ML20056G020
| ML20056G020 | |
| Person / Time | |
|---|---|
| Issue date: | 08/06/1993 |
| From: | Beckjord E NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Taylor J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| References | |
| REF-GTECI-MI, REF-GTECI-SC NUDOCS 9309010170 | |
| Download: ML20056G020 (134) | |
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UNITED STATES l
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NUCLEAR REGULATORY COMMISSION i
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f wAsmucTON, D.C. 20555 AUG b 61333 l
MEMORANDUM FOR:
James M. Taylor j
Executive Director for Operations FRON:
Eric S. Beckjord, Director Cffice of Nuclear Regulatory Research I
SUBJECT:
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM - THIRD QUARTER FY-93 UPDATE l
Enclosed is the Third Quarter FY-93 update of the Generic Issue Management Control System (GIMCS) for your information. This report reflects the following major activities that occurred during the reporting period.
l (1)
Six generic safety issues (GSIs) were resolved:
i 105 (HIGH)
Interfacing Systems LOCA at LWRs l
142 (MEDIUM)
On-Line Testability of Protection Systems l
i 153
(!i!GH)
Loss of Essential Service Water in LWRs B-56 (HIGH)
Diesel Reliability HF5.1 (HIGH)
Local Control Stations i
HF5.2 (HIGH)
Review Criteria for Human Factors Aspects i
of Advanced Controls and Instrumentr tion i
(2)
Two GSIs were prioritized:
l 166 (NEARLY-Adequacy of Fatigue Life of Metal RESOLVED) Components 168 (NEARLY-Environmental Qualification of Electrical RESOLVED) Equipment I
(3)
Three new generic issues were identified.
In response to your July 16, 1993 memorandum, RES conducted a review of the
[
six non-safety generic issues previously tracked in GIMCS and removed two l
Regulatory Impact issues: 119.4 and 119.5. Of the four Licensing Issues, I.D.5(5) and 67.5.1 will be closed out sy the end of FY-93; GSIs 147 and 148 are being resolved as part of the IPEEE review guidance that is now being i
developed.
9309010170 930806 i
PDR ORG NREA
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PDR 3/
AUG 0 61933 cc: w/ enclosure RES NRR C. Ader, NLS-324 G. Barber, 12E4 R. Baer, NLS-314 M. Malloy,11H3 R. Emrit, NLS-314 R. Borchardt, 13E4 F. Cherny, NLS-314 P. Cota, 12D20 F. Coff; nan, NLN-316A F. Gillespie,12G18 T. King, NLS-007 W. Long, 13H15 J. Murphy, NLS-007 T. Murley, 12G18 G. Marino, NLS-007 J. Richardson, BH3 G. Mazetis, NLS-324 A. Gautam, 9Al W. Minners, NLS-007 T. Boyce, 11H3 J. Flack, NLS-324 J. Wilson, 11H3 A. Murphy, NLS-007 C. Miller, 11H3 P. Norian, NLS-314 J. Persensky, NLN-316 J. Heltemes, NLS-007 NMSS i
T. Ryan, NLN-316 R. Bernero, 6E6 C. Serpan, NLS-217C R. Bangart, SE4 L. Shao, NLS-007 B. Sheron, NLS-007 AEOD l
L. Shotkin, NLN-353 E. Jordan, 3302 T. Speis, NLS-007 H. Bailey, 5211 R. Kornasiewicz, NLS-260 T. Novak, 3701 L. Soffer, NLS-324 J. McCausland, NLS-139 P. Kadambi, NLS-314 REGIONS
/
H. VanderMolen, NLS-372 T. Martin, Region I r
l M. Cunningham, NLS-372 S. Ebneter, Region II A. Davis, Region III J. Milhoan, Region IV OTHERS J. Martin, Region V M. Taylor, EDO, 17G21 D. Adams, ACRS, P-315 S. Duraiswanty, ACRS (6), P-315 J. Kopeck, 265 K. Olive, 10204 i
H. Schecter, IP, 3H5 W. Usilton, P-612 PDR i
'O ENCLOSURE GENERIC ISSUE MANAGEMENT CONTROL SYSTEM THIRD QUARTER FY-93 UPDATE OFFICE OF NUCLEAR REGULATORY RESEARCH JULY 1993 O
O umM
i ii M OF CONTJg75 (a)
Generic Issue Management Control System (1)
Description (2)
Abbreviations (b)
Table 1 -
Generic Safety issues Scheduled for Resolution Issues Resolved, and Issues Integrated
{-
(c)
Table 1A -
Resolution, Issues Ro olved, and Issues IrtegS (d)
Table 2 -
rated Number of Generic Safety Issues Resolved and Scheduled for Resolution (Through 3rd Ouarter FY 93)
(e)
Table 3 -
Generic Safety Issues Resolved by Fiscal s' ear (f)
Table 4 -
Generic Safety Issues Scheduled for Resolution (by Fiscal Year)
(g)
Table 4A -
Generic Safety Issues Scheduled for Resolution (by Priority)
(h)
Table 5 -
Number of Generic Issues Prioritized from FY 83 through the 3rd Quarter of FY-93 (i)
Table 6 -
Generic issues Prioritized as of 3rd Quarter FY 93 (j)
Table 7 -
Generic Issues to be Prioritized (k)
Table 8 -
Generic Issues to be Reprioritized (1)
Table 9 -
Regulatory Impact Issues Sched>> led for Resolution (m)
Table 10 -
Licensing Issues Scheduled for Resolution (n)
Work Scope & Schedules for each Approved Generic I ssue
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ENCLOSURE I
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GENERIC ISSUE MANAGEMENT CONTROL SYSTEM THIRD QUARTER FY-93 UPDATE l
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OFFICE OF NUCLEAR REGULATORY RESEARCH i
JULY 1993 t
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TABLE OF CONTENTS (a)
Generic Issue Management Control System (I)
Description (2)
Abbreviations (b)
Table 1 -
Generic Safety Issues Scheduled for Resolution, Issues Resolved, and Issues Integrated (c)
Table 1A - Summary of Generic Safety Issues Scheduled for Resolution, Issues Resolved, and Issues Integrated (d)
Table 2 -
Number of Generic Safety Issues Resolved and Scheduled for Resolution (Through 3rd Quarter FY-93)
(e)
Table 3 -
Generic Safety Issues Resolved by Fiscal Year (f)
Table 4 -
Generic Safety Issues Scheduled for Resolution (by Fiscal Year)
(g)
Table 4A - Generic Safety Issues Scheduled for Resolution (by Priority)
T (h)
Table 5 -
Number of Generic Issues Prioritized from FY-83 through the 3rd Quarter of FY-93 (i)
Table 6 -
Generic Issues Prioritized as of 3rd Quarter FY-93 (j)
Table 7 -
Generir. Issues to be Prioritized (k)
Table 8 -
Generic Issues to be Reprioritized (I)
Table 9 -
Regulatory Impact Issues Scheduled for Resolution (m)
Table 10 - Licensing Issues Scheduled for Resolution (n)
Work Scope & Schedules for each Approved Generic Issue O'
f l
iii GENERIC ISSUE MANAGEMENT CONTROL 5" STEM DESCRIPTION
~
l' The Generic Issue Management Control System (GIMCS) provides appropriate inft,rmation 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 i
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 l
been incorporated into one or more of the following documents:
l (a)
Commission Ordet (e)
Regulatory Guide l
(b)
NRC Policy Statement (f)
Generic Letter (c)
Rule (g)
Bulletin
[
(d)
Standard Review Plan (SRP)
(h)
Information Notice GIMCS is part of an integrated system of reports and procedures that is designed to manage generic safety issues through the stages of prioritization and resolution (development of new criteria, management review and approval, public comments, and incorporation into the regulations, as appropriate), The priority evaluation for each issue listed in this report is contained ia NUREG-0933, "A Prioritization of Generic Safety Issues." The procedur<e and
^
criteria for adding new generic issues to the system are outled in RES Office Letter No. 1.
(Prior to the NRC reorganization of Apri. 12, 1937, NRR Office Letter No. 40 was used for identifying new issuer ) Guidance for resolving issues is provided in RES Office letter No..
GIMCS provides the proposed schedules for managing and controlling the resolution of: (1) issues that are ranked HIGH-priority; (2) issues that are i
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 i
issues designated to receive resources for resolution. Issues ranked as either LOW or DROP are not allocated resources for resolution and, thern ore, l
are not tracked in GIMCS.
Some prioritized generic issues may not have resources allocated for resolu-tion; these issues are listed in GIMCS as inactive issues. Generally, these will be MEDIUM-priority issues that have no safety deficiency demanding high-priority attention, but have potential for safety improvements or reduction in uncertainty of analysis that may be substantial and worthwhile. Efforts for i
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 1
is monitored by GIMCS.
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iv ANPRM Advance Notice of Proposed Rulemaking BNL Brookhaven National Laboratory BTP Branch Technical Position DTR Draft Technical Resolution EPRI Electric P.wer Research Institute FIN Financial Identification Number FRN Federal Register Notice FTR Final Technical Resolution GL Generic letter GSI Generic Safety Issue H
High-priority GSI 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 PNL Pacific Northwest Laboratories PRA Probabilistic Risk Assessment RAI Request for Additional Information l
RG Regulatory Guide R1 Regulatory Impact 5
Subsumed in Another Issue (No.)
S0W Statement of Work SRP Standard Review Plan STS Standard Technical Specification T/A Technical Assistance TAP Task Action Plan TBD To be Determined T1 Temporary Instruction TS Technical Specification USl Unresolved Safety Issue O
V DATA ELEMENTS Management and control indicators used in GIMCS are defined as follows:
I.
Issue No.
- Generic Issue Number 2.
Title
- Generic Issue Title I
l 3.
Jdentification Date
- Date the issue was identified 4.
Prioritization Datg
- The date that the prioritization evaluation j
was approved by the RES Director 5.
Tyng
- Generic Safety (GSI), Licensing (LI), or Regulatory Impact (RI) 6.
Priority
- High (H) or Medium (M) 7.
Task Manaaer
- Name of assigned individual responsible for resolution 8.
Office / Division / Branch - The Office, Division, and Branch of the Task Manager who has lead responsibility for resolving the issue.
9.
Action level
- Active Technical assistance funds appropriated for resolution and/or Task Manager actively pursuing resolution Inactive -
No technical assistance funds appropriated for resolution, Task Manager L6 signed 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 N2 requirements);
5 - (Licensing or Regulatory Impact issue that has been assigned resources for completion)
II.
TAC Number
- Task Action Control (TAC) number assigned to the issue
vi 12.
Resolution Date
- Scheduled resolution date for the issue
~
13.
Work Authorization
- Who or what authorized work to be done on the issue 14.
EIN
- Financial identification number assigned to contract (if any) for technical assistance 15.
Contractor
- Contractor name 16.
Contract Title
- Contract litle (if contract issue) 17.
Work Scope
- describes briefly the work necessary to technically resolve and complete the generic issue 18.
Status
- Describes current status of work 19.
Affected Documents
- Identifies documents into which the technical resolution will be incorporated 20.
Problem / Resolution
- Identifies problem areas and describes what actions are necessary to resolve them 21.
Milestones
- Selected significant milestones:
(a) the " original" scheduled dates reflect 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"
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O' TA8LE 1 GENERIC SAFETY ISSUES SCHLDULED FOR RESOLUTION.
l ISSUES RESOLVED AND ISSUES INTEGRATED FY-83111ROUGil FY-93 (3RD OVARTER)
FY-83 FY-84 FY-85 ISSUE Gls New Gis Gis New Gis Gls New Gis TYPE Start +
issues - Resolved - End Start +
Issues - Resolved - End Start +
issues - Resolved - End i
USI 16 0
2 14 14 0
2 12 12 0
0 12 IIIGil 24 2
0 26 26 1
1 26 22*
41 6
57 MEDIUM 31 2
0 33 33 4
3 34 28*
1
'10 19 l
NR 20 3
4 19 19 5
9 15 15 11 7
19 10iAL:
91 7
6 92 92 10 15 87 77 53 23 107 FY-86 FY-87 ISSUE Gis New Gis ISSUE GIs New Gls Gls TYPE Start +
Issues - Resolved - End TYPE Start + lssues
- Resolved - Integrated End USI 12 0
1 11 USI 11 0
2 0
9 lilGH 57 (16)*
3 38 tilGil 38 4
3 7
32 MEDIUM 19 7
2 24 NE010M 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
- Extenstee revisions to Human factors issues resulted in priority changes.
T1-1 As of 3rd Quarter FY-93
TABLE 1 (Continued)
GENERIC SAFETY ISSUES SCllEDULED FOR RESOLUT10th ISSUES RESOLVED AND ISSUES INTEGRATED fY-83 TliROUGil FY-93 (3RD OUARTER)
FY-88 FY-89 ISSUE Gis New Gis Gis ISSUE GIs New Gis GIs TYPE Start +
lssues - Resolved - Integrated - End TYPE Start +
lssues - Resolved - Integrated - End USI 9
0 5
0 4
USI 4
0 4
0 0
llIGil 32 1
6 3
24 lilGil 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 Gis New Gis Gis ISSUE Gis New Gis GIs TYPE Start + Issues - Resolved - Integrated - End TYPE Start +
lssues - Resolved - Integrated - End ilIGil 16 0
2 0
14 IIIGil 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 ISSUE Gis New Gis Gis TYPE Start + Issues - Resolved - Integrated - End lilGil 14 0
4 0
10 MEDIUM 11 1
2 0
10 NR 4
2 1
0 5
TOTAL:
29 3
7 0
25 T1-2 As of 3rd Quarter F Y-93
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TABLE I (Continued)
GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION.
ISSUES RESOLVED AND ISSUES INTEGRATED FY-83 THROUGH FY-93 (3RD OUARTER)
FY-93 ISSUE Gls New Gls Gls TYPE Start + issues
- Resolved - Integrated -
End S
filGli 10 0
5 0
5 NEDIUM 10 0
2 0
8 NR S
2 0
0 7
TOTAL:
25 2
7 0
20 f
I 8
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t 1
TI-3 As of 3rd Quarter FY-93
- - - - - _ _ _ _ _. -. - - - - _ _ _ _ - - - _.. _ _ _ _ _ _ _ _ -. - -, - - _ _ _. _ _, _ - -... -.,, _ _. _ -...- _. +. ~.. --., - - - -
Table 1A
SUMMARY
OF GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION.
ISSUES RESOLVED. AND ISSUES INTEGRATED Cumulative Totals FY-83 Through FY-93 (3RD Ouarterl ISSUE GIs New Gls Gis TYPE Start + 1ssues - Sub-Total - Resolved -
Integrated" - Remainder USI 16 0
16 16 0
0 lilGli 24 32*
56 41 10 5
MEDIUM 31 17 48 31 9
8 NR 20 22*
42 34 1
7 TOTAL:
91 71 162 122 20 20
- Extensive revisir,ns to Human factors issues resulted in priority changes in FY-85 and FY-86.
" Gls 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.l.b into Issue 124 issues I.B.I.l(6) and I.B.I.l(7) into issue 75 issue B-6 into issue 119.1 issue 67.7 into 135 FY-88:
Issue 77 into A-17 Total (6)
Issues I.D.5(5), II.B.5(1), II.B.5(2), II.B.5(3), and II.F.5 were integrated into the Research Activities Program and were reclassified as Licensing Issues.
FY-89:
Total (1)
Issue 131 was integrated into the External Events IPE Program.
T1-4 e
e As of 3rd&' rt
TABLE 2 NUMBER OF GENERIC SAFETY ISSUES RESOLVED AND SCHEDULED FOR RESOLUTION fThrouah 3RD Ouarter FY-93)
RESOLVED ISSUE PRIORITY FY-83 FY-84 FY-85 FY-86 FY-87 FY-88 FY-89 FY-90 FY-91 FY-92 FY-93 TOTAL USl 2
2 0
1 2
5 4
0 0
0 0
16,~
HIGH 0
1 6
3 3
6 9
2 2
4 5
41 HEDIUM 0
3 10 2
4 2
3 2
1 2
2 31 NR 4
9 7
3 1
3 2
3 1
1 0
34 Total:
6 15 23 9
10 16 18 7
4 7
7 122 StilEDULED FOR RESOLUTION ISSUE PRIORITY FY-93 FY-94 FY-95 FY-96 TBD Total HIGH 2
1 1
1 0
5 MEDIUM 1
4 1
1 1
8 i
NR 2
2 0
0 3
7 i
Total:
5 7
2 2
4 20 l
l l
T2-1 As of 3rd Quarter IY-93 1
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TABLE 3 GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR
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issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved IY-83 l
A-Il Reactor Vessel Materials USI GL 82-26 01/79 10/82' Toughness A-16 Steam Effects on BWR Core Spray NR MPA D-12 NRR-OP FY83 03/29/83 1
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-OP FY83 07/28/83 II.E.5.1 (B&W) Design Evaluation NR No. Req.
NRR-OP FY83 03/21/83 IV.C.1 Extend lessons Learned From NR No Req.
NRR-OP FY83 04/15/83 TMI to Other NRC Programs FY-84 12 BWR Jet Pump Integrity Medium No. Req.
NRR-OP FY83 09/25/84 20 Effects of Electromagnetic NR NUREG/
NRR-OP FY83 11/15/83 Pulse on Nuclear Plant Systems CR-3069 40 Safety Concerns Associated NR MPA B-65 07/18/83 12/27/83 With Breaks in the BWR Scram System 45 Inoperability of Instruments NR SRP Revision 09/08/83 03/23/84 Due to Extreme Cold Weather T3-1
. As of 3rd Quarter FY-93 L-.
- - - -. - - -.. ~..., - -.... - -.. - - - -....
TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-84 (Cont'd) 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 llammer 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 til High SRP Revision NRR-OP FY83 09/10/84 Containments B-26 Structural Integrity of Medium No Req.
NRR-OP FY83 09/27/84 Containment Penetrations B-60 Loose Parts Monitoring NR GL NRR-OP FY83 09/25/84 Systems (LPMS) 1.A.I.4 Long-lerm Upgrading of NR New Rule NRR-OP fY83 01/01/84 Operating Personnel ll.A.1 Siting Policv Reformulation Medium No Req.
NRR-OP FY83 09/20/84 II.E.5.2 (B&W) Reacto.
.ansient NR NUREG-0667 NRR-0P FY83 09/28/84 Response Task force 111.0.2.5 Offsite Dose Calculation Manual NR NUREG/
NRR-OP FY83 01/17/84 CR-3332 T3-2 As of 3rd Quarter FY-93 O
O O.
Y 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-0P FY83 10/10/84 '
B-19 Thermal-Hydraulic Stability NR GL 01/03/85 05/21/85 B-54 Ice Condenser Containments Medium NUREG/
NRR-OP FY83 10/22/84 CR-4001 i
B-58 Passive Mechanical Failures Medium No Req.
NRR-0P FY83 07/09/85 C-Il Assessment of Failure and Medium No Req.
NRR-0P FY83 07/09/85 Reliability of Pumps and Valves l
1.A.2.2 Training and Qualifications High Policy NRR-OP FY83 06/24/85 of Operating Personnel Statement (No Req.)
1.A.2.6(4)
Operator Workshops Medium No Req.
NRR-0P FY83 09/25/85 I
1.A.2.7 Accreditation of Training Medium Policy NRR-OP FY83 06/24/85 Institutions Statement l
(No Req.)
{
I.A.3.4 Licensing of Additional Medium Policy NRR-OP FY83 02/12/85 Operations Personnel Statement (No Req.)
l.G.2 Scope of Test Program Medium No Req.
NRR-OP FY83 10/05/84
[
l T3-3 As of 3rd Quarter FY-93
TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved TY-85 (Cont'd)
II.B.6 Risk Reduction for Operating fligh No Req.
NRR-0P FY83 09/25/85 Reactors at Sites With High Population Densities II.B.8 Rulemaking Proceedings on liigh Degraded Core Accidents (a) flydrogen Rule Rule /
NRR-OP FY83 07/19/65 (b) Severe Accidents Policy NRR-0P TY83 08/12/85 Statement II.C.1 Interim Reliability Evaluation liigh No Req.
NRR-OP TY83 07/09/85 Program II.C.2 Continuation of Interim liigh No Req.
NRR-0P TY83 09/25/85 Reliability Evaluation Program II.E.2.2 Research on Small-Break LOCAs Medium No Req.
NRR-OP FY83 07/25/85 and Anomalous Transients III.A.I.3(2)
Maintain Supplies of Thyroid-NR Policy NRR-OP FY83 08/15/85 Blocking Agent for Public Statement III.A.3.4 Nuc1 car Data link Medium No Req.
NRR-0P TY83 06/26/85 111.D.2.3(1)
Develop Procedures to Dis-NR ESRP NRR-OP FY83 08/28/85 criminate Between Sites / Plants Revision III.D.2.3(2)
Discriminate Between Sites NR ESRP NRR-OP FY83 08/28/85 and Plants that Require Revision Consideration of liquid Pathway Interdiction Techniques III.D.2.3(3)
Establish feasible Method of NR ESRP NRR-OP FY83 08/28/85 Pathway Interdiction Revision 13-4 As of 3rd Quarter FY-93
L TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED 8Y FISCAL YEAR Issue Resolution Date Approved Date Number Titic Priority Product for Resolution Resolved 4
FY-85 (Cont'd) lil.D.2.3(4)
Prepare a Summary Assessment NR ESRP NRR-OP FY83 08/28/85 r
Revision IV.E.5 Assess Currently Operating liigh No Req.
NRR-0P FY83 09/25/85 Plants FY-86 3
Setpoint Drift in NR Reg Guide NRR-OP FY83 05/19/86 Instrumentation Rev.
(No Req.)
14 PWR Pipe Cracks NR No Req.
NRR-OP 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 11 Containments A-43 Containment Emergency USI SRP Revision 01/19 10/85 l
Sump Performance (Req.)
I.C.9 Long-Term Plan for Upgrading Medium No Req.
NRR-0P FY83 06/07/85 of Procedures 111.D.3.1 Radiation Protection Plans liigh No Req.
NRR-0P FY83 05/19/06 IlF1.2 Engineering Expertise on fligh No Req.
10/01/84 10/28/85 l
Shift ilFl.3 Guidance on limits and liigh No Req.
10/01/84 06/26/86 Conditions of Shift Work i
T3-5 As of 3rd Quarter F Y-93 l
TA8LE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-87 91 Main Crankshaft failures in NR NUREG-1216 07/85 09/87 Transamerica Delaval Diesel (No Req.)
Generators A-46 Seismic Qualification of USI GL 87-02 02/81 02/87 Equipment in Operating Plants (Req.)
A-49 Pressurized Thermal Shock USI Rule / Reg.
12/81 02/87 Guide 1.154 (Req.)
1.A.2.6(1) long-Term Upgrading of liigh Reg. Guide 10/82 05/87 Training and Qualifications -
1.8 (Req.)
Revise Reg. Guide 1.8 1.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 0S/87 Simulators 1.149, Rev. 1 (Req.)
1.B.1.1 Organization and Management Lona-Term improvements I.8.1.l(1)
Prepare Draft Criteria Medium No Req.
12/82 01/87 I.B.I.l(2)
Prepare Commission Paper Medium No Req.
12/82 01/87 I.B.I.l(3)
Issue Requirements for the Medium No Req.
12/82 01/87 Upgrading of Management and Technical Resources I.8.1.l(4)
Review Response to Determine Medium No Req.
12/82 01/87
. Acceptability T3-As of 3rd ter FY-93 w
n--
~ n n
c
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 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 1
(Req.)
i 93 Steam Binding of Auxiliary liigh GL 88-03 10/84 02/88 Feedwater Pumps (No Req.)
1.D.4 Control Room Design Standard Medium No Req.
NRR-OP FY83 03/88 II.E.4.3 (Containment) Integrity Check liigh NUREG-1273 NRR-OP FY83 03/88 (No. Req.)
B-5 Ductility of Two-Way Medium No Req.
NRR-0P FY83 04/88 Slabs and Shells and Buckling Behavior of Steel Containments lif8 Maintenance and Surveillance fligh Policy 03/85 05/88 Program Statement (No Req.)
1.A.4.2(4)
Review Simulators for liigh Rule NRR-OP FY83 05/88 Conformance (Req.)
A-44 Station Blackout USI Rule / Reg.
01/79 06/88 Guide 1.155 (Req.)
43 Reliability of Air Systems liigh GL 88-14 12/87 09/88 (Req.)
1 T3-7 As of 3rd Quarter FY-93
~-._,_
LI M EU Mum m TABLE 3 (Continuedl GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-88 (Cont'd) 66 Steam Generator Requirements NR NUREG-0844 11/83 09/88 (No Req.)
102 Iluman Error in Events involving NR NUREG-1192 02/85 09/88 Wrong Unit or Wrong Train (No Req.)
125.11.7 Reevaluate Provision to liigh NUREG-1332 09/86 09/88 Automatically isolate Feedwater (No Req.)
from Steam Generator During a Line Dreak A-3,4,5 Steam Generator Tube integrity USI NUREG-0844 01/19 09/88 (No Req.)
A-45 Shutdown Decay lleat 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/RilR Suction Line interlocks liigh GL 88-17 08/85 11/88 on PWRs (Req.)
101 BWR Water Level Redundancy liigh GL 89-11 05/06/85 06/89 (Req.)
13-8 As of 3rd uarter FY-93
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'd) 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-81eed High No Req.
01/86 04/89 i
l 124 Auxiliary feedwater System NR 2 Plant-02/86 01/89 Reliability Specific Backfits (Req.)
125.1.3 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-il74 01/79 08/89 (No Req.)
A-40 Seismic Design Criteria USl SRP Revisions 01/79 09/89 (Req.)
A-47 Safety implications of Control USI GL 89-19 02/81 08/89 Systems (Req.)
A-48 flydrogen Control Measures and USI Rules (Req.)
02/81 04/89 Effects of flydrogen Burns on Safety Equipment Ilfl.1 Shift Staffing liigh Reg. Guide 10/01/84 05/89 1.114, Rev. 2 (Req.)
T3-9 As of 3rd Quarter FY-93
TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED 8Y FISCAL YEAR issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-89 (Cont'd)
IIF4.1 Inspection Procedure for fligh IN 86-64 10/01/84 10/88 Upgraded Emergency Operating (No Req.)
Procedures l.F.1 Expand QA list liigh No Req.
NRR-OP FY83 01/89 II.C.4 Reliability Engineering liigh No Req.
NRR-OP FYB3 10/88 II.E.6.1 Test Adequacy Study Medium GL 89-10 NRR-0P FY83 06/89 (Req.)
FY-90 70 PORV and Block Valve Medium GL 90-06 05/14/84 06/90 Reliability 75 Generic Implications of NR Req.
10/19/83 05/90 AlWS Events at the Salem Nuclear Power Plant 84 CE PORVs NR SECY-90-232 02/27/85 06/90 (No Req.)
94 Additional low-Temperature liigh GL 90-06 07/23/85 06/90 Overpressure Protection for (Req.)
LWRs 103 Design for Probable NR GL 89-22 09/04/85 11/89 Maximum Precipitation (Req.)
T3-As of 3rd arter FY-93
. =. -
I I
TABLE 3 (Continued)
GEhERIC SAFETY ISSUES RESOLVE 0 BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-90 (Cont'dl A-29 Nuclear Power Plant Medium No Req.
NRR-OP FY83 10/89 Design for the Reduction l
of Vulnerability to Industrial Sabotage C-8 Main Steam Line fligh No Reg.
NRR-0P FY83 03/90 f
Isolation Valve leakage Control Systems FV-91 128 Electrical Power liigh GL 91-06, 11/28/86 09/91 Reliability GL 91-11 (Reg.)
130 Essential Service Water Nigh GL 91-13 03/10/87 09/91 System Failures at (Req.)
Multiplant Sites 135 Steam Generator Medium No Req.
05/27/86 03/91 and Steam Line Overfill II.J.4.1 Revise Deficiency NR Rule NRR-0P FY83 07/91 Report Requirements (Req.)
1 T3-11
.As of 3rd Quarter FY-93
TABLE 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-92 29 Bolting Degradation or liigh No Req.
NRR-OP FY-83 10/91 Failure in Nuclear Power Plants 73 Detached Thermal Sleeves NR NilREG/
08/20/91 09/92 CR-6010 No. Req.
79 Unanalyzed Reactor Medium GL 92-02 NRR-OP FY-84 05/92 Vessel Thermal Stress No. Req.
During Natural Convection Cooldown 87 failure of IIPCI Steam liigh No Req.
09/26/85 12/91 Line Without Isolation 113 Dynamic Qualification High No Req.
07/02/87 08/92 Testing of Large Bore liydraulic Snubbers 121 Hydrogen Control for High No Req.
09/26/85 03/92 Large, Dry PWR Containments 151 Reliability of ATWS Medium No Req.
08/27/91 09/92 Recirculation Pump Trip in BWRs T3-12 As of 3rd Quarter FY-93
m...._.
TABLE 3 (Continued) r GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-93 105 Interfacing Systems LOCA liigh No Req.
06/11/85 06/93 at 1.WRs 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 153 Loss of Essential Service High No Req.
03/29/91 06/93 Water in LWRs B-56 Diesel Reliability High Reg Guides:
NRR-OP FY83 06/93 1.9, Rev. 3 l.160 (Req.)
liFS.1 Local Control Stations High No Reg.
10/01/84 06/93 HF5.2 Review Criteria for Human liigh No Req.
10/01/84 06/93 Factors Aspects of Advanced Controls and Instrumentation L
l l
l l
T3-13 As of 3rd Quarter FY-93
. -. -.... -. - - -...... -. - ~.... _ _....-.. -.- -_.. -.~. - -,_._.
f' t
TABLE 4 20 GSIs SCllEDULED FOR RESOLUTION fBY FISCAL YEAR)
L PRIORITY FY-93 FY-94 FY-95 FY-96 FY-97 fY-98 180 10iAL i
filGli II.H.2 143 23 15 5
Hf4.4 l
k MEDIUM 106 24 1.D.3 B-55 78 8
57 i
B-17 B-61 NR 83 145 B-64 7
I.D.5(3) 155.1 166 168 1
TOTAL:
5 7
2 2
0 0
4 20 i
i l
l T4-1 As of 3rd Quarter FY-93 i
l
... _ - -.. -..., _ ~.. -...
-..... -. - - -.. - ~. - - - - - -.. - -... - - -,..... - - - - -. -, _. - -, -........,... _.,, - - -.. -,. -,. -.. -,,.. _ _, -. - - -,. - -... - -, - - -.. - ~. - - -.. _... -... -... _. -. - -... _
Table 4A GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTIO" Date Resolution Current issue Lead Office /
Approved for Date at end Resolution Number Title Division / Branch Priority Resolution of FY-92 Date 15 Radiation Effects an h tur RES/DSIR/EIB 11 02/89 03/96 03/96 Vessel Supports 23 Reactor Coolant Pump m;
RES/DSIR/ElB 11 NRR-0P FY83 07/94
'12/94 failures 143 Availability of Chilled Water RES/DSIR/EIB ll 03/29/91 01/94 01/94 Systems and Room Cooling II.H.2 Obtain Technical Data on the RES/DSR/AEB H
NRR-OP FY83 06/93 09/93 Conditions inside the IMI-2 Containment Structure HF4.4 Guidelines for Upgrading Other RES/DSR/HFB H
10/01/84 12/93 07/93 Procedures 24 Automatic Emergency Core Cooling RES/DSIR/SAIB M
07/23/91 03/S4 08/94 System Switch to Recirculation 57 Effects of fire Protection RES/DSIR/SAIB M
06/08/88 08/93 12/93 System Actuation on Safety-Related Equipment 78 Monitoring of fatigue Transient RES/DSIR/EIB M
07/10/92 TBD TBD Limits for Reactor Coolant System 106 Piping and Use of Highly RES/DSR/RBSB M
11/03/87 12/92 07/93 Combustible Gases in Vital Area >
B-17 Criteria for Safety-Related RES/DSR/HFB M
03/22/82 04/93 09/94 Operator Actions B-55 Improve Reliability of Target RES/DSIR/EIB M
NRR-OP 06/96 06/96 Rock Safety Relief Valves T4-2 As of 3rd Quarter FY-93 O
O O.
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Table 4A (Continued)
GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION Date Resolution Current issue lead Office /
Approved for Date at end Resolution Number Title Division /B anch Priority Resolution of FY-92 Date B-61 Allowable ECCS Equipment Outage RES/DSR/PRAB M
NRR-OP 12/93 09/94 Periods I.D.3 Safety System Status Monitoring RES/DSIR/EIB M
NRR-OP FY83 12/94 12/94 83 Control Room Habitability RES/DSIR/SAIB NR 08/83 05/93 09/93 145 Improve Surveillance and RES/DSIR/PRAB NR 02/11/92 10/93 11/93 Startup Testing Program; 166 Adequacy of Fatigue Life NRR NR 04/01/93 NA TBD of Metal Components 168 Environmental Qualification NRR NR 04/01/93 NA TBD of Electrical Equipment 155.1 More Realistic Source RES/DSIR/SAIB NR 02/26/92 03/93 11/93 Term Assumptions B-64 Decommissioning of Nuclear N'iSS/LLWM/LLRB NR NRR-OP FY84 10/92 TBD Reactors I.D.5(3) On-Line Reactor Surveillance RES/DE/EMEB NR NRR-OP FY83 01/93 07/93 Systems Total: 20 T4-3 As of 3rd Quarter FY-93 L_
m
=
..__ = _. _ _.
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TABLE 5 NUMBER Of GENERIC ISSUES PRIORITIZED FROM FY-831HROUGil Tile 3RD OVARTER OF FY-93 Issue Type FY-83 FY-84 FY-85 FY-86 FY-87 FY-88 FY-89 FY-90 FY-91 FY-92 FY-93 Total Issues Identified 56 19 54 45*
6 3
38 3
29 7
5 265 To Be Prioritized Issues Identified 19 2
0 1
1 2
0 0
0 0
0 25 To Be Reprioritized Total:
75 21 54 46 7
5 38 3
29 7
5 290 New Issues (Entered into GIMCS)
High 2
1 41 6
4 1
1 0
2 0
0 58 Medium 2
4 1
1 1
2 0
1 3
2 0
17 Nearly-Resolved 3
5 6
1 0
1 0
0 1
2 2
21 Subtotal:
7 10 48 8
5 4
1 1
6 4
2 96 Resolved 4
0 1
0 0
1 1
1 0
2 0
10 Low 1
4 0
2 1
0 0
2 0
4 1
17 Drop 1
4 4
6 13 9
2 8
5 24 0
79 RI/LI O
O 4
6 0
2 33 1
1 3
0 50 Integrated 8
2 3
6 0
1 1
3 0
5 0
29 Total Issues 21 20 60 28 19 17 38 16 12 42 3
281 Prioritized:
1 Remaining issues
+54
+1
-6
+18
-12
-12 0
-13
+17
-35
+2 9
To Be Prioritized or Reprioritized:
- Extensive revisions to Human factors issues resulted in priority changes.
T5-1 As of 3rd Quarter FY-93 '
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TABLE 6 GENERIC ISSUES PRIORITIZED AS OF 3RD OVARTER FY-93 Action item /
Identification Date Current issue No.
Title Date Prioritized Priority FY-83 1
31 Natural Circulation Cooldown 09/02 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 09/02 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 03/82 07/83 RESOLVED 42 Combination Primary / Secondary System LOCA d9/82 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 8WRs 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 lilGil Cooling Water System failures 77 Flooding of Safety Equipment Compartments by 06/83 09/83 lilGil 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 RESOL VED T6-1 As of 3rd Quarter FY-93
TABLE 6 (Continuedl GENERIC ISSUES PRIORITIZED AS Of 3RD 00AR1[R FY-93 Action item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-84 34 RCS Leak 09/82 02/84 DROP 35 Degradation of Internal Appurtenances in LWRs 09/82 02/84
. LOW 36 Loss of Service Water 09/82 02/84 NR 43 Contamination of Instrument Air lines 09/82 11/83 DROP' 44 Failure of Saltwater Cooling System 09/82 10/03 S(43) 48 LCO for Class IE Vital Instrument Buses in 09/82 10/83 NR Operating Reactors 49 Interlocks and LCOs for Redundant Class IE 09/82 07/84 MEDIUM Tie Breakers 53 Consequences of a Postulated Flow Blockage 09/82 09/84 DROP Incident in a BWR 60 Lamellar Tearing of Reactor Systems Structural 10/82 11/83 S(A-12)
Supports 61 SRV Line Break inside the BWR Wetwell Airspace 10/82 11/83 MEDIUM of Mark I and 11 Containments 66
,tcam Generator Requirements 06/83 11/83 NR 68 Postulated loss of Auxiliary feedwater System 06/83 04/84 IIIGil Resulting from Turbine-Driven Auxiliary Feedwater Pump Steam Supply line Rupture 69 Make-up Nozzle Cracking in ll&W Plants 06/83 12/83 NR 70 PORV and Block Valve Reliability 06/83 05/84 MfDIUM 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 l0W lic Lines in the Drywells of BWR Mark I and 11 Containments 82 Beyond Design Basis Accidents in Spent fuel 08/83 12/83 MEDIUM Pools 90 Technical Specifications for Anticipatory Trips 02/84 08/84 LOW 92 fuel Crumbling During LOCA 04/83 07/84 LOW B-65 lodine Spiking 09/82 06/84 DROP 16-2 As of 3rd Quarter f Y-93 O
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TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 3RD OVARTER FY-93 Action item /
Identification Date Current issue No.
Title Date Prioritized Priority FY-85 37 Steam Generator Overfill and Combined Primary 09/82 05/85 S(A-47) and Secondary Blowdown St 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 Staf f Actions 06/83 03/85 MEDIUM 81 Potential Safety Problems Associated With Locked 11/83 10/84 DROP Doors and Barriers in Nuclear Power Plants 83 Control Room Habitability 11/83 06/84 NR 84 CE PORVs 11/83 02/85 NR 85 Reif ability 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 Auxtllary Feedwater Pumps 07/84 10/84 ilIGH 94 Additional low Temperature Overpressure 08/84 07/85 llIGH
^
Protection for Light Water Reactors 98 CRD Accumulator Check Valve Laakage 09/84 02/85 DROP 99 RCS/RHR Suction Line Interlocks on PWRs 09/84 08/85 filGH 101 BWR Water Level Redundancy 09/84 05/85 tilGil 102 iluman Error in Events involving Wroeg Unit or 09/84 02/85 S(IIF-02)
Wrong Train 103 Design for Probable Maximum Precipitalien 10/84 09/85 NR 105 Interfacing Systems LOCA at LWRs 10/84 06/85 HIGil 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 16-3 As of 3rd Quarter IY-93
TABLE 6 (Continued)
GENLRIC ISSUES PRIORITIZED AS OF 3RD OUARTER FY-93 Action item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-85 (Cont'dl B-19 Thermal-flydraulic Stability 02/83 01/85 NR 0-50 Post Operating Basis Earthquake Inspection 02/83 04/85 Rl(LOW)
B-59 N-1 Loop Operation in BWRs and PWRs 02/83 06/85 RESOLVED flF-01 iluman Factor Program Plan (HFPP with 24 08/83 10/84 tilGli subtasks)
HF-02 Maintenance and Surveillance Program Plan 04/d4 03/85 lilGli (MSPP with 10 subtasks)
FY-86 21 Vibration Qualification of Equipment 03/83 06/86 DROP 30 Potential Generator Missiles - Generator Rotor 09/82 10/85 DROP Retaining Rings 74 Reactor Coolant Activity Limits for Operating 06/83 05/06 DROP Reactors 97 PWR Reactor Cavity Uncontrolled Exposures 09/84 10/85 S(III.D.3.1) til 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 Rl(R)
Out-of-Service Times 114 Seismic-Induced Relay Chatter 03/85 06/86 S(A-46) j 115 Reliability of Westinghouse Solid State 04/85 07/86 IIIGli Protection System i
122.1.a Common Mode Faf'
? of Isolation Valves in 08/85 01/86 lilGil Closed Position 122.1.b Recovery of Auxii.ary feedwater 08/85 01/86 MEDIUM l
12.l.c Interruption of Auxiliary feedwater flow 08/85 01/86 illGli 122.2 Initiating feed-and-8leed 08/85 01/86 IIIGil 122.3 Physical Security System Constraints 08/85 01/86 LOW 124 Auxiliary feedwater System Reliability 12/85 02/86 NR 16-4 As of 3rd Quarter FY-93 l
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=.
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TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 3RD OVARTER FY-93 Action item /
Identification Date Current issue No.
Title Date Prioritized Priority FY-86 (Cnnt'd) 125.I.2.a PORV Reliability - Test Program 11/85 06/86 S(70) 125.1.2.b PORV Reliability - Surveillance 11/85 06/86 S(70) 125.I.2.c Auto Block Valve Closure 11/85 06/86 DROP 125.I.2.d Equipment Qualification for feed-and-Bleed 11/85 06/86 5(A-45)
Environment 125.11.3 Review Steam / feed Line Dreak Hitigation 11/85 08/86 DROP Systems for Single failure 125.11.4 OTSG Dryout and Reficod Effects 11/85 09/86 DROP 125.11.7 Reevaluate Provisions to Automatically 11/85 09/86 111G11 Isolate Feedwater from Steam Generator During Line Break s
125.11.9 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 ifours 134 Rule on Degree and Experience Requirement 07/86 07/86 ilIGli C-4 Statistical Methods for ECCS Analysis 02/83 06/86 Rl(R)
C-5 Decay Heat Update 02/83 06/86 RI(R)
C-6 LOCA fleat Sources 02/83 06/86 RI(R)
FY-87 113 Dynamic Qualification Testing of large Bore 03/85 07/87 lilGil flydraulic Snubbers 125.1.1 Availability of the STA 11/85 07/87 DROP 125.1.4 Plant-Specific Simulator 11/85 02/87 DROP 125.1.7.b Realistic Ilands-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 3rd Quarter FY-93
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 3RD OVARTER FY-93 Action item /
Identification Date Current issue No.
Title Date Prioritized Priority FY-87 (Cont'd) 125.II.l.a Two-Train AFW Reliability 11/85 10/86 DROP 125.11.1.b Review Existing AFW Systems for Single Failure 11/85 10/86 tilGil 125.II.l.c NUREG-0737 Reliability Improvements 11/85 10/86 DROP 125.ll.l.d AFW Steam and feedwater Rupture Control 11/85 10/86 OROP System /ICS Interactions in B&W Plants 125.11.2 Adequacy of Existing Maintenance Requirements 11/85 06/87 DROP for Safety-Related Systems 125.11.5 Thermal-flydraulic Effects of Loss and 11/85 06/87 DROP Restoration of Feedwater on Primary System Components 125.11,6 Reexamine PRA Estimates of Core Damage Risk 11/85 03/87 DROP from loss of All feedwater 125.11.8 Reassess Criteria for feed-and-Bleed Initiation 11/85 03/87 DROP 125.11.10 Hierarchy of Impromptu Operator Actions 11/85 02/87 DROP 125.11.12 Adequacy of Training Regarding PORV Operation 11/85 03/87 DROP 127 Testing and Maintenance of Manual Valves in 05/86 06/87 LOW Safety-Related Systems 128 Electrical Power Reliability 05/86 11/86 lilGil 130 Essential Service Water Pump Failures at 06/86 03/87 IIIGil Multiplant Sites 135 Steam Generator and Steam Line Overfill 05/86 06/87 MEDIUM FY-88 43*
Reliability of Air Systems 04/87 12/87 lilGli 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 3rd Quarter IY-93 O
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TABLE 6 (Continued) 4 GENERIC ISSUES PRIORITIZED AS OF 3RD OVARTER FY-93 Action item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-88 (Cont'd) 62 Reactor Systems Bolting Applications 10/82 08/88 S(29) 88 Earthquakes and Emergency Planning 01/84 10/87 RESOLVED 104 Reduction of Boron Dilution Requirements 10/84 08/88 DROP 106 Piping and Use of Highly Combustible Gases 10/84 11/87 MEDIUM in Vital Areas 125.I.3 SPDS Availability 11/85 05/88 NR 125.I.6 Valve Torque Limit and Bypass Switch Settings 11/05 12/87 DROP 125.1.7A Recover Failed Equipment 11/85 12/87 DROP 125.11.11 Recovery of Main Feedwater as Alternative to AfW 11/85 06/88 DROP 125.11.13 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 Quantitles of 09/86 03/88 LI Cryogenic Combustibles on Site C-14 Storm Surge Model for Coastal Sites 02/83 05/88 LI(DROP) 111.D.1.l(2) Review Information on Provisions for leak 12/82 09/88 DROP Detection 111.D.1.l(3) Develop Proposed System Acceptance Criteria 12/82 09/88 DROP FY-89 i
15*
Radiation Effects on Reactor Vessel Supports 09/88 02/89 HIGil 125.1.5 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 02/83 02/89 Li(DROP) 0-2 ECCS Capability for Future Plants 06/83 10/88 DROP i
- Previous priority evaluation published in NUREG-0933.
]
T6-7 As of 3rd Quarter TY-93 4
J
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 3RD OVARTER FY-93 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 RL50LVED Recirculation Spray 96 RHR Suction Valve Testing 04/84 02/90 S(105) l 107 Generic Implications of Main Transformer 11/84 02/90 LOW Failures l
109 Reactor Vessel Closure Failure 12/84 02/90 DROP l
116 Accident Management 04/85 09/90 S
l 117 Allowable Time for Diverse Simultaneous 05/85 02/90 DROP Equipment Outages l
129 Valve Interlocks to Prevent Vessel 05/86 02/90 DROP Drainage During Shutdown Cooling 137 Refueling Cavity Seal Failure 10/86 05/90 DROP 140 Fission Product Removal Systems 03/87 02/90 DROP 141 LBLOCA With Consequential SGTR 04/87 05/90 DROP 142 Leakage Through Electrical Isolators 06/87 06/90 MEDIUM B-29 Effectiveness of Ultimate Heat Sinks 02/83 08/90 Li(RESOLVED)
B-32 Ice Effects on Safety-Related Water Supplies 02/83 08/90 S(153)
FY-91 24 Automatic Emergency Core Cooling 03/83 07/91 MEDIUM System Switch to Recirculation 38 Potential Recirculation System 09/82 08/91 DROP Failure as a Consequence of Ingestion of Containment Paint flakes or Other Fine Debris l
T6-8 As of 3rd f)uarter FY-93
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TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 3RD OVARTER FY-93 Action item /
Identification Date Current issue No.
Title Date Prioritized Priority 72 Control Rod Drive Guide Tube Support Pin 06/83 10/90 DROP Failures 73 Detached Thermal Sleeves 06/83 08/91 NR 100 Once-Through Steam Generator Level 09/84 09/91 DROP 120 On-line Testability of Protection Systems 08/85 11/90 MEDIUM 143 Availability of Chilled Water Systems and 10/87 03/91 HIGH Room Cooling 150 Overpressurization of Containment 04/89 08/91 DROP Penetrations 151 Reliability of Anticipated Transient 04/89 08/91 MEDIUM Without Scram Recirculation Pump Trip in BWRs 153 Loss of Essential Service Water in LWRs 05/90 03/91 HIGli 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 HEDIUM 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 i
f i
- Previous Priority Published in NUREG-0933 i
T6-9 As of 3rd Quarter FY-93
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 3RD OVARTER FY-93 Action item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-92 (Cont) 123 Deficiencies in the Regulations 11/85 12/91 QROP 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 11 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 145 Improve Surveillance and Startup Testing 09/88 02/92 NR Programs 147 Fire-Induced Alternate Shutdown / Control Room 04/89 08/92 LI Panel Interactions 148 Smoke Control and Manual Fire-Fighting 04/39 08/92 Effectiveness 154 Adequacy of Emergency and Essential Lighting 09/90 01/92 LOW 155.1 Nore 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 flydrology and Ability to Withstand Floods 02/91 01/92 DROP 156.1.4 Industrial llazards 02/91 03/92 DROP 16-10 As of 3rd Quarter lY-93
O O
O' TABLE 6 (Continued)
GENERIC ISSVES PRIORITIZED AS OF 3RD OUARTER FY-93 Action Item /
Identification Date Current Issue No.
Title Date Prioritized Priority FY-92 (Cont _).
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 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 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
!!:6.3. 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 i
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-93 149 Adequacy of Fire Barriers 04/89 10/92 LOW 152 Design Basis for Valves That Hight Be 03/90 01/93 LOW Subjected to Significant Blowdown loads 155.3 Improve Design Requirements for Nuclear 02/91 01/93 DROP Facilities 156.3.6.2 Emergency DC Power 02/91 03/93 LOW 161 Use of Non-Safety-Related Power Supplies in 10/91 03/93 DROP Safety-Related Circuits 164 Neutron Fluence in Reactor Vessel 10/92 03/93 DROP 166 Adequacy of Fatigue Life of Metal Components 04/93 04/93 NR T6-11 As of 3rd Quarter FY-93
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF 3RD OVARTER FY-93 Action item /
Identification Date Current issue No.
Title Date Prioritized Priority l
FY-93 168 Environmental Qualification of Electrical 04/93 04/93 NR, Equipment T6-12 As of 3rd Quarter iY-93 O
O O.
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TABLE 7 t
GENERIC ISSUES TO BE PR10R111 ZED AS OF 3RD OVARTER FY-93 Action item /
Identification Current issue No.
Title Date Schedule 146 Support Flexibility of Equipment and Components 01/89 08/93 156 SEP issues 156.6.1 Pipe Break Effects on Systems and Components 02/91 08/93 158 Performance of Power-0perated Valves Under 10/91 11/93 Design Basis Conditions 159 Qualification of Safety-Related Pumps 10/91 09/93 While Running on Minimum Flow 160 Spurious Actions of Instrumentation 10/91 08/93 Upon Restoration of Power 162 Inadequate Technical Specifications for 10/91 08/93 Shared Systems at Multiplant Sites When One Unit Is Shut Down 163 Multiple Steam Generator Tube Leakage 06/92 07/93 165 Safety and Safety / Relief Valve Reliability 10/92 12/93 167 Combustible Gas Storage Facilitter 06/93 TBD TOTAL: 9 i
e T7-1 As of 3rd Quarter FY-93 u
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3 Action Item /
Previous identification Current Issue No.
Title Priority Date Schedule NONE 1
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T8-1 As of 3rd Quarter FY-93
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TABLE 9 REGULATORY IMPACT ISSUES SCllEDULED FOR RESOLUTION Date Resolution Current Issue lead Office /
Approved for Date at end Resolution Number Title Division / Branch Priority Resolution of FY-92 Date NONE 4
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Y 19-1 As of 3rd Quarter f Y-93
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TABLE 10 LICENSING ISSUES SCHLDVLED FOR RESOLUTION Lead Office /
Issue Division /
Resolution Number Title Rranch Date 67.5.1 Reassessment of Radiological Consequences RES/DSIR/RPSI 09/93 147 Fire-Induced Alternate Shutdown / Control Room RES/DSIR/SAI'B
,10/93 Panel Interactions 148 Smoke Control and Manual Fire-Fighting Effectiveness RES/DSIR/SAIB 11/93 1.D.5(5)
Disturbance Analysis Systems RES/DSR/HFB 09/93 TOTAL: 4 i
5 T10-1 As of 3rd Quarter f Y-93
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RUN DATE. 07/27/93 INDEX OF ISSUES GENERIC ISSUE MANAGEMENT CONTROL SYSTEM ISSUE NUMBER T ITLE PAGE 15 RADIATION EFFECTS ON REACTOR VESSEL SUPPORTS 1
23 REACTOR COOLANT PUMP SEAL FAILURES 5
24 AUTOMATIC EMERGENCY CORE COOLING SWITCHOVER TO RECIRCULATION 9
57 EFFECTS OF FIRE PROT. SYS. ACTUATION ON SAFETY-RELATED EQUIP.
11 67.5.1 REASSESSMENT OF SGTR DESIGN BASIS 14 78 MONITORING OF FATIGUE TRANSIENT LIMITS FOR REACTOR COOLANT 17
'83 CONTROL ROOM HABITABILITY 19 105 INTERFACING SYSTEMS LOCA AT LWRS 22 106 PIPING AND USE OF HIGHLY COMBUSTIBLE GASES IN VITAL AREAS 26 142 LEAKAGE THROUGH ELECTRICAL ISOLATORS 30 143 AVAILADILITY OF CHILLED WATER SYSTEM AND ROOM COOLING 32 145 ACTIONS TO REDUCE COMMON CAUSE FAILURES 34 147 FIRE-INDUCED ALTERNATE SHUTDOWN / CONTROL ROOM PANEL INTERACTIONS 36 148 SMOKE CONTROL AND MANUAL FIRE-FIGHTING EFFECTIVENESS 38 153 LOSS OF ESSENTIAL SERVICE WATER SYSTEM IN LWRS 40 155.1 MORE REALISTIC SOURCE TERM ASSUMPTIONS 42 166 ADEQUACY OF FATIGUE LIFE OF METAL COMPONENTS 45 168 ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT 46 B-17 CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS 45 B-55 IMPROVE RELIABILITY OF TARGET ROCK SAFETY-RELIEF VALVES 50 B-56 DIESEL GENERATOR RELIABILITY 53 B-61 ALLOWAULE ECCS EQUIPMENT OUTAGE PERIODS
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IS TITLE: RADIATION EFFECTS ON REACTOR VESSEL SUPPORTS IDENTIFICATION DATE: 06/80 PRIORITIZATION DATE: 02/89 TYPE: GSI PRIOR 11Y-H TA5K MANAGER:
R.
JOHNSON OFFICE / DIVISION /5 RANCH: RES /DSIR/EIB ACTION LEVEL. ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE 03/96 WORK AUTHORIZATION: FEB. 8 1989 MEMO FROM E. BECKJORD TO R.W.
HOUSTON FIN CONTRACTOR CONTRACT TITLE h256 khl hHkPPkhbPbkhkHkhlbhkhK hkhhhhb(Mhh)
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BNL TROJAN SUPPORT STABILITY ANALYSIS (ESGBl 8041?
ORNL TROJAN SHIELD FLUX ATTENUATION ( M! 3 )
B5848 MEA MTR IRRADIATION OF STRUCTURAL STEELS (MEDI B6071 LLNL CONSEQUENCE EVALUATION OF EMORITTLED RPV SUPPORTS (SSEB) 862?4 NIST TROJAN CAVITY DOSIMETRY MEASUREMENT (MEB)
GIl69 MPD NETWOR NUCLE AR MATERI ALS DTTA RE TRIEVAL F ROM THE MPD NETWORK (EIB)
L1098 ORNL HEAVY-SECTION STEEL IRRADIATION PROGRAM (MEB)
LII91 PAL ASSOCI RPV SUPPORTS TECHNICAL ASSISTANCE (EMTB)
LI296 INEL RADIATION EFFECTS ON REACTOR VESSEL SUPPORTS (EIB)
L1386 BNL IRRADIATION ANALYSES (EIB)
L2552 ORNL HFIR NEUTRON SPECTRUM MEASUREMENT (EIBl WDRK SC0PE WORK SCOPE REVISION. (NOTED TO BE UNDERWAY IN LAST PRESSURE VESSEL STEEL SURVEILLANCE SPECIMENS.
QUARTERLY REPORil:
3.
DETERMINE THE APPLICABILITY OF THE FINDINGS TO I.
QUANTITATIVELY EVALUATE THE HFIR NEUTRON Ft.UX OVER THE OPERATING REACTOR PRESSURE VESSEL SUPPORTS.
FULL ENERGY SPECTRUM.
4.
RESOLVE GSI-15 WITH EITHER A GENERIC LE TTER TO 2.
REEVALUATE THE SIGNIFICANCE OF THE MEASURED AND LICENSEES REQUESTING REASSESSMENT OF RPV SUPPORTS OR A REPORTED CHANGES IN MECHANICAL PROPERTIES OF THE HFIR CLOSEuuT MEMORANDUM IF THE SAFETY ASPECTS CAN BE ANNULLED STATUS 1.
THE INEL T/A CONTRACT WAS MODIFIED TO INCLUDE ADDITIONAL PROPERTIES (STRENGTH TOUGHNESS RESULTING FROM TIME IN TASKS, SPECIFICALLY-AUDIT THE HFIR SURVEILLANCE DATA SERVICE.
BEFORE TAKiNG ANY ACT ON. THE PROGRAM WILL BE IN PREPARATION FOR REVISED FLUENCE RESULTS AND CALCULATE REVIEWED BY NRC MANAGEMENT AND SUBMITTED TO E PRI AND THE GAMMA FLUX IN SELECTED REACTORS IN CASE THAT RADIA-PORTLAND GE (FOR TROJAN) FOR COMMENT OTHER TION IS SHOWN TO INFLUENCE THE SUPPORT STEEL BEHAVIOR.
DECOMMISSIONED PLANTS WILL BE INCLUDED IF AND WHEN THEY 2.
A PROGRAM IS BEING DEVELOPED BY THE MATERIALS AGREE TO PARTICIPATE.
THUS FAR, No SCHEDULE HAS BEEN ENGINEERING BRANCH (DE/RES) TO OBTAIN SAMPLES FRDM RPV ESTABLISHED.
SUPPORTS AND DETERMINE THE CHANGE IN RELEVANT MECHA1ICAL AS OF F Y93 QUAR TER 3
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T RUN DATE. 07/27/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE.
5 ISSUE NUMBER.
23 TITLE: REACTOR COOLANT PUMP SEAL F AILURES IDENTIFICATION DATE: 12/80C PRIORITIZATION DATE: 04/83C TYPE: GSI PRIORITY: H TASK MANAGER.
K.
SHAUKAT OFFICE / DIVISION / BRANCH: RES /DSIR/EIB ACTION LEVEL: ACTIVE STATUS.
TAC NUMBERS:
RESOLUTION DATE: 12/94 WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN, (APPENDIX G)
FIN CONTRACTOR CONTRACT TITLE k3hh5 bhk hk bhbR bbbkkkk PbbP kRbP kkkL khhkbRkkY A3771 BNL ASSESS EFFECT OF MECH. MA NT. RCP SEAL A3800 BNL EVAL. ADEQ. OF RCP SEAL INSTR. & RESP. TO RCP A6322 INEL RCP SHAFT SEAL BEHAVIOR DURING ST. BLACKOUT B2953 PNL REACTOR COOL. PUMP SEAL FAIL. VAL IMP. ANALYSIS B3049 ETEC LEAK RATE ANALYSIS OF WESTINGHOUSE RCP DI760
'"IENTECH REG. ANAL. FOR GI-23 RCP SEAL rAILURES W0RK SC0PE THE TAP FOR THIS ISSUE WAS REVISED TO INCOR-SHOULD TAKE, IF ANY. TO REDUCE RCP SEAL FAILURE TO AN P0 RATE WORK NECESSARY TO COMPLETE GSI 65.
REVIEW ACCEPTABLE LEVEL COMMENSURATE WITH THE POTENTI AL SAF E TY PWR RCP SE AL F AILURES CAUSED BY MECHANICAL F AILURES CONSEQUENCES OF SEAL FAILURE.
THE PROGRAM CONSISTS OF AND LOSS OF SEAL COOLING TO ASCERTAIN IF INCREASED NRC THE F OLL.0 WING MAJOR TASKS:
REQUIREMENTS ARE NECESSARY TO MINIMIZE SEAL FAILURES.
TASK I - DE TERMINE ACTUAL SEAL FAILURE MECHANISMS EVALUATE THE EFFECTS OF SYSTEM DESIGN, HATERIALS.
TASK 2 - EVALUATE RCP SEAL COOLING F OR ALL MODE S OF OPE RA-OPERATION, TESTING. AND MAINTENANCE ON SEAL FAILURE TION FOR WHICH SEAL COOLING IS REQ'D USING THE 4'
MECHANISMS.
REVIEW THE RELIAU OF SEAL COOLING SYSTEMS RELIABILITY OF TYPICAL RCP SEAL COOLING SYSTEM AND IDE NTIFY METHODS TO MINIMIZE THE EFFECTS OF LOSS OF DESIGNS.
SEAL COOLING.
PERFORM A RISK ASSESSMENT OF SEAL FAllORE 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 MUST EFFECTIVE FIX.
STATUS kk kkk bkhkkkb LkhkkR hbh khhbhMkhkbh bhth kb bShkb hhbblkhbRhbbibkbb5500kkbbkHhbhkkhREbblkhbkhkhkthbks MAY 2, 1991. TO INFORM LICENSEES OF THE POTENTIAL IMPACT NUREG-1401 - THE STAFF DECIDED TO PROCEFD WITH A RULEMAKING ON $80 ANALYSES.
A FEDERAL REGISTER NOTICE WAS PUBLISHED FOR OFF-NORMAL CONDITIONS, WHILE THE NORMAL CONDITIONS ARE APRIL 19, 1991, REQUESTING PUBLIC COMMENT ON DRAFT BEING ADDRESSED BY A PROPOSED GENERIC LETTER.
AS OF FY93 QUARTER 3
RUN DATE- 07/27/93 GENERIC ISSUE MANAGEMENT CONTROL SYST[M PAGE.
6 ISSUE NUMBER-23 TITLE: REACTOR COOLANT PUMP SEAL FAILURES AFFECTED DOCUMENTS PROBLEM / RESOLUTION hhkhbkkbWkhbRkPbkhkHkVkbkkhkShbhb bbkhbkkkkhbkVkPbblib~bbhhkkh5 hhkRhbblbhkbh
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NUREG/CR-4077, " REACTOR COOLANT PUMP SHAFT SEAL DEHAVIOR*
PACKAGE IS TAMING CONSIDERABLY MORE TIME THAN ANTICIPATED NUREG/CR-4294, " LEAK RATE ANALYSIS OF THE WESTINGHOUSE THREE MAJOR TECHNICAL ISSUES WlRE RAISED ALSO. A TEST REACTOR COOLANT PUMP" OPTION FOR QUALIFICATION OF SEALS IS BEING INCLUDING IN THE NUREG/CR-4821, " REACTOR COOLANT PUMP SHAFT SEAL STABILITY REGULATORY GUIDE SPECIFICATIONS FOR SUCH A TEST'WERE DURING STATION " LACK 00T" DEVELOPED BY A CONSUL TANT A RULEMAKING PACKAGE HAS BEEN NUREG/CR-4643 " EVALUATION OF LORE DAMAGE SEQUE NCE S PREPARED THE MILESTONES HEFLECT RULEMAKING EFFORTS INITIATED BY LOSS OF REACTOR COOLANT PUMP SEAL COOLING" NUREG/CR-4400, "THE IMPACT OF MECHANICAL AND MAINTENANCE-INDUCED FAILURE OF MAIN REACTOR COOLANT PUMP SEALS ON PLANT SAFETY" NUREG/CR-4544, " REACT 0R COOLANT PUMP SEAL-RELATED INSTRU-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" NUREG/CR-5918, " ANALYSIS OF PUBLIC COMMENTS ON GI-23 REACTOR COOLANT PUMP SEAL FAILURE" (IN PREPARATION)
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE TAP ISSUED FOR COMMENT 04/83 03/83 TAP APPROVED BY DSI DIR 10/83 10/83 ISSUED REQUEST FOR PROPOSAL TO BNL FOR 11/83 11/83 COMPONENT COOLING WATER PRA TRANSFER RESOLUTION REPONSIBILITY FROM DSI TO 06/84 06/84 DE TRANSFER RESOLUTION RESPONSIBILTY FROM DE TO 05/85 05/85 DST /GIB COMPLETE DOCUMEN. OF DACKGROUND PAST 05/85 12/85 SEAL FAILURES. INCLUDING LER SEARCH,REV 0F INDUST. EXP & REV.0F BWR SCR.(TASK 1]
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4 RUN DATE. 07/27/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
9 ISSUE NUMBER: 24 TITLE: AUTOMATIC EMERGENCY CORE COOLING SWITCHOVER TO RECIRCULATION IDENTIFICATION DATE: 03/83C PRIORITIZATION DATE: 07/91C TYPE: GSI PRIORITY: M TASK MANAGER: G.
BURDICK OFFICE / DIVISION / BRANCH: RES /DSIR/SAIB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE: 08/94 WORK AUTHORIZATION: MEMORANDUM FROM E. BECKJORD TO W.
MINNERS ON JULY 23, 1991 FIN CONTRACTOR CONTRACT TITLE L1854 SEA AUTOMATIC ECCS SWITCHOVER TO RECIRCULATION WORK SCOPE RESOLUTION OF THIS ISSUE WILL DE ACCOMPLISHED BY A WOULD COST (WITH UNCERTAINTY) FOR A LICENSEE TO INSTALL SUCH REEVALUATION OF THE STUDY PERFORMED IN 1981, USINO UP-TO.
AN AUTOMATIC SWITCHOVER CONTROL SYSTEM. THESE RESULTS WILL DATE HUMAN RELIABILITY AND AUTOMATED EQUIPMENT PRA BE USED TO PROVIDE THE BASES FOR A STAFF RECOMMENDATION TO ANALYSIS METHODS TO DETERMINE THE CORE DAMAGE FREQUENCY AND THE CootilSSION REGARDING WHE THER OR NOT PWR'S THAT CURRENTLY RISK CHANGES lAND UNCERTAINTY) THAT WOULD RESULT F ROM RELY ON A MANUAL SWITCHOVER SYSTEM SHOULD BE REQUIRED TO CHANGE 0VER TO AN AUTOMATIC SWITCHOVER CONTROL SYSTEM.
THIS INSTALL AN AUTOMATIC SWITCHOVER SYSTEM.
REEVALUATION WILL ALSO INCLUDE MAKING AN ESTIMATE OF WHAT IT STATUS CONTRACT WORK UNDERWAY.
FIRST LETTER REPORT (TASK 4.01, DECEMBER 1992.
MODEL FOR MANUAL SWITCHOVERl SUBMITTED DURING LAST WEEK OF AFFECTED DOCUMENTS PROBLEM / RESOLUTION PbhkkhkkLCHkNbkSkbhRP bbkKhkhbktkVEbkhkhRhkhbbbE hbhRbhhkkbfhPPROVk 0F HUMAN FACTORS CONSULTANT. WORK HAS RECENTLY (1/5/931 BEEN DELAYED BY NRC REQUEST FOR ADDITIONAL WORK REGARDING JUSTIFICATION FOR HUMAN FACTORS METHOD SELECTFD BY REPLACE-ME NT HUMAN F ACTORS CONSUL TANT. SE A DRAF T REPORT WAS L ATE.
AND NEW PRIORITY WORK IS IMPACTING SCHEDULE.
AS OF FY93 QUARTER 3
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m RUN DATE- 07/27/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
II ISSUE NUMBER.
57 TITLE: EFFECTS OF FIRE PROT. SYS. ACTUATION ON SAFETY-RELATED EQUIP.
IDENTIFICATION DATE: 09/82C PRIORITIZATION DATE: 06/88C TYPE: GSI PRIORITY: M TASK MAMAGER:
R. WOODS OFFICE / DIVISION / BRANCH: RES /DSIR/SAIB ACTION LEVEL: ACTIVE STATUS:
TAC NUMDERS:
RESOLUTION DATE. 12/93 WORK AUTHORIZATION: MEMO TO B.SHERON FROM E. BECKJORD DATED 8/8/88.
FIN CONTRACTOR CONTRACT TITLE bhhb5 hkL kh5bVkkikkh'kbibkhibk'bh~kkkk Pkhkkbhkbh khhhkkh kbk$h75 PkkLkkihIkh/
SCOPING STUDY ONLY LI220 INEL GENERIC ISSUE 57
- EFFECTS OF FIRE PROTECTION SYSTEM ACTUATION ON SAFE TY-RELA TED E6UIPMENT*
LI334 SNL OENERIC ISSUE 57
- EFFECTS OF FIRE PROTECTION SYSTEM ACTUATION ON SAFETY-RELATED EQUIPMENT" LI592 NIST GENERIC ISSUE 57 EFFECTS OF FIRE PROTECTION SYSTEM ACTUATION ON SAFETY RELATED EQUIPMENT.
W0RM SC0PE ACTUATIONS OF FIRE PROTECTION SYSTEMS l FPS *S) HAVE CAUSED PLANT WAlkDOWNS, FIRE ZONE AND VITAL AREA ANALYSES, DAMAGE TO PLANT EQUIPMENT WITH CONSIDERABLE FREQUENCY AND CUTSETS DEVELOPMENT, RISK ESTIMATES, ANO VALUE-IMPACT t
SAFETY IMPLICATIONS. A PROGRAM TO RESOLVE 0I.57 WAS ANALYSES OF POTENTIAL BACMFITS INCLUDING UNCERTAINIY AND INITIATED IN FY 1989 INVOLVING THE EVALUATION OF FOUR PLANTS SENSITIVITY ANALYSES.
A TASK IO DEVELOP AND APPLY A AND THE COLLECTION OF GENERIC PLANT DATA TO SUPPORT A DECISIONMAKING UNDER UNCERTAINTY ANALYSIS METHOD WAS ADDED GENERIC EVALUATION OF THE SAFETY CONCERNS OF GI-S7.
THESE IN RESPONSE TO ACRS COMMENTS ON USE OF PRA*S.
EVALUATIONS INVOLVE REVIEWS OF FPS DESIGNS AND LAYOUTS, STATUS kbbhikkbhbkIhkkhk[kkPbkhkbhkhkhkhPkkkhkVktbkhkbhhkh
~ hkbkhbkk [h9h " hkbPbhEb RkhbLbhkbh kh hb bbkhkbkR hhk RECEIVED FOR PUBLICATION IN SEPTEMBER 1992.
THE DRAFT PRINCIPAL CDF-CONTRIBUTING EVENTS AS PART OF THE IPEEE AND FINAL GENERIC [ VALUATION REPORT WAS RECEIVED IN AUGUST RESOLVE ISSUE 57 WITH NO NEW REQUIREMENTS.
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RUN DATE: 07/27/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE.
18 ISSUE NUMBER: 78 TITLE: MONITORING OF FATIGUE TRANSIENT LIMITS F OR RE ACTOR COOLANT AFFECTED DOCUMENTS PRODLEM/ RESOLUTION REVIEW. CURRENTLY EXPECTED DURING THE THIRD QUARTER OF FY
'93, COULD IMPACT THE SCOPE AND SCHEDULE FOR RESOLUTION OF GENERIC ISSUE 78 DALANCE OF HILESTONES, IF ANY, TO DE DEVEL OPED AF TE R INPUT ON GI-78 0F SENIOR MANAGEMENT RFVIEW OF LICENSE' RENEWAL EFFORT IS DE TERMINED AND A DE TERMINATION IS MADE OF EIB's ROLE.
FATIGUE ANALYSIS TASK ACTION PLAN (?AP) WAS ISSUED BY NRR ON JULY 13, 1993 IN ITS TAP NRR INDICATES THAT IT WILL USE THE RESULTS OF RES FATIGUE STATISTICAL ANALYSIS THERE WAS DELAY DUE TO hDLDUP OF THE ANL CONTRACT IN THE CHICAGO DOE OFFICE.
ORIGINAL CURRENT ACTUAL MILE $T0NES DATE DATE DATE GI-78 ASSIGNED TO RES/DSIR/EIB 07/92 01/92 DRAFT PRA PARAMETRIC STUDY ISSUED FOR PEER 10/92 11/92 REVIEW AND COMMENT TO OTHER NRC DIVISICNS PREPARE DRAFT SDW FOR ANL CONTRACT 02/93 02/93 FIN-6077-3 SDW APPOVED BY DSIR DIRECTOR 03/93 03/93 ISSUE SDW FOR ANL CONTRACT FIN-6077-3 03/93 03/93 ANL RECEIVES NRC/RES APPROVAL TO START WORK 05/93 06/93 ANL/RES MEETING TO DISCUSS STATISTICAL 07/93 07/93 STUDIES ANL COMPLETES DRAFT REPORT 08/93 11/93 ANL COMPLETES FINAL REPORT 09/93 12/93 l
AS OF FY93 QUARTER 3 I
t l
O O
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RUN DATE: 07/27/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
19 ISSUE NUMBER: 83 TITLE: CONTROL ROOM HABITABILITY IDENTIFICATION DATE: 11/83C PRIORITIZATION DATE: 06/84C TYPE: GSI PRIORITY:
TASK MANAGER: C. FERRELL OFFICE / DIVISION / BRANCH: RES /DSIR/SAIB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS:
RESOLUTION DATE: 09/93 WORK AUTHORIZATION: MEMO FOR H. DENTON FROM W. DIRCKS, DATED 8/15/83.
FIN CONTRACTOR CONTRACT TITLE h3kk kh[
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A2334 ANL IN-PLANT REVIEWS ON CONTROL ROOM HABITABILITY B2929 PNL MATH. MODELS CONTROL ROOM HABITABILITY D2098 SAIC CONTROL ROOM VULNERABILITIES L2580 PNL CONTROL ROOM HABITABILITY SYSTEM REVIEW MODELS W0RK SC0PE khbEbh kbkbbEbh bk bkhkk bkLkkh bkkkkkkk hkR RkVkkh hbbk Rkkkhb hkhbLkh hb Pkbhkbkhb kkbbhhkhbkkkbkh PLANT SYSTEMS AND COMPONENTS AND TESTING PRO EDURES TWO TASKS (DEVELOP MODELS OF CHALLENGES TO HABITABILITY RELATIVE TO CONTROL ROOM HABITABILITY, INCLUDING THOSE AREAS AND REVIEW PROCEDURES) HAVE BEEN ADDED.
OF ACRS CONCERN. A FINAL REPORT WILL BE PREPARED STATUS kkh L RhPbRh khbb hkkb bh bbbkhbl hbbh hkbkkkbkLkkh kkkkkH ' ~ kkPbkk bh kbkkhkkk LkVkth kSkbkb~3bLh khhk hbRkb/bh$hh6hh REVIEW MODELS" (NUREO/CR-5659)N COMPUTER CDDE ISSUED IN DECEMBER 1990.
NRR GENERIC LETTER IN CONCURRENCE. PNL HAB TABILITY MODEL FINAL REPOR T FROM PNL ON EXTRA RECEIVED; BEING CHECKED.
(NUREG/CR-5658) ISSUED IN MARCH 1991.
PNL CONTRACTOR AFFECTED DOCUMENTS PROBLEM / RESOLUTION hRP h k h k k kh h 6 h k h h h h k h h h PkbPbbkbbLhkhbkEhPLkhkbbhHbtbI 1.95 1.52, 1,101, 1.140; NUREG-0737 9.5 1: RGS 1.78, ITEM III.D.3.4, II B.k,1.29, 10 CFR 50:
$0.48, APPENDIX R TO 10 CFR 50; NUREG-0700; NUREG-0737, SUPPLEMENT 1.
AS OF FY93 QUARTER 3 t
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20 ISSUE NUMBER: 83 TITLE: CONTROL ROOM HABITABILITY ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE AWARD OF CONTRACT 02/84 01/84 VISIT TO INITIAL PLANT 03/84 05/84 REPORT ON CRH CRITERIA TO NRR DIRECTOR 08/84 06/84 COMPLETION OF CONTRACTOR VISITS TO 08/84 08/84 OPERATING AND NTOL PLANTS S0W WRITTEN FOR 12-PLANT SURVEY AND 11/84 10/84 GENERIC STUDIES RFP SENT TO POTENTIAL CONTRACTOR (S]
12/84 11/84 RECEIPT OF PROPOSAL (5) 02/85 03/85 INITIATE PROGRAM TO VISIT 12 09/85 09/85 ADDITIONAL OPERATING PLANTS COMPLETE VISIT TO 11 OPERATING REACTORS 09/86 01/87 ISSUE TRANSFER MEMO TO RES 03/87 12/87 l
S0W SENT TO PNL FOR 04/88 04/88
" MATHEMATICAL MODELS OF CONTROL ROOM HABIT-i ABILITY SYSTEMS EFFECTIVENESS * (FIN 82929-8)
S0W SENT TO SAIC FOR
- CONTROL ROOH VULNER.
04/88 04/88 ABILITIES" FIN 020969 REQUEST FOR PROCUREMENT ACTION SENT TO CHANGE 05/88 05/88 NRR CONTRACT WITH SAIC TO INCLUDE T/A IN MODELING CONTROL ROOM VULNERABILITIES [D2096)
RECEIPT OF PROPOSAL 06/88 06/88 DRAFT CODE FPFP 10/88 11/88 l
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21 ISSUE NUMBER: 83 TITLE: CONTROL ROOM HABITABILITY ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE DRAFT CODE EXTRAN 10/88 12/8,8 DRAFT REPORT ON 1GXIC LEVELS 11/88 01/89 PNL CONTRACT EXTENDED ON "NO-COST BASIS
- 10/89 10/89 UNTIL 03/90 f
ISSUE.SAIC CONTRACT 03/89 10/89 REVISE TASK ACTION PLAN 10/89 03/90 RECOMMENDED REVISED DOSE ASSESSMENT MODELS 09/89 06/90 FINAL REPORTS ON MODELS STUDY 02/89 01/91 DRAFT CLOSEOUT MEMO 07/91 05/93 ISSUE MEMO TO ACRS 07/91 07/93 ACRS REVIEW 08/93 08/93 PNL UPDATE COMPUTER CODE DOCUMENTATION 09/92 09/93 1
CLOSEOUT MEMO 09/93 09/93 i
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22 ISSUE NUMBER: 105 TITLE: INTERFACING SYSTEMS LOCA AT LWR $
IDENTIFICATION DATE: 10/84C PRIORITIZATION DATE: 08/85C TYPE: GSI PRIORITY. H TASK MANAGE 4; G.
BURDICK OFFICE / DIVISION / BRANCH: RES /DSIR/SAIB ACTION LEVEL: ACTIVE STATUS: 3B TAC NUMBERS:
RESOLUTION DATE: 06/93C WORK AUTHORIZATION: MEMO FOR R. BERNER0 FROM H. DENTON DATED 6/11/85.
FIN CONTRACTOR CONTRACT TITLE A3829 BNL INTERFACING SYSTEMS LOCA B5699 INEL INTERSYSTEM LOCA (01-105)
W0RK SC0PE PkRkbkh k DkhkkLkb kk Lbbk kPkbkkkb Pkk kbk 3 PWh PLkkkk hb VklVkhkhkkkkkkkhkkbhkhhkkkkbkSkPkkkhkkbhbkhkbkkh DETERMINE CORE-MELT FREQUENCIES AND RISK CONTRIBUTED BY PRESSURE RCS FROM ATTACHED LOW PRESSURE SYSTEMS, SHOULD BE FAILURE OF REACTOR COOLANT PRESSURE BOUNDARY AS CAUSED BY PERIODICALLY LEAK-RATE TESTED OR VISUALLY INSPECTED. SOME FAILURE OF PRESSURE ISOLATION VALVES (PIVS) AND RESULTING OLDER PLANTS DO NOT PERFORM SUCH TESTS ON ALL PIV S.
INTERFACING SYSTEMS LOCA.
WHEN SUFFICIENT PROGRESS IS MADE STUDIES HAVE BEEN PERFORMED TO ATTEMPT TO DETERMINE IF ON FWR STUDIES, AND IN LIGHT OF INSIGHTS THUS GAINED, THE IMPOSING SUCH PERIODIC TESTING ON ALL PIV'S IN ALL PLANTS 15 BWR WORK SCOPE WILL BE FORMULATED DEVE LOP NEW LICENSING JUST IF IED. THESE STUDIES SUPPLEMENT THOSE ONGOING TO CRITERIA IF NECESSARY FOR THE GENERIC RESOLUTION.
IT HAS IDENTIFY SIGNIFICANT HARDWARE AND HUMAN CONTRIBUTIONS TO BEEN PROPOSED THAT PRESSURE ISOLATION VALVES, WHICH ARE TWO RISK OF IS-LOCA OUTSIDE CONTAINMENT F ROM 3 PWR ' S.
5TA TUS THE RESOLUTION OF GI-105 WILL ENCOMPASS GI-96, "RHR NUREG/CR-5 744 AND NUREG/CR-5745 F OR WESTINGHOUSE AND CE SUCTION VALVE TESTING.*
THE PERTINENT MILESTONES FROM PL ANTS RE SPECTIVELY. PUBLISHED IN MAY WAS NUREG/CR-5862, GENERIC ISSUE II.E 6.1 HAVE BEEN TRANSFERRED TO GENERIC
- SCREENING METHODS FOR DEVELOPING INTERNAL PRESSURE ISSUE 105 AND REVISED. NUREG/5102, *INTERF ACING SYSTEM LOCA CAPACITIES IN SYSTEMS INTERFACING WITH NUCLIAR POWER PLANT IN FWR'S
- AND NUREG/5154 " INTERFACING SYSTEM LOCA IN REACTOR COOLANT SYSTEMS.
- RESOLUTION PACKAGE DELIVERED 10 BWR'S," dRE COMPLETE. ETlc HAS ALSO COMPLETED A STUDY OF ACRS AND NRR.
PACKAGE CONSISTS OF INFORMATION NOTICE, THE EFFECTIVENESS OF LEAK-RATE TESTING AS AN INDICATION OF FINAL NUREG/CR, AND REGULATORY ANALYSIS.
ADVANCED REACTOR VALVE CONDITION.
NUREG/CR-5604 " ASSESSMENT OF IS-LOCA SRP DRAFT SENT TO NRR.
ACRS MEETING HELO. AND ACRS RISK-METHODOLOGY AND APPLICATION TO A BABCOCK AND WILCOX CONCURRENCE LETTER RECEIVED RESOLUTION MEMORANDUM SENT, NUCLEAR POWER PLANT,* WAS PUBLISHED IN APRIL 1992 AS WERE AND EDO CONCURRENCE RECEIVED.
THE ISSUE IS RESOLVED.
AS OF FY93 QUARTER 3 O
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23 ISSUE NUMBER-105 TITLE: INTERFACING SYSTEMS LOCA AT LWRS AFFECTED DOCUMENTS PROBLEM / RESOLUTION BROADENED DOCUMENTATION SCOPE FOR THE CONTRACTOR CAUSED A ONE-TO TWO-MONTH SLIP IN DOCUMENTATION MIEESTONE.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE (RES/EIB) REVIEW RES PROPOSALS FOR PRESSURE 05/84 05/84 ISOLATION VALVE LEAK TESTS & OTHERS. PROVIDE RECS TO RES FOR REVS TO TEST SCOPE / LAB SEL.
(RES) INITIATE CONTRACT FOR PIV LEAK RATE 05/84 10/84 TESTING (ETEC)
GSI 105 ASSIGNED TO RSB/DSI/NRR 06/85 06/85 PRELIMINARY DISCUSSION OF WORK PLAN WITH BNL BNL PRELIMINARY COST ESTIMATE OF WORK PLAN 09/85 08/85 DEVELOP WORK PLAN AND CONTRACT PROPOSAL DRAFT WORK PLAN 10 DIRECTORS DSI, DE, DL DHFS.AE00 INCORPORATE COMMENTS INTO WORK PLAN 10/85 10/85 FINAL WORK PLAN APPROVED BY DSI DIRECTOR AND 10/85 11/85 FORWARDED TO DST ISSUE CONTRACT TO BNL 10/85 12/85 MODIFY CONTRACT 01/86 01/86 EXPAND CONTRACT TO INCLUDE PWRS 03/86 02/86 lRES/EIB) PREPARE GENERIC LETTER TO ALL 07/86 07/86 LICENSEES ASKING FOR PROOF OF VERIFICATION OF RCPB BY TESTING PIV'S (NRR) DIRECTOR NRR FORWARD 50.54(F) GENERIC 08/86 02/87 LETTER FOR CRGR APPROVAL l
AS OF FY93 QUARTER 3 i
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24 ISSUE NUMBER: 105 TITLE: INTERFACING SYSTEMS LOCA AT LWRS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE
[bkbh kEVkEbkNb kPPkbVE hb$5k[F) LkkkbkLL hhhhh b3hhh LICEN EES RE VERIF. OF PIV'S; (NRR/DSRO)
ISSUE 10CFR50.54(F) LTR ON PIV VERIFICATION (RES/EIB) REVIEW LIC RESP TO 10 CFR 50 54(F) 01/87 10/87 ON PIV VERIF. DETERMINE PROCS. ARE ADEQUATE TO ASSURE INTEG OF RCTR COOLANT PRES BOUNDARY JINAL DRAFT REPORTS RECEIVED FROM BNL 07/86 02/88 4NCLUDING VALUE/ IMPACT ANALYSIS PUBLISH NUREG REPORTS 02/89 02/89 REVISED TAP 04/89 02/90 NRR IS-LOCA AUDITS OF THREE PLANTS 04/90 08/90 COMPLETE B&W PLANT ANALYSIS 09/90 09/90 PUBLISH IMPEL COMPONENT FRAGILITY RESULTS 09/90 10/90 ACRS REVIEW B&W PLANT ANALYSIS 11/90 12/90 COMPLETE WESTINGHOUSE ANALYSIS COMPLETE CE PLANT ANALYSIS 12/90 06/91 EVALUATE IS-LOCA INSIDE CONTAINMENT 12/90 06/91 EVALUATE IS-LOCA EXTERNAL EVENT INITIATORS ENVIRONMENTAL QUALIFICATION ANALYSIS 08/91 08/91 BWR SITE VISIT 10/91 10/91 OGCB GUIDANCE REQUESTED 04/92 04/92 ADVANCED REACTOR INSIGHTS 04/92 05/92 NRR INFORMATION NOTICE 04/92 05/92 LEAD PM ASSIGNMEN7 REQUESTED 04/92 06/92 l
AS OF FY93 QUARTER 3 l
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[
EDO CONCURRENCE 06/93 06/93 REG ANALYSIS PUBLISHED 07/93 07/93 i
i AS OF FV93 QUARTER 3
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26 ISSUE NUMBER: 106 TITLE; PIPING AND USE OF HIGHLY COMBUSTIBLE GASES IN VITAL AXEAS IDENTIFICATION DATE: 10/84C PRIORITIZATION DATE: II/87C TYPE: GSI PRIORITY: M TASK MANAGER:
R. WOODS OFFICE / DIVISION / BRANCH: RES /DSIR/SAIB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE: 07/93 WORK AUTHORIZATION: MEMORANDUM FOR G. ARLOTTO FROM E. BECKJORD DATED 11/3/87 FIN CONTRACTER CONTRACT TITLE k6k98 khkL DkkhRkhbhibNbF bybRbbkhbkbkhVkiktkRkkS W0RK SC0PE
..............................................---................h..........................................................
SEARCH LERS AND INDUSTRIAL DATABASES FOR OPERATIONAL B EVALUATION OF THE RISK ASSOCIATED WITH HYDROGEN STORAGE SAFETY EXPERIENCE INVOLVING COMBUSTIBLE GASES.
EVALUATE FACILITIES USING INF ORMATION F ROM THE REGIONAL OF F ICE S RE -
INFORMATION TO ESTIMATE FREQUENCY AND SEVERITY OF POSSIBLE QUESTED BY NRR AND Cl A REVISED PRA APPROACH FOR PWR*S EVENTS.
ASSESS EVENTS IN TERMS OF CURRENTLY ACCEPTABLE BASED ON A DEidILED EVALUATION OF INDIAN POINT 2 AND SENSI-STAFF GUIDELINES FOR EQUIPMENT DESIGN AND HANDLING OF TIVITY CALCULATIONS FOR OTHER PLANTS COMBUSTIBLE GASES AND REEVALUATE RISK ASSOCIATED WITH LACK H2 STORAGE FACILITIES REMOVED FROM SCOPE IN 04/92, OF PLANT CONFORMANCE TO CURRENTLY ACCEPTABLE GUIDELINES REASON IS NEED FOR PEER REVIEW OF NEW DETONATION AND (E A).
INCORPORATION OF EXCESS FLOW CHECK VALVES OR BUILDING RESPONSE CALCULATIONS WHICH DO NOT USE TNT EQUIVdLENT PROTECTION AGAINST H2 PIPE BREAKS).
EVALUATE EQUIVALENCY METHOD.
NEW SEPARATION DISTANCE CRITEPIA NEED FOR ANY REVISION TO GUIDELINES AND PREPARE RESOLUTION SIGNIF ICANTLY L ARGER THAN EPRI GUIDELINE VALUES FOR LARGER PACKAGE WITH V/I ANALYSIS.
THE SCOPE WAS EXPANDED TO SUPPLIES.
IMPACT OF NEW CALCULATIONS METHOD ON PLANTS NOT INCLUDE: A) SITE VISITS TO RWR'S AND A SCOPING ANALYSIS TO EVALUATED.
DETERMINE THE NEED FOR MORE DETAILED RISK ANALYSES OF BWR'S, STATUS MEETINGS HELD WITH A) ACRS SUBCOMMITTEE IN 07/92 ACRS GENERIC LETTER AND THAT SUBJECT COULD BE COVERED UNDER FULL COMMITTEE IN 07/92 AND C) CRGR IN 09/92 AC IPEEE.
REVISED LETTER FROM EDO TO ACRS PREPARED TO REFLECT RECOMMENDED THAT PROPOS$D GENERIC LETTER BE S(NT TO BOTH THIS CONCLUSION.
NEW GENERIC LE TTER WILL BE SENT FOR BWRS AND PWRS AND THAT PLANT EVALUATIONS INCLUDE WEAKNESSES INFORMATION ONLY TO BWRS AND PWRS AND WILL REFER TO NEW OF FIRE BARRIERS IN EVALUATION OF DETONATION DAMAGE.
CROR INFORMATION DEVELOPED UNDER GSI-108 AND THE STAFF INTEREST CONCLUDED THAT RISK IS INSUFFICIENT TO JUSTIFY BURDEN OF IN THE COVERAGE OF RISK FROM HYDROGEN IN THE IPEEE.
AS OF FY93 QUARTER 3 O
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27 ISSUE NUMBER: 106 TITLE: PIPING AND USE OF HIGHLY COMBUSTIBLE GASES IN VITAL AREAS i
AFFECTED DOCUMENTS PROBLEM / RESOLUTION SRP 9.5.1 TELEPHONE DISCUSSIONS HELD WITH SANDIA PERSONNEL CONCERNING PEER REVIEW OF INEL REPORT ON HYDROGEN STORAGE FACILITIES.
INFORMATION NOTICE HELD UP IN NRR DUE TO HIGHER PRIORITY WORK. PEER REVILW WAS DONE UNDER INEL SUBCONTRACT TO SNL.
PRELIMINARY RESULTS INCONCLUSIVE.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE PREIIMINARY DISCUSSIONS WITH CONTRACTOR 08/88 09/88 DRAFT S0W ISSUED TO CONTRACTOR 09/88 09/88 ISSUE CONTRACT 08/88 12/88 TAP APPROVED 08/88 01/89 COMPLETE SURVEY OF PLANT INFORMATION 02/89 02/89 COMPLETE REPORT ON SURVEY 03/89 03/89 COMPLETE REPORT ON RECOMENDATIONS FOR 05/89 03/89 HYOROGEN SYSTEMS ISSUE REVISED TAP 10/89 12/89 COMPLETE PRELIMINARY TER ON TASK $ WORK ON 11/89 11/89 TANK FARM HAZARD COMPLETE DRAFT TR ON TASK 2 (LEAK FREQ AND 01/90 01/90 POTENTIAL DAMAGE ]
COMPLETE LETTER REPORT ON TASK 3 RESULTS OF 01/90 01/90 CONSULTATION WITH INDUSTRY COMPLETE FINAL TER ON TASK 5 WORK ON TANK 02/90 04/90 FARM HAZARD AS OF FY93 QUARTER 3 P
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28 ISSUE NUMBER: 100 TITLE: PIPING AND USE OF HIGHLY COMBUSTIBLE GASES IN VITAL AREAS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE bbMPLETEDkkFhTEkbN kkSKhbN[ER Pkk hk/hh hk/h,h COMPLETE DRAFT TER ON TASK 1 (SURVEY OF 06/90 07/90 BWR'S)
COMPLETE DRAFT NUREG/CR ON TASK 1 (SCOPING 02/91 04/91 PRA FOR UWRS)
COMPLETE FINAL DRAFT NUREG/CR ON PWRS 03/91 03/91 KENNEDY DRAFT REPORT COMPLETE 04/91 04/91 KENNEDY REPORT ON EXPLOSION STANDARDS 05/91 05/91 COMPLETE COMPLETE CAMERA READY COPY NUREG/CR ON PWRS 04/91 08/91 DRAFT REGULATORY ANALYSIS COMPLETED 01/90 09/91 COMPLETE CAMERA READY COPY OF NUREG/CR TASK 03/91 12/91 1 (BWRS)
DTR PACKAGE COMPLETED 02/90 03/92 DTR PACKAGE TO ACRS C4/92 04/92 l
l DTR PACKAGF TO NRR, AEOD, OGC FOR COMMENTS 06/92 06/92 ACRS REVIEW (SUBCOMMITTEE AND FULL 07/92 07/92 COMMITTEEI DTR PACKAGE TO DIRECTOR, RES 07/92 08/92 CRGR MEETING ON PROPOSED RESOLUTION 08/92 09/92 PREPARE GENERIC LETTER PKG WITH DRAFT 10/92 11/92 REGULATORY ANALYSIS GENERIC LETTER PACKAGE SENT TO NRR FOR 10/92 12/92 ISSUANCE AS OF FY93 QUARTER 3 O
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ISSUE NUMBER: 142 TITLE: LEAKAGE THROUGH ELECTRICAL ISOLATORS IDENTIFICATION DATE: 06/87C PRIORITIZATION DATE: 06/90C TYPE: OSI PRIORITY: M TASK MANAGER: C.
ROURK OFFICE / DIVISION / BRANCH: RES /DSIR/EIB ACTION LEVEL: ACTIVE STATUS: 3B TAC NUMBERS:
RESOLUTION DATE: 03/93C WORK AUTHORIZATION: MEMORANDUM FOR W.
MINNERS FROM E. BECKJORD DATED JUNE 20, 1990.
FIN CONTRACTOR CONTRACT TITLE LI842 SNL RISK ASSESSMENT OF ISOLATION DEVICES IN SAF ETY SYSTEMS WDRK SC0PE THE OBJECTIVE OF THIS ACTIVITY IS TO: Il PERFORM A SURVEY JANUARY I, 1971, 3) PERFORM A RISK ASSE SSME NT OF FAILURES OF OF THE DEGRADATION AND/OR FAILURE OF ISOLATION DEVICES USED ISOL ATION DEVICE S, OR A LACK OF ISOL ATION DEVICES {THAT CAN IN SAFETY SYSTEMS, 2) ASSESS THE TYPE OF ISOLATION DEVICES, p0TENTIALLY EXIST IN OLDER PLANT DESIGNS)6LVEAND 4) EVALUATE IF ANY, USED IN PLANTS THAT WERE LICENSED BEFORE IF ADDITIONAL NRC ACTION IS NEEDED TO RES THIS ISSUE STATUS hkWkkkkkhkbbkhkhhkR k9hh khthkhhbhPLkkkbhhk PkhPhhkbkkhhlhhhh khbkhLhkhhhhkhbkkhbhhhhhEkhh NUREO/CR ON OPERATIONAL EXPERIENCE AND HAS ISSUED THE DRAFTED.
ACRS CONCURRED WITH RESOLUTION IN FEDRUARY 1993.
NUREG/CR FOR PUBLICATION. NRR HAS VERBALLY CONCURRED IN THE CLOSE OUT MEMO ISSUED MARCH 9, 1993 AFFECTED DOCUMENTS PROBLEM / RESOLUTION CRIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE GSI I42 ASSIGNED TO RES/DSIR/EIB 07/90 07/90 DRAFT TAP TO DSIR DEPUTY DIRECTOR 11/90 12/90 AS OF FY93 QUARTER 3 O
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31 ISSUE NUMBER: 142 TITLE: LEAKAGE THROUGH ELECTRICAL ISOLATORS i
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE TAP APPROVED BY DSIR DIRECTOR AND 12/90 12/90 FORWARDED TO OTHER RES AND NRR DIVISIONS i
INITIATE PROGRAM 01/91 01/91 i
SURVEY OF ISOL. DEV. FAILURE 06/91 0F/91 ASSESS ISOL. DEVICES IN PRE-71 PLANTS OT/91 07/91 RISK ASSESSMENT OF ISOL. DEVICES 11/91 01/92 EVALUATION OF NEED FOR ADDITIONAL ACTION 01/92 01/92 (TASK 4)
DEVELOP POSITIONS AND PREPARE DRAFT 08/92 03/92 PACKAGE DIVISION DIRECTOR REVIEW OF DRAFT 09/92 03/92 RESOLUTION i
OFFICE DIRECTOR REVIEW OF DRAFT 10/92 04/92 RESOLUTION CONCURRENCE BY OTHER OFFICES 12/92 02/93 ACRS REVIEW COMPLETE 02/93 03/93 ISSUE DRAFT FINAL RESOLUTION 05/93 03/93 5
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RUN DATE: 07/27/93 OENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
33 ISSUE NUMBER: 143 TITLE. AVAILABILITY OF CHILLED WATER SYSTEM AND ROOM COOLING ORIGINAL CURRENT ACTUAL i
MILE $T0NE$
DATE DATE DATE f
bkVhthPbRkhhhhkkkMhNhhhhhRK (hhhhhkTH hhhh1 5-hhh9,1 1
CONTRACTOR 1
ISSUE SDW AND WORK AUTHORIZATION 07/91 07/91 1
EXAMINE HVAC DATA BASE (TASK 1) 11/91 12/91 ISSUE, TAP 07/91 01/92 SELECT REPRESENTATIVE PLANTS AND EMAMINE 0S/92 06/92 RISK DUE TO HVAC FAILURES (TASK 21 QUANTIFY SPECIFIC RISK FOR SEQUOYAH AND 08/92 08/92 GRAND GULF (TASK 2A)
QUANTIFY SPECIFIC RISK FOR OCONEE AND PALO 09/92 09/92 VERDE (TASK 2B)
DETERMINE HVAC FAILURE RISK (GENERIC) FOR 10/92 10/92 l
PWR AND BVR (TASK 2C)
(
IDENTIFY CORRECTIVE MEASURES AND PERFORM 09/92 01/93 VALUE/ IMPACT ANALYSIS (TASK 3) k DRAFT NUREG/CR REPORT (TASK 4) 11/92 03/93 i
FINAL NUREG/CR REPORT FROM CONTRACTOR 12/92 04/93 l
(TASK S) l ISSUE DTR (TASK 61 01/93 07/93 l
SUBMIT DTR TO ACRS/CRGR (TASK 7) 02/93 07/93 ACRS/CRGR REVIEW 04/93 08/93 ISSUE CLOSE00T MEMORANDUM (TASK 11) 01/94 01/94 i
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AS OF FY93 QUARTER 3 i_,.-____
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RUN DATE: 07/27/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
34 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 /DSIR/PRAB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS:
RESOLUTION DATE. 11/93 WORK AUTHORIZATION: MEMORANDUM FROM E. S. BECKJORD TO W. MINNERS DATED FEBRUARY II, 1992 FIN CONTRACTOR CONTRACT TITLE L2553 BNL TECHNICAL SUPPORT TO GI-145 W0RK SC0PE THE ACTIONS REQUIRED TO RE90LVE THE ISSUE ARE MINIMAL.
THE AVAILABLE ON COMMON MODE FAILURES AND PUBLISH IT IN A SCOPE OF THE ISSUE IS ONLY TO COLLECT THE INFCRMATION NUREG REPORT, 50 AS TO BE READILY AVAILABLE TO LICENSEES.
STA TUS bNLkbh[fihTEbkhhRb58h bb5RPRbVkbhbkbhbkhbhbhhkRh M h kh khhh DNL'S WORK ON APRIL 23, 1993.
BNL STARTED THE WORK ON AFFECTED DOCUMENTS PROBLEM / RESOLUTION PbbhkhlkhbRkb/bR hhNE ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE COMPLETION OF GI PRIORITIZATION 02/92 02/92 COMPLETION OF TAP 04/92 04/92 ISSUE CONTRACT FUND 01/93 04/93 AS OF FY93 QUARTER 3 O
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OENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE.
36 ISSUE NUMBER: 147 TITLE: FIRE-INDUCED ALTERNATE SHUTDOWN / CONTROL ROOM PANEL INTERACTIONS IDENTIFICATION DATE: 08/89C PRIORITIZATION DATE: 08/92C TYPE: LI PRIORITY.
TASK MANAGER: J. CHEN OFFICE / DIVISION /DRANCH: NRR /DSIR/SAIB ACTION LEVEL: ACTIVE STATUS: 5 TAC NUMBERS:
RESOLUTION DATE: 10/93 WORK AUTHORIZATION: MEMORANDUM FOR W. MINNERS FROM E.
BEcrJORD OATED AUGUST 26, 1992 FIN CONTRACTOR CONTRACT IITLE l
NONE NONE NONE WDRK SC0PE hhhkhk[hPhhhhkhhkkhR kHkhhkFkkEVkkhhkLkbEhkEkkPkkk Shhhhhhh/bbbhkhl kbbh PkhEL khkkRkh hhh SUBMITTALS IN THE AREA RELATED TO FIRE-INDUCED ALTERNATE STATUS hkkkkkkkkkhhEhhbhkhbkhkkbkhEkV khh3$
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ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE 01-147 ASSIGNED TO RES/DSIR/EIB 09/92 09/92 REASSIGNED TO SAIB 02/93 02/93 DRAFT STAFF REVIEW GUIDANCE ON FIRE-INDUCED 08/93 08/93 ALTERNATE SHUTDDWN/ CONTROL ROOM PANEL INTERACTION AS OF FY93 QUARTER 3 O
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RUN DATE: 07/27/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
38 ISSUE NUMBER:
148 TITLE: SMOME CONTROL AND MANUAL FIRE-FIGHTING EFFECTIVENESS IDENTIFICATION DATE: 04/89C PRIORITIZATION DATE: 08/92C TYPE: LI PRIORITY:
TASK MANAGER:
J. CHEN OFFICE / DIVISION /DRANCH: RES /DSIR/SAIB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS; RESOLUTION DATE: 11/93 WORK AUTHORIZATION: MEMOR ANDUM F ROM E.
S.
BECKJORD TO W.
MINNERS DATED
+
AUGUST 26, 1992 FIN CONTRACTOR CONTRACT TITLE W0RK SC0PE I
TO DEVELOP STAFF GUIDANCE FOR THE REVIEW OF LICENSEES' MANUAL F IRE-F IGHTING EF F ECTIVENESS.
IPEEE SUDMITTALS RELATED TO THE EFFECTS OF SMOKE AND STA TUS kkhkkkkkhkbhkDkhhkkhhhkbkkbhhkhFEbkhkkhkh93$
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AFFECTED DOCUMENTS PROBLEM / RESOLUTION PbShkhlkhukkbhhh hhNk 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 RELATED TO SMOKE 09/93 09/93 AND MANUAL FIRE. FIGHTING EFFECTIVENESS AS OF F Y93 QUAR TER 3 O
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39 ISSUE NUMBER: 148 TITLE: SMOKE CONTROL AND MANUAL FIRE-FIGHTING EFFECTIVENESS ORIGINAL CURRENT ACTUAL MILEST0NE$
DATE DATE DATE STAFF REVIEW OU1 DANCE FOR G1-148 11/93 11/93 i
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RUN DATE: 07/27/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
40 ISSUE NUMBER: 153 TITLE: LOSS OF ESSENTIAL SERVICE WATER SYSTEM IN LWRS IDENTIFICATION DATE: OS/90C PRIORITIZATION DATE: 02/91C TYPE: 3SI PRIORITY H TASK MANAGER:
T. M.
SU OFFICE / DIVISION /DRANCH: RES /DSIR/SAIB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: L1843 RESOLUTION DATE: 06/93C WORK AUTHORIZATION: MEMO TO R.
Y.
LDWRY FROM W.
MINNERS, DATED 03/27/91 FIN CONTRACTOR CONTRACT TITLE
[k84h hh[
Lbkhbkkkhkkkkk[hkkVkbhhkkkkkh[hkhfbkk3hh L1854 SEA WDRK SC0PE THIS ISSUE DEALS WITH POTENTIAL UNAVAILABILITY OF THE UNAVAILABILITY EXCEPT THOSE (SUCH AS BI0F OULING) WHICH ARE ESSENTIAL SERVICE WATER SYSTEM IN ALL OPERATING PLANTS CONSIDERED TG BE RESOLVED BV IMPLEMENTING THE REQUIREME NTS EXCEPT THOSE WHICH HAVE BEEN STUDIED UNDER 01-130.
THIS SPECIFIED IN GENERIC LETTER 89-13.
ISSUE WILL INCLUDE ALL POTENTIAL CAUSES FOR THE ESW SYSTEM S7 ATUS kPkhPbhkbkkhbLbkkbhPkbkbkhbkkbkhbEhkhkbkhhbkhkh kkhbtbkkbhbkbEhERkbkkhbE [hh[bk$khb}IAbkhbi[hhkhikk[
l REVIEWEC AND CONCURRED BY NRR STAFF ON MAY 12 1993.
IN A SERVICE WATER IN LWR'S," WAS ISSUED.
INSIGHTS FROM THE MEMOR6NDUM DATED MAY 24 1993 THE ACRS INDICdTED THAT NO GI-153 STUDY WILL BE PUBLISHED AS NUREG-1461, " REGULATORY FORMAL REVIEW OF THE PAdKAGE IS NEEDED.
ON JUNE 14, 1993, A ANALYSIS FOR THE RESOLUTION OF GI-153, " LOSS OF ESSENTIAL MEMORANDUM FROM ERIC S.
BECKJORD DIRECTOR OF RESEARCH TO SERVICE WATER IN LWR'S."
JAMES M.
TAYLOR, EXECUTIVE DIRECT 0R FOR OPERATIONS, SU6 JECT:
AFFECTED DOCUMENTS PROBLEM / RESOLUTION
- NONE, NONE.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE AS OF FY93 QUARTER 3 O
O O.
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m RUN DATE: 07/27/93 OENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
41 ISSUE NUMBER: 153 TITLE: LOSS OF ESSENTIAL SERVICE WATER SYSTEM IN LWRS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE kkhbk PHkhk k bb Fbk CbMThkbTbR b4/hk b3/h,5 ISSUE PHASE I AND II TAP 02/91 07/91 DRAFT CONTRACTOR REPORT ON PHASE I STUDY 10/91 12/91 DECISION ON INTERIM RESOLUTION 12/91 02/92 DECISION ON TECH SUPPORT 04/92 04/92 FINAL CONTRACTOR (SNL) REPORT ON PHASE I 06/92 08/92 STUDY DTR PACMAGE PREPARED 07/92 12/92 CONTRACTOR (SEA) REPORT ON PHASE I 08/92 01/93 SUPPLEMENTAL STUDY RES DIRECTOR REVIEW OF DTR PACKAGE 08/92 02/93 COMPLETED DTR PACMAGE REVIEWED BY OTHER OFFICES (NRR, 09/92 04/93 AE00, DGC)
DTR SENT TO ACRS 10/92 04/93 ACRS REVIEW DTR COMPLETED 11/92 05/93 ISSUED CLOSEOUT MEMO 06/93 06/93 PUBLISH REGULATORY ANALYSIS 07/93 01/93 4
AS OF FY93 QUARTER 3
i l
l I
RUN DATE: 07/27/93 i
i GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
42 1
1 ISSUE NUMBER:
155.1 TITLE: MORE REALISTIC SOURCE TERM ASSUMPTIONS IDENTIFICATION DATE: 03/79 PRIORITIZATION DATE: 02/92C TYPE: GSI PRIORITY; TASK MANAGER. L.
SOFFER OFFICE / DIVISION / BRANCH: RES /DSIR/SAIB ACTION LEVEL. ACTIVE STATUS: NR TAC NUMBERS:
RESOLUTION DATE: 11/93 WORM AUTHORIZATION: MEMO FOR W. MINNERS FROM E. BECKJORD DATED 2/26/92 FIN CONTRACTOR CONTRACT TITLE 808$4 ORNL IODINE CHEMICAL FORMS L1535 BNL RADIONUCLIDE RELEASE CHARACTER L1611 INEL TIMING ANALYSIS OF FUEL F AILURES L2035 SNL SOURCE TERM REMOVAL MECHANISMS W8067 ORNL CHEMICAL FORM OF SOURCE TERMS WDRM SC0PE DEVELOP A REVISED ACCIDENT SOURCE TERM TO REPLACE THAT AND IODINE CHEMISTRY.
IMPLEMENT REVISED ACCIDENT SOURCE GIVEN IN TID-14844. MAKING USE OF CURRENT RESEARCH TERM TOGETHER WITH SEVERE ACCIDENT INSIGHTS. IN A REVISION INSIGHTS ON FISSION PRODUCT TIMING, COMPOSITION, MAGNITUDE, OF 16 CFR PART 50.
STATUS kkkkL kkPbkkb bh kbbkhE bb[MIb L kbkM khb TkMkhb bbkkb/bk$
hkbY$92 k2k Ikb bRkkk hhbPbbkb bbR b hbkhbbh hb 5
5732 AND NUREG/CR-5787) HAVE BEEN ISSUED. DRAFT EPORT EVISED ACCI ENT SOURCE TERM HAVE BEEN ISSUED.
A COMMISSION ON FISSION PRODUCT COMPOSITION AND MAGNITUDE (NUREG/CR-5747)
MEETING WAS HELD ON APRIL 20, 1992.
NUREG-1465 ISSUED HAS BEEN ISSUED.
CONTRACTOR STUDIES ON FISSION PRODUCT JULY 28 1992.
BNL AND ORNL REVIEW OF PUBLIC COMMENTS REMOVAL MECHANISMS ARE CONTINUING. A COMMISSION PAPER RECEIVED APRIL 27, 1993.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION kb$k3 k4IhkPkb6$b hkl hbkkhhlkbbkht khbbMPLkkkhhhhkkh/hR kkPbkhb R.G.
1,7, 1.25 SCHEDULE ALSO IMPACTED BY DETAIL OF TASK MANAGER TO OFFICE OF THE CHAIRMAN.
O O.
x RUN DATE: 07/27/93 OENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE-43 ISSUE NUMBER:
155.1 TITLE: MORE REALISTIC SOURCE TERM ASSUMPTIONS ORIGINAL CURRENT ACTUAL MILEST0#FS DATE DATE DATE kbbkhkhTkbhbbEbbLkTbbbMMIhhkbh h4)hh hhhh,b PRA BASED SOURCE TERM PAPER TO C0t94ISSION 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 COMENT PROPOSED REV. TO TID TO RES DIRECTOR 07/91 09/91 PROPOSED REVISION TO NRR/00C 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 ORAFT 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 COMENT lINEL)
ISSUE REVISED TID FOR COWENT 02/92 07/92 ISSUE ORNL IODINE REPORT AS FINAL 04/92 04/92 SNL REPORT ON POOL DF NURE0/CR ISSUED FOR 08/92 09/92 COMMENT ISSUE INEL REPORT FINAL 08/92 09/92 END COMMENT PERIOD ON DRAFT SOURCE TERM 08/92 10/92 NUREO AS OF FY93 QUARTER 3
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RUN DATE: 07/27/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
44 ISSUE NUMBER:
155.1 TITLE: MORE REALISTIC SOURCE TERM ASSUMPTIONS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE RESPONSE TO SRM ON IMPACT OF INCREASED 09/92 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 NURE0/CR ISSUED FINAL 11/92 06/93 SNL REPORT ON POOL OF NURE0/CR ISSUED FINAL 11/92 07/93 ISSUE BNL REPORT FINAL 06/92 07/93 SNL SUPP. POOL NUREG/CR ISSUED FINAL 03/93 09/93 SNL AEROSOL NUREG/CR ISSUED FINAL 03/93 10/93 COMPLETE REVISED DRAFT SOURCE TERM NUREG 11/92 10/93 (FOR USE WITH PART 50 REVISION)
TRANSMIT CLOSE00T MEMO TO ACRS 11/92 10/93 ISSUE CLOSE00T MEMO 12/92 11/93 l
l AS OF FY93 QUARTER 3 I
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RUN DATE' 07/27/93 GENERIC 73 SUE MANAGEMENT CONTROL SYSTEM PAGE 45 ISSUE NUMBER:
166 TITLE: ADEQUACY OF FATIGUE LIFE OF METAL COMPONENTS IDENTIFICATION DATE: 04/93C PRIORITIZATION DATE: 06/93C TYPE: GSI PRIORITY:
TASK MANAGER: J. FAIR OFFICE / DIVISION / BRANCH: NRR /DE /EMEB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS: M86344 RESOLUTION DATE:
WORK AUTHORIZATION: APRIL 1, 1993. MEMORANDUM FROM T. MURLEY TO J. SNIEZEK FIN CONTRACTOR CONTRACT TITLE WORK SCOPE EVALUATEFATIGUEAbkhbkbhbhbPhRkkkhbPLkhhbbMPbhEkhS$
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ORIGINAL CURRENT ACTUAL MILEST0NE$
DATE DATE DATE TASK ACTION PLAN UNDER DEVELOPMENT AS OF F Y93 QUAR TER 3 l
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RUN DATE: 07/27/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
46 ISSUE NUM8ER: 168 TITLE: ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT IDENTIFICATION DATE: 04/93C PRIORITIZATION DATE: 06/93C TYPE: GSI PRIORITY:
TASK MANAGER: G. HUBBARD OFFICE / DIVISION / BRANCH: NRR /
/SPLB ACTION LEVEL: ACTIVE STATUS; NR TAC NUMBERS: M85648 RESOLUTION DATE: ______
WORK AUTHORIZATION: APRIL I, 1993, MEMORANDUM FROM T, MURLEY TO J.
SNIEZEK FIN CONTRACTOR CONTRACT TITLE A2336 ANL RISK IMPACT OF EQ E2095 SCIENTECH EQ FOR OPERATING REACTORS W0R K SC0PE I.
TO GATHER, REVIEW, AND EVALUATE OPERATING EXPERIENCE RESOURCES IN THE PERFORMANCE OF EQ AGING REVIEWS.
DATA AND EQUIPMENT REPLACEMENT SCHEDULES FOR NUCLEAR POWER 2.
TO PERFORM A DETAILED ASSESSMENT OF THE RISK PLANTS TO PROVIDE INSIGHT AS TO WHERE NRC SHOULD F UCUS ITS ASSOCIATED WITH EQ ISSUES.
STATUS A PRELIMINARY RISK SCOPING ASSESSMENT WAS ISSUED ON EQ TASK ACTION PLAN.
THE EQ TASK ACTION PL AN WAS ISSUED TO MARCH 30, 1993.
USER NEED MEMU WAS ISSUED TO RESEARCH ON THE COMMISSION ON JULY I, 1993.
THE PROGR AMMATIC RE VIEW APRIL 22, 1993.
COMMISSION WAS INFORMED ON MAY 28, 1993.
AND DATA COLLECTION AND ANALYSIS HAVE STARTED.
A CONTRACT NRR AND RES MET WITH NUMARC ON JUNE 16, 1993 REGARDING THE IS IN PLACE FOR A DETAILED RISK ASSESSMENT.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION IN 92-81 AND 93 33.
NONE.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE kNFbRMbbMMikSkbN hhhh3 5
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RUN DATE: 01/27/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE; 48 J
ISSUE NUMBER B-17 TITLE: CRITERIA FOR SAFETY-RELATED EPERATOR ACTIONS IDENTIFICATION DATE: 08/78C PRIORITIZATION DATE: II/83C TYPE: GSI PRIORITV' M TASK MANAGER: J.
KRAMER OFFICE / DIVISION / BRANCH; RES /DSR /HFB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE: 09/94 WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN (APPENDIX G)
FIN CONTRACTOR CONTRACT TITLE kOkkh hhhb khhkbkkhkbhbhhbhhPkhhbRhhbhhkbhbkShbtLhkkhbhhE hELIkbitkkh EVALUATION PROCESS (TASKS 5 AND 6)
W0RK SC0PE khk5bkKhbbPkkhb[bbkh k) bEVk[bP khkbkkEhkbh kIhbI[bPkkkkbhkbkkbhbkkbbhkkkbkbhkbh hhhhbbPEbh FOR SAFETY RELATED OPERATOR ACT ONS: (2) DETERMINE WHETHER THIS GENERIC ISSUE COVERS DESIGN BASIS ACCIDENTS OR EVENTS.
OR NOT AUTOMATIC ACTUATION WILL BE REQUIRED; AND (3) DEVELOP CRITERIA FOR SAFE TY REL ATED OPER ATOR ACTIONS DURING SEVERE GUIDANCE 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 W.
RUSSELL TO T. SPEIS).
WHICH SPOULD LEAD TO RESOLUTION OF THIS GSI BY E NDORSING l
NO WORK HAD BEEN COMPLETED ON THE ISSUE PRIOR TO TRANSFER.
ANSI /ANS 58.8.
THIS STANDARD IS REING REVISED BASED ON NEW i
DURING 1983 AND 1984, RES WORKED ON THIS ISSUE.
DURING INDUSTRY DATA LLNL BEGAN WORK TO MANAGE THE TECHNICAL THAT TIME DATA WERE COLLECTED BY RES CONCERNING OPERATOR EFFORT INVOLVING EPRI AND A SUBCO*fTRACTOR TO EPRI IN MARCH RESPONSE TIMES.
ANST/ANS 18.8 WAS PUBLISHED IN SEPTEMBER 1989.
1984.
THE GENERIC ISSUE WAS LATER TRANSFERRED TO NRR.
NO AFFECTED DOCUMENTS PROBLEM / RESOLUTION hbbkhRbVkbkb[kkkk kbhEbblEbkhhLkPPkbbbE bh[kPPkbEkbkN EDbl F0 SC APPROVAL OF STANDARD ANSI /ANS 58 8.
ALSO, SINCE NRC ENDORSEMENT WILL BE IN THE FORM OF A REGULATORY GUIDE.
TIME IS NEEDED TO GO THROUGH THE REGULATORY GUIDE APPROVAL PROCESS.
i AS OF FY93 QUARTER 3 O
O O.
a RUN DATE: 07/27/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
49 ISSUE NUMBER:
B-17 TITLE: CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE NEET WITH ANSI /ANS 58.8 07/88 06/8,9 DEVELOP TAP 08/87 06/89 NUPPSCO SUBMITS DRAFT OF 58.8 04/92 04/92 COMPLETE DRAFT OF 58.8 08/92 08/92 NUPPSCO BALLOTS DRAFT STD 58.8 10/92 03/93 NUPPSCO ISSUES FINAL 58.8 08/93 12/93 (SCHEDULE DEPENDS UPON ISSUANCE OF ANS 58.8 REVISION BY END OF 08/93.l ISSUE DRAFT REG. GUIDE FOR 90-DAY COMMENT 12/93 12/93 PERIOD ACRS REVIEW 04/93 02/94 CRGR REVIEW 04/93 02/94 REVISE REO. QUIDE TO REFLECT PUBLIC COMMENTS 05/94 05/94 ACRS REVIEW 07/94 07/94 CRGR REVIEW 07/94 07/94 ISSUE FINAL REG QUIDE 09/94 09/94 CLOSE OUT ISSUE 09/94 09/94 AS OF FY93 QUARTf.R 3
RUN DATE: 07/21/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
50 ISSUE NUMBER:
B-55 TITLE: IMPROVE RELIABILITY OF TARGET ROCK SAFETY-RELIEF VALVES IDENTIFICATION DATE: 06/18C PRIORITIZATION DATE: 11/83C TYPE: GSI PRIORITY-M TASK MANAGER: F. CHERNY OFFICE / DIVISION / BRANCH: RES /DSIR/EIB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE: 06/96 WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN. (APPENDIX 0)
FIN CONTRACTOR CONTRACT TITLE W0RK SC0PE kkVkkhhhRbkkLkTY PPkhkhHkS b bRkkkkhbhkV bbhFbRM bbk kb hhh5 VkhbbR khhTRbbkkhhh (2h RELIABILITY TO OBTAIN SUFFICIENT DATA BASE TO SUPPORT DEMONSTRATING SUFFICIENT RELIABIL ITY OF 2-STAGE VALVES THE CONCLUSION THAT THIS ISSUE HAS BEEN RESOLVED.
AFTER DESIGN AND/OR SYSTEM MODIF ICATIONS, AND (3)
THE UTILITY APPROACHES MAY INCLUDE:
(1) DEMONSTRATING USING DIFFERENT VALVES AND DEMONSTRATING THEIR SUFFICIENT RELIABILITY OF 3-STAGE VALVES BY STRICT RELIABILTY.
STATUS WHILE INITIAL PERFORMANCE WITH THE PH 13-8 HO REPLACE-IS VERY EFFECTIVE IN REDUCING OXYGEN CONCENTRATION AT THE MENT DISCS INDICATED AN IMPROVEMENT. ADDITIONAL PERF ORMANCE VALVE DISK / SEAT INTERFACE.
PILOT VALVE CYCLING TESTS DATA MADE IT APPARENT THE NEW DISCS ARE NOT PROVIDING THE THAT DEMONSTRATE CATALYST ADHERENCE TO THE TREATED IMPROVED PERFORMANCE THAT WAS ORIGINALLY EXPECTED.
THE SURFACES HAVE ALSO BEEN SUCCESSFULLY COMPLETED A DESIGN BWROG CONCLUDED THE PH 13 8 MO REPLACEMENT DISCS ARE NOT A SPECIFICATION FOR THE ALLOY COATING AND THE TREATED VI ABLE SOLUTION FOR ELIMINATING SETPOINT DRIFT AND RECOM.
SURFACES HAS BEEN SUBMITTED TO THE BWROG FOR APPROVAL THE MENDED THEY NO LONGER BE INSTALLED TO RESOLVE THIS PROBLEM.
PILOT VALVE CONTACT SURFACES ARE A STELLITE TO STELLITE THE BWROG IS CURRENTLY WORKING ON THE DESIGN OF CATALYSTS MATERIAL WITH THE PLATINUM-STELLITE ALLOY COATING APPLIED (OPTION 1l FOR THE TARGET ROCK 2. STAGE SRV'S.
INSTALLATION TO THE PILOT VALVE DISK AND THE STABILIZER DISK.
- HOWEVER, OF REDESIGNED SRV'S WITH CATALYSTS IS SCHEDULED FOR THE AT THE FEBRUARY 1993 BWR00 MEETING. IT WAS DECIDED TO APPLY FALL OF 1993.
THEY ARE ALSO WORKING ON A PARALLEL THE ALLOY COATING TO THE PILOT VALVE DISK ONLY AND NOT TO CONTINGENCY OPTION 2; I.E.,
THE USE OF PRESSURE SWITCHES THE STABILIZER DISK.
IT WAS ALSO DECIDED TO GIVE EQUAL SIMILAR TO THOSE USED ON BWR/6 PLANTS.
THE BWROG HAS STATUS TO BOTH THE CATALYST OPTION AND THE PRESSURE SWITCH MODIFIED THE SCHEDULE WITH THE CATALYST DESIGN FOR THE OPTION.
THIS IS IN APPARENT RECOGNITION OF THE FACT THAT TARGET ROCK 2-STAGE SRV's, THE STAFF MET WITH THE BWR00 ON SOME OF THE BWROG MAY DE LOSING INTEREST IN THE CATALYST 1992 AND DISCUSSED DETAILS OF THE CATALYST DESIGN OPTION DUE TO THE LONG LEAD TIME TO OBTAIN THE CATALYTIC AUGUST 11} AND ALSO THE 1
PROGRESS ON THE PARALLEL CONTINGENCY COATED VALVE PARTS.
A LICENSING TOPICAL REPORT ON THE (OPTION OPTION 2.
AN INDEPENDENT DESIGN REVIEW HAS BEEN COMPLE TED PRESSURE SWITCH OPTION AND A DETAILED LETTER STATUS FROM IN THE THIRD QUARTER OF F Y '92 FOR OPTION 1.
LABORATORY THE BWROG HAD BEEN SCHEDULED F OR SUBMITTAL TO THE NRC IN TESTING IS COMPLETE AND DEMONSTRATES THAT THE ALLOY COATING APRIL 1993.
AS OF FY93 QUARTER 3
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RUN DATE: 07/27/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
52 ISSUE NUMBER:
D-55 TITLE: IMPROVE RELIABILITY OF TARGET ROCK SAFETY-RELIEF VALVES ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE OWNERS BEGIN TO INSTALL NEW PILOT DISKS 01/88 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 BWROG SELECT / DESIGN CATALYST 03/91 02/91 NRC STAFF ISSUE STATUS REPORT ON INDUSTRY 06/91 08/91 PROGRESS BWROG COMPLETES FINALIZING DESIGN AND 04/92 07/92 LABORATORY TESTING NRC STAFF ISSUE STATUS REPORT ON INDUSTRY 03/92 08/92 PROGRESS REASSESS ISSUE 03/93 05/93 BWROG SUBMIT TOPICAL REPORT TO NRC DESCRIBING 12/91 07/93 PRESSURE SWITCH (CONTINGENCY) OPTION DWNERS BEGIN TO INSTALL CATALYSTS TO TEST IN 09/91 09/93 PLANTS FOR FIRST FUEL CYCLE NRR ISSUE APPROVAL FOR PRESSURE SWITCH 06/92 10/93 CONTINGENCY OPTION ISSUE CLOSE0VT MEMO 02/95 06/96 AS OF F Y93 QUAR TE R 3 O
O O.
'g '
s s l
RUN DATE. OT/2T/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE-53 ISSUE NUMBER:
B-56 TITLE: DIESEL GENERATOR RELIABILITY IDENTIFICATION DATE: 06/78C PRIORITIZATION DATE: II/83C TYPE: GSI PRIORITY: H TASK MANAGER: A.
SERKIZ OFFICE / DIVISION / BRANCH: RES /DSIR/EIB ACTION LEVEL: ACTIVE STATUS: 3A TAC NUMBERS:
RESOLUTION DATE: 06/93C WORK AUTHORIZATION: NRR F Y-83 OPERATING PLAN (APPENDIX G).
FIN CONTRACTOR CONTRACT TITLE ikb6 khl~
~
bbhbkLibkh kbk~khkkb$ bkkkkL bkkkkkhbk kbbi kkthkbkLkkh PRbbkkkh~
B2937 PNL AGING CONSIDERATIONS-DIESEL GENERATOR R LIABILITY PROGRAM J
W0RK SC0PE khkhbkkhbbPkbkbhhkhbLbbkLhbbbkbkhkkkbhkkbkhk LkVkthhktkbhkbkbRRkhPbhhkibhhkhbbkbLkfkhbkkSb[
RESOLUTION OF USI A-44 STATION BLACKOUT.
RESOLUTION OF SECTION 50 631.
USI A-44 INCLUDES AMONG OTHER THINGS THE NEED FOR A DIESEL THE CONCLUDING EFFORTS ON 0-56 WILL BE DIRECTED AT RELIABILITY PROGRAM TO MAINTAIN THE RdLIABILITY LEVEL OF CARRYING OUT ACTIONS RELATED TO THE SRh IN RESPONSE TO EMERGENCY DIESEL GENERATORS (EDG) AT OR ABOVE RELIABILITY SECV-93-044 STATUS khkbbbhkkkkbhbkkkbkkbkbhhhkkkfhkhbbhkb9kbbk/bbkk kbb hhkkk kVkLbkhkb bbbbkkhh kkbkkVkb khb kbhhhhkkD k DATED JUNE 26 1991) TO REVISE THE SB0 RULE TO ADDRESS EDG RECOMMENDATION TO THE COMMISSION THAT THE PROPOSED RULE RELIABILITY THROUGH A RESULTS-ORIENTED APPROACH UTILIZING AMENDMENT BE WITHDRAWN (SECY-93-044).
IN PLACE OF THE THE FAILURE TO START AND LOAD-RUN TRIGGERS OUTLINED IN PROPOSED RULE. THE STAFF RECOMMENDED THAT GUIDANCE FOR NUMARC'S INITIATIVE 5A.
A REVISED RULE AND ACCOMPANYING MONITORING EDG PERFORMANCE AGAINST TARGE T LEVELS SELECTED REGULATORY GUIDE (RG I.9, REV. 3) WAS ISSUED FOR COMMENT FOR THE 580 ANALYSES BE INCORPORATED INTO THE REGUL ATORY ON APRIL 21, 1992.
GUIDE AND GUIDANCE BEING DEVELOPED BY NUMARC FOR IMPLEMENTA-NUMARC AND INDUSTRY RESPONDEES OPPOSED THE NEED FOR THIS TION OF THE MAINTENANCE RULE 10 CFR 50 65).
THE STAFF lS RECOMMENDATIONS ON RULE CITING CURRENTLY INDUSTRY-WIDE EDG RELIABILITY LEVELS COMMISSION APPROVED THE OF 99% AND RECOMMENDED THAT THE PLANNED MAINTENANCE RULE 03/25/93.
THE MAINTENANCE RULE REGULATORY GUIDE WAS GUIDANCE BE USED TO MAINTAIN CURRENT LEVELS OF EDG ISSUED JUNE 1993.
RELIABILITY.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION Rkh bbkbk k h hill bE hkVikkb Tb'bbhFbkM kb hkM hbbk
~
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AS OF FY93 QUARTER 3
~ -
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RUN DATE 07/2T/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
54 ISSUE NUMBER:
B-56 TITLE: DIESEL GENERATOR FELIABILITY AFFECTED DOCUMENTS PROBLEM / RESOLUTION l
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE bhk khkNh h h hhhhh hY hhk b k b b hhR hhhh hhhhh STAFF. COMMENT PACKAGE TO NRR DIRECTOR 04/83 03/83 PACKAGE TO CRGR (29);
05/83 07/83 CRGR REVIEW COMPLETE SCOPE OF ISSUE MODIFIED TO COORDINATE 09/83 09/83 TECHNICAL RESOLUTION OF B-56 WITH USI A-44 SCOPE OF ISSUE MODIFIED TO CONSIDER NUMBER OF 11/83 11/83 COLD FAST START SURVEILLANCE TESTS COORDINATED GSI B-56 AND USI A-44 CRGR PACK-02/84 01/84 AGE SENT TO NRR DIRECTOR REVISED PACKAGE TO CRGR - ACTUAL DATE 03/84; 05/84 05/84 CRGR REVIEW COMPLETE ISSUED 50.54(F) GL 84-15 TO LICENSEES 06/84 07/84 RECEIVED PUBLIC COMMENTS 09/84 11/84 ISSUED T/A CONTRACT TO BNL 06/85 06/85 PUBLISH CONTRACTOR REPORT ON LICENSEE 04/86 04/86 RESPONSE TO 50.54(F)
REVISE SRPS AND REG. GUIDES [NRR) 03/88 05/88 DEVELOP DIESEL GENERATOR RELIABILITY PROGRAM 10/86 04/88 GUIDELINES AS OF FY93 QUARTER 3 O
O O.
RUN DATE. 07/27/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
55 ISSUE NUMBER:
8-56 TITLE: DIESEL GENERATOR RELIABILITY ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE CRGR PACKAGE TO RES DIRECTOR 01/87 07/88 PACKAGE TO CRGR/ACRS (531 03/87 08/88 CRGR REVIEW COMPLETE 05/87 09/88 ACRS REVIEW COMPLETE; ISSUE FOR PUBLIC 06/87 11/88 COMMENTS PUBLISH NUREG/CR-5078. VOL 2 11/88 01/89 RECEIVE PUBLIC COMMENTS 08/87 03/89 FTR TO RCS DIRECTOR; FTR TO CRGR/ACRS 09/87 08/89 RECEIVE NUMARC APPENDIX D SUBMITTAL 04/90 05/90 REVISE CRGR PACKAGE NRR & OGC CONCURRENCES 06/90 06/90 CRGR/ACRS MEETINGS lACRS MEETING HELD IN 07/90 07/90 AUGUST OF 1990)
COMMISSION PAPER TO EDO 10/90 10/90 RECEIVE B-56 SRM 07/91 06/91 REVISE 580 RULE; R.G.
1.9 REV. 3; PREPARE 07/91 11/91 DRAFT FRN PACKAGE TO ACRS 10/91 11/91 PACKAGE TO CRGR 08/91 11/91 CRGR AND ACRS MEETINGS 09/91 11/91 ISSUE LETTER TO NUMARC ON ACCELERATED 10/91 11/91 TESTING SUBMIT DRAFT PACKAGE TO EDO 10/91 01/92 AS OF FY93 QUARTER 3 t
RUN DATE: 07/21/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
56 ISSUE NUMBER:
B-56 TITLE. DIESEL GENERATOR RELIABILITY ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE PkhKkhk hh hh khhhhN fhhhhhhhhh hk/hh bh/h,h COMMISSION RESPONSE 12/91 03/92 ISSUE PACKAGE FOR COMMENT 12/91 04/92 END 75-DAY PUBLIC COMMENT PERIOD 02/92 01/92 REVISE PACKAGE AND SUBMIT TO RES DIRECTOR 03/92 11/92 FORWARD B-56 PACKAGE TO ACRS 11/92 11/92 ACRS REVIEW 12/92 12/92 CRGR REVIEW 12/92 01/93 FORWARD RECOMMENDATION TO EDO 01/93 01/93 COMMIS$10N REVIEW C2/93 03/93 ISSUE MAINTENANCE RULE REO. QUIDE (WITH EDO 06/93 06/93 GUIDANCEI CLOSE00T MEMO TO EDO 06/93 06/93 WITHDRAW S00 RULE AMENDMENT 08/93 08/93 AS OF FY93 QUARTER 3 O
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RUN DATE: 07/2F/93 OENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
58 ISSUE NUMBER:
B-61 TITLE ; ALLOWABLE ECCS EQUIPMENT OUTAGE PERIODS AFFECTED DOCUMENTS PROBLEM / RESOLUTION IN TECHNICAL SPECIFICATIONS IS NEEDED, THIS ISSUE WILL BE CLOSED OUT.
THE SCHEDULE GIVE N BE LOW ASSfp4E S THAT A CHANGt IN TECHNICAL SPECIF ICAT IONS IMPLE ME N T ING SOME FORM OF CUMULATIVE OUTAGE REQUIREMFNT WILL BE REQUIRED.
CURRENTLY. THERE IS NO TECHNICAL ASSISTANCE CONTRACT ON THIS ISSUE, NOR IS ONE CURRENTLY PLANNED, ALL WORK IS BE ING PE RFORMED IN-HOUSE.
THE ORIGINAL SCHEDULE FOR AN INITIAL RECOMME NDATION F OR STAFF COMMENTS HAS BEEN DELAYED BY OTHER WORK ALSO, THE COST-BENEFIT ANALYSIS IS TAKING MORE TIME THEN ORIGINALLY ANTICIPATED.
THE DRAFT TECHNICAL RESOLUTION HAS DEEN SUOMITTED FOR MANAGEMENT REVIEW.
NO TECHNICAL SPECIFICATION CHANGES ARE R E COP 94E NDE D. BUT REVISED INSPECTION GUIDANCE ON VOLUNTARY ENTRY INTO LCO*S IS RECOMMENDED.
NO WORK WAS PERFORMED ON THIS ISSUE DURING F Y '93 QUARTER 2 OR 3 BECAUSE OF HIGHER PRIORITY WORK.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE DRAFT TAP ISSUED FOR DD APPROVAL 01/84 01/84 COMPLETE COORDINATION OF TECHNICAL RESOLUTION 04/84 08/84 WITH RES TAP APPROVED BY DIVISION DIRECTOR 05/84 07/84 TASK I-METHODOLOGY REVIEW AND
!!/84 04/85 DEVELOPMENT COMPLETED TASK II-APPLY TO A PWR OR BWR 02/85 02/92 DEVELOP AN INITIAL RECOMMENDATION FOR STAFF 08/87 09/92 COMMENTS APPLY METHODOLOGY TO A SELECTION OF PLANTS 08/85 09/92 AS OF FY93 QUARTER 3 O
O O.
RUN DATE: 07/21/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
59 ISSUE NUMBER:
B-61 TITLE: ALLOWABLE ECCS EQUIPMENT OUTAGE PERIDOS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE PREPARE DTR 04/86 07/93 PREPARE CRGR PACMAGE 06/86 08/93 REVIEW OF CRGR PACKAGE BY DIVISION 07/86 09/93 DIRECTORS RES DIRECTOR REVIEW COMPLETE /
08/88 10/93 PACKAGE TO CRGR CRGR REVIEW AND EDO APPROVAL COMPLETED 09/86 11/93 ISSUANCE OF FRN FOR PUBLIC COMMENT 11/86 12/93 SIXTY-DAY COMMENT PERIOD ENDS 01/87 02/94 DIVISION REVIEW OF PUBLIC COMMENTS 02/87 04/94 COMPLETED, AND FINAL CRGR PACKAGE COMPLETED RES REVIEW OF CRGR PACKAGE COMPLETED 04/87 06/94 (DIVISION REVIEW AND RES DIRECTOR REVIEW)
ACRS REVIEW 09/93 07/94 CRGR REVIEW AND EDO APPROVAL COMPLETED 05/87 08/94 CLOSE DUT ISSUE 09/93 09/94 AS OF FY93 QUARTFR 3 i
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RUN DATE: 07/27/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
61 ISSUE NUMBER:
B-64 TITLE: DECOMMISS ING OF REACTORS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE EDO APPROVAL OF DECOMMISSIONING - SECY -
09/84 09/84 34-354 COMMISION APPROVAL OF SECY-84-354 I2/84 12/84 ISSUANCE OF DRAFT RULE CHANGE FOR 02/85 02/85 PUBLIC C0t94ENT FORMAT AND CONTENT FOR DECOMMISSIONING 02/84 06/85 EXTENDED PUBLIC COMMENT PERIOD ON RULE 07/85 07/85 COMPLETE ISSUE TRANSFER MEMO TO RES (SRP) 0I/86 0I/86 REVISE DRAFT RULE INCORPORATING PUBLIC 02/86 II/86 COMMENTS PREPARE FOR RES MANAGEMENT REVIEW REVISE DRAFT RULES /PUBLIC COMMENTS 08/86 08/87 REVIEWED AND APPROVED BY CROR (53l FTR TO EDO FOR TRANSMITTAL TO COMMISSION 10/86 12/81 FRN OF FINAL RULE 01/87 06/88 SRP TO DIVISION FOR REVIEW 06/89 SRP TO OFFICES FOR CONCURRENCES 02/90 SRP TO CROR 03/90 ISSUE SRP CHANGE 04/90 AS OF FY93 QUARTER 3
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RUN DATE: 07/2T/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
62 ISSUE NUMBER: HF 4.4 TITLE: GUIDELINES FOR UPGRADING OTHER PROCEDURES IDENTIFICATION DATE: 08/83C PRIORITIZATION DATE: 10/84C TYPE: GSI PRIORITY: H TASK MANAGER: J. WACHTEL OFFICE / DIVISION / BRANCH: RES /DSR /HFB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE. 07/93 WORK AUTHORIZATION: MEMO FOR H THOMPSON FROM H. DENTON DATED 10/1/84,
" HUMAN FACTORS PROGRAM PLAN
- FIN CONTRACTOR CONTRACT TITLE b236b Phl bkVktbP bbhbkhbh khb RhbbLkhbRY kbkhbh FbR BPS k kbPh B2935 PNL VALVE IMPACT ASSESSMENT OF PLANT OPERATING PROCEDURES U2968 PNL DEVELOP GUIDANCE & REGULATORY ACTION FOR OPS & AOPS I2005 PNL DEVELOP GUIDANCE & REGULATORY ACTION FOR OPS & AOPS L1827 PNL GUIDANCE FOR REVIEW OF PROGRAMS TO UPGRADE PROCEDURE AT NUCLEAR POWER PLANTS WDRK SC0PE RECOMMEND IMPROVEMENTS IN NUCLEAR POWER PLANT NECESSARY FOR E ACH TYPE OF PROCEDURE BASED ON OPERATING PROCEDURES AND DEVELOP AN IMPLEMENTATION A CONTRACTOR INTERIM REPORT AND INDUSTRY PLAN FOR UPGRADING OPERATING PROCEDURES. NRC INPUTS WITH RESPECT TO COST AND BENEF ITS WILL E*ETERMINE THE AMOUNT OF UPGRADE EFFORT STAiUS THIS ISSUE WAS TRANSFERRED FROM NRR TO RES WITH THE MANAGER WAS ASSIGNED, AND THE SCHEDULE, BUDGET, AND SCOPE 4/I2/87 NRC REORGANIZATIJN (4/10/87 MEMO FROM W.
RUSSELL WERE REVISED IN JULY 1988.
NUREG/CR-5458 WAS PUBLISHED IN TO T.
SPEIS).
CONTRACTOR EFFORTS ON FIN 82360/PNL AND DECEMGER 1989.
AGRE EME NT RE ACHED WITH NRR TO DEVELOP A FIN B2966/PNL WERE COMOLETED AT THAT TIME. NUREG/CR'S-PROCEDURES UPGRADE " GOOD PRACTICES" GUIDE.
WORK TO BE 3968 AND -4613 WERE PUBLISHED IN FEBRUARY 1987 AS A INITIATED FEBRUARY 1991.
STATEMLNT OF WORK FOR " GOOD RESULT OF WORK UNDER THESE FINS.
REVIEW OF NUREG/
PRACTICES" PROJECT ISSUED MAY 1991 EFFORT EXPANDED BEYOND CR'S-3968 AND -4613 PRIOR TO THE NRC REORGANIZATION NORMAL AND ABNORMAL PROCEDURES PER NRR. TO INCLUDE PRO-INDICATED THE NEED FOR A REGULATORY ANALYSIS OF THIS ISSUE.
CEDURES DURING ADNPOWER OPERATIONS. AT A MEETING WITH NRR AWARDED AN ADDITIONAL CONTRACT TO PNL IN JUNE 1987 TO J.
SNIEZEK IN NOVEMBER 1991 THE FOCUS OF THIS PROJECT WAS CONDUCT THAT ANALYSIS UNDER FIN I.2005.
RESPONSIBILITY FOR CHANGED TO EMPHASIZE NONPOWER OPERATIONS AND MINIMIZE THE THAT CONTRACT WAS TRANSFERRED TO RES BY NOVEMBER 16 1987 ATTENTION PAID TO NORMAL AND ABNORMAL PROCEDURES MEMORANDUM FROM L. RUTH TO M. MALTMAN. A NEW RES TASK AS OF FY93 QUARTER 3
4 4
L I
RUN DATE; 07/27/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
63 ISSUE NUMBER: HF 4.4 TITLE: GUIDELINES FOR UFORADING OTHER PROCEDURES AFFECTED DOCUMENTS PROBLEM / RESOLUTION LITERATURE REVIEW DOCUMENTING PROCEDURES PRACTICES AT ALTHOUGH FINAL NUREG/CR WAS PUBLISHED IN DECEMBER 1989 NUCLEAR POWER PLANTS.
REQUESTS FRO *4 OTHER OFFICES RESULTED IN MAINTAINING THIS ISSUE OPEN PENDING A RESOLUTION OF WHETHER ' ADDIi. 'JAL EFF OR T IS NECESSARY UNDER THIS ISSUE. AS A RESULT OF NOVEMBER 1991 MEETING WITH J.
SNIEZEK, THE CONTRACI WAS RT. VISED TO ADDRESS ONLY THOSE PROCEDURES RELATED TO SHUTDOWN AND LOW POWER OPERATIONS. A RECENT NRR USER NEED LETTER (3/8/93 ME MO F ROM T. MURLEY) HAS WITHDRAWN THE NEED FOR ANY OF THE REMAINING WORK AND ACCORDINGLY THIS ISSUE WILL BE CLOSED OUT BASED UPON THE WORK DONE TO DATE.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE PUBLISH FINAL REPORT ON OPERATING I2/85 02/87 PROCEDURES PROJECT AS NUREG/CR PUBLISH FINAL REPORT ON PROCEDURES 05/86 02/87 INTERFACE PROJECT AS NURE0/CR CONDUCT REGULATORY ANALYSIS FOR OPERATING 02/87 07/89 PROCEDURES. ABNORMAL OPERATING PROCEDURES DEVELOP PLAN FOR REGULATORY GUIDANCE 06/89 09/89 PREPARE CLOSEOUT MEMO 04/93 04/93 CLOSE OUT ISSUE 08/89 01/93 CLOSE OUT CONTRACT GY DOCUMENTING LITERATURE 08/92 09/93 SEARCH ON PROCEDURES FOR LOW POWER AND SHUTDOWN OPERATIONS AT NUCLEAR POWER PLANTS i
AS OF FY93 QUARTER 3 L
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RUN DATE: 07/27/93 CENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
65 ISSUE NUMBER: HF S.I TITLE: LOCAL CONTROL STATIONS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE bEbhk5kLbE/k[Pkbh Shbbh bF Lbbk bbkhRbL b2/h8 b5/h,h STATIONS COMPLETE PRELIMINARY VALUE/ IMPACT STUDY 07/88 02/89 NRC COMPLETE REVIEW OF S10DY RESULTS 09/88 02/89 COMPLETE PLANT-SPECIFIC VALUE-IMPACT STUDY 09/90 04/S1 FOR ERPANDED LCS DEFINITION PREPARE CLOSE OUT MEMO 05/93 05/93 CLOSE OUT MEMO TO EDO 12/92 06/93 CONTRACTOR TO PREPARE FINAL REPORT ON 12/92 09/93 0000 PRACTICES FOR DESIGN OF LOCAL CONTROL STATIONS AS OF FY93 QUARTER 3
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G RUN DATE: 07/27/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
61 ISSUE NUMBER: HF 5.2 TITLE: REV. CRIT. FOR HUMAN FACTORS ASPECTS OF ADV CONTROLS AND INSTRUMENT.
AFFECTED DDCUMENTS PROBLEM / RESOLUTION NEW TASK MANAGER ASSIGNED FEBRUAR 1990 DUE TO REVISED NEEDS FROM NRR AS A RESULT OF DCRDR C0btilTHENTS, THE UTILITY OF THE PRESENT COURSE WAS REASSE SSED.
WORK STOPPED OCTOBER 1, 1990 DUE TO BUDGET CONSTRAINTS. WORK RESUMED JANUARY 1991 But HAS EXPERIENCED DELA.YS DUE TO GAINING SITE ACCESS FOR DATA COLLECTION. BASED UPON WORK TO DATE. ISSUE CAN BE CLOSED OUT.
SINCE FOCUS OF ISSUE HAS CHANGED, THIS ISSUE IS BEING ADDRESSED IN THE DEVELOPMENT OF GUIDELINES FOR THE REVIEW Or ADVANCED CONTROL ROOMS.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE BEGIN VALUE/ IMPACT STUDY OF ANNUNCIATORS 02/88 04/88 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 OUT HEMO TO EDO 06/93 06/93 COMPLETE ALARM REDUCTION STUDY 11/89 10/93 AS OF FY93 QUARTER 3 l
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RUN DATE: 07/27/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
69 l
ISSUE NUMBER:
1.D.3 TITLE: SAFETY SYSTEM STATUS MONITORING ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE bhbbhhEbKbkhbhbbF kHkIhhbkkhb hh/hh hh/h,h EVALUATE THE NEED FOR REVISION TO EXISTING GUIDANCE PROVIDED IN R.G. 1.47 PREPARE TASK ACTION PLAN 06/92 06/92 TAP. APPROVED BY DSIR DIRECTOR 07/92 08/92 LETTER REPORT TO REDEFINE ISSUE IN LIGHT OF 01/93 01/93 CURRENT STATUS OF SSSM PRELIMINARY VALUE IMPACT 05/93 03/93 NRR REVIEW OF RESOLUTION PACKAGE 03/94 07/93 TR PACKAGE TO DIR/DSIR 05/93 07/93 PACKAGE TO ACRS 05/94 07/93 ACRS REVIEW COMPLETE 07/94 08/93 ISSUE CLOSE OUT MEMO I2/94 12/94 I
f AS OF FY93 QUARTER 3 s
f
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RUN DATE 07/27/93 GENERIC ISSUE MANAGEMFNT CONTROL SYSTEM PAGE.
70 ISSUE NUMBER:
I.D.513)
TITLE: ON-LINE REACTOR SURVEILLANCE SYSTEMS IDENTIF ICATION DATE : OS/80C PRIORITIZATION DATE: II/83C TYPE: GSI PRIORITY:
TASK MANAGER: M.
VAGINS OFFICE / DIVISION / BRANCH: RES /DE /EMEB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS: NONE RESOLUTION DATE: 07/93 WORK AUTHORIZATION: TMI ACTION PLAN, NUREG-0660 FIN CONTRACTOR CONTRACT TITLE h0B28 bkhb bbkhkhbbbhbh$khbkkkbhbkhbkkkhhhhhhEhktbkhkbbk l
W0RK SC0PE hhkbbhkbhkVkbkhhkhkkPbkhhhkbPkkkbRhkkkkkhbh bh kkhk kbkhk kbkVkkkkkhbh khhhhh kb hb hkR[bRh TO DCTERMINE THE FEASIBILITY OF DETECTING AND DIAGNOSING DEMONSTRATIONS OF SUCH A SYSTEM IN AN NRC-LICENSED NUCLEAR POWER PLANT OPERATING ANOMALIES USING A CONTINUOUS COMMERCIAL BWR PLANT.
STATUS kbkhbbkhkkkkbhbkhhkkkhkkkkkhktkkhkhkk
~~khkbh5khkbbkVkklLEkbhhkkkbhkhkkhhkhhhkhkhk'5kQbbhkh'~
L OPERATING PWR (SEQUOYAH UNIT 2) HAS BEEN COMPLETED THE UNIT 2 PWR IN 1983/84 PLUS AVAILABLE NOISE DATA FROM SURVEILLANCE INSTRUMENT SYSTiM WAS INSTALLED AT THE PEACH MEASUREMENTS AT THE BROWNS FERRY BWR TO DEVELOP AN BOTTOM UNIT 2.
DUE TO THE LONG OUTAGE AT PEACH BOTTOM (24 ACCEPTABLE EVALUATION OF THE ON-L INE SURVE IL L ANCE SYSTEM.
l MONTHS). THE EXPERIMENT WAS TERMINATED AND THE EQUIPMENT A RIL SUMMARIZING THE RESEARCH RESULTS WAS REMOVED AND PLACED IN STORAGE AT ORNL.
PREPARED.
IT IS BELIEVED THAT SUFFICIENT DATA IS AVAILABLE FROM l
AFFECTED DOCUMENTS PROBLEM / RESOLUTION RECOMMEN0ATIONS FROM THE RESEARCH ON THIS ACTION ITEM, RES MEMO SEND TO NRR PRIOR TO CLOSE0VT ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE i
l INSTALL SYSTEM AT A PWR 09/80 l
AS OF FY93 QUARTER 3 1
9 O
O.
RUN DATE: 07/21/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
71 ISSUE NUMDER:
I.D.513)
TITLE: ON-LINE REACTOR SURVEILLANCE SYSTEMS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE COMPI.ETE PWR DATA ACQUISITION 06/84 01/8,4 INSTALL SYSTEM AT A BWR 04/84 06/85 REMOVAL OF SYSTEM FROM PEACH BOTTOM 12/88 04/89 ISSUE RIL TO NRR WITH CONCLUSIONS AND 09/88 04/93 l
RECOP94ENDATIONS l
ISSUE CLOSEOUT MEMO TO EDO 12/88 07/93 l
AS OF FY93 QUARTER 3
RUN DATE: 07/27/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
72 ISSUE NUMBER:
I.0 515)
TITLE: DISTURBANCE ANALYSIS SYSTEMS IDENTIFICATION DATE: 05/80C PRIORITIZATION DATE: II/83C TYPE: LI PRIORITY:
TASK MANAGER: L.
BELTRACCHI 0FFICE/ DIVISION / BRANCH: RES /DSR /HFB ACTION LEVEL: ACTIVE STATUS: 5 TAC NUMBERS:
RESOLUTION DATE: 09/93 WORK AUTHORIZATION: TMI ACTION PLAN, NUREG-0660 FIN CONTRACTOR CONTRACT TITLE bhkh2 bkhl hkV bRkh kbk hbkkk Fkbhbkh kPEbkh bk kbVkhbEh bbkhRbLb k khhkRbh WDRK SC0PE hhbhkkkbkhbbhhbkbkkhbhbkhbhkhkthkkhhhhkkh(bkhh bkkkkbbthkkhkhbEhkRkkkhbkhbhkhkkhkhbhhhkbbbkkbhbk DEALING WITH UPSET DIAGNOSIS AND REMEDIAL ACTION ARE THE LOGIC MODELS MUST BE OVERCOME BEFORE APPLYING A DASED ON DETAILED LOGIC MODELS THAT TRACE THE TIME-DAS TO A COMMERCIAL REACTOR ON A TOTAL PLANT BASIS.
DEPENDENT CONSEQUENCES OF COMPONENT FAILURES. THE STA~US bhhkhbkkbbhbkhkbbkbkhbEk12 khhhkkbR khkkkhP kbhkhbhb bbkhkbth khb khhhkbbkhikhkbh WktL kVktbkhk SPEIS, FROM BRIAN W.
SHERON,
SUBJECT:
RECOMMENDED DISTURBANCE ANALYSIS SYSTEMS ALONG WIiH OINER ADVANCED CONVERSION OF GENERIC ISSUES TO RESEARCH ISSUESI SPEIS TECHNOLOGIES. SUCH AS COMPUTER-BASED OPER ATOR AIDS AND AGREES WITH THE DIVISION OF REACTOR AND PLANT SYSTEMS ARTIFICIAL INTELLIGENCE.
THIS ISSUE WILL CONTINUE TO PE RECOMMENDATION THAT THIS ISSUE BE RECLASSIFIED AS A RESEARCH TRACKED AS A LICENSING ISSUE TO FOLLOW THE RESEARCH WC9K.
ISSUE.
THE REASON GIVEN FOR THE RECOMMENDATION IS THE NEED FINAL REPORT ISSUED-
" HUMAN FACTORS ISSUES FOR SPECIFIC RESEARCH TO DETERMINE IF A SAFETY PROBLEM ASSOCIATED WITH ADVANCED INSTRUMENTATION AND CONTROLS EXISTS IN THIS AREA.
A CURRENTLY FUNDED RESEARCH PROJECT, TECHNOLOGIES IN NUCLEAR PLANTS," NUREG/CR-5439.
CLOSE FIN 0852, REVIEW CRITERIA FOR HUMAN FACTORS ASPECTS OF OUT MEMO TO BE PREPARED.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION
-.-----.---------....----.----------~~----------------------
NONE NONE AS OF FY93 QUARTER 3 O
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RUN DATE: 07/27/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:
74 ISSUE NUMBER:
II.H.2 TITLE: OBTAIN DATA ON CONDITIONS INSIDE THI-2 CONTAINMENT IDENTIFICATION DATE: 05/80C PRIORITIZATION DATE: II/83C TYPE: GSI PRIORITY: H TASK MANAGER: A.
RUBIN OFFICE / DIVISION / BRANCH: RES /DSR /ACB ACTION LEVEL: ACTIVE STATUS:
TAC NUMDERS:
RESOLUTION DATE: 09/93 WORK AUTHORIZATION: TMI ACTION PLAN, NUREG-0680 FIN CONTRACTOR CONTRACT TITLE k2kb kht kkk$kbbkkkkIkkhkkkbh A6899 EGAG THI-2 LOWER HEAD COMPANION SAMPLE EXAM & ANALYSIS D20T2 MPR TEST SPECIMENS FROM DAMAGED TMI-2 REACTOR BOTTOM HEAD W0RK SC0PE hkb hkh bbbPkkkkkD wkkh bbk khb hbbbkRh bh hkhkkkbh kkbhbFbbkkhkkkkkkLk THk PRbbkkkh kkk bkhkkktLY hkkkkkb AND DATA-GATHERING PROGRAMS WITHIN THE THI-2 CONTAINMENT.
OUT WITH FUNDS FROM DOE AND OTHERS, E AR t.Y IN CY88, NRC THESE PROGRAMS CONCENTRATE ON RETRIEVING DATA WHICH INITIATED ITS OWN COOPERATIVE PROGRAM TO EXAMINE THE DAMAGED CHARACTERIZE THE PROGRESSION OF THE ACCIDENT AND THE BOTTOM HEAD.
PRESSURE VESSEL Watt SPECIMENS. INS T RUME N T RESULTING RADIOLOGICAL SOURCE TERM.
PRIOR TO CY83, NRC TUBE PENETRATIONS, GUIDE TUBE SPECIMENS, AND BOTTOM HEAD PRIMARILY PROVIDED TECHNICAL EXPERTISE AND HOT-CELL EXAMINA-ONCE MOLTEN DEBRIS SPECIMENS ARE TO BE REMOVED AND ANALYZED.
5TATUS PRIOR EFFORTS CONCENTRATED ON THI-2 CORE EXAMINATION FIFTEEN PRESSURE VESSEL WALL SAMPLES. 14 INSTRUME NT TUDE BOTH ONSITE AND OFFSITE.
PENETRATIONS, AND 2 OUIDE TUBE SPECIMENS WERE OBTAINED.
TWO CORE EXAMINATIONS INDICATE A LARGE FLOW OF MOLTEN NATIONAL LABORATORIES ARE DEING UTILIZED TO EXAMINE AND MATERIAL (MORE THAN 15 TONS) INTO THE LOWER PLENUM AFTER THE ANALYZE THE SPECIMENS.
ACCIDENT HAD BEEN IN PROGRESS FOR ABOUT 225 MINUTES. DOE IN APRIL 1991 THE MANAGEMENT BOARD OF THE JOINT OECD HAD *f0T BUDGETED FOR THE ADDITIONAL RESCARCH TO EXAMINE THE TMT VESSEL INSPECTION PRO ^9AM VOTED TO E XTEND THE PROGRAM EFFECTS OF THIS MOLTEN MATERIAL ON THE VESSEL BOTTOM AND FOR A PERIOD OF 18 MONTES BEYOND THE ORIGINAL PROGRAM-THE VESSEL COMPONENTS.
THE CHAIRMAN INDICATED THAT HE BELIEVED E XTENDED PROGR AM INCLUdib DE T AILED TESTING AND E X AMIN ATION THIS EXAMINATION TO BE VERY IMPORTANT NRC ASKED DOE TO OF ALL THE VESSEL, N0 *.N E AND GUIDE TUBE SAMPLES EXTRACTED PERFORM THE EXAMINATION BUT DOE DECLINED.
FROM TMI-2.
A SCOPIb3 ANALYSIS OF POTENTIAL REACTOR NRC INITIATED A COOPERATIVE PROGRAM JANUARY IS, 1988.
VESSEL FAILURE MODES AND MARGIN TO FAILURE WILL DE EPRI AND 10 OECD-NEA COUNTRIES PARTICIPATED.
PERFORMED.
THE SAMPLING EFFORT WAS COMPLETED ON MARCH 1, 1990.
AS OF FY93 QUARTER 3 9
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