THIS BNL STUDY IS TO REVIEW AND GSI 171 AS "HIGH."
THIS EVALUATION WAS BASED ON CONSERVA-EVALUATE ASSUMPTIONS RELATED TO THE PROBABILITY OF NON-TIVE ASSUMPTIONS REGARDING FAILURE RATES, EQUIPMENT DAMAGE RECOVERABLE DAMAGE TO EDG*S AND ECCS PUMPS USED IN THE AND NONRECOVERY FROM POTENTIAL OVER-CURRENT LOAD EFFECTS.
INITIAL ISSUE PRIORITIZATION.
l STATU$
BNL'S ANALYSIS IS NEARING COMPLETION AND THE RESULTS SHOW ACTION. UPON COMPLETION OF STAFF REVIEW. BNL*S REPORT WILL 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 RE UEST LICENSEE CONFIRMAlION THAT THE PLANT HAS BEEN ADEQUA ELY 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.
i
?
I AS OF FY97 QUARTER 2 e
_ = _ =. = _ _
. m
-m--
RUN DATE: 05/23/97 GENERIC XSSUE MANAGEMENT CONTROL SYSTEM PAGE:
32 ISSUE NUMBER: 171 TITLE: ESF FAILURE FROM LOOP SUBSEQUENT TO LOCA ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE ISSUE TASK ACTION PLAN 12/95 12/95 INITIATE INDEPENDENT EVALUATION 01/96 02/96 BNL TASK 1 RESULTS 03/96 07/96 BNL TASK 2 RESULTS 04/96 07/96 BNL TASK 3.1 09/96 09/96 BNL TASK 3.2 10/96 10/96 BNL TASK 3.3 11/S6 12/96 UPDATED SAFETY EVALUATION (DRAFT) 09/96 12/96 BNL TASK 4 (NUREG/CR) 03/97 04/97 REEVALUATION OF SAFETY ISSUE (DRAFT 11/96 04/97 NUREG/CR)
DRAFT CRGR PACKAGE (INCLUDES GENERIC LETTER) 11/96 04/97 CRGR AND ACRS REVIEW 12/96 05/97 CONCLUDING REVISIONS AND ACTIONS 02/97 06/97 ISSUE GL FOR PUBLIC COMMENT 04/97 07/97 COMMENT PERIOD ENDS 11/97 11/97 REVISE GL AND ISSUE 12/97 12/97 CLOSEOUT MEMO TO EDO 06/97 12/97 AS OF FY97 QUARTER 2 O
O O
vg 6
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT. CONTROL ' SYSTEM
~ PAGE:
33 ISSUE NUMBER: 172 TITLE: MULTIPLE SYSTEM RESPONSES PROGRAM'
. ?
IDENTIFICATION DATE: 07/9IC PRIORITIZATION DATE: 12/95C TYPE: GSI PRIORITY:
b
. TASK MANAGER: M. CUNNINGHAM
_ OFFICE / DIVISION / BRANCH: RES /DSR /PRAB ACTIN LEVEL: ACTIVE STATUS: MR TAC NUMBERS:
RESOLUTION DATE: 12/98 i
WORK AUTHORIZATION: MEMORANDUM TO D. MORRISON FROM L. SHA0 DATED AUGUST 2. 1995 l
FIN CONTRACTOR CONTRACT TITLE i
WDRK 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 i
PRO 8LEM/ RESOLUTION AFFECTED DOCUMENTS MUREG/CR-5420 NOME.
MILEST0NES DATE DATE DATE:
^
ORIGINAL' CURRENT ACTUAL kbb kkhPbNhk hb Ckk bf3f96 LETTEk bh96 bbf9h f
COLLECT DATA AND PREPARE
SUMMARY
REPORT 12/98 12/98 I
TO ACRS i
CLOSE OUT ISSUE WITH MEMORANDUM TO EDO 12/98 I2/98-i P
AS OF FY97 QUARTER 2 l
.__ _ _______- _ _ _ _ _ - _ _ _ _ - _ _ _ - _ - - _ _. = _ _ _ _ _ _ _ _ _ - - _ _ _ - _ _ _ _,
.. - =
QUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
34 ISSUE NUMBER:
173.A TITLE: SPENT FUEL STORAGE POOL: OPERATING 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: H68094 RESOLUTION DATE: 10/98 WORK AUTHORIZATION:
FIN CONTRACTOR CONTRACT TITLE W0RK SC0PE SPECIFIC ACTIONS INCLUDED IN PART A 0F THE GENERIC ACTION PLAN ARE: (I) DETFChfNATION OF THE SAFETY ACTIONS TO ADDRESS SIGNIFICANT ISSUES AT OPERATING AND PERMANENTLY SHUTDOWN FACILITIES. BASED ON FINDINGS FROM SIGNIFICANCE OF IDENTIFI' D CONCERNS, (2) DETERMINATION THESE REVIEW AREA $ AND THEIR RISK SIGNIFICANCE, THE STAFF OF THE FACILITIES WHERE THE CONCERNS MAY BE APPLICABLE.
WILL DEVELOP CRITERIA FOR SPECIFIC SPENT FUEL PDOL EVALUATION OF THE ADEQUACY OF PRESENT SFP DESIGNS.
OPERATIONS FOR POTENTIAL USE IN FORMULATING GENERIC EVALUATION OF THE A3E00ACY OF CURRENT NRC GUIDANCE FOR COMMUNICATIONS, REVISIONS OF REGULATORY GUIDANCE. AND DESIGNS, AND (5) EVAeJATION OF THE NEED FOR GENERIC OTHER APPROPRIATE REGULATORY ACTIONS.
STATUS THE ACTION PLAN IS CLOSED. TASKS FOR RESOLUTION WILL
- 2) CONDUCT PLANT SPECIFIC REGULATORY ANALYSIS FOR BE TRACKED SEPARATELY. RESOLUTION COMPRISED OF THREE PARTS:
MARDWARE BACKFITS AT SELECTED SITES:
I) CONDUCT REGULATORY ANALYSIS TO EVALUATE JUSTIFICATION
- 3) UPDATE REGULATORY GUIDANCE.
FOR IMPOSING FUEL STORAGE POOL OPERATIONS RULE:
AFFECTED DOCUMENTS PROBLEM / RESOLUTION IN 93-83 AND SUPPLEMENT 1 IN 94-38 NONE ***
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE TAP APPROVED 10/94 10/94 AS OF FY97 QUARTER 2 O
O O
h, ~
(
U O<~g.
p A
RUN DATE: 05/23/97 I
GENERIC ISSUE' MANAGEMENT CONTROL. SYSTEM PAGE:
35 ISSUE NUM8En.
173.A TITLE: SPENT FUEL STORAGE ~ POOL: OPERATING FACILITIES k
ORIGIRAL CURRENT ACTUAL MILEST0NES DATE DATE DATE e
' REVIEW EXISTING NRC GUIDANCE AND 08/94 08/94 REQUIREMENTS 3
IDENTIFY SIGNIFICANT SFP CONCERNS 12/94 12/94 I
I REPORT SIGNIFICANT SFP PROBLEMS TO NRR 12/94 12/94 MANAGEMENT DEVELOP AN SFP INSPECTION PLAN 01/95 01/95 i
CONDUCT INSPECTIONS OF SELECTED PLANTS 06/95 06/95
[
EVALUATE AND REPORT RESULTS OF INSPECTIONS 09/95 09/95 COMMISSION BRIEFING ON SFP ISSUES 02/96 02/96 i
COMMISSION BRIEFING ON SFP ISSUES 04/96 04/96
[
ASSESS RISK / SIGNIFICANCE OF INDIVIDUAL 06/96 07/96 i
CONCERNS
.I ASSESS MONITORING OF POTENTIAL OFFSITE 06/96 07/96 RELEASES ASSESS RADIOACTIVE-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 08/96 08/96 REG. ANALYSIS FOR RULE 05/97 05/97 PLANT-SPECIFIC REG. ANALYSIS FOR HARDWARE 05/97 08/97 BACKFITS AT SELECTED SITES REVISE R.G.
1.13 10/98 10/98 g
i t
AS OF FY97 QUARTER 2 l
I l-
~
RUN DATE: 05/23/97 i
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
36 ISSUE NUMBER:
173.A TITLE: SPENT FUEL STORAGE POOL: OPERATING FACILITIES ORIGINAL CURRENT ACTUAL 6
M1LEST0NES DATE DATE DATE REVISE SRP 9.1.2. 9.1.3 10/98 10/98 I
t 1
I
't i-i AS OF FY97 QUARTER 2 t
0 0
O
m _
_m.
b pm m
\\
RUN DATE: 05/23/97 i
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
.37 ISSUE NUMBER:
173.B TITLE: SPENT FUEL STORAGE POCL: PERMANENTLY SHUTDOWN FACILITIES IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE: 06/96C TYPE: GSI PRIORITY:
TASK MANAGER: S.' JONES OFFICE / DIVISION / BRANCH: NRR /DSSA/SPLB.
ACTION LEVEL: ACTIVE STATUS: NR b
TAC NUMBERS: M40004 M90441 M93805 RESOLUTION DATE: 10/96C WORK AUTHORIZATION:
FIN CONTRACTOR CONTRACT TITLE WDRK SC0PE
-f SPECIFIC ACTIONS INCLUDED IN PART B 0F THE GENERIC AND IMPLEMENTATION OF ADDITIONAL REQUIREMENTS SPECIFICALLY l
ACTION PLAN ARE: (I) THE DETERMIf,ATION OF SIGNIFICANT APPLICABLE TO PERMANENTLY SHUT DOWN FACILITIES WITH IDENTIFIED CONCERNS FROM PART A APPLICABLE TO STORED, IRRADIATED FUEL.
PERMANENTLY SHUTDOWN FACILITIES AND (2) THE EVALUATION STATUS THE STAFF DETERMINED THAT.ALL SIGNIFICANT IDENTIFIED FACILITIES. STAFF RESOURCES WILL BE TRACKED THROUGH CONCERNS FROM PART A APPLICABLE TO PERMANENTLY SHUTDOWN TACS ASSIGNED TO THE ASSOCIATED ACTION PLANS.
FACILITIES WERE ENCOMPASSED BY THE SPECIAL INSPECTION THE GENERIC ACTION PLAN FOR PART B. PERMANENTLY ACTIVITIES. THE SPECIAL INSPECTIONS FOUND NO SIGNIFICANT SHUTDOWN FACILITIES (ISSUE 173.B), WAS CLOSED WITH THE DEFICIENCIES OTHER THAN AT DRESDEN I.
IN RESPONSE TO THE RESOLUTION
SUMMARY
IN THE OCTOBER 1996 DIRECTOR'S MONTHLY-DRESDEN I SPECIAL INSPECTION FINDINGS. PDND WILL PROCEED STATUS REPORT OF THE OFFICE OF NUCLEAR REACTOR REGULATION i
WITH ISSUANCE OF THEIR DECOMMISSIONING ACTION PLAN.
THE IN ACCORDANCE WITH NRR OFFICE LETTER NO. 504 " PROCEDURE DIVISION OF SYSTEMS SAFETY AND ANALYSIS WILL PROVIDE FOR DEVELOPMENT, IMPLEMENTATION, AND MANAGEMENT OF ACTION TECHNICAL SUPPORT FOR THAT ACTION PLAN AND OTHER EXISTING PLANS."
ACTION PLANS ASSOCIATED WITH RULEMAKING FOR DECOMMISSIONING i
AFFECTED DOCUMENTS PROBLEM / RESOLUTION
[
IN 94-38 NONE BULLETIN 94-01 t
i AS OF FY97 QUARTER 2
[
t
=
=----.
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
38 ISSUE NUMBER:
173.B TITLE: SPENT FUEL STORAGE POOL: PERMANENTLY SHUTDOWN FACILITIES ORIGINAL CURRENT ACTUAL MILE $T0NES DATE DATE DATE TAP APPP.0VED 10/94 10/94 IDENTIFY SIGNIFICANT SFP CONCERNS 11/95 11/95 APPLICABLE TO PERMANENTLY SHUT-DOWN FACILITIES DECISION DN RULE OR OTHER GENERIC 09/96 09/96 ACTIVITY CLOSE OUT PART B 0F ACTION PLAN 09/96 10/96 AS OF FY91 QUARTER 2 I
O 9
9
- x
,/
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
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:
TAC NUMBERS: M86716 M86717 RESOLUTION DATE:
WORK AUTHORIZATION: MEMO FROM T. MURLEY TO J. TAYLOR ON JULY 22, 1993 FIN CONTRACTOR CONTRACT TITLE W0RK SC0PE AhEbhbRkRhkNkTRUbhkbhHkSBEEkDhVELbPEbFbRkNSPEbTbRS TkbNS WERhEVLbkTEbkbDETERMkNb[F bkbkbbTb 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 SURVIVABILITY OR RAPID REACTOR FACILITIES BETWEEN FEBRUARY AND JUNE 1996.
DATA RECOVERABILITY OF THESE CIRCUITS FROM A SEVERE NATURAL COLLECTED FROM THOSE INSPECTIONS, AS WELL AS PAST INSPEC-EVENT.
STATUS ITEM 1 A TEMPORARY INSTRUCTION (TI 2515/131)
THROUGH 06/30/96.
IssukD01/1/96 INCORPORATING REGIONAL COMMENTS, HAS BEEN (ITEM 2) THE ACTION TO PROVIDE GUIDANCE FOR INSPECTORS WRITTEN TO PROVIDE REGIONAL INSPECTORS GUIDANCE FOR HAS BEEN INCORPORATEO 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 02/01/96 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 INSPECTION PROCEDURE 82701.
AS OF FY97 QUARTER 2
RON DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
40 ISSUE NUMBER: 178 TITLE: EFFECT OF HURRICANE ANDREW ON TURKEY POINT ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE TAP APPROVED 07/93 07/93 EVAL THE ADEQUACY OF NRC GUIDANCE FOR REVIEW-05/96 05/95 ING LICENSEE PREPARATION & RESPONSE TO NATUR-AL DISASTERS & INDUSTRY PREPLANNED SUPPORT COLLECT INFORMATION ON LICENSEE COMMUNICATION 07/96 06/96 CAPABILITIES AND VULNERABILITIES VIA REGION INSPECTION ANALYZE INSPECTION FINDINGS AND REPORT ON 10/9E 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 t
AS OF FY97 QUARTER 2 O
O O
,(v; s
s v
v RUN OATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
41 ISSUE NUM3ER: 179 TITLE: CORE PERFORMANCE IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE: 06/96C TYPE: LI PRIORITY:
TASK MANAGER: E. KENDRICK OFFICE / DIVISION / BRANCH: NRR /DSSA/SRXB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M91257 M91602 M9S671 RESOLUTION DATE: 12/97 WORK AUTHORIZATION:
FIN C0bTPiCTOR CONTRACT TITLE J2029 PNL CORE PERFORMANCE EVALUATION
' ACTION PLAN SUPPORTi J2512 PNL CORE PERFORMANCE EVALUATION JACTION PLAN SUPPORTh J2513 PNL CORE PERFORMANCE EVALUATION JACTION PLAN SUPPORTh L1351 PARAMETERS CORE PERFORMANCE EVALUATION LACTION-PLAN SUPPORT?
TBD TO BE DETE TO BE DETERMINED W0RK SC0PE hPhb[ Fib EbTkbhb [kbLbbEb kk THk bTfbk PL k RE bbb - THE kT[bkPLkk[bEkTkFfEbbkEbRMbRbLkCEkSEE (1) EVmLUATE FUEL VENDORS PERFORMANCE THROUGH PERFORMANCE-INSPECTIONS IN LACH REGION THAT SHALL BE PERFORMED, IN BASED INSPECTIONS THAT EVALUATE THE RELOAD CORE DESIGN.
COORDINATION WITh THE REGIONAL INSPECTORS, TO ASSESS SAFETY ANALYSIS, AND LICENSING PROCESS. FUEL ASSEMBLY f ICENSEE PERFORMAheF IN RELOAD CORE ANALYSIS OVERSIGHT AND MECHANICAL DESIGN, AND FUEL FABRICATION ACTIVITIES, PARTICIPATION. I.iLZNSEE INSPECTIONS WILL NORMALLY BE ISSUE-(2) EVALUATE THE PERFORMANCE OF LICENSEES THAT PERFORM CORE DRIVEN, BUT A TOTAL LT 10 LICENSEE / VENDOR INSPECTIONS IS RELOAD ANALYSIS FUNCTIONS, (3) IDENTIFY, DOCUMENT, AND BUDGETED FOR FY '97.
THE DATA ACQUIRED THROUGH LICENSEE /
CATEGORIZE CORE ?irf0RMANCE PROBLEMS AND ROOT CAUSE 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 UATED FOR GENERIC CORE PERFORMANCE INDICATORS AND INDUSTRY REGIONAL ENFORCEMENT ACTIONS AS APPROPRIATE, (4) TRAIN AND CONFORMANCE TO CURRENT REGULATORY REQUIREMENTS. THE END COORDINATE REGIONAL SUPPORT STAFF PARTICIPATING Ih THESE PRODUCT OF THE OVERALL ASSESSMENT WILL INCLUDE GUIDANCE FOR ACTIVITIES, AND (5)ING GENERIC COMMUNICATIONS, EVALUATE THE RESULTS OF THESE ACTIVITIES RESIDENT INSPECTORS AND REGIONAL STAFF. THESE ACTIVITIES FOR USE IN FORMULAT REVISIONS OF ARE SCHEDULED TO BE COMPLETED IN FY '97.
THE ONGOING REGULATORY GUIDANCE AND 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 BE UPDATED TO REFLECT THE LIVING PLAN.
OF CONTROL RODS TO FULLY INSERT, THE ACTION PLAN IS BEING DISP - THE ACTION PLAN IDENTIFIES 10 VENDOR INSPECTIONS EXTENDED THROUGH 1997 AND EXPANDED TO REVIEW THE ADEQUACY OF THAT SHALL BE PERFORMED BY MULTI-DISCIPLINED INSPECTION VENDOR LEAD TESTING PROGRAMS FOR NEW FUEL DESIGNS (TASK 6)
TEAMS, LED BY THE SPECIAL INSPECTION BRANCH (PSIB), WITH AND TO CONDUCT A WORKSHOP DN CORE PERFORMANCE ISSUES CONTRACTED TECHNICAL ASSISTANCE. THESE INSPECTIONS BEGAN IN (TASK 7) Ih
,?" 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 AS OF FY97 QUARTER ?
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
42 ISSUE NUMBER:
179' TITLE: CORE PERFORMANCE STATUS AND IDENTIFICATION OF EMERGING 2SSUES. AN ISSUE-DRIVE WERE PRESENTED TO THE EDO IN SEPTEMBER 1996.
VENDOR INSPECTION AT GE WAS CONDUCTED IN MAY 1996 SUPPORTED DISP - THE INSPECTION OF FRAMATOME COGEMA FUELS BY SRXB/DSSA STArF AND CONTRACT SPECIALISTS IN RELOAD (FORMERLY BABCOCK AND WILCOX FUEL COMPANY). LOCATED IN DESIGN.
INTERACTION WITH THE REGIONS IS ONGOING TO GENERATE LYNCHBURG VIRGINIA. OCCURRED IN MARCH ANO APRIL 1996.
A LICENSEE INSPECTION SCHEDULE. SRXB PARTICIPATED IN THE THE REMAINING PLANNED ISSUE-DRIVEN INSPECTIONS INCLUDE ABB REGION I INSPECTOR COUNTERPARTS MEETINGS IN DECEMBER 1995 CONBUSTION ENGINEERING *S SUPPLY OF A BWR TRANSITION CORE AND MAY 1996.
DSSA IS REEVALUATING THE ACTION PLAN TO RELOAD FOR WNP-2 AND A COMPREHENSIVE FOLLOWUP INSPECTION BETTER INTEGRATE AND PRIORITIZE ITS ACTIVITIES. OPTIONS AND OF SIEMENS POWER CORPORATION ISSUES.
RECOMMENDATIONS WERE PROVIDED FOR MANAGEMENT REVIEW AND AFFECTED DOCUMENTS PROBLEM / RESOLUTION ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE INSPECT SPC (PWR AIT FOLLOVUP) 06/94 06/94 INSPECT ZION RELOAD ANALYSIS 10/94 10/94 INSPECT ABB/CE (PWR RELOADS) 11/94 11/94 INSPECT TELEDYNE-WAH CHANG (TWC) 12/94 12/94 INSPECT SANDVIK SPECIALTY METALS (SSM) 12/94 12/94 INSPECT DUKE RELOAD ANALYSIS 03/9 5 03/95 INSPECT VESTINGHOUSE 07/95 07/95 INSPECT GE 10/95 10/95 INSPECT THI-1 RELOAD ANALYSIS 12/95 12/95 IDENTIFY ISSUES FOR CORE PERFORMANCE 06/96 06/96 WORKSHOP AS OF FY97 QUARTER 2 O
O O
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
43 ISSUE NUMBER: 179 TITLE: CORE PERFORMANCE ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE
.DATE INSPECT GE (SLMCPR & LOW DENSITY PELLETS) 07/96 07/96 INSPECT FRAMATOME/COGEMA (B&W FUELS) 08/96 10/96 CONDUCT CORE PERFORMANCE WORKSHOP 10/96 10/96 COMPREHENSIVE REINSPECTION OF SPC 02/97 04/97 INSPECT ABB/CE BWR (WNP-2 TRANSITION CODE) 10/96 06/97 INSPECT REGION I LICENSEE (S) 03/97 12/97 INSPECT REGION II LICENSEE (S) 06/97 12/97 INSPECT REGION III LICENSEE (S) 09/97 12/97 COMPLETE CORE *ERFORMANCE EVALUATION 12/96 12/97 l
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 l
CLOSE OUT ISSUE 12/97 12/97 e
t-i i
AS OF FY97 QUARTER 2 i
1 t
RUN DATE: OS/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
44 ISSUE NUMBER: 18I TITLE: FIRE PROTECTION IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE: 06/96C TYPE: LI PRIORITY:
TASK MANAGER: D. OUDINCT OFFICE / DIVISION / BRANCH: NRR /DSSA/SPLB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M866S2 M82809 M84S92 M85142 M89SO9 RESOLUTION DATE: 09/97 WORK AUTHORIZATION:
FIN CONTRACTOR CONTRACT TITLE WORK SC0PE TkkFPTkPTRkCKShHEkkPLEkEkhkh[bkbFkhDkRkkGEbF h5THkkPkkk[5bkTkkFfkkPkbTkbh[bhFbkbTibbkL[kkPEbh[Nb TECHNICAL AND PROGRAMMATIC FIRE PROTECTION ISSUES. IT (FPFI) PROGRAM AND CENTRALIZING THE MANAGEMENT, BY NRR, OF INCLUDES RECOMMENDATIONS FOR ACTION (PART I), RECOMMENDA-THE FPF: PROGRAM AND ALL OTHER REACTOR FIRE PROTECTION TIONS F(P FURTHER STUDY (PART II), CONFIRMATION ISSUES WORK. THE PRINCIPAL OBJECTIVE OF THESE EFFORTS IS TO ENSURE (PART iia i. AND LESSONS LEARNED (PART IV).
THE STAFF IS THAT THE NRC HAS A STRONG, BROAD-BASED AND COHERENT FIRE IMPLEMENTIN9 THE RECOMMENDATIONS, IN PRIORITY ORDER, AS PROTECTION PROGRAM WHICH IS COMMENSURATE WITH THE SAFETY RESOURCES ALLOW.
THE STAFF FOCUS IS NOW ON IMPLEMENTING ITS SIGNIFICANCE OF THE SUBJECT.
PLAN FOR FUTURE DIRECTION OF THE NRC FIRE PROTECTION PROGRAM STATUS hklkTkFbbkPkkhkbkbb[TfbkLkkELLkbkLkF[kkTkkhk TkE bVikbkYbbkk[hhkkbkkkbhbRkFkGbkbh~(bkk)bk~~
S OF FIRE BARRIER MATERIALS OTHER THAN THERMO-LAG AT NIST.
FEBRUARY 29, 1996. BY LETTER OF MARCH IS, 1996. 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 2S, 1996.
THE BARRIER PANELS AND PANEL /BtANKET COMBINATIONS." 0ATED STAFF IS ASSESSING THE RECOMMENDATIONS MADE BY THE ACRS AND AUGUST 20 1996. THE STAFF'S REVIEW OF THE REPORT OF TEST HAS REFERRED THESE COMMENTS TO THE PRA REVIEW COMMITTEE FOR FR 4008 IS ONGOING.
FURTHER CONSIDERATION.
PROBABILISTIC RISK ASSESSMENT (PRA))
THE PLANT SYSTEMS BRANCH (SPLB CONTINUED TO WORK WITH IN SECY-96-134 THE STAFF STATED THAT, AS PART OF THE BRANCH STAFF AND RULEMAKING. IT WOULD REVIEW OPERATING EXPERIENCE AND WDULD BROOKHAVEN NATIONAL LABORATORY (BNL). 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 OF TWO THE POST-FIRE SAFE-SHUTDOWN METHODOLOGY THAT IMPOSES A SELF-REMAINING ISSUES FOR FURTHER STUDY. ADEQUACY OF OPERABILITY INDUCED STATION BLACKOUT. THE STAFF PLANS TO APPLY THE PRA REQUIREMENTS FOR POST-FIRE SAFE SHUTDOW 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 2 O
O O
T
^%..
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
45 ISSUE NUMBER: 181 TITLE: FIRE PROTECTION STATUS FOR DEVELOPING THE FIRE PROTECTION FUNCTIONAL INSPECTION CALENDAR YEAR 1997.
(FPFI) PROCEDURES. SCIENTECH AND BNL SUBMITTED THE FIRST THE DEVELOPMENT OF A FIRE PROTECTION TRAINING PROGRAM DRAFT OF THEIR WORK PRODUCT CN SEPTEMBER 6 AND SEPTEMBER 16 IS ON HOLD UNTIL THE FPFI PROGRAM IS IMPLEMENTED.
RESPECTIVELY. THE STAFF IS PREPARING A SECY PAPER TO INFORM THE STAFF ISSUED THE SEMIANNUAL REPORT TO THE COMMISSION THE COMMISSION DF THE DETAILS OF THE FPFI PROGRAM AND TO ON THE STATUS OF THE FP-TAP ON OCTOBER 31, 1996. THE NEXT PROVIDE STAFF PLANS FOR IMPLEMENTING THE PROGRAM. THE STAFF STATUS REPORT IS DUE APRIL 1997. NRR/SPLB IS PREPARING AN HAS SELECTED 12 CANDIDATE PILOT PLANT 3 (3 PER REGION). THE RES USERS NEED MEMO OUTLINING THE NECESSARY TECHNICAL STAFF IS CURRENTLY WORKING WITH THE REGIONAL OFFICES TO ISSUES THAT NEED TO BE ADDRESSED IN ORDER TO SUPPORT
+
SELECT 4 FINAL CANDIDATES (1 PER REGION} AND TO SCHEDULE PERFORMANCE-BASED FIRE PROTECTION APPROACHES AT NUCLEAR THE 4 FPFI PILOT INSPECTIONS. THE STAFr PLANS TO BEGIN THE POWER PLANTS. RES IS PREPARING A RULEMAKING PLAN.
PILOT INSPECTIONS NO LATER THAN THE FIRST QUARTER OF AFFECTED DOCUMENTS PROBLEM / RESOLUTION NUREG/CR-6224 NONE.
BULLETIN 95-02 IN 95-47 REVISION 1 IN 93-34 AND SUPPLEMENT 1 BULLETIN 93-02 AND SUPPLEMENT 1 IN 92-85 IN 92-71 IN 88-28 ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE OTHER ISSUES (PART IV) 08/95 08/95 SEMIANNUAL COMMISSION STATUS REPORT 04/96 04/96 I
SEMIANNUAL COMMISSION STATUS REPORT 10/96 10/96
[
RECOMMENDATIONS FOR FUTURE STUDY (PART II) 05/97 10/96 l
CONFIRMATION ISSUES 05/97 10/96 t
AS OF FY97 QUARTER 2 h
1 RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
46 i
ISSUE NUMBER: 181 TITLE: FIRE PROTECTION i
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE SEMIANNUAL COMMISSION STATUS REPORT 04/97 05/97 RECOMMENDATIONS FOR ACTION (PART I) 01/97 09/97 1
s i
t
)
L f
i AS OF FY97 QUARTER 2 t
s P
I i
t 9
9 9
.m....
m
.m.
S RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
47 ISSUE NUMBER: 182 TITLE: GENERAL ELECTRIC EXTENDED POWER UPRATE IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE: 06/96C TYPE: RI PRIORITY:
TASK MANAGER: T. J. KIM OFFICE / DIVISION / BRANCH: NRR /DRPW/PD31 ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M91571 RESOLUTION DATE:
WORK AUTHORIZATION:
FIN CONTRACTOR CONTRACT TITLE WORK SCOPE
[
SPECIFIC ACTIONS INCLUDED IN THE GENERIC ACTION PLAN (3) REVIEW THE LEAD PLANT APPLICATION AND ISSUE A SAFETY ARE: (1) REVIEW ELTR1 AND ISSUE A STAFF POSITION PAPER, EVALUATION REPORT. AND (4) DEVELOP A STANDAP.D REVIEW (2) REVIEW ELTR2 AND ISSUE A SAFETY EVALUATION REPORT.
PROCEDURE BASED ON ELTRI. ELTR2 AND THE LEAD PLANT REVIEW.
i STATUS THE STAFF POSITION 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 r
OF MILESTONE 2).
THE STAFF ALSO MET WITH GE AND THE ELTR2 IS ONGOING. THE LEAD PLANT APPLICATION FROM INTERESTED BWR UTILITIES ON FEBRUARY 14 1996 TO DISCUSS MONTICELLO IS NOW EXPECTED IN JUNE 1996.
l THE CONTENTS OF THE STAFF POSITION PAPER AND THE OVERALL
- SEE NRR DIRECTOR'S MONTHLY REPORT FOR STATUS.
STATUS OF THE POWER UPRATE PROGRAM. ON MARCH 26, 1996. GE i
AFFECTED DOCUMENTS PROBLEM / RESOLUTION NEDC-32424 GENERIC GUIDELINES FOR GE BWR EXTENDED POWER NONE.
UPDATE ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE GE TOPICAL ELTR1 SUBMITTED 03/95 03/95 i
i AS OF FY97 QUARTER 2 I
i
RUN DATE: 05/23/97
. GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
4B ISSUE NUMBER: 182 TITLE: GENERAL ELECTRIC EXTENDED POWER UPRATE ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE MEETING WITH GE/NSP 04/95 04/95 IDENTIFY DIFFERENCES BETWEEN LTR1 AND ELTR1 08/95 08/95 ISSUE RAI*S AS APPROPRIATE 09/95 09/95 INCORPORATE INFORMATION ON FOREIGN 10/95 10/95 EXPERIENCE 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 02/9E RECEIVE ELTR2 PARTS 1 & 2 06/96 06/96 RECEIVE LEAD PLANT APPLICATION 06/96 06/96 HEETING 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 2 O
O O
__.____,_..____...._-._._.____.____,_-_._.--.._m L
5 t
D' k
I l
RUN DATE: 05/23/97-GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
49
')
~ ISSUE NUMBER:
182-TITLE: GENERAL ELECTRIC EXTENDED POWER UPRATE t
b ORIGINAL CURRENT ACTUAL-MILESTONES DATE DATE DATE I
ISSUE LEAD PLANT SE 06/97 06/97 DEVELOP A STANDARD REVIEW PROCEDURE AND 06/97 06/97 INCORPORATE LESSONS LEARNED FRDM LEAD PLANT ACTIVITY CLOSE OUT ISSUE i
1
.5 i
P t
k
.5 i
)
i
)
I AS OF FY97 QUARTER 2
=_ _.
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
50 ISSUE NUMBER: 184 TITLE: ENDANGERED SPECIES IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE: 06/96C TYPE: EI PRIORITY:
TASK MANAGER: J. WILSON OFFICE / DIVISION / BRANCH: NRR /DRPM/
ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M88282 RESOLUTION DATE:
WORK AUTHORIZATION: COMMISSION HEMORANDUM DATED JULY 30, 1991 FIN CONTRACTOR CONTRACT TITLE W0RK SC0PE bbNbbbTkVILbkhkbkhbFPLkkhhPkbfFkbLhShkbFkkDkbkkkb
[kFbkkLbkFbkkkLbbkkbLhh[bk5[hbE[hhkRTbbkkhibkkL SPECIES AND EXISTING LICENSEE COMMITMENTS TO FURTHER THE MARINE FIsiiERIES SERVICE OR THE FISH AND WILDLIFE SERVICE CONSERVATION OF THE PROTECTED SPECIES AND DETERMINE IF IS VARRANTED.
STATUS A LIST OF CURRENTLY LISTED PROTECTED SPECIES IN THE WITH RESPECT TO SEPARATING GENERIC AND PLANT-SPECIFIC VICINITY OF EACH NUCLEAR POWER PLANT SITE WAS DEVELOPED BY ASPECTS AS PART OF MILESTONE 4.
A REPORT IS EXPECTED IN A CONTRACTOR AND DELIVERED TO NRC ON 04/25/96. THIS REPORT NOVEMBER THAT PRIORITIZES SITES AND RECOMMENDATIONS FOR IS NOW UNDER REVIEW. THIS ACTION PLAN WILL BE EVALUATED FOLLOWP ACTIONS.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE bkVELbP bh[bhPLk 06/b5 b6/b5 DEVELOP LIST OF CURRENTLY LISTED PROTECTED 11/95 11/95 SPECIES IN THE VICINITY OF EACH NUCLEAR POWER PLANT SITE AS OF FY97 QUARTER 2 O
O O
........;.w.-.
RUM DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
51
-ISSUE NUMBER: 184 TITLE:. ENDANGERED' SPECIES P
ORIGINAL CURRENT ACTUAL MILEST0NES 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 TO~
12/96 03/97 PROJECTS DEVELOPMENT AND IMPLEMENTATION OF PROCESS FOR-03/97 04/97 MAINTAINING STATUS AND COMPLIANCE WITH THE i
ESA AT EACH SITE b
CLOSE OUT ISSUE I
k i
D
?
-l e
[
s AS OF FY97 QUARTER 2 i
h i
i
[
t i
t
RUN DATE: 05/23/97 GENERIC 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 DATEt 08/96C TYPE: GS1 PRIORITY:
TASK MANAGER: K. SHAUKAT OFFICE / DIVISION / BRANCH: RES / DER /GSIB ACTION LEVEL: ACi!VE STATUS:
TAC NUMBERS:
RESOLUTION DATE: 12/97 VORK AUTHORIZATION: MEMO TO A. THADANI FROM T. SPEIS ON 08/26/96, "GSI-166,
- ADEQUACY OF FATIGUE LIFE OF METAL COMPONENTS *"
FIN CONTRACTOR CONTRACT TITLE WS671 PNL r'ATIGUE ANALYSIS OF SELECTED COMPONENTS FOR 60-YEAR PLANT LIFE WDRK SC0PE EVLUhhtA 5t'k bE b bh bF bPER k[hb PLkkh bbhPbkEkhs FkbhkbhRkkbkREbhbR RkhbLbhfbhhfLL[kbLbbkbbkkkbEkh[bk IN ACCORDANLt. dITH 0 /05/94 MEHORANDUM TO THE NRR DIRECTOR OF A 60-YEAR PROJECTED PLANT LIFE.
STATU$
FATIGUE ANALYSIS OF COMPONENTS FOR CO-YEAR PLANT LIFE IS GI-78 AND THE RESIDUAL WORK ON GI-166 WILL BE CARRIED ON UNDERWAY. THIS WORK COMPLETES THE ONGOING WORK UNDER UNDER THIS GENERIC ISSUE.
AFFECTED DOCUMENTS PROBLEH/ RESOLUTION TO ALLOW TIME TO RESPOND TO NRC STAFF COMMENTS ON DRAFT FINAL REPORT.
ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE RES DECISION TO ESTABLISH NEW GSI 08/96 08/96 EXTEND THE ors RISK STUDY OF FATIGUE 09/96 03/97 FAILURE FRL: 40 TO 60-YEAR PLANT LIFE AS OF FY97 QUARTER 2 O
O O
--m
..u..
_ _ - -.. --- ---- -. -.~ - - -..--., _.___...... _._.. - ~... -. _. -. -.... _ -
-_.....-m i
s RUN.DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM-PAGE:
53 l
4 ISSUE NUMBER:
190'
' TITLE: FATIGUE EVALUATION OF METAL COMPONENTS FOR 60-YEAR. PLANT LIFE t
e
'l i
ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE __-
DEVELOP A STAFF POSITION PAPER FOR LICENSE 01/97 06/97 RENEWAL TION IN THE STAFF POSITION MEET WITH ACRS ON LICENSE RENEWAL RECOMMENDA-05/97 07/97 RESOLUTION. PLAN FOR LICENSE RENEWAL 09/97 09/97 CLOSE OUT MEMO TO EDO 12/97 12/97 l
F 4
6 E
1
+
i i
s t
I J
E i
i
?
1 e
'AS OF FY97 QUARTER 2 4
i i
i t
m 4
- i
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
58 ISSUE NUMBER: 191 TITLE: ASSESSMENT OF DEBRIS ACCUMULATION ON FWR EUMP PERFORMANCE IDENTIFICATION DATE: 09/96C PRIORITIZATION DATE: 09/96C TYPE: GSI PRIORITY:
TASK MANAGER: M. MARSHALL OFFICE / DIVISION / BRANCH: RES / DER /GSIB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS:
RESOLUTION DATE:
VORK AUTHORIZATION: MEMO TO D. HORRISON FROM W. RUSSELL, " THIRD SUPPLEMENTAL USER NEED REQUEST... ACCIDENT GENERATED DEBRIS." 12/07/95 FIN CONTRACTOR CONTRACT TITLE W6650 SEA WORK SC0PE IN LIGHT OF THE RESOLUTION (I.E., NRC BULLETIN 96-03 AND BLOCKAGE OF PWR SUMPS WILL BE REASSESSED TO DETERMINE REGULATORY GUIDE 1.82, REV. 2) 0F S-08 1 " POTENTIAL IF THERE IS A NEED FOR FURTHER ACTIONS TO BE tar;EN FOR FOR LOSS OF EMERGENCY COOLING IN BWR*S DUE TO LOCA PWR*S BEYOND THE ORIGINAL RESOLUTION OF USI A-43, GENERATED DEBRIS" (I.E., THE BWR EMERGENCY CORE
" CONTAINMENT EMERGENCY SUMP PERFORMANCE."
COOLING SYSTEMS
- SUCTION STRAINER BLOCKAGE). DEBRIS STATUS kEkEkkbbkEbbLhhbbhkkEbFbkkEkbLV[kGhbkhhkbTkikkR kEEbEb kb bbkkhb TbEbk kEh bbkbkkhk[ bPbhkkbk[PTbFkk ISSUE HAVE IDENTIFIED NEW PHENOMENA AND FAILURE MODES NOT NRR USER NEED LETTER. WHICH IS BEING PREPARED, A PROGRAM CONSIDERED IN THE RESOLUTION OF USI A-43.
IN ADDITION, PLAN, SCHEDULE. AND COST ESTIMATES WILL BE PREPARED TO EXPERIENCES AT OPERATING PLANTS HAVE IDENTIFIED NEW ADDRESS THIS ADDITIONAL RESEARCH. FOLLOWING AGREEMENT ON CONTRIBUTORS (SUCH AS DEGRADED OR FAILED CONTAINMENT WORK SCOPE AND SCHEDULE SUPPLEMENTAL FUNDING WILL BE g
PAINT COATINGS) TO DEBRIS AND POSSIBLE BLOCKAGE OF PWR REQUIRED TO SUPPORT NRR S NEEDS.
SUMPS. THEREFORE, AN EXPANDED RESEARCH EFFORT WILL BE AFFECTED DOCUMENTS PROBLEM / RESOLUTION I
REGULATORY GUIDE 1.82, REV. 2 SUPPLEMENTAL FUNDING WILL BE NEEDED TO CARRY OUT THE I
NUREG-0800 CONFIRMATORY RESEARCH NEEDED TO RESPOND TO NRR
- S d
GENERIC LETTER 85-22 ADDITIONAL NEEDS. THE CURRENT GSI-191 PROGRAM SCOPE AND FUNDING LEVEL ARE INADEQUATE TO MEET THESE NEW NEEDS.
AS OF FY97 QUARTER 2 O
O O
.-_._m,.,.m
,_..,.. ~.. - -... - _..... - _ - - -..
. _. -. -... _ _... -... -..... _. - _ - - _. ~ ~., - - -,. _..... -.,. - _..
'n i
)
RUN DATE d5/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
'PAGE:
-55
- - I T
ISSUE NUMBER: 191 11TLE: ASSESSMENT OF DEBRIS ACCUMULATION ON PWR-SUMP PERFORMANCE-I L
L I
ORIGINAL-
.CURREIiT
- ' ACTUAL' MILEST0NES DATE DATE DATE
. [
NRR USER NEED REQUEST SENT TO RES.-
12/SS:
12/95-
[
j --
. USER NEED REQUEST ASSIGNED.TO GSIB 01/96 01/96
{
. REASSESSMENT DECLARED A NEW GSI~
09796 09/96
. [
r ISSUE S0W FOR REASSESSMENT' 11/96 11/96 i
COMPLETE REASSESSMENT 04/97
' 04/97 f
ISSUE CLOSE-00T-MEMO TO EDO
' I 3
.5 i
. }
l
)
- i i
k
.l i
f 1
' I
+
f i
t t
y 9
i 4
. 3 AS OF FY97 QUARTER 2-t E.
?
I h
f 6
-it d
n.
+
w RUN DATE: 05/23/97 GECERIC ISSUE MACAGEMENT CONTROL SYSTEM PAGE:
56' ISSUE NUMBER: B-17 TITLE: CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS IDENTIFICATION DATE: 06/7BC PRIORITIZATION DATE: 11/83C TYPE: GSI PRIORITY: M TASK MANAGER: J. KRAMER OFFICE / DIVISION / BRANCH: RES /DSR /HFBR ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE: 01/98 WORK AUTHORIZATION: NRR FY-84 0FERATING PLAN (APPENDIX G)
FIN CONTRACTOR CONTRACT TITLE kb4kb LLkt
~
ikhkGRkhfbk bh bbkkk PkkkbkMkkbh kkbhbkS FbLkh 5kTb hkk kELikkfLkhh ~
~
~
EVALUATION PROCESS (TASKS 5 AND 6)
W0RK SC0PE hkkWbkKkbbPk5kbLbbkk$
)bkVELbPh[kkbk[TEkibk M kb L bPEkEkbk kbhibk bk bhbkkh5b bhibk5 EHk kbbPh bk FOR SAFETY RELATED OPERATOR ACT NS: (2) DETERMINE WHETHER THIS GENERIC ISSUE COVERS DESIGN BASIS ACCIDENTS OR EVENTS.
OR NOT AUTOMATIC ACTUATION WILL BE REQUIRED: AND (3) DEVELOP CRITERIA FOR SAFETY RELATED OPERATOR ACTIONS DURING SEVERE l
CUIDANCE AND REVIEW CRITERIA FOR LICENSEE PROPOSALS TO USE ACCIDENTS WILL BE COVERED UNDER THE SEVERE ACCIDENT PROGRAM.
I 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 MEMO FROM V. RUSSELL TO T. SPEIS).
WHICH SHOULD LEAD TO RESOLUTION OF THIS GSI BY ENDORSING l
NO WORK HAD BEEH COMPLETED ON THE ISSUE PRIOR TO TRANSFER.
ANSI /ANS 53.8.
THIS STANDARD-15 BEING REVISE 0 BASED ON NEW l
DURING 1983 AND 1984 RES WORKED ON THIS ISSUE. DURING INDUSTRY DATA.
LLNL BEGAN WORK TO MANAGE THE TECHNICAL l
THAT TIME DATA VERE COLLECTEC BY RES CONCERNING GPERATOR EFFORT INVOLVING EPRI AND A SUBCONTRACTDR 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 l
l AEEEEEEE E9EUME$15 gRgB([d{gESQ(Ul[gN TO BE PROVIDED LATER LAST TWO MILESTONES WERE REVISED TO INCLUDE TIME FOR COMPLIANCE WITH SBRFA LEGISLATION A3 OGC IS NOT LIKELY TO GRANT GENERIC EXEMPTION ON FINAL REG. GUIDES. ALSO, ADDITIONAL PROPRIETARY OATA TO BE RECEIVED FROM WESTINGHOUSE WILL HAVE TO BE PROCESSED, EVALUATED, AND TRANSMITTED TO ACRS.
STATUS REPORT GIVEN TO ACRS 05/97. DST MANAGEMENT l
DECIDED TO TAKE CLOSER LOOK AT PROPOSED RESOLUTION FOR 1
I l
t AS OF FY97 QUARTER 2 i
l l
t O
O O
,x eN fw LJ (v)
(
\\
)
v RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
57 ISSUE NUMBER:
B-17 TITLE: CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS AFFECTED DOCUMENTS PROBLEM / RESOLUTION l
THIS ISSUE AND SCOPE OF B-17 WITHIN CONTEXT OF~ RISK-INFORMED, PERFORMANCE-BASED METHODS.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE MEET WITH ANSI /ANS 58.8 07/88 06/89 OEVELOP 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 STO 58.8 10/92 03/93 DEVELOP REGULATORY GUIDE TO ENDCSSE C3/94 03/94 ANS 58.8 NUPPSCO ISSUES FINAL 58.8 08/93 08/94 ANSI /ANS 58.8 PUBLISHED 03/95 ISSUE DRAFT REG GUIDE FOR 60-DAY C0tC4ENT 12/93 07/95 PERIOD REVISE REG GUIDE TO REFLECT PUBLIC COMMENTS 05/94 09/95 ACRS REVIEW 07/94 11/95 ISSUE FRN AND REVISED DRAFT REG GUIDE 03/96 11/95 DG-1052 FOR 60-DAY PUBLIC COMMENT PERIOD ISSUE REQUEST TO GSIB FOR REASSESSMENT OF 11/96 11/96 RISK ANALYSIS ACRS REVIEW-STATUS REPORT 09/9 6 05/97 REVISE DG-1052 TO REFLECT PUBLIC COMMENTS 07/96 02/97 AS OF FY97 QUARTER 2 1
RUN OAYE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
58 ISSUE NUMBER:
B-17 TITLE: CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS ORIGINAL CURRENT ACTUAL HILEST0NES DATE DATE DATE ISSUE FINAL REG GUIDE 09/94 11/97 CLOSE OUT ISSUE WITH MEMORANDUM TO EDO 09/94 01/98 i
i i.
i i
L AS OF FY97 QUARTER 2 I
9 O
O
y
-w s
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT C0hfROL SYSTEM PAGE:
59 ISSUE NUMBER: B-55 TITLE: IMPROVE RELIABILITY OF TARGET ROCK SAFETY-RELIEF VALVES IDENTIFICATION DATE: 06/78C PRIORITIZATION DATE: 11/83C TYPE: GSI PRIORITY: M TASK MANAGER: G. HAMMER OFFICE / DIVISION / BRANCH: NRR /DE /EMEB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE: 08/97 WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN, (APPENDIX G)
FIN CONTRACTOR CONTRACT TITLE WORK SC0PE REVIEW BWR UTILITY APPROACHES TO INCREASING SRV CONFORMANCE TO NSSS VENDOR INSTRUCTIONS: (2)
RELIABILITY TO OBTAIN SUFFICIENT DATA BASE TO SUPPORT DEMONSTRATING SUFFICIENT RELIABILITY OF 2-STAGE VALVES THE CONCLUSION THAT THIS ISSUE HAS BEEN RESOLVED.
AFTER DESIGN AND/OR SYSTEM MODIFICATIONS, AND (3)
THE UTILITY APPROACHES MAY INCLUDE: (I) DEMONSTRATING USING OIFFERENT VALVES AND DEMONSTRATING THEIR SUFFICIENT RELIABILITY OF 3-STAGE VALVES BY STRICT RELIABILTY.
STATUS WHILE INITIAL PERFORMANCE WITH THE PH 13-8 MO REPLACE-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 DATA MADE IT APPARENT THE NEW DISCS ARE NOT PROVIDING THE ISSUE WAS EXPECTED TO BE UNDERTAKEN WITHIN NRR, AND SINCE IMPROVED PERFORMANCE THAT WAS ORIGINALLY EXPECTED. THE ANY PLANT MODIFICATIONS RESULTING FROM THE RESOLUTION OF BWROG CONCLUDED THE PH 13-8 HO REPLACEMENT DISCS ARE NOT A THIS ISSUE WERE EXPECTED TO BE EITHER VOLUNTARY OR VIABLE SOLUTION FOR ELIMINATING SETPOINT DRIFT AND RECOM-JUSTIFIED ON A " COMPLIANCE" BASIS, RES HAS FORMALLY MENDED THEY NO LONGER BE INSTALLED TO RESOLVE THIS PROBLEM.
TRANSFERRED THE ISSUE TO NRR FOR THE BALANCE OF THE GENERIC BECAUSE CORROSION BONDING OF THE PILOT DISK TO ITS SEAT WAS RESOLUTION PERIOD AND SUBSEQUENT PLANT SPECIFIC IMPLEMENTA-IDENTIFIED AS THE CAUSE OF THE UPWARD SETPOINT DRIFT, THE TION.
BWROG THEN DEYCLOPED A PLATINUM ALLOY PILOT DISK DESIGN.
THE STAFF MET WITH THE BWROG ON APRIL 24, 1996. TO THIS CATALYST DISK WAS VERY EFFECTIVE IN REDUCING OXYGEN DISCUSS THE PERFORMANCE OF THE CATALYTIC DISKS AND SEAT CONCENTRATION AT THE PTLOT DISK SEAT LOCATION WHICH COULD LEAKAGE ISSUES. THE BWROG HAS DETERMINED THAT, BY THEN REDUCE THE CORROSION BONDING. THE BWROG ALSO DEVELOPED SPRING 1997. ENOUGH SETPOINT DATA SHOULD BE AVAILABLE TO AN EQUAL PARALLEL CONflNGENCY OPTION WHICH INVOLVES THE USE EVALUATE THE DISKS. THE BWROG IS ALSO DEVELOPING OF PRESSURE SWITCHES SIMILAR TO THOSE USED ON BWR/6 PLANTS.
RECOMMENDATIONS TO LESSEN LEAKAGE BY BETTER MONITORING ANC A LICENSING TOPICAL REPORT AND ADDITIONAL INFORMATION FOR MAINTENANCE, SINCE LEAKAGE MAY AFFECT THE SETPOINT THE PRESSURE SWITCH DESIGN WAS SUBMITTED WHICH NRR HAS PERFORMANCE. CtMRENTLY, THE STAFF PLANS TO DISCUSS THE RECENTLY APPROVED. SEVERAL OF THE CATALYTIC DISKS HAVE BEEN AVAILABLE TEST DATA WITH THE BWROG IN THE SPRING 1997 AND INSTALLED IN SEVERAL BWR'S ON A TRIAL BASIS FOR SUBSEQUENT EVALUATE THE PERFORMANCE OF THE PLATINUM ALLOY DISKS AND SETPOINT TESTING.
ADDITIONAL ACTIONS IF NECESSARY.
AS OF FY97 QUARTER 2
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
60 ISSUE NUMBER:
B-55 TITLE: IMPROVE RELIABILITY OF TARGET ROCK SAFETY-RELIEF VALVES STATUS AFFECTED DOCUMENTS PROBLEM / RESOLUTION CRIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE 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 AND 80STON EDISON REPORTS COMMUNICATION TO OG RE: NRC 03/85 COMMENTS / CONCERNS OG PRESENTATION TO THE STAFF 10/85 10/85 STAFF RECEIVES OWNERS' 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 2 O
O O
.. -... _. _..... ~..... _ - _..
..-...-.~.-----m m_.
_ - ~. ~ ~
m.
fn
- 4 1
t RUN'DATE: 05/23/97 6
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
61
- i ISSUE NUMBER: B-55 TITLE:_ IMPROVE RELIABILITY OF TARGET ROCK ~ SAFETY-RELIEF VALVES t
5:
i I
ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE j
[
BWROG SELECT / DESIGN CATALYST 03/91 02/91 f
MRC STAFF ISSUE STATUS REPORT ON INDUSTRY 06/91.
08/91 PROGRESS BWROG COMPLETES FINALIZING DESIGN AND
'04/92 07/92 LABORATORY TESTING-
- ?
I NRC STAFFIISSUE STATUS REPORT ON INDUSTRY 03/92
~08/92 t
PROGRESS i!
-REASSESS ISSUE 03/93 05/93 i
i REASSIGN TO NRR 08/93 08/93 r
NRR RESPONSE TO REASSIGNMENT 10/93 10/93 BWROG SUBMIT TOPICAL REPORT TO NRC 12/91-04/94 h
i 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 NRR 11/94 04/95 i
NRR ISSUE APPROVAL FOR PRESSURE. SWITCH-02/95 10/95 f
OPTION i
i EVALUATE PERTORMANCE OF PLATINUM DISKS AND.
05/97 05/97 DETERMINE ADDITIONAL ACTIONS IF NECESSARY t
1 ISSUE CLOSE00T MEMORANDUM TO EDO 08/97 08/97-a I
I i
AS OF FY97 QUARTER 2 3
I k
r
}
u 2"
A
=-
a
- a
--m a-E
="
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
62 ISSUE NUMBER:
B-61 TITLE: ALLOWABLE ECCS EQUIPMENT OUTAGE PERIOOS IDENTIFICATION DATE: 06/7BC PRIORITIZATION DATE: II/B3C TYPE: GSI PRIORITY: M TASK MANAGER: A. BUSLIK OFFICE / DIVISION / BRANCH: RES /DSR /PRAB ACTIOR LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE: 04/97 WORK AUTHORIZATION: NRR FY-B4 OPERATING PLAN (APPENDIX G)
FIN CONTRACTOR CONTRACT TITLE W0RK SCOPE IN GENERAL, PLANTS WILL BE CLASSIFIED SUCH THAT OF SUPPORT SYSTEM OUTAGES MUST BE INCLUDED. DETAILS IN EACH CLASS SIMILAR ECCS OUTAGE UNAVAILABILITIES OF THE WORK SCOPE ARE CONTAINED IN THE DRAFT ACTION WILL HAVE SIMILAR IMPACTS ON RISK.
THE EFFECT OF A PLAN, BECAUSE CUMULATIVE OUTAGE TIMES ON COMPONENTS OTHER GIVEN ECCS AVAILABILITY ON RISK WILL BE DETERMINED.
THAN FCCS COMPONENTS APPEAR IMPORTANT THE WORK SCOPE HAS FOR EACH CLASS OF PLANT, AS WELL AS THE IMPACTS OF ANY BEEN EXPANDED TO INCLUDE ALL SAFETY-RELATED COMPONENTS.
CHANGES IN ALLOWABLE ECCS OUTAGE PERIOD. CONSIDERATION STATUS hkkK k b k BkkN bbHPLkhEb$ kkkb kb bRS U TH PkbPbkEb bkPbkhbkRkb5bR bkR$
RESOLUTION WAS INITIATED BY PRAB IN 09/96; MEMO IS WITH AFFECTED DOCUMENTS PROBLEM / RESOLUTION hkbbbkbkL kPkbiFfbkhkbb bbkNbEk Rk PbkkfBLk$
kHk kkbbk PkbSLkh kkbbfkhkb UfTb kHk kkkbLbh[bN bF b bI kk REVISED INSPECTION GUIDANCE FOR VOLUNTARY ENTRY INTO AN ANALYSIS OF THE COSTS AND BENEFITS OF THE IMPOSITION OF LCO*S.
A CUMULATIVE OUTAGE REQUIREMENT. A STUDY OF THE NEED FOR CONTROL OF CUMULATIVE OUTAGE IS BEING PERFORMED IN-HOUSE.
THE WORK TAKES INTO ACCOUNT THE MAINTENANCE RULE AND THE NUMARC GUIDANCE FOR THE IMPLEMENTATION OF THE MAINTENANCE RULE AS WELL AS CURRENT INSPECTION GUIDANCE ON VOLUNTARY ENTRY INTO LIMITED CONDITIONS OF OPERATION ACTION STATEMENTS TO PERFORM PREVENTIVE MAINTENANCE. AN INITIAL RECOMMENDA-TION FOR STAFF COMMENTS WAS COMPLETED IN SEPTEMBER 1992:
THIS INCLUDED A FA0 POSED DRAFT TECHNICAL RESOLUTION.
AS OF FY97 QUARTER 2 O
O O
m. _... _.. _ _ _.
._m, m..
O O
O RUN DATE:- 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
63 ISSUE NUMBER:
B-61 TITLE: ALLOWABLE ECCS EQUIPMENT OUTAGE PERIODS AFFECTED DOCUMENTS PROBLEM / RESOLUTION COMMENTS WERE RECEIVED ON THIS PROPOSED DTR FROM IMMEDIATE MANAGEMENT IN AUGUST 1993.
IT IS CLEAR THAT A CUMULATIVE OUTAGE REQUIREMENT ON UNSCHEDULED MAINTENANCE WILL NOT BE IMPOSED. THE CURRENT PLAN IS TO ARGUE THAT EXISTING PROGRAMS (MAINTENANCE RULE. CURRENT INSPECTION GUIDELINES)
ARE SUFFICIENT TO CONTROL THE CUMULATIVE MAINTENANCE UNAVAILABILITY AND THAT THE "NO ACTION" ALTERNATIVE SHOULD BE SELECTED. MODIFICATIONS TO THE GUIDANCE FOR THE MAINTENANCE RULE TO EMPHASIZE THE RISK IMPLICATIONS OF PERFORMING SCHEDULED MAINTENANCE ON RISK-SIGNIFICANT COMPONENTS DURING POWER OPERATION APPEAR DESIRABLE. A MEMORANDUM FROM RES TO NRP SUGGESTING THAT B-61 BE RESOLVED i
THRDUGH THE MAINTENANCE RULE. BY MODIFYING THE INSPECTION GUIDANCE FOR THE MAINTENANCE RULE. HAS BEEN SENT.
THIS MEMORANDUM INDICATED THAT, SINCE THE IPE'S HAVE NOT INDICATED ANY VULNERABILITIES WITH RESPECT TO ONLINE MAINTENANCE OF COMPONENTS, IF THE INSPECTION GUIDANCE FOR THE MAINTENANCE RULE REQUIRED THAT THE ASSUMPTIONS MADE IN THE PLANT IPE WITH RESPECT TO ONLINE MAINTENANCE WERE l
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.
i DISCUSSIONS WITHIN RES ON THE APPROPRIATE COURSE OF ACTION ARE TAKING PLACE.
ORIGINAL CURRENT ACTUAL
---__------ U 1 b 5 5 1 9 N { [- _,___________,,,
,__gpl{,,,
,__ 3J{,__
g
,,_ 3J[,,,
g DRAFT TAP ISSUED FOR DD APPROVAL 01/84 01/84 COMPLETE COORDINATION OF TECHNICAL RESOLUTION 04/84 08/84 r
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 2 I
i l
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
64 ISSUE NUMBER:
B-61 TITLE: ALLOWABLE ECCS EQUIPMENT CUTAGE PERIODS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE bEVElbP h[kkhikLRkbbkhEkbEhibhhbRhkFF bb)bh I-bb)bh COMMENTS APPLY METHODOLOGY TO A SELECTION OF PLANTS 08/85 09/92 PREPARE DRAFT DTR 04/8S 04/94 DRAFT RESOLUTION 02/95 06/96 DTR TO ACRS 08/96 04/97 CLOSE OUT ISSUE 02/95 04/97 i
s AS OF FY97 QUARTER 2 l
O O
m-N m._
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
65 ISSUE NUMBER: HF 5.2 TITLE: REY. 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: 3B 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 A3CS7 BNL ANNUNCIATORS WDRK SC0PE TbkbkhkbkCbhBikkhhbb[bSbkhkkbkThkUbhEkFEbhbR[
b5kbkikkbkhkTibkkkbkCbkTRbLBbkkbEkkbkbkETbRh hbk PROGRAM PLAN OF SECTION I.5.2 RESULTS FROM A PRA ESTABLISHED THE MAGNITUDE OF THE RISK LAR COMPUTER AND COMPUTER DISPLAYS INVOLVED AND THE POTENTIAL REDUCTION IN RISK EXPECTED. A L EVALUATION OF OPERATOR AID SYSTEMS VALUE/ IMPACT ANALYSIS WAS COMPLETED AND ESTIMATED THE COST l
J ANNUNCIATORS OF POTENTIAL MODIFICATIONS TO ANNUNCIATORS.
p
[J 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. T!1IS DECISION ALSO CONCLUDED THAT THE REMAINING PLAN TO USE THE RESEARCH RESULTS ON ADVANCED ALARM SYSTEMS ISSUES BE REASSIGNED AS RESEARCH ISSUES. A RESEARCH CONDUCTED AT THE HALDEN PROJECT. THE RESULTS FROM THIS PROJECT ENTITLED " REVIEW CRITERIA FOR HUMAN FACTORS ASPECTS EFFORT WILL Dt:VELOP GUIDELINES ON COMPUTER-BASED ANNUNCIATOR OF ADVANCED CONTROL AND INSTRUMENTAION." FIN B0852, SYSTEMS. THESE GUIDELINES WILL SERVE AS THE BASIS FOR A ADDRESSES THESE ISSUES.
NUREG ON ANNUNCIATORS. NRR WILL INCORPORATE RESULTS OF THIS THE GOAL OF THIS WORK IS TO DETERMINE THE RISK TO WORK IN THEIR MODIFICATIONS TO THE STANDARD REVIEW PLAN.
PUBLIC HEALTH AND SAFETY RESULTING FROM HUMAN ERROR IN THE STATUS BY LETTER DATED DECEMBER 29, 1987. THE S0W FOR THE VALUE-COMPLETED IN NOVEMBER 1988. ALARM REDUCTION STUDY BEGAN IMPACT STUDY WAS FORWARDED TO BNL.
PROJECT AND BUDGET OCTOBER 1990.
WORK TERMINATED. (SEE MEMORANDUM FROM PROPOSAL FOR NRC WORK (NRC FORM 189)/ IMPACT STUDY WAS RECEIVED MARCH 7, 1988.
E. ".ECKJORD TO THE EDO ON JUNE 29, 1993.)
BNL BEGAN WORK IN APRIL 1988.
VALUE AS OF FY97 QUARTER 2
f RUN DATE: 05/23/97' GENERIC IRSUE MANAGEMENT CONTROL SYSTEN PAGE:
66 ISSUE NUMSER: HF 5.2 TITLE: REV. CRIT. FOR HUMAN FACTORS ASPECTS OF ADV CONTROLS AND INSTRUMENT.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION
~~-----------------------------------
NUREG/CR-6105 " HUMAN FACTORS ENGINEERING GUIDANCE FOR THE N0hE.
REVIEW OF ADVANCED ALARM SYSTEMS."
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE bkbkhVLbk/IMPbhbhbbhbFkkkbhbkkhbab b2/bb OUbb COMPLETE VALUE/ IMPACT STUDY 07/88 10/88 NRC COMPLETES REVIEW OF STUDY RESULTS 09/88 11/88 ISSUE S0W FOR ALARM REDUCTION EVALUATION 11/88 01/89 BEGIN ALARM REDUCTION STUDY 01/89 03/89 PREPARE CLOSEOUT PACKAGE 04/93 04/93 CLOSE DUT MEMO TO EDO 06/93 06/93 ISSUE INTERIM ALARM GUIDELINES (NUREG/CR-08/94 09/94 6105)
COMPLETE ALARM REDUCTION STUDY 11/89 12/97 AS OF FY97 QUARTER 2 i
O O
O
(
[j
(
i l
I l
k b/
./
RUN DATE: 05/23/9~
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
67 ISSUE NUMBER:
II.E 5.1 TITLE: IN-SITU ".' STING OF VALVES IDENTIFICATION DATE: 05/80C PRIORITIZATION DATE: 11/83C TYPE: GSI PRIORITY: M TASK MANAGER: T. SCARBROUGH OFFICE / DIVISION / BRANCH: NRR /DE /EMEB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M80330 M82072 M75089 M88898 RESOLUTION DATE: 06/89C WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN (APPENDIX G)
FIN CON 774CTOR CON 1 DAFT TITLE r
A3821 BNL ADEQUACY OF CURRENT VALVE INSERVICE TFST METHODS WDRK SC0PE hDEb[F[b bhkV[T[kS [kbLbbEb ik ThE bEkkkkb kbT5bh PL h Tb bPR[ hbh PkkFbRM kbk PREDIchibk PkbbRkM bk k kbh [b[
2 f
IMPROVE MOV PERFORMANCE ARE:
96 THE STAFF ISSUED SE ON THE EPRI MOV PERFORMANCE (1) REGULATORY IM"ROVEMENTS - THE STAFF IS WORKING WITH ASME PREDICTION PROGRAM. THE STAFF IS REVIEWINu 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 OMh-1, " ALTERNATIVE RULES FOR PRESERVICE AND INSERVICE TEST-CF MOV DESIGN-BASIS CAPABILITY.
ING OF CERTAIN ELECTRIC MOTOR OPERATED VALVE ASSEMBLIES IN (4) MOV INSPECTION MODULE - THE STAFF PLANS TO PREPARE AN LWR POWER PLANTS OM - CODE 1995 EDITION: SUBSECTION ISTC."
INSPECTION MODULE FOR INSPECTING MOV PROGRAMS OVER THE LONG STAFF REFERENCES CODE CASE IN GL 96-05.
TERM AND PROVIDE APPROPRIATE TRAINING FOR INSPECTORS.
STATUS COORDINATION WITH INDUSTRY AND SUPPORT TO NRC REGIONAL STAFF HAS BEEN ALERTING LICENSEES, NEI, AND EPRI TO THE STAFF, EFFORTS ON CODES AND STANDARDS AND MOV DESEARCH AND STAFF'S FINDINGS FROM THE EPRI PROGRAM REVIEW AND HAS BEEN ANALYSIS ARE ONGOING ACTIVITIES. ON SEPTEMBER 18, 1996 COMMLNICATING 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 WonKING TO THE STAFr 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 2 L
UUd DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEH PAGE:
68 ISSUE NUHBER:
II.E.6.1 TITLE: IN-SITU TESTING OF VALVES AFFECTED DOCUMENTS
~~
PROBLEM / RESOLUTION L }II BULLET k 85~0E ~
~ ""~
~~
~~~
~ ~~~
EbkE
~
~
GL 85-10 AND 7 $UPPLEMENTS f ? NUREG-1352 dJ GL 96-05 ORIGINAL CURRENT ACTUAL MILESTONcS DATE DATE DATE INSERVICE TESTING OF CHECK VALVES (INPO) ISSUE SOER REGARDING 07/86 10/86 AUGMENTED TESTING OF CHECK VALVES (NRR/RES) REVIEW SOER TO SEE IF NRC 10/86 02/87 CONCERNS CN IN-SITU TESTING OF " SIMPLE" CHECK VALVES SATISFIED. ISSUE RPT &/OR iTR (NSSS OWNERS GROUP) ISSUE OWNERS 05/87 11/87 GROUP APPLICATION GUIDE FOR CHECK VALVES (NRR/RES) REVIEW OWNERS GROUP APPL GUIDE TO 08/87 01/88 SEE IF NRC CONCERNS ON IN-SITU TEST OF
" SIMPLE" r3ECK VALVt:S ARE SATIFIED (NRR/RES) REPORT (ACRS) 08/87 03/88 14 RMAL OVERLEAD PROTECTION OF MOV'S (RES/EIB) COMPLETE REVIEW TO DETERMINE REQ'D 05/85 10/87 MODS, IF ANY, TO RG 1.106 REGARDING TOL PROTECTION FINAL NUREG ISSUED 07/88 06/88 LETTERS TO ASME & IEEE 12/88 12/88 CLOSE OUT MEMD ON CHECK VALVES & TOL 01/89 06/69 i
AS OF FY97 QUARTER 2 O
O O
(- )
(~
I l
I
(%.J ks' RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
69 ISSUE NUMBER:
II.E.6.1 TITLE: IN-SITU TESTING OF VALVES ORIGINAL CURRENT ACTUAL MILE 5T0NES DATE DATE DATE kNkkRh[bhTkkTkNGbbMbh*h (RES) ISSUE HOVATS REPORT REGARDING USE OF 09/G5 01/86 SIGNATURE TRACING TECHNIQUES TO EVAL. THE OPERASILITY OF MOV*S (NRR/RES) REVIEW MOVATS REPORT AND AE00 11/85 08/86 COMMENTS ON MOVATS REPORT (NRR) REVIEV RESPONSES TO IE CULLETIN 85-03 01/87 12/88 FROM LICENSEES AND APPLICANTS (RES/EIB) PREPARE STAFF POSITION ON ADDITI-02/86 10/87 ONAL AND/OR MODIFIED IN SITU TESTING OF MOV'S (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 OS/89 NRR ISSUANCE OF GENERIC LETTER ON MOV*S 09/89 06/89 CLOSE OUT MEMO TO EDO (TASK MANAGER - OWEN 06/89 06/89 ROTMBERG, EIB/DSIR/RES)
ISSUE GL 89-10, SUPPLEMENT 7 01/95 01/95 AS OF FY97 QUARTER 2 i
l l
RUN DATE: 05/23/07 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
70 ISSUE NUMBER:
II.E.6.1 TITLE 56-SITU TESTINC OF VALVES ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE
[hkbEkEbbEhEkkbLETTEkb5bb[PER[bb[b b2/bb b2/bb VERIFICATION FOR PUBLIC COMMENT SER ON EPRI MOV PERFORMANCE PREDICTION 02/96 03/96 PROGRAM FINAL ISSUANCE OF NEW GENERIC LETTER ON 08/96 09/96 MOV PERIDOIC VERIFICATION SER SUPPLEMENT ON EPRI MOV PERFORMANCE 08/96 01/97 PREDICTION PROGRAM CLOSE OUT ISSUE 01/97 02/97 PREPARE MOV INSPECTION MODULE 10/96 06/97 COMPLETE POST-RESOLUTION FOLLO'JUP WORK AS OF FY97 QUARTER 2 O
O O
m.
m
~s -
(f
-s v
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
71 ISSUE NUMBER: RGA 001 TITLE: BOILING WATER REACTOR INTERNALS IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE:
TYPE:
PRIORITY:
TASK MANAGER: D. TERA 0 0FFICE/ DIVISION / BRANCH: NRR /DE /EMCB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M9189B M93627 M93925 M93926 M94959 M94975 M95369 RESOLUTION DATE:
[
WORK A JTHORIZAT10N:
FIN CONTRACTOR CONTRACT TITLE WORK SC0PE THE STAFF WILL CONTINUE TO ASSESS THE REPORTS THAT HAVE BEEN OF INDUSTRY AND STAFF RESOURCES THAT WILL BE NEEDED OR HAVE YET TO BE SUBMITTED BY THE BWRVIP CONCERNING
-IN THE FUTURE, IT IS IMPORTANT FOR THE STAFF TO INSPECTIONS OF BWR INTERNALS AND REINSPECTIONS OF CORE CONTINUE INTERACTING WITH THE INDUSTRY ON A GENERIC 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.
STAFF WILL ISSUE SEPARATE SAFETY EVALUATIONS REGARDING
-THE BWRVIP HAS SUBMITTED 12 GENERIC DOCUMENTS SUPPORTING THE ACCEPTABILITY OF CORE SHROUD REPAIR DESIGNS. THE PLANT-SPECIFIC SUBMITTALS FOR STAFF REVIEW. THE STAFF IS STAFF HAS BEEN INTERACTING WITH THE BWRVIP AND ENSURING THAT THE GENERIC REVIEWS ARE INCORPORATING RECENT INDIVIDUAL LICENSEES. IN AN EFFORT TO LOWER THE NUMBER OPERATING EXPERIENCE ON ALL BWR INTERNALS.
STATUS ALL BWR*S COMPLETED INSPECTIONS OR REPAIRS OF CORE BWR LICENSEES.
SHROUDS DURING REFUELING OUTAGES AS OF THE FALL OF 1996.
THE BWRVIP HAS ISSUED 12 GENERIC REPORTS FOR STAFF VARIOUS REPAIR METHODS HAVE BEEN USED TO PROVIDE ALTERNATE REVIEW. THE NRC STAFF HAS ISSUED REQUESTS FOR ADDITIONAL LOAD CARRYING CAPABILITY, INCLUDING PREEMPTIVE REPAIRS, INFORMATION ON 5 BWRVIP REPORTS AND RECEIVED RESPONSES INSTALLATION OF A SERIES OF CLAMPS, AND USE OF A SERIES OF ON 3 REPORTS. THE STAFF IS CONTINUING ITS REVIEW OF ALL TIE-ROD ASSEMBLIES. THE NRC HAS REVIEWED AND APPROVED ALL 12 GENERIC REPORTS.
SHROUD MODIFICATION PROPOSALS THAT HAVE BEEN SUBMITTED BY AFFECTED DOCUMENTS PROBLEM / RESOLUTION GL 94-03 NONE.
NUREG-1544 AS OF FY97 QUARTER 2
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
72 ISSUE NUMBEra RGA 001 TITLE: ROILING WATER REACTOR INTERNALS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE ISSLE GL 94-03 07/94 07/94 TAP APPROVED 04/95 04/95 COMPREHENSIVE PLAN (BWRVIP-06) RECEIVED BY 12/95 10/95 NRC BWRVIP-07 RECEIVED BY NRC 02/96 02/96 ISSUE NUREG-1544 03/9 6 03/96 REVIEW BWR VESSEL SHELL WELD INSPECTION 08/96 03/97 RECOMMENDATIONS (BWRVIP-05)
REVIEW RPV AND INTERNALS EXAMINATION GUIDE-08/96 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-08)
SAFETY ASSESSMENT OF BWR REACTOR INTERNALS 08/96 06/97 (BWRVIP-06)
EVALUATION OF CRACK GROWTH IN BWR STAINLESS 12/96 06/97 STEEL RPV INTERNALS (BWRVIP-14)
REVIEW ASSESSMENT OF BWR JET PUMP RISER ELBOW 06/97 06/97 TO THERMAL SLEEVE CRACKING CORE SPRAY INTERNAL INSPECTION AND FLAW 07/97 07/97 EVALUATION GUIDELINES (BWRVIP-le)
REVIEW GENERIC REPAIR TECHNOLOGY, CRITERIA 08/96 08/97 AND GUIDANCE REVIEW GENERIC MITIGATION GUIDELINES 08/97 08/97 AND CRITERIA AS OF FY97 QUARTER 1 O
O O
I g
i RUN DATE: 05/23/97-GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
73 1
ISSUE NUMBER: RGA 001 TITLE: BOILING WATER REACTOR INTERNALS-i DRIGINAL 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 i
CRITERIA (BWRVIP-19)
REVIEW ROLL / EXPANSION OF CRD AND IN-CORE 09/97 09/97 i
INSTRUMENT PENETRATIONS IN BWR VESSELS (BWRVIP-17)
REVIEW CORE PLATE INSPECTION AND FLAW 09/9 7 09/97 4
EVALUATION GUIDELINE (BWRVIP-25)
REVIEW TOP GUIDE INSPECTION AND FLAW 09/97 09/S7 EVALUATION GUIDELINE CLOSE OUT ACTIVITY 4
t t
i AS OF FY97 QUARTER 2 I
'I l
i f
r
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM P4GE:
74 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: NMSS/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 JULY 28, 1995 FIN CONTRACTOR CONTRACT TITLE W0RK SC0PE kbhIbkS kkbLbbkb Ik ikk PLkN kkkI k RhVkkb k bb GkhkR L bbhbLbPbbRRkbThkkbh5bNkFbREbHPRb8LkH kNb ISSUE AND IDENTIFY THE SPECIFIC PR B EMS TO BE ADDRESSED.
IMPLEMENT THE CORRECTIVE ACTIONS.
STATUS THE FOLLOWING ACTION PLAN ISSUES HAVE BEEN COMPLETED:
HAS BEEN ISSUED FOR COMMENT. PUBLIC COMMENTS ARE DUE BY CASK TRUNNIONS, CASK WEEPING, HYDROSTATIC TESTING, SAFE-JUNE 18 ISOS. ALL OF THE COMMUNICATIONS ISSUES ARE ONGOING GUARDS CONCERNS, PART 72 REPORTING REQUIREMENTS, INSPECTION EFFORTS WITH NO SPECIFIC CRITERIA FOR CLOSURE. HOWEVER, OF SITE ACTIVITIES. AND VENDOR INSPECTIONS. THE INSPECTION THERE HAVE BEEN SIGNIFICANT IMPROVEMENTS IN THESE AREAS.
PROCEDURES FOR DRY CASK ACTIVITIES (SITE AND VENDOR) WERE THE REGIONS, NMSS, AND NRR HOLC REGULAR INTERFACE CALLS TO ISSUED IN FLBRUARY 1996.
THESE PROCEDURES INCLUDED RESOURCE DISCUSS DRY CASK ISSUES. TRAINING HAS BEEN GIVEN TO THE ESTIMATES FOA 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 UNLDADING 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 ECO FOR THE REVIEW OF THE FIRST SUBMITTAL FOR ISSUES ASSOCIATED WITH CASK LOADING AND UNLUADING. 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/SFPO INCLUDING THE PREPARATION OF AN INFORMATION NOTICE SPONSORED A PUBLIC WORKSHOP ON 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 LOAD CONTROL) IS ON SCHEDULE. A 50.59 ISSUE STORAGE PROGRAM ON MAY 30, 1996.
IN RESPONSE TO A INVOLVING HEAVY LOAD CONTROL IN GENERAL IS THE SUBJECT OF HYDROGEll IGNITION EVENT AT POINT BEACH ON MAY 28. THE STAFF NRC BULLETIN 96-02 ISSUED APRIL 11, 1996.
THE DRAFT SRP ISSUED INFORMATION NOTICE 96-34 ON MAY 31, 1996.
AS OF FY97 QUARTER 2 O
O O
c,
.....~
~ -...
.. ~,...,,, ~
~,
k O
v t
~
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
75-ISSUE NUMBER: RGA 003 TITLE: DRY CASK ~ STORAGE OF SPENT FUEL AFFECTED DOCUMENTS
' PROBLEM / RESOLUTION
- T 0 BE DETERHINED NONE ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE
.DATE ISSUE IN ON SEISMIC REQUIREMENTS FOR PADS 06/95 06/95 DEVELOP ACTION PLAN 07/95 07/95 MEET WITH NEI ON CASK WEEPING 08/95 08/95 DEVELOP POSITION ON REPORTING REQUIREMENTS 09/,4's 09/53
[2VELOP STAFF POSITION ON CASK TRUNIONS 09/95 09/95 i
FORM WORKING GROUP ON CASK LOADING /UhLOADING 10/95 10/95 PROCEDURES DEVELOP WORKING GROUP PLAN ON HEAVY LOADS /
11/95 11/95 l
CRANES f
HYORDSTATIC TESTING 12/95 12/95 COMPLETE ANALYSIS OF SAFEGUARDS DESIGNS 12/95 12/95 1
. ISSUE REVISED PROCED!!RES FOR VENDOR 02/S6 02/96
+
INSPECTIONS ISSUE REVISED PROCEDURES FOR INSPECTION OF 02/96 02/96 SITE ACTIVITIES ISSUE SRP AND 10 CFR 50.59 GUIDANCE 03/96 03/96 I
COMPLETE ACTION ON HEAVY LOADS / CRANES 12/96 12/96 REVIEW PROPOSED SOLUTIONS FOR FAILED FUEL 03/97 03/97 STORAGE I
i I
AS OF FY97 QUARTER 2 f
1 RUN DATE: 05/23/97 GENERIC ISSUE MA.<AGEMENT CONTROL SYSTEM PAGE:
76 ISSUE NUMEER: RGA 003 TITLE: DRY CASK STORAGE OF SPENT FUEL ORIGINAL CURRENT ACTUAL MILE $T0NES DATE DATE DATE CLbSE bbh bhIhkkh i
I t
6 r
t i
i b
I i
i t
AS OF FY97 QUARTER 2 i
i i
l l
{
t O
O O
m
4 r~
(
Lj)
LJ (w.J' l
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
77 ISSUE NUMBER: RGA 005 TITLE: RCS DRAINDOWN IDENTIFICATION DATE: 02/9BC 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: 04/98 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)UED 03/25/96:
IN 95-03 ISSUED 01/12/95,AND SUPPLEMENT TO IN 95-03 N DRAINDOWN VULNERABILITIES AND THE HEASURES THEY ISS IMPLEMENTED TO DIMINISH THE PROBABILITY OF A DRAINDOWN.
(2) REQUEST ALL PWR LICENSEES. VIA AN INFORMATION GATHERING STATUS bhikkbikbEkkkbbETEbb5/2h/bh[Cbkk[kkkbhRkQbikkk hTbbbkkbkkkkLLkbbkkbbkCERh[kbkkbbLkTbkhkkb THAT CERTAIN REFERENCES TO GDC 34 AND 35 SHOULD BE REPLACED LICENSING REQUIREMENTS.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION IN 95-03 COMMISSION RE UIREMENTS, AS STATED A30VE. WILL HAVE IMPACT AEOD/S95-01 ON THE DATE O ISSUE OF THE GL.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE IN 95-03 ISSUED 01/95 01/95 DRAFT GL 11/95 11/95 AS OF FY97 QUARTER 2
~
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMEh.~ C00 TROL SYSTEM PAGE:
78 ISSUE NUMBER: RGA 00S TITLE: RCS DRAINDOWN ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE ISSUE SUPPLEMENT 1 TO IN 95-03 03/96 03/96 GL TO CRGR 06/96 08/S6 COMPLETE ORAFT TI-ISSUE TO REGIONS FOR 06/96 08/97 COMMENTS ISSUE GENERIC LETTER 06/S6 08/97 RECEIVE REGIONAL COHMENTS ON TI 08/96 10/97 COMPLETE EVALUATION OF RESPONSES TO GL 11/96 01/98 ISSUE TI 11/96 01/98 COMPLETE INSPECTIONS 02/97 04/98 CLOSE OUT ACTIVITY 11/97 04/98 AS OF FY97 QUARTER 2 O
O O
-3 g.
/
\\
f i
A N
.Y RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
79 ISSUE NUMBER: RGA 006 TITLE: SRP REVISION IDENTIFICATION DATE: 02/96C PRIORITIZATION DATE:
TYPE:
PRIORITY:
TAS% MANAGER: A. MASCIANTONIO OFFICE / DIVISION / BRANCH: NRR / DISP /PIPB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: M40047 MB3832 RESOLUTION DATE:
WORK AUTHORIZATION: MEMORANDUM FROM J. TAYLOR TO THE CHAIRMAN ON 11/IB/91.
FIN CONTRACTOR CONTRACT TITLE W0RK SC0D E SPECIFIC TASKS INCLUDED IN THE ACTION PLAN ARE: I) IDENTIFY INCORPORATE THE CHANGES RECOMMENDED: 4 PREPARE NEW DRAFT ESTABLISHED STAFF POSITIONS AND HEW REGULATORY REQUIREMENTS SRP SECTIONS THAT ARE SUPPORTED BY EST BLISHED STAFF FROM A 3EVIEW OF SENERIC 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:
REQUIREMENTS.
- 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 MEW SRP SECTION DEVELOPMENT. BOTH AVAILABLF BASIS CONSISTENT WITH A PRIORITY 3 EFFORT. AN CONTRACTORS HAVE COMPLETED DRAFT PEVISION 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.
AFFEC1ED DOCUMENTS PROBLEM / RESOLUTION NUREG-0800 NONE.
AS OF FYS7 QUARTER 2
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
80 ISSUE NUMBER: RGA 006 TITLE: SRP REVISION s
GRIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE TAP APPROVED 05/94 05/94 CLOSE OUT ACTIVITY l
)
L AS OF FY97 QUARTER 2 O
O O
_~ ~__.... - -.
.~
"N
]
\\
)
\\
w)
Q/
\\
RUN DATE: 05/23/97 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
81 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 M9244B M92449 MS86SO M91431 RESOLUTION DATE:.
WORK AUTHORIZATION:
FIN CONTRACTOR CONTRACT TITLE WORK SCOPE
[
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 OURING THE EVALUATION OF DEVELOPED DRAFT GUIDANCE TO FORMULATE REGULATORY GUIDANCE VOLUNTEER PLANT ACTIVITIES.
ON ALCEPTABLE METHODS FOR IMPLEMENTING GRADED QA.
THE IN ADDITION TO THE ABOVE, THE FOLLOWING TAC NUMBERS STAFF WILL DEVELOP A REGULATCRY GUIDE. A STANDARD REVIEW WERE INITIATED: M91432 M91433, M91434, M91435 M91436, PLAN REVISION FOR CHAPTER 17 AND A REACTIVE INSPECTION AND M91437.
PROCEDURE (IP) FOR GRADED QA.
AN INTEROFFICE TEAM HAS BEEN STATUS OUTLINES OF A DRAFT REG. GUIDE AND SRP FOR BOTH RISK CONTRACTORS). STAFF COMMENTS VERE PROVIDED TO STP DURING RANKING AND GRADING OF QA CONTROLS HAVE BEEN PREPARED AND A MEETING ON JUNE 19 AND VIA LETTER DATED AUSUST 16, 1996.
CIRCULATED FOR REVIEW FOR THE INTEROFFICE TEAM. A MEETING STAFF IS AWAITING SUBMITTAL OF A REVISED QA PROGRAM.
- ALSO, WAS HELD WITP THE THREE VOLUNTEER LICENSEES ON APRIL 11 NEI SUBMITTED 96-02, " GUIDELINE FOR IMPLEMENTING A GRADED 1996. TO RECLIVE THEIR FEEDBACK ON THE STAFF DEVELOPED APPROACH TO QUALITY DATED MARCH 21, 1996.
THE STAFF HAS EVALUATION GUIDE. THE LICENSEES EXPRESSED CONCERNS ABOUT PERFORMED A CURSORY REVIEW OF THE DOCUMENT AND CONCLUDED THE LEVEL OF DETAIL CONTAINED IN THE GUIDE. PARTICULARLY THAT IT DOES NOT REFLECT THE PROGRESS AND LEVEL OF DETAIL THAT RELATED TO PRA AND COMMERCIAL GRADE ITEM DEDICATION.
THAT HAS BEEN ACHIEVED THROUGH THE VOLUNTEER PLANT EFFORT.
THE LICENSEES CONTEND THAT EXISTING INDUSTRY GUIDANCE (PSA THE STAFF INFORMED NEI BY LETTER DATED MAY 2, 1996. THAT APPLICATION GUIDE AND EPRI-56S2) 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.
NEI. SUBMITTED AN UPDATED VERSIDN 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.
nS OF FY97 QUARTER 2
= _ _ _ _ = - _
RUN DATE: 05/23/97 EENERIC ISSUE RANAGEMENT CONTROL SYSTEM
- ?GE:
82 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 IMPLEMENTATIONS 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 COULD DIVERT STAFF RESOURCES FROM THIS ACTION PLAN EFFORT. THE IMPOSITION OF COMMISSION LEVEL APPROVAL OF QA PROGRAM CHANGES THAT RELY ON RISK INFORMED DECISIONMAKING INVOLVING POLICY ISSUES COULD 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 TEXAS)
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 ISSUE LTR TO 3 VOLUNTEER PLANTS OUTLINING PRO 01/96 01/96 GRAM OBJECTIVES & REVIEW EXPECTATIONS. DIS-TRIBUTE STAFF EVALUATION GUIDE TO LICENSEES.
EVALUATION GUIDE ISSUED FOR USE BY STAFF IN 01/95 01/96 EVALUATING VOLUNTEER PLANTS AS OF FY97 QUARTER 2 O
O O
. _.~
- =
- ,
d V
U
^
RUN DATE: 05/23/97 GENERIC ISSUE. MANAGEMENT CONTROL SYSTEM PAGE:
83 1SSUE NUMBER: RGA 007.1.2D TITLE: PRA IMPLEMENTATION PLAN - GRADED QA L
ORIGINAL CURPENT ACTUAL Ji MILEST0NES DATE
.DATE DATE.
ACRS BRIEFING: EXPERT PANEL AND DETERMINIS-02/96 02/96 t
TIC CONSIDERATIONS ACRS BRIEFING: GRADED QA 04/96 04/96 MEETING HELD WITH VOLUNTEER PLANTS TO RECEIVE 04/96 04/96 FEEDBACK ON STAFF EVALUATION GUIDE ON 04/11/96.
INDUSTRY COMMENTS ON STAFF EVALUATION GUIDE 05/96 05/96
'PROVIDED DRAFT SRP AND RG FOR COGNIZANT OFFICE 07/96 10/96 REVIEW AFD COMMENT
-v 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 06/97 PLANTS ISSUE LESSONS' LEARNT.D NUREG REPORT REGARDING 02/97 09/97 GRADED QA PROGRAMS AT VOLUNTEER PLANTS FINA* DRAFT SRP AND RG FOR ACR$/CRGR REVIEW 09/07 09/97 ISSUE STAFF INSPECTION GUIDANCE (REACTIVE 05/97 12/97 IP) t FINAL DRAFT SRP AND RG FOR INTEROFFICE 12/57 12/97 CONCURRENCE 4
PUBLISH FINAL SRF T RG 17/97 12/97 I
s i
AS OF FY97 QUARTER 2 y
)
~
RUN DATE: 05/23/S7 GENERIC ILSUE MANAGEMENT COCTROL SYSTEM PAGE:
G4 ISS*JE NUMBER: RGA 007.1.20 TITLE: PRA IMPLEMENTATION PLAN - GRADED QA ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE
....---------~~--------------------------
CONDUCT NRC STAFF TRAINING 05/97 01/93 PUBLIC WORKSHOPS ON GRADED QA 02/97 02/98 ISSUE SECY UPDATE (CLOSEOUT OF ACTION PLAN) 12/97 04/98 k
i t
AS OF FY97 QUARTER 2 O
O O
.