ML20154Q924
| ML20154Q924 | |
| Person / Time | |
|---|---|
| Issue date: | 05/31/1988 |
| From: | NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | |
| Shared Package | |
| ML20154Q921 | List: |
| References | |
| REF-GTECI-086, REF-GTECI-NI NUDOCS 8806070165 | |
| Download: ML20154Q924 (225) | |
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i . ENCLOSURE !
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} i GENERIC ISSUE MANAGEMENT CONTROL SYSTEM l I
l SECOND QUARTER FY-88 UPDATE I l l
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1 0FFICE OF NUCLEAR REGULATORY RESEARCH MAY 1988 -
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TABLE OF CONTENTS (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 - 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 2nd Quarter FY-88)
(e) Table 3 -
Generic Safety Issues Resolved by Fiscal Year C) (f) Table 4 -
Generic Safety Issues Scheduled for Resolution j (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 Second Quarter of FY-88 (i) Table 6 -
Generic Issues Prioritized as of 2nd Quarter FY-88 (j) Table 7 -
Generic Issues.to be Prioritized (k) Table 8 -
Generic Issues to be Reprioritized (1) Table 9 -
Regulatory Impact Issues Scheduled for Resolution (m) Table 10 - Licensing Issues Scheduled for Resolution (n) Work Scope & Schedules for each Approved Generic Issue l
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GENERIC ISSUE MANAGEMENT CONTROL SYSTEM DESCRIPTION The Generic Issue Management Control System (GIMCS) provides appropriate infor-mation necessary to manage the resolution.of safety-related as well as non-safety related generic issues. For the purpose of this management control system, resolved is defined as the point where the staff's final resolution product is issued. For safety-related issues, this gene ally occurs when the resolution has been incorporated into one or more of the following documents:
(a) Commission Policy Statement /0rders (b) NRC Regulations <
(c) Standard Review Plan (SRP) l (d) Regulatory Guide j (e) Generic Letter 1 1
GIMCS is part of an integrated system of reports and procedures that is I designed to manage generic safety issues through the stages of prioritization !
and resolution (development of new criteria, review and approval, public I comments, and incorporation into the SRP, as appropriate). NUREG-0933 provides an evaluation for a recommended priority listing based on the potential safety
[3 significance and cost of implementation for each issue. The procedure and j
\'j criteria for adding new generic issues to the system are outlined in RES Office !
Letter No. 1 dated December 3, 1987. (Prior to the NRC reorganization of April 12, 1987, NRR Office Letter No. 40 was used for identifying new issues.) l GIMCS provides the proposed schedules for managing and controlling the resolution of the issues on the prioritized listing. These include: (1) issues that are ranked HIGH priority; (2) issues that are ranked MEDIUM-priority; (3) issues for which possible resolutions have been identified for evaluation; (4) issues for which technical resolutions are available (as documented by memorandum, analysis, NUREG, etc.); and (5) other issues designated to receive resources for resolution. Issues ranked as either "LOW" )
i or "0 ROP" are not allocated resources for resolution and, therefore, are not tracked in GIMCS.
Some prioritized generic issues may not have resources allocated for resolution; these issues are listed in GIMCS as inactive issues. Generally, these will be MEDIUM priority issues that have no safety deficiency demanding high priority attention, but have potential for safety improvements or reduction in uncertainty of analysis that may be substantial and worthwhile.
Efforts for the resolution of these issues will be planned over the next several years, but on a basis that will not interfere with work on the resolution of HIGH priority generic issues or other high priority work. Thus, some (MEDIUM priority) generic issues may be inactive until such time as resources become available to resolve them. The detailed schedule for resolving generic issues is monitored by GIMCS.
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Management and control indicators used in GIMCS are defined as follows:
- 1. Item No. - Generic Issue Number
- 2. Issue Type - Generic Safety (with priority High, Medium, or Nearly Resolved), licensing, or Regulatory Impact.
- 3. Action Level Active - T/A funds appropriated for resolution, and/or Task Manager actively pursuing resolution.
Inactive - No T/A funds appropriated for resolution, Task Manager assigned to more important work, or no Task Manager assigned.
- 4. Office /Div/Br - First-listed has lead responsibility for resolving issue; others listed have input to resolution.
- 5. Task Manager - Name of assigned individual rer.ponsible for resolution
- 7. Title - Generic Issue Title
- 8. Work Authorization - Who or what authorized work to be done on the issue.
- 9. Contract Title - Contract Title (if contract issued).
- 10. Contractor Name/flN - Contractor Name and FIN. (If contract is not yet issued, indicate whether the contract is included in the flN plan.)
- 11. Work Scope - Describes briefly the work necessary to techni-cally' resolve and complete the generic issue.
- 12. Affected Documents - Identifies documents into which the technical resolution will be incorporated.
- 13. Status - Describes current status of work,
- 14. Problem / Resolution - Identifies problem areas and describes what actions are necessary to resolve them.
- 15. Technical Resolution - Identifies detailed schedule of milestone dates that are required for completing the issue through the issuance of SRP revisions or other changes that document requirements.
Milestones - Selected significant milestones. The "original" scheduled dates remains unchanged. Changes in scheduled dates are listed under "Current."
Actual completion dates are listed under "Actual."
-v-LEGEND AIF - Atomic Industrial Forum ;
ANPRM - Advanced Notice of Proposed Rulemaking BNL - Brookhaven National Laboratory j DTP - Branch Technical Position ;
JTR - Draft Technical Resolution l EPRI - Electric Powe'r Research Institute j FRN - Federal Register Notice FTR - Final Technical Resolution GL - Generic Letter GSI - Generic Safety Issue '
H - HIGH-Priority GSI IEB - Inspection & Enforcement Bulletin INEL - Idaho Nuclear Engineering Laboratory LI - Licensing Issue M - ME010M-Priority GSI NR - Nearly-Resolved GSI ORNL - Oak Ridge National Laboratory PNL - Pacific Northwest Laboratories PRA - Probabilistic Risk Assessment RAI - Request for Additional Information R.G. - Regulatory Guide RI - Regulatory Impact 5 - Subsumed in Another (Issue No.)
S0W - Statement of Work SRP - Standard Review Plan ,
STS - Standard Technical Specification ;
T/A - Technical Assistance l TAP - Task Action Plan i TBD - To Be Determined I TI - Temporary Instruction .i TS - Technical Specification !
USI - Unresolved Safety Issue I
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TABLE 1 GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION, ISSUES RESOLVED AND ISSUES It:1EGRATED FY-83 IHROUG*l FY-88 (2ND QUARTER)
FY-83 FY-84 FY-85 ISSUE GIs New GIs GIs New GIs GIs New GIs TYPE Start + Issues - Resolved = End Start + Issues - Resolved = End Start + Issues - Resolved = End USI 16 0 2 14 14 0 2 12 12 0 0 12 HIGH 24 2 0 26 26 1 1 26 22* 41 6 57 MEDIUM 31 2 0 33 33 4 3 34 28* 1 10 19 NR 20 3 4 19 19 5 9 15 15 11 7 19 TOTAL: 91 7 6 92 92 10 15 87 77 53 23 107 1
i FY-86 FY-87 ISSUE Gls New GIs ISSUE GIs New GIs GIs TYPE Start + Issues - Resolved = End TYPE Start + Issues - Resolved - Integrated = End USI 12 0 1 11 USI 11 0 2 0 9 HIGH 57 (16)* 3 38 HIGH- 38 4, 3 7 32 MEDIUM 19 7 2 24 MEDIUM 24 1 4 5 16 NR 19 (3)* 3 13 NR 13 0 1 1 11 TOTAL: 107 (12)* 9 86 TOTAL: 86 5 10 13 68
- Extensive revisions to Human factors issues resulted in priority changes.
- T1-1 As of 2nd Quarter FY-88 i
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TABLE I (Continued)
GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION, ISSUES RESOLVED AND ISSUES INTEGRATED FY-83 THROUGH IY-88 FY-88 ISSUE GIs New GIs GIs TYPE Start + Issues - Resolved - Integrated = End USI 9 0 0 0 9 HIGH 32 1 2 3 28 MEDIUM 16 1 1 3 13 NR 11 0 1 0 10 l TOTAL: 68 2 4 6 60 i
I T1-2 As of 2rni Quarter FY-88 O - -
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Table 1A
SUMMARY
OF GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION, j ISSUES RESOLVED, AND ISSUES INTEGRATED 1 Cumulative Totals j FY-83 Through FY-88 (2nd Quarter) i j
TYPE Start + Issues Sub-Total Resolved Integrated = Remainder USI 16 0 16 7 0 9 HIGH 24 29* 53 15 10 28 MEDIUM 31 ~ 10 41 20 8 13 NR 20 16* 36 25 1 10 TOTAL: 91 55 146 67 19 60 4
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- Extensive revisions to Human Factors issues resulted in priority changes 1
- GIs Integrated i
! 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.Il 1 h into Issue 124 I Issues I.B.1.1(6) and I.B.1.1(7) into Issue 75 1 Issue B-6 into Issue 119.1 Issue 67.7 into 135 l 1st Qtr FY-88: Issue 77 into A-17 i TotaT--(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 1
Research Activities Program and were reclassified as Licensing Issues.
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T1-3 As of 2nd Quarter. FY-88
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NUMBER OF GENERIC SAFETY ISSUES RESOLVED j AND SCHEDULED FOR RESOLUTION -
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RESOLVED SCHEDULED FOR RESOLUTION j ISSUE Cumulative PRIORITY FY-83 FY-84 FY-85 FY-86 FY-87 FY-88 FY-88 FY-89 FY-90 FY TBD Total -
USI 2 2 0 1 2 0 5 3 1 0 0 16
- i HIGH 0 1 6 3 3 2 8 9 6 3 2 43 MEDIUM 0 3 10 2 4 1 3 4 3 1 2- 33 i
NR 4 9 7 3 1 1 2 4 2 0 2' 35 i ' Total: 6 15 23 9 10 4 18 20 12 4 6 127 i'
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l T2-1 As of 2nd Quarter FY ! ,
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TABLE 3 GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR
^ A Issue Resolution Date Approved Date Number Title Priority Product for Resolution- Resolved FY-83 ,
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Reactor Vessel Materials USI GL 82-26 01/79 10/82 Toughness A-16 Steam Effects on BWR Core Spray NR MPA D-12 NRR-0P FY83 03/29/83 Distribution
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] 5 A-39 Jetermination of Safety ' USI SRP Revision 01/79 10/82 Relief Valve (SRV) Pool _
Dynamic Loads and Temperature '
- . N Li.mits for BWR Cbntainment x _
B-53 Load Break Switch NR - SRP Revision " NRR-0P FY83 07/28/83 II.E.5.1 (B&W) Design Evaluation NR 7
No Req. NRR-0P 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 l
FY-84 12 BWR Jet' Pueo Integrity Medium No Req. NRR-0P FY83 09/25/84 20 Effects of Electromagnetic NR NUREG/ NRR-0P FY83 11/15/83
- Pulse on Nuclear Plant Systems CR-3069 5
40 Safety Concerns Associated NR MPA B 07/18/83 12/27/83 With Breaks in the BWR Scram System ;
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45 Inoperability of Instruments NR SRP Revision 09/08/83 03/23/84 Due to Extreme Cold Weather ,_,
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- _ 13-1 As of 2nd Quarter Ff.r33
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Table 3 (Continued)
GENERIC SAFETY ISSUES RESOLV20 BY FISCAL YEAR Issue Resolution Date Approved Date Nueber Title Priority Product for Resolution Resolved FY-84 (cont'd) 50 Reactor Vessel Level NR MPA-F26 07/28/83 09/06/84 Instrumentation in BWRs 69 Make-Up Nozzle Cracking in NR "PA- 12/06/83 09/27/84 B&W Plants A-1 Water Hammer USI SRP Revision 01/79 03/IS/84 A-12 Steam Ge:wrator and Reactor USI SRP Revision 01/79 10/83 Coolant Pump Supports B-10 Behavior of BWR Mark III High SRP Revision NRR-OP FY83 09/10/84 Containments B-26 Structural Integrity of Medium No Req. NRR-0P FY83 09/27/84 Containment Penetrations B-60 Loose Parts Monitoring NR GL NRR-0P FY83 09/25/84 Systems (LPMS)
I.A.1.4 Long-Term Upgrading of NR New Rule NRR-OP FY83 01/01/84 Operating Personnel II.A.1 Siting Policy Reformulation Medium No Req. NRR-OP FY83 09/20/84 II.E.S.2 (B&W) Reactor Transient NR NUREG-0667 NRR-0P FY83 09/28/84 Response Task Force III.D.2.5 Offsite Dose Calculation Manual NR NtlREG/ NRR-0P FY83 01/17/84 CR-3332 T3-2 As of 2nd Quarter FY-88 O
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Table 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Prodrict 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 5tabiiity NR GL 01/03/85 05/21/85 B-54 Ice Condenser Containments Medium NUREG/ NRR-0P FY83 10/22/84 CR-4001
) B-58 Passive Mechanical failures Medium No Req. NRR-0P FY83 07/09/85 i
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C-11 Assessment of Failure and Medium No Req. NRR-OP FY83 07/09/85 l Reliability of Pumps and j Valves I
, I.A.2.2 Training and Qualifications High Policy NRR-0P FY83 06/24/85 i of Operating Personnel Statement
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j I.A.2.6(4) Operator Workshops Medium No Reg. NRR-OP FY83 09/25/85
! I.A.2.7 Accreditation of Training Medium Policy NRR-OP FY83 06/24/85 i Institutions Statement i No Reg.
i I.A.3.4 Licensing of Additional Medium Policy NRR-OP FY83 02/12/85 Operations Personnel Statement j No Req.
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GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-85 (cont'd)
II.B.6 Risk Reduction for Operating High No Req. NRR-OP FY83 09/25/85 Reactors at Sites With High Population Densities II.B.8 Rulemaking Proceedings on High - - -
Degraded Core Accidents (a) Hydrogen Rule Rule NRR-OP FY83 07/19/85 (b) Severe Accidents Policy NRR-OP FY83 08/12/85 Statement II.C.1 Interim Reliability Evaluation riigh No Req. NRR-0P FY83 07/09/85 Program II.C.2 Continuation of Interim High No Req. NRR-0P FY83 09/25/85 Reliability Evaluation Program II.E.2.2 Research on Small Break LOCAs Medium No Req. NRR-0P FY83 07/25/85 and Anomalous Transients III.A.I.3(2) Maintain Supplies of Thyroid- NR Policy NRR-OP FY83 08/15/85 Blocking Agent For Public Statement III.A.3.4 Nuclear Data Link Medium No Req. NRR-0P FY83 06/26/85 III.D.2.3(1) Develop Procedures to Dis- NR ESRP NRR-OP FY83 08/23/85 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 T3-4 As of 2nd Quarter FY-88 O O O
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GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-85 (cont'd)
III.D.2.3(4) Prepare a Summary Assessment NR ESRP NRR-0P FY83 08/28/85 Revision 1
] IV.E.5 Assess Currently Operating liigh No Req. NRR-0P FY83 09/25/85 Plants ,
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3 Setpoint Drift in NR Reg Guide NRR-DP FY83 05/19/86
- Instrumentation Rev. No Req.
I i 14 PWR Pipe Cracks NR .lo Req. NRR-0P FY83 10/04/85 36 Loss of Service Water NR SRP Revision 02/15/84 05/13/86 j No Req.
j 61 SRV Discharge Line Break Medium No Reg. 11/30/83 08/08/86 t
Inside the Wetwell Airspace i of BWR Mark I and Mark II j Containments
! A-43 Containment Emergency USI SRP 01/79 10/85 i
Sump Performance Revision t
! I.C.9 Long-Term Plan for Upgrading Medium No Req. NRR-0P FY83 06/07/85 4 of Procedures i
III.D.3.1 Radiation Protection Plans liigh No Req. NRR-0P FY83 05/19/86 j HF1.2 Engineering Expertise on fligh No Req. 10/01/84 10/28/85 4
Shift
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HF1.3 Guidance on Limits and fligh No Req. 10/01/84 06/26/86 l
Conditions of Shift Work
- T3-5 As of 2nd Quarter FY-88 l
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l l Table 3 (Continued) l GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR l Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-87 l 91 Main Crankshaft failures in NR NUREG-1216 07/85 09/87 l Transamerica Delaval Diesel (No Reg.)
Generators A-46 Seismic Qualification of U S '. GL87-02 02/81 02/87 Equipment in Operating Plants (Req.)
l A-49 Pressurized Thermal Shock USI Rule / Reg. 12/81 02/87
) Guide 1_154 (Req.)
l 1.A.2.6(1) long-Term Upgrading of High Reg. Guide 10/82 05/87 Training and Qualifications - 1.8 (Req.)
Revise Reg. Guide 1.8 I.A.3.3 Requirement for Operator High No Req. 12/82 01/87 Fitness I.A.4.2(1) Research on Training High Reg. Guide 10/84 05/87 Simulators 1.149, Rev.1 (Req.)
I . B .1.1 Organization and Management - - - -
Long-Term Improvements I.B.1.1(1) Prepare Draft Criteria Medium No Reg. 12/82 01/87 I.B.I.1(2) Prepare Comission Paper Medium No Req. 12/82 01/87 I.B.1.1(3) Issue Requirements for the Medium No Req. 12/82 01/87 Upgrading of Management and Technical Resources T3-6 As of 2nd Quarter FY-88 O O O
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GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR l Issue Resolution Date Approved Date Number Title Priority Product Jor Resolution Resolved i
I.B.I.1(4) Review Responses to Determine Medium No Reg. 12/82 01/87 i Acceptability fl.,$$
l 86 Long Range Plan for Dealing NR NUREG-0313, 10/84 01/88
- with Stress Corrosion Cracking Rev. 2, l in BWR Piping GL 88-01 l (Req.)
93 Steam Binding of Auxiliary High GL 88-03 10/84 02/88 feedwater Pumps (No Req.)
i I.D.4 Control Room Design Standard Medium No Req. NRR-0P FY83 03/88 i 1
j II.E.4.3 (Containment) Integrity Check High- NUREG-1273 NRR-0P FY83 03/88 i (No Req.)
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j T3-7 As of 2nd Quarter FY-88 l
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TABLE 4 l
60 GSIs SCHEDULED FOR RESOLUTION (BY FISCAL YEAR) i PRIORITY FY-88 FY-89 FY-90 FY-91 T80 TOTAL USI A-3 A-17 A-45 - ~-
9 A-4 A-40 -
A-5 A-47 A-44 A-48 1
HIGH 99 43 23 87 121 28 105 94 29 113 I . F.1 122.2 115 101 HFS.2 I.A.4.2(4) 125.II.7 128 II.C.4 130 II.H.2 i HF1.1 134 HFS.1
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A-29 82 B-61 B-17 8-5 B-55 II.E.6.1 I. D. 3 j NR 66 103 75 -
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- 124 B-64 83 102
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t l TOTAt: 18 20 12 4 6 60 T4-1 As of 2nd Quarter FY-88 i
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Table 4A GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION Date Resolution Current Issue Lead Office / Approved for Date at end Resolution Number Title Division / Branch Priority Resolution of FY-87 Date A-3,4,5 Steam Generator Tube Integrity NRR/ DEST /EMTB USI 01/79 12/87 06/88 A-17 Systems Interaction RES/DE/EIB USI 0I/79 04/89 09/89 A-40 Seismic Design Criteria RES/DE/EIB USI 01/79 04/89 06/89 A-44 Station Blackout RES/DRPS/RPSI USI 01/79 03/88 05/88 A-45 Shutdown Decay Heat Removal RES/DRPS/RPSI USI 02/81 12/89 04/90 Requirements A-47 Safety Implications of Control RES/DE/EIB USI 02/81 04/89 04/89 Systems A-48 Hydrogen Control Measures and RES/DRAA/SAIB USI 02/81 01/88 06/88 Effects of Hydrogen Burns on Safety Equipment 23 Reactor Coolant Pump Seal RES/DE/EIB H NRR-0P FY83 04/90 04/90 Failures 29 Bolting Degradation or Failures RES/DE/EIB H NRR-OP FY83 10/89 03/90 in Nuclear Power Plants 43 R'e liability of Air Systems RES/DRPS/RPSI H 12/87 NONE 04/89 87 Failure of HPCI Steam Line RES/DRPS/RPSI H 09/26/85 12/90 12/90 Without Isolation T4-2 As of 2nd Quarter FY-88 O O O
O O O Table 4A (Continued)
GENERIC SAFETY ISSUES SCilEDULED FOR RESOLUTION Date Resolution Current Issue Lead Office / Approved for Date at end Resolution Number Title Division / Branch Priority Resolution of FY-87 Date 94 Additional Low-Temperature RES/DRPS/RPSI H 07/23/85 12/88 12/88 Overpressure Protection For Light Water Reactors 99 RCS/RHR Suction Line Interlocks RES/DRPS/RPSI H 08/13/85 04/88 08/88 on PWRs 101 BWR Water Level Redundancy RES/DE/EIB H 05/06/85 03/90 03/90 105 Interfacing Systems LOCA at BWRs RES/DE/EIB H 06/11/85 12/88 08/88 113 Dynamic Qualification Testing of RES/DE/EIB H 07/02/87 09/91 09/91 Large Bore Hydraulic Snubbers 115 Enhancement of the Reliability RES/DRPS/RPSI H 07/07/86 05/89 05/89 of Westinghouse Solid State Protection System 121 Hydrogen Control for large, RES/DRA/RDB H 09/20/85 02/88 06/88 Dry PWR Containments 122.2 Initiating Feed-and-Bleed N'RR/ DEST /SRXB H 01/86 12/87 06/88 125.II.7 Reevaluate Provision to Auto- RES/DRPS/RPSI H 09/10/86 08/89 08/89 matica11y Isolate Feedwater from Steam Generator During a Line Break 14-3 As of 2nd Quarter FY-88
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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 Numbe.- Title Division / Branch Priority Resolution of FY-87 Date 128 Electrical Power Reliability RES/DE/EIB H 11/28/86 12/89 12/89 130 Essential Service Water Pump RES/DRPS/RPSI H 03/10/87 06/89 06/89 Failures at Multiplant Sites 134 Rule on Degree and Experience RES/DRA/RDB H 01/23/86 09/89 08/89 Requirements for Senior Operators B-56 Diesel Reliability RE5/UNPS/RPSI H NRR-0P FY83 12/88 04/89 C-8 Main Steam Line Isolation Valve RES/DRPS/RPSI H NRR-OP FY83 02/89 04/89 Leakage Control Systems I.A.4.2 Review Simulators for Confor- NRR/DLPQ/LOLB H NRR-OP FY83 10/87 06/88 (4) mance I.F.1 Expand QA List RES/DRA/ARGIB H NRR-0P FY83 12/86 TBD II.C.4 Reliability Engineering RES/DRPS/RHFB H NRR-OP FY83 06/88 09/88 II.H.2 Obtain Technical Data on the R'ES/0RAA/AEB H NRR-0P FY83 03/91 12/89 Conditions Inside the TMI-2 Containment Structure HF1.1 Shift Staffing RES/DRPS/RHFB H 10/01/84 06/88 06/88 HF4.1 Inspection Procedure for NRR/DLPQ/LHFB H 10/01/84 09/87 07/88 Upgraded Emergency Operating Procedures T4-4 As of 2nd Quarter FY-88 O O O
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Table 4A (Continued)
GENERIC SAFETY ISSUES SCHF0"Liu FOR RESOLUTION Date Resolut;on Current i Issue Lead Office / Approved for Date at end Resolution Number Title Divison/ Branch Priority Resolution of FY-87 Date HF4.4 Guidelines For Upgrading Other RES/0RPS/RilFB H 10/01/84 06/89 06/89 Procedures liFS.1 Local Control Stations RES/DRPS/RHFB H 10/01/84 12/90 09/90 HF5.2 Review Criteria for Human RES/DRPS/RHFB H 10/01/84 12/90 05/91 Factors Aspects of Advanced Controls and Instrumentation HF8 Maintenance and Surveillance NRR/DLPQ/LPEB H 03/06/85 01/88 05/88 Program 51 Proposed Requirements for RES/DE/EIB M 06/03/83 05/88 07/90 Improving Reliability of Open Cycle Service Water Systems 70 PORV and Block Valve Reliability RES/DE/EIB M 05/14/84 12/87 10/88 79 Unanalyzed Reactor Vessel RES/DE/EIB M 07/25/83 12/86 08/88 Thermal Stress During Natural C.onvection Cooldown 82 Beyond Design Bases Accidents in RES/DRPS/RPSI M 12/07/83 08/87 05/89 Spent Fuel Pools 106 Piping and Use of Highly RES/DRPS/RPSI M 11/03/87 NONE TBD ,
Combustible Gases in Vital 1 Areas 14-5 As of 2nd Quarter FY-88
Table 4A (Continued)
GENERIC SAFETY ISSUES SCHEDULEL FOR RESOLUTION Date Resolution Current Issue Lead Office / Approved for Date at end Resolution Nud,er Title Division / Branch Priority Resolution of FY-87 Date 135 Steam Generator and Steam Line RES/DE/EIB M 05/27/86 11/90 11/90 Overfill l 08/89 06/88 l A-29 Nuclear Power Plant Design for F.ES/DRPS/RPSI M NRR-OP FY83 the Reduction of Vulnerability to Industrial Sabotage B-5 Ductility of Two Way Slabs and RES/DE/EIB H NRR-9P FY83 08/88 04/88 Shells and Buckling Behavior of Steel Containments B-17 Criteria for Safety-Related RES/DRPS/RHFB M 03/22/82 06/90 TDB Operator Actions B-55 Improve Reliability of Target RES/DE/EIB 11 tiFR-OP 03/89 03/89 Rock Safety Relief Valves B-61 Allowable ECCS Equipment Outage RES/DRAA/PRAB M NRR-0P 10/88 04/90 Per.iods I.D.3 Safety System Status Monitoring RES/DE/MEB 4RR-0P FYB3 05/89 02/89 II.E.6.1 Test Adequacy Study RES/DE/ElB H NRR-OP FYB3 05/90 10/83 66 Steam Generator Requirements NRR/ DEST /EMTB NR 11/16/83 12/86 06/88 75 Generic Irplications of ATWS RES/DRA/ARGIB NR 10/19/83 01/90 01/90 Events at the Salem Nuclear Plant 14-6 As of 2nd Quarter FY-88 9 9 -
e _
- F O
- Table 4A (Continued)
GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION l
- Date Resolut;on Current Issue Approved for Lead Office / Date at end Resolution Number Title Division / Branch Priority Resolution of FY-87 Date l
83 Control Room Habitability RC.5/DRAA/SAIB NR 08/83 04/90 04/90 l 84 CE PORVs RES/DRPS/RPSI !!R 02/27/85 TBD TBD 1
i 102 Human Error in Events Involving NRR/DLPQ/LPEB NR 02/13/35 10/87 TBD j Wrong Unit or Wrong Train I
! 103 Design For Probable Maximum RES/DE/EIB NR 99/04/85 09/87 04/89
! Precipitatfor -'
l l 124 Auxiliary Feedwater System NRR/ DEST /SPLB NR 02/86 02/88 08/P8
{ Reliability j B-64 Decommissioning of Nuclear RES/DE/MEB ;<R NRR-OP FY84 01/89 04/89
! Reactors
- I,0.5(3) On-Line Reactor Surveillance RES/DE/MEB NR NRR-0P FY33 06/89 12/88 Systems i .
! II.J.4.1 Revise Deficiency Report AE00/DSP/R0AB NR NRR-0P FY83 09/P8 11/88 Requirements Total: 60 i
1 i
i l
i T4-7 As of 2nd Quarter FY-88 t -
O O TABLE 5 NUMBER OF CENERIC ISSUES PRIORITIZED IN FY-83 THROUGH THE SECOND QUARTER OF FY-88 Issue Type FY-83 FY-84 FY-85 FY-86 FY-87 FY-88 Total Issues Identified 56 19 54 45* 6 2 182 To Be Prioritized '
Issues Identified 19 2 0 1 1 1 23 To Be Reprioritized
~~
Total: 75 21 54 46 7 3 205 New Issues (Entered into GIMCS)
. High 2 1 41 6 4 1 55 Medium 2 4 1 1 1 1 10 Nearly Resolved 3 5 6 1 0 0 15 Subtctal: 7 10 48 8 5 2. 80 Resolved 4 0 1 0 0 1 6 tw 1 4 0 2 1 0 8 Drop 1 4 4 6 13 4 30 Regulatory Impact /LI 0 0 4 6 0 2 10 Subsumed 8 2 3 6 0 0 19 Total Issues 21 20 60 28 19 9 153 Prioritized Remaining Issues To Be 54 1 -6 18 -12 -6 49 Prioritized or Reprioritized
- *Extensive revisions to Human factors issues resulted in priority changes.
2
.j T5-1 As of 2nd Quarter FY-88
\ )
J '
J TABLE 6 GENERIC ISSUES PRIORITIZED AS OF SECOND QUARTER FY-88 Action Item / Identification Date Current Issue No. Title Date Prioritized Priority FY-83
- 31. Natural Circulation Cooldown 09/82 07/83 S(I.C.1)
- 32. Flow Blockage in Essential Equipment Caused 09/82 05/83 S(51) by Corbicula
- 33. Correcting Atmospheric Dump Valve Opening Upon 09/82 08/82 S(A-47)
Loss of Integrated Control System Power
- 39. Potential for Unacccptable 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 i 41. BWR Scram Discharge Volume Systems 09/82 07/83 RESOLVED
- 42. Combination Primary / Secondary System LOCA 09/82 04/83 5(18)
- 45. Inoperability of Instrumentation Due to Extreme 09/82 09/83 NR Cold Weather 1 46. loss of 125 Volt DC Bus 09/82 02/83 S(76)
- 47. Loss of Off-Site Power 09/82 04/83 RESOLVED
- 50. Reactor Vessel Level Instrumentation in BWRs 09/82 07/83 NR 3 51. Proposed Requiraments for Improving the 4 Reliability of Open Cycle Service Water Systems 09/82 06/83 MEDIUM
- 52. SSW Flow Blockage by Blue Mussels 09/82 05/83 S(51)
- 56. Abnorma' Transient Operating Guidelines as 09/82 02/63 S(A-45/I.D.1)
Applied to a Steam Generator Overfill Event i 58. Inadvertent Centainment 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 Cool- 02/83 07/83 HIGd ing Water System Failures
- 77. Flooding of Safety Equipment Compartments by 06/83 09/83 HIGH Back-Flow Through Floor Drains
- 79. Unanalyzed Reactor Vessel Thermal Stress During 06/83 07/83- MEDIUM Natural Convection Cooldown 4 D-1 Advisability of a Seismic Scram 09/82 06/83 LOW IV.E.2 Plan for Early Resolution of Safely Issues 09/82 06/83 RESOLVED T6-1 As of 2nd Quarter IY-88 1
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF SECOND QUARTER FY-88 Action Item / Identification Date Current Issue No. Title Date Prioritized Priority FY-84 34 RCS Leak 09/82 02/RA DROP
- 36. Loss of Service Water 09/82 02/84 NR
- 43. Contamination of Instrument Air Lines 09/82 11/83 DROP
- 44. Failure of Saltwater Cooling System 09/82 10/83 5(43)
- 48. LCO for Class IE Vital Instrument Buses in 09/82 10/83 NR Operating Reactors
- 49. Intericcks and LOCs for Redundant Class IE 09/82 07/84 MEDIUM Tie Breakers
- 53. Consequences of a Postulated Blow Blockage in 09/82 09/84 DROP Incident in a BWR
- 60. Lamellar Tearing of Reactor Systems Structural 10/82 11/83 S(A-12)
Supports
- 66. Steam Generator Requirements 06/83 11/83 NR
- 68. Postulated Loss of Auxiliary feedwater System 06/83 04/84 HIGH Resulting from Turbine-Driven Auxiliary Feedwater Pump Steam Supply Line Rupture.
- 69. Make up Nozzle Cracking in B&W Plants 06/83 12/83 NR
- 70. PORV and Block Valve Reliability 06/83 05/84 MEDIUM
- 75. Generic Implications of ATVS Events at the Salem 06/83 10/83 NR Nuclear Plants
- 80. Pipe Break Effects on Control Rod Drive Hydrau- 06/83 01/84 LOW lic Lines in the Drywells of BWR Mark I and II
- 82. Beyond Design Basis Accidents in Spent Fuel 08/83 12/83 MEDIUM Pools
- 90. Technical Specifications for Anticipatory Trips 02/84 08/84 LOW
- 92. Fuel Crumbling During LOCA 04/83 07/84 LOW B-65 Iodine Spiking 09/82 06/84 DROP T6-2 As of 2nd Quarter TY-88 O O O
O J~ J -
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS Of SECOND QUARTER FY-88 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(USI A-47) and Secondary Blowdown 54 Valve Operator-Related Events Occurring 09/82 06/85 5(II.E.6.1)
During 1978, 1979, and 1980
- 55. Failure of IE Safety-Related Switchgear Circuit 09/82 03/85 DROP Breakers
- 59. Technical Specification Requirements for Plant 10/82 02/85 RI Shutdown
- 67. Steam Generator Staff Actiens 06/83 03/85 MEDIUM
- 81. Potential Safety Probims Associated With Locked 11/83 10/84 DROP Doors and Barriers in Nuclear Power Plants
- 83. Control Room Habitability 11/83 06/84 NR
- 85. Reliability of Vacuum Breakers Connected 11/83 Otis 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 03/84 07/85- NR Generator Main Crankshaft failure
- 93. Steas Binding of Auxiliary Feedwater Pumps 07/84 10/84 HIGH
- 94. Additional Low-Temperature-Overpressure 08/84 07/85 HIGH Protection For Light Water Reactors
- 98. CRD Accumulator Check Valve Leakage 09/84 02/85 DROP
- 99. RCS/RHR Suction Line Interlocks on PWRs 09/84 08/85 IIIGH 101. BWR Water Level Redundancy 09/84 05/85 HIGH 102. Human Error in Events Involving Wrong Unit or 09/84 02/85 $(HF-02)
Wrong Train 103. Design For Probable Maximum Precipitation 10/84 09/85 NR 105. Interfacing System LOCA at BVRs 10/84 06/85 HIGH 108. BWR Suppression Pool Temperature Limits 12/84 02/85 RI(LOW) 119. Piping Review Committee Recommendations 07/85 09/85 RI(NR) 121. Hydrogen Control for La- Dry Containments 08/85 09/85 HIGH 16-3 As of 2nd Quarter FY-88
TA8LE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF SECOND QUARTER FY-88 Action Item / Identification Date Current Issue No. Title Date Prioritized Priority FY-85(cont'd)
B-19 Thermal-Hydraulic Stability 02/83 01/85 NR B-50 Post Operating Basis Earthquake Inspection 02/83 04/85 RI(LOW)
B-59 N-1 Loop Operation in BWRs and PL'Rs 02/83 06/85 RESOLVED HF-01 Human Factor Program Plan (HFPP with 24 08/83 10/84 HIGH subtasks)
HF-02 Maintenance and Surveillance Program Plan 04/84 03/85 HIGH (MSPP vith ten subtasks)
FY-86 T. ~ Vibration Qualification of Equipment 03/83 06/86 DROP
- 30. Potential Generator Missiles - Generator Rotor 09/82 10/85 DROP Retaining Rings
- 74. Reactor Coolant Activity Limits for Operating 06/83 05/86 GROP Reactors
- 97. PWR Reactor Cavity Uncontrolled Exposure 09/84 10/85 S(III.D.3.1) 111. Stress Corrosion Cracking of Presure Boundary 01/85 11/85 LI Ferritic Steels in Selected Environments 112. Westinghouse RPS Surveillance frequencies and 01/85 10/85 RI(R)
Out-of-Service Times 114 Seismic-Induced Relay Chatter 03/85 06/86 S(USI A-46) 115 Reliability of Westinghouse Solid State 04/85 07/86 HIGH Protection System 122.1.a Common Mode Failure of Isolation Valves in 08/85 01/86 HIGH Closed Position 122.1.b Recovery of Auxiliary Feedaater 08/85 01/86 MEDIUM 122.1.c Interruption of Auxiliary Feedwater Flow 08/85 01/86 HIGH 122.2 Initiating Feed-and-Bleed 08/85 01/86 HIGH 122.3 Physical Security System Constraints 08/85 01/86 LOW 124 Auxiliary Feedwater System Reliability 12/85 02/86 NR 125.I.2.a PORV Reliability - Test Program 11/85 06/86 S(70) 125.I.2.b PORV Reliability - Surveillance 11/85 06/86 S(70) 125.I.2.c Auto Block Valve Closure 11/85 06/86 DROP T6-4 As of 2nd Quarter FY-88 O O O
s ,.
Q TABLE 6 (Continued)
GEVERIC ISSUES PRIORITIZED AS OF SECOND QUARTER FY-88 Action Item / Identification Date Current Issue No. Title Date Prioritized Priority ,
FY-86 (cont'd) 125.I.2.d Equipment Qualification for feed-and-Bleed 11/85 06/86 S(USI A-45)
Environment 125.II.3 Review Steam / Feed Line Break Mitigation 11/85 08/86 ,
DROP Systems for Single Failure 125.11.4 OTSG Dryout and Reflood Effects 11/85 09/86 DROP
~
125.11.7 Reevaluate Provisions to Automatically 11/85 09/86 HIGH Isolate Feedwater from Steam Generator During Line Break 125.II.9 Enhance Feed-and-Bleed Capability 11/85 08/86 S(USI A-45) 125.11.14 Remote Operation of Equipment Which Must 11/85 08/86 LOW Now be Operated Locally 133 Update Policy Stateament on Nuclear Plant 07/86 07/86 LI Staff Working Hours 134 Rule on Degree and Experience Requirement 07/86 07/86 HIGH C-4 Statistical Methods for ECCS Analysis 02/83 06/86 RI(R)
C-5 Decay Heat Update 02/83 06/86 RI(R)
C-6 LOCA Heat Sources 02/83 06/86 RI(R)
FY-87 113 Dynamic Oualification Testing of Large Bore 03/85 07/87 HIGH Hydraulic Snubbers 125.I.1 .Tvailability of the STA 11/85 07/87 DROP 125.I.4 Plant-Specific Simulator 11/85 02/8/ DROP 125.I.7.b Realistic Hand-On Training 11/85 03/87 DROP 125.I.8 Procedures and Staffing for Reporting 11/85 06/87 DROP to NRC Emergency Response Center 125.II.1.a Two-Train AFW Reliability 11/85 10/86 DROP 125.II.1.b Review Existing AFW Systems for Single failure 11/85 10/86 HIGH 125.II.1.c NUREG-0737 Reliability Improvements 11/85 10/86 DROP I6-5 As of 2nd Quarter FY-88
TABLE 6 (Continued)
GENERIC ISSUES PRIORITIZED AS OF SECOND QUARTER FY-88 Action Item / Identification Date Current Issue No. Title Date Prioritized Priority FY-87 (cont'd) 125.II.1.d AFW Steam and Feedwater Rupture Control 11/85 10/86 DROP System /ICS Interactions in B&W Plants 125.II.2 Adequacy of Existing Maintenance Requirerents 11/85 06/87 DROP for Safety-Related Systems 125.II.5 Thermal-Hydraulic Effects of Loss and 11/85 06/87 DROP Restoration of feedwater on Primary System Components 125.II.6 Reexamine PRA Estimates of Core Damage Risk from Loss of All Feedwater 11/85 03/87 DROP 125.II.8 Reassess Criteria for Feed-and-Bleed Initiation 11/85 03/87 DROP 125.II.10 Hierarchy of Impromptu Operator Actions 11/85 02/87 DROP 125.II.12 Adequacy of Training Regarding PORV Operation 11/85 03/87 DROP 127 Testing and Maintenance of Manual valves in 05/86 06/87 LOW Safety-Related Systems 128 Electrical Power Reliability 05/86 11/86 HIGH 130 Essential Service Water Pump failures at Multi- 06/86 03/87 HIGH plant Sites 135 Steam Generator and Steam Line Overfill 05/86 06/87 MEDIUM FY-88
- 43 Reliability of Air Systems 04/87 12/87 HIGH
'55 Failure of Class IE Safety-Related Switchgear 09/85 02/88 DROP Circuit Breakers to Close on Demand P8 Earthquakes and Emergency Planning 01/84 10/87 RESOLVED 106 Piping and Use of Highly Combustible Gases 10/84 11/87 MEDIUM in Vital Areas 125.I 6 Valve Torque Limit and Bypass Switch Settings 11/85 12/87 DROP 125.I.7A Recover Failed Equipment 11/85 12/87 DROP 125.II.13 Operator Job Aids 11/85 03/88 DROP 126 Reliability of PWR Main Steam Safety Valves 03/86 03/88 LI 136 Storage and Use of Large Quantities of 09/86 03/68 LI Cryogenic Combustibles on Site T6-6 As of 2nd Quarter FY-88 O O .
O
O TABLE 7 O
GENERIC ISSUES TO BE PRIORITIZED AS OF SECOND QUARTER FY-88 Action Item / Identification Current Issue No. Title Date Schedule 38 Potential Recirculation System failure as a Consequence of 09/82 09/88 Injection of Containment Paint Flakes or Other Fine Debris 57 Effects of Fire Protection System Actuation on Safety-Related 09/82 05/88 Equipment 62 Reactor Systems Bolting Applications 10/82 07/88 63 Use of Equipment Not Classified as Essential to Safety in 10/82 05/89 BWR Transient Analysis 71 Failure of Resin Demineralizer Systems and Their Effects on 06/83 09/89 Nuclear Power Plant Safety 72 Control Rod Drive Guide Tube Support Pin Failures 06/83 11/88 73 Detached Thermal Sleeves 06/83 06/88 76 Instrumentation and Control Power Interactions 06/83 12/88 78 Monitoring of Fatigue Transient Limits for Reactor Coolant 06/83 08/88 System 89 5 tiff Pipe Clamps 02/84 08/88 95 Loss of Effective Volume for Containment Recirculation 08/84 10/88 Spray
% RHR Suction Valve Testing 0C/84 07/88 100 OTSG Level 09/84 05/88 104 Reduction'of Boron Dilution Requirements 10/84 11/89 107 Generic Implications of Main Transformer failures 11/84 12/88 109 Reactor Vessel Closure Failure 12/84 03/89 110 Equipment Protection Devices on Engineered Safety Features 12/84 02/89 116 Accicent.Managenent 04/85 07/89 117 Allowable Outages Times for Diverse Simultaneous Equipment Outages 05/85 03/89 118 Tendon Anchorage Failure 07/85 11/88 120 On-Line Testability of Protection Systems 08/85 10/88 123 Deficiencies in the Regulations Governing DBA and Single Failure 11/85 07/88 Criterion Suggested by the Davis-8 esse Incident of June 9, 1985 125.I.3 SPDS Availability 11/85 05/88 125.I.5 Safety Systems Tested in All Conditions Required by Design Basis 11/85 05/88 Analysis T7-1 As of 2nd Quarter FY-88
TABLE 7 (Continued)
GENERIC ISSUES TO BE PRIORITIZED AS OF SECOND QUARTER FY-88 Action Item / Identification Current Issue No. Title Date Schedule 125.II.11 Recovery of Main Feedwater as Alternative to AFW 11/85 05/88 129 Valve Interlocks to Prevent Vessel Drainage During Shutdown Cooling 05/86 06/88 131 Potential Seismic Interaction Involving the Movable In-Core 07/86 05/88 Flux Mapping System in Westinghouse Plants 132 RHR Pumps Inside Containment 07/86 05/88 137 Refueling Cavity Seal Failure 10/86 07/88 138 Deinerting Upon Discovery of RCS Leakage 10/86 07/88 139 Thinning of Carbon Steel Piping in LVRs 12/86 05/88 140 Fission Product Removal by Containment sprays or Pools 03/87 06/88 141 LBLOCA With Consequential SGTR 04/87 05/88 142 Leakage Through Electrical Isolators 06/87 08/88 143 Availability of Chilled Water Systems 10/87 02/89 144 Scram Without a Turbine / Generator Trip 03/88 09/88 TOTAL: 36 T7-2 As of 2nd Quarter FY-88 O O O
O C O TABLE 8 GENERIC ISSUES TO BE REPRIORITIZED AS OF SECOND QUARTER FY-88 Action Item / Previous Identification Current Issue No. Title Date Priority Schedule 2 Failure of Protective Services on Essential Equipment 05/83 24 MEDIUM 10/88 Automatic Emergency Core Cooling System Switch to NR 03/83 08/88 Recirculation
- 81 Potential Safety Problems Associated with Locked Doors and 12/86 DROP 06/88 8arriers in Nuclear Power Plants A-19 Digital Computer Protection System LI 02/83 B-22 04/89 LWR Fuel LI 02/83 B-29 04/89 Effectiveness of Ultimate Heat Sinks LI 02/83 03/89 B-31 Dam Failure Model R1 02/83 08/88 8-32 Ice Effects on Safety-Related Water Supplies LI 02/83
- C-9 12/88 RHR Peat Exchanger Tube Failures DROP 07/84 06/88 C-14 Storm Surge Models for Coastal Sites RI 02/83 05/88 D-2 Emergency Core Cooling System Capability for future Plants 5 (A-45) 06/83 05/88 III.D.I.1(2) Review Information on Provisions for Leak Detection 1 12/82 05/88 III.C.I.1(3) Develop Proposed System Acceptance Criteria I 12/82 05/88 TOTAL: 13 Previous priority evaluation published in NUREG-0933 18-1 As of 2nd Quarter FY-88
__._._.m__ ._. . _ _ - . _ _ _ _ _ _ . . _____ ___ _ . ._ __ __ _ _ . - . . _ _ _ _ __ _ __ _ _ _ _ _ _ _ _ __ . . _ . . _
i j TABLE 9 l REGULATORY IMPACT ISSUES SCHEDULED FOR RESOLUTION I
i Date Resolution Current
- Issue Lead Office / Approved for Date at end Resolution I Number Title Division / Branch P.-iority Resolution of FY-87 Date i !
! i
) 119.1 Piping Rupture Requireents NRR/ DEST /EMIB RI 09/10/85 05/88 05/88 !
{ and Decoupling of Seismic '
i and LOCA Loads 1
l 119.2 Pipe Damping Valees RES/DE/SEB RI 09/10/85 11/87 06/88 i
! 119.3 Decoupling OBE from SSE RES/DE/SEB RI 09/10/85 TBD TBD
- l 4
119.4 BWR Piping Materials ,
RES/DE/MEB RI 09/10/85 12/87 05/88 l' 119.5 Leak Detection Requirements RI 09/10/85 RES/DE/MEB 01/88 06/88 :
- 5 i >
1 .
l TOTAL: S I -
, t 1
I T9-1 As of.2nd Quarter FY-88' i
TABLE 10 LICENSING ISSUES SCHEDULED FOR RESOLUTION Lead Office / Current Issue Division / Resolution Number Title Branch Date
'(I 67.5.1 Reassessment of Radiological Consequences RES/DRPS/RPSI 03/89
.i 67.5.2 Reevaluation of SGTR Design Basis RES/DRPS/RPSI 03/89 i
- 133 Update Policy Statement on Nuclear Power Plant Staff NRR/DLPQ/LHFB 04/88 ,
Working Hours i
! I.D.5(5) Disturbance Analysis Systems RES/DRPS/RHFB 06/89 1
II.B.5(1) Behavior of Severely Damaged fuel RES/DRAA/AEB 06/94 .
1 II.B.5(2) Behavior of Core-Melt RES/DRAA/PRA8 06/94 i
! II.B.5(3) Effect of Hydrogen Burning and Explosions on RES/DRAA/AEB 09/91 i
Containment Structure II.F.5 Classification of Instrumentation, Control, and RES/DE TBD
. Electrical Equipment I -
j TOTAL: 8 l' I
I
! ;i r
h I
i 1
) :
i i T10-1 As of 2nd Quarter FY-88 I
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_ E F F R V E T N R E D WV E O O C N O Y
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INDFM OF ISSUES GENERIC ISSUE MANAGEMENT CONTROL SYSTEM 1
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..--...-------- .PAGE A-47 SAFETY IMPLICATION OF CONTROL SYSTEMS '
' 114 .
J t.-48 HYDROGEN CONTROL MEASURES AND EFFECTS OF HYDROGEN BURNS 117 B-5 BUCKLING BEHAVIOR OF 07tFt' CONTAINMENTS w 120 _
B-17 CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS 123 6-55 IMPROVE RELIABILITY OF TARGET, ROCK SAFETY-RELIEF VALVES ' "'
125 B-56 DIESFL GENERr.!ssR RELIABILITY 128
[, 8-61 ALLOWABLE ECCS EQUIPMENT OUTAGE PERIODS 131 8-6( DECOMMISSIONING'0F REACTORS 134 1
C-8 MAIN STEAM LINE LEAKAGE CONTROL 136 HF 1.1 SHIFT STAFFING '
141 HF 4.1 INSPECTION PROCEDURE FOR UPGRADED EMERGENCY OPERATING PROCEDURES (EOPS ' 143 HF 4.4 GUIDELINES FOR UPGRADING OTHER PROCFDURES
~
145 HF 5.1 LOCAL CONTROL STATIONS 147 l HF 5.2 REV. CRIT. FOR HUMAN FACTORS ASPECTS OF ADV CONTROLS AND INSTRUMENT. 149 HF S MAINTENANCE AND SURVEILLANCE PROGRAM i 152 %
- I.A.4.214) REVIEW SIMULATORS FOR CONFORMANCE TO CRITERIA 154
) I.D.3 SAFETY SYSTEM STATUS MO ITORING 156~
L I.D.4 CONTROL ROOM DESIGN STANDARD 159 I.D.5(3) ON-LINE REACTOR SURVEILLANCE SYSTEMS 160
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I D.5(5) DISTURBANCE ANALYSIS SYSTEMS - 162 I.F.1 EXPAND OA LIST 163 11.8.5(1) BEHAVIOR OF SEVERELY DAMAGED FUEL 165 -
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II.B.5(2) BEHAVIOR OF CORE-MELT ~ 167 9
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i RUN DATE: 05/11/88 INDEX OF ISSUES GENERIC ISSUE *iANAGEMENT CONTROL SYSTEM ISSUE NUMBER T I T LE PAGE II.B.5(3) EFFECT OF HYDR 6 GEN COMBUSTION ON CONTAINMENT SIRUCTURES 168 II.C.4 RELIABILITY ENGINEERING 171 II E.4.3 CONTAINMENT DESIGN-INTEGRIYY CHECK 173 II.E.6.1 IN-SITU TESTING OF VALVES 175 II.F.5 CLASSIFICATION OF INSTRUMENTATION CONTROL AND ELECTRICAL EQUIPMENT 181 II.H.2 9BTAIN DATA ON CONDITIONS INSIDE TMI-2 CONTAINMENT 183 II J.4.1 REVISE DEFICIENCY REPORTING REQUIREMENTS 185 4
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' \j RUN DATE: b5/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 1 i ISSUE NUMBER: 23 TITLE. REACTOR CO3LANT PUMP SEAL FAILURES IDENTIFICATION DATE: 12/80C PRIORITIZATION DATE- 04/83C TYPE: GSI PRIORITY: H TASK MANAGER: J. JACKSON OFFICE / DIVISION / BRANCH- RES /DE /EIB nCr!DN LEVEL: ACTIVE STATUS:
TAC NUMBERS: RESOLUTION DATE: 04/90 WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN. (APPENDIX G) i FIN CONTRACTOR CONTRACT TITLE
\
- A3751 BNL REACTOR COOLANT PUMP (RCP) SEAL INTEGRITY A3771 BNL ASSESS EFFECT OF MECH. MAINT, RCP SEAL A3806 NONE EVAL. ADEQ. OF RCP SEAL INSTR. & RESP. TO RCP A6322 NONE RCP SHAFT SEAL BEHAVIOR DURING ST. BLACKOUT B2953 JL REACTOR COOL. PUMP SEAL FAIL. VAL. IMP. ANALYSIS B3049 ..JNE LEAK RATE ANALYSIS OF WESTINGHOUSE RCP D1760 SCIENTECH REG. ANAL. FOR GI-23. RCP SEAL FAILURES W0RK SCOPE THE TAP FOR THIS ISSUE HAS BEEN REVISED TO INCOR- SHOULD TAKE. IF ANY. TO REDUCE RCP SEAL FAILURE TO AN PORATE WORK NECESSARY TO COMPLETE GSI 65. REVIEW ACCEPTABLE LEVEL COMMENSURATE WITH THE POTENTIAL SAFETY PWR RCP SEAL FAILURES CAUSED BY MECHANICAL FAILURES CONSEQUENCES OF SEAL FAILURE. THE PROGRAM CONSISTS OF AND LOSS OF SEAL COOLING TO ASCERTAIN IF INCREASED NRC THE FOLLOWING MAJOR TASKS:
REQUIREMENTS ARE NECESSARY TO MINIMIZE SEAL FAILURES. TASK 1 - DETERMINE ACTUAL SEAL FAILURE MECHANISMS.
EVALUATE THE EFFECTS OF SYSTEN DESIGN. MATERIALS. TASK 2 - EVALUATE RCP SEAL COOLING FOR ALL MODES OF OPERA-OPERATION. TESTING. AND MAINTENANCE ON SEAL FAILURE TION FOR WHICH SEAL COOLING IS REO'D USING THF MECHANISMS. REVIEW THE REtIAB. OF SEAL COOLING SYSTEMS RELIABILITY OF T' ICAL RCP SEAL COOLING SYSTEM AND IDENTIFY METHODS TO MINIMIZE THE EFFECTS OF LOSS OF DESIGNS.
SEAL COOLING. PERFORM A RISK ASSESSMENT OF SEAL FAILURE TASK 3 - REVIEW MECHANICAL AND MAINTENANCE-INDUCED FROM MAINTENANCE AND MECHANICAL EFFECTS. FAILURE MECHANISMS.
THIS PROGRAM WILL DETERMINE WHAT STEPS THE NRC a
STATUS WORK IS CURRENTLY IN PROGRESS ON TASKS 1.2 & 3. OF LOSS OF SEAL COOLING. ' INPUT IS BEING PROVIDED THROUGH
, RSB PROVIDED INPUT TO TASK 1 (ASSEMBLE BACKGROUND CONTRACTS WITH AECL AND ETEC. THE AECL WORK IS COMPLFTE AND INFORMATION ON SEAL FAILURES) WHICH INCL: AN LER NUREG/CR-4077. "REACTOR COOLANT PUMP SHAFT SEAL BEHAVIOR 4 SEARCH. A REVIEW OF INDUSTRY EXPERENCE, AND A BWR DURING STATION BLACKOUT" HAS BEEN ISSUED. THE ETEC WORK HA3 3
SCREENING REVIEW. BNL HAS COMPLETED ADDITIONAL WORK ON BEEN COMPLETED AND NUREG/CR-4294 "LEAK RATE ANALYSIS OF THE 1 THIS TASK UNDER FIN A-3771 PUBLISHED AS NUREG/CR-4400. WESTING. REACTOR COOLANT PUMP" HAS BEEN ISSUED. ADDITIONAL EIB IS WORKING ON TASK 2.1 EVALUATING THE EFFECTS CONCERNS REGARDING SEALS DISCOVERED THROUGH RESEARCH AT AtCL AS OF FY88 OUARTER 2 e
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4
RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 2 ISSUE NUMBER: 23 TITLE- REACTOR COOLANT PUMP SEAL FAILURES S T A TUS WAS INVESTIGATED THROUGH A FOLLOW -ON CONTRACT AT AECL PUMP SEAL RELATED INSTRUM AND OPERATOR RESPONSE." HAS THIS WORK WAS PUBLISHED IN NUREG/CR-4821 "REACTOR COOLANT 6EEN ISSUED IN ADDITIbN. BNL IS WORKING ON A DRAFT PUMP SHAFT SEAL STABILITY DURING STATION BLACKOUT." TECHNICAL FINDINGS DOCUMENT WHICH WILL INCORPORATE THE EIB. UNDER CONTRACT FIN A-3751 WITH BNL, IS RESULTS OF ALL THE VARIOUS STUDIES AND OTHER PERTINENT WORhlNG ON TASK 2.2 EVALUATING THE RELIABILITY OF RESULTS TO BE PUBLISHED IN A SINGLE NUREG DOCUMENT.
COOLING WATER SYSTEMS. THE BNL WORA ON SUBTAS' 2 2 HAL EIB. UNDER CONT:;AC T F IN B-2953 IS WORKING ON A BEEN COMPLETED AND NUREG/CR-4643. "LVALUATION UF CORE VALUE-IMPACT ANALYSIS 9F PROPOSED RESOLUTIONS TO GSI-23 DAMAGE SEQUENCES INITIATED BY L0bs OF REACTOR COOLANT WHICH THE STAFF DRAFTED IN 06/86 WITH THE AID OF THE RCP PUMP SEAL COOLING" HAS BEEN ISSUED. SEAL SUPPORT CONTRACTORS. AFTLR RECEIVING AND REVIEWING EIB. L'NDER COMINACT FIN A- 3771 WITH BNL. HAS A DRAFT OF THE FINAL REPORT FROM THIS STUDY. THE STAFF COMPLETED TASK 3.1 EVALUATING THE EFFECT OF MECHANICAL HAS DETERMINED ADDITIONAL WORK WILL BE REQUIRED.
AND MAINTENANCE-INDUCED RCP SEAL FAILURES ON RISK. ISCIENTECH WAS CONTRACTED TO COMPLETE THIS TASK UNDER NUREG/CR-4400 "THE IMPACT OF MECHANICAL AND FIN NO D1760 BY 05/88).
MAINTENANCE-INDUCED FAILURES OF MAIN REACTOR COOLANT THE STAFF HAS RECEIVED THE WESTINGHOUSE REPORT PUMD SEALS ON PLANT SAFETY" HAS PEEN ISSUED. WITH THE RESULTS OF THE FRENCH RCP SEAL TEST AND THE EIB. UNDER CONTRACT FIN A-3806 WITH BNL HAS FESPONSE TO THE STAFF CONCERNS REGARDING WCAP-10541 ON COMPLETED TASK 2.3 AND 3.2 EVALUATING- THE ADEQUACY OF ISP SEAL PERFORMANCE DURING STATION BLACKOUT.
CURRENT RCP SEAL AND SEAL COOLING SYSTEM INSTRUMENTATION ADDITIONAL CONCERNS REGARDING ALL TYPES OF RCP SEALS TO DETECT RCP SEAL DEGRADATION AND FAILURES. THE WERE RAISED AS A RESULT OF THE AECL TEST PROGRAM. THE ADECUACY OF CURRENT AUTOMATIC ACTIONS AND MANUAL TEST PROGRAM AT AECL IS BEING EXTENDED TO FURTHER OPERATOR RESPONSES TO PREYENT RCP SEAL LOCAS OR OTHER INVESTIGATE THESE CCNCERNS. THE REVISED MILESTONES UNACCEPTABLE EVENTS AND TO PROPOSE POSSIBLE INCORPORATE THE RESULTS OF THE FRENCH TEST. WESTINGHOUSE INSTRUMENTATION CHANGES. AUTOMATIC ACTIONS OR MANt'AL REPORT. AND THE AECL WORK TO THE EXTENT POSSIBLE AT THIS OPERATOR RESPONSES WHICH COULD IMPROVE THE CURRENT RCP TIME.
SEAL SAFETY PROCEDURES. NUREG/CK-4544 "REACTOR COOLANT AFFECTED DOCUMENTS PROBLEM / RESOLUTION ISSUE NUREG- *** NONE ***
REVIEW AND ISSUE SRP SECTION 9.2.2 (TBD)
REVISE AND ISSUE SRP SECTION 9.3.4 (TBD)
ISSUE NEW REGULATORY GUIDE AND SRP SECTION (TBDI 041GINAL CURRENT ACTUAL MI LESTONES DATE DATE DATE T P kbSbEbFbRbbMMENT b4hh3 -
bh/h3 AS OF FY88 QUARTER 2 O O O
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(J RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 3 ISSUE NUMBER: 23 TITLE: REACTOR COOLANT FUMP SFAL FAILURES ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE 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 ?9 06/84 --
06/84 DE TRANSFER RESOLUTION RESPONSIBILTY FROM DE TO 05/85 --
05/85 DST /GIB COMPLETE DOCUMEN. OF BACKGROUND PAST 05/85 --
10/84
[ SEAL FAILURES. INCLUDING LER SEARCH.REV t OF INDUST. EXP.& REV.0F BWR SCR.l TASK 1)
EVAL. RCP SEAL COOLING. INCL. DETERM. EFFECT 12/84 --
05/86 OF LOSS COOLING, EVAL RELIAB. OF COOLING SYS.
AND REV. RCP SEAL COOLING INSTR. (TASK 21 EVALUATE MECHANICAL AND MAINTENANCE-INDUCED 01/85 --
09/86 j FAILURE MECHANISMS (TASK 3l COMPLETE FEASABILITY STUDY TO IDENTIFr 03/85 05/88 --
MOST EFFECTIVE FIX. SCIENTECH REG, ANAL FOR GI-23 (TASK 4)
DTR PACKAGE COMPLETE 07/85 4%i15 --
DIVISION DEPUTY DIRECTOR REVIEW COMPLETED ^G/f; 48/88 --
CONCURRENCE BY OTHER OFFICES 09/85 10/88 --
DTR SENT TO CRGR F?O! 10/85 10/88 --
ACPS 70/L44 GA GTR COMPLETE 11/85 11/88 --
cMr.7 KiviLW OF DTR COMPLETE 11/85 12/88 --
FRN OF ISSUANCE OF PROPOSED RESOLUTION 12/85 03/89 --
FOR PUBLIC COMMENT AS OF FY88 QUARTER 2
a RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE. 4 ISSUE NUMBER: 23 TITLE: REACTOR COOLANT PUMP SEAL FAILURES ORIGINAL CURRENT ACTUAL M ILESTON ES DATE DATE DATE CCMDLETE DE REVIEW OF PUBLIC COMMENT 5 AND 04/86 08/89 --
PREPARE FTR PACKAGE DIVISION DEPUTY DIRECT 9R REVIEW OF FTR 05/86 09/89 --
COMPLETED CONCURRENCE BY OTHER OFFICES 11/89 11/89 --
CRGR REVIEW OF FTR COMPLETED (53) 06/86 01/90 --
FRN OF ISSUANCE OF FTR 07/86 04/90 --
i.
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AS OF FY88 OUARTER 2 O - - - - _ _
O O
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l RUN DATE: 05/11/88 j GENERIC ISSUE MANAGEMENT C04 TROL SYS TEM PAGE:. 5 ISSUE NUMBER:. 29 TITLE: BOLTING DEGRADATION OR FAILURE IN NUCLEAR POWER PLANTS IDENTIFICATION DATE: 10/81C PRIORITIZATION DATE: 08/82C TYPE: GSI PRIORITY: H TASK MANAGER: R. JOHNSON OF F ICE /DIVISI0'N/ BRANCH : RES /DE /EIB ACTION LEVEL: ACTIVE STATUS-TAC NUMBERS:
RESOLUTION DATE 03/90 WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN (APPENDIX Gl FIN CONTRACTOR CONTRACT TITLE A3359 BNL BOLTING APPLICATIONS REQUIREMENTS l A3782 BNL BOLTING APPLICATIONS REOUIREMENTS B2593 PNL BOLTING DEGRADATION VALUE IMPACT ANALYSIS W0RK SC0PE THIS ISSUE INCLUDES ALL SAFETY RELATEC BOLTING. WITH THE "DEGRADATION OF THREADED FASTENERS IN THE REACTOR EMPHASIS ON REACTOR COOLANT PRESSURE BOUNDARY BOLTING COOLANT PRESSURE BOUNDARY OF PWR PLANTS.-
DEGRADATION OR FAILURE. TASKS INCLUDE: 3. DRAFT STAFF RECOMMENDATION FOR PROPOSED CRITERIA /
- 1. DEVELOPMENT OF THE TECHNICAL BASES FOR BOLTING GUIDELINES TO BE INCGRPORATED INTO THE SRP.
APPLICATION REQUIREMENTS. 4. DEVELOP A PROPOSED IMPLEMENTATION PLAN FOR
- 2. REVIEW LICENSEE RESPONSES TO IEB 82-02 MANAGEMENT CONSIDERATION.
STA T US EPWI Pe0VIDED A COPY OF THE REVISED DRAFT FINAL REPORT. INITIATIVES WERE ONGOING. NRR MANAGEMENT HAD DECIDED TO "DEGRADATION AnG TAILURE OF BOLTING IN NUCLEAR POWER LIMIT THE SCOPE OF THIS ISSUE TO ONLY PRIMARY PRESSURE PLANTS." AFTER REVIEW. IT 9AS DECIDED THAT THE REPORT IN BOUNDARY BOLTING. CAREFUL RE-REVIEW OF THE ORIGINAL 1985 CONJUNCTION WITH OTHER RESULTS of IM988%TR Y INITIATIVES (SEE REGULATORY ANALYSIS. IN CONJUNCTION WITH PREPARING THE DRAFT PP 29-1 THROUGH 29-3) PROVIDES THE-TECHNICAL CASTS FOR THE CRGR PACKAGE. REVEALED THAT. CONSISTENT WITH THE NRR INTENT.
RESOLUTION OF THIS GI UTILIZING THE RECENTLY COMPLET.Lu ONLY PRIMARY PRESSURE BOUNDARY BOLTING HAD BEEN ADRESSED BY INDUSTRY DEVELOPED TECHNICAL BASIS DOCUMENTS AND A DRAFT FML FnR NRR. IN ORDER TO EXPAND THE SCOPE OF SAFETY RELATED REGULATORY ANALYSIS. PREPARED BY PACIFIC NORTHWEST BOLTING TO CE ADDRESSED BY THE GI 29 RESOLUTION TO MAKE LABORATORY FOR THE PREVIOUS TASK MANAGER IN 1985. ASSEMBLING MAXIMUM USE OF THE INDUSTRY DEVELOPED TECHNICAL BASES OF A DRAFT CRGR PACKAGE WAS BEGUN. BECAUSE THE FINAL DOCUMENTS. THE ORIGINAL REGULATORY ANALYSIS MUST BE REVISED INDUSTRY INITIATIVES HAVE ADDRESSED ALL SAFETY RELATED EIB HAS REQUESTED ASSISTANCE FROM PRAB. RES FOR THIS EFFORT.
BOLTING. THE RESOLUTION OF GI 29 WILL ADDRETS AS LARGE A EIB HAS CONCLUDED THAT THIS IS THE MOST EXPEDITIOUS WAY TO SCOPE OF SAFETY RELATED BOLTING AS CAN BE JUSTIr IED ON THE EFFECT THE NEEDED REVISIONS. PRAB IS UNDERTAKING THE BASIS OF THE REGULATORY ANALYSIS. THIS WILL ENABLE GI 6; . REQUIRED REVISIUNS ON A HIGH PRIORITY BASIS: HOWEVER. BASED REACTOR SYSTEMS BOLTING APPLICATION" TO BE SUBSUMED INT' GI ON THE PRAB ESTIMATE FOR COMPLETION OF THIS EFFORT. A
- 29. SCHEDULE SLIP OF 5 MONTHS WAS PROJECTED TO OCCUR AND IN THE 1984-1985 TIME FRAME WHEN THE BROAD:R INDUSTRY MILESTONES WERE REVISED ACCORDINGLY IN THE PREVIOUS UPDATE.
AS OF-FY88 OUARTER 2
RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 6 YSSUE NUMBER: 29 TITLE: BOLTING DEGRADATION OR FAILURE IN NUCLEAR POWER PLANTS AFFECTED DOCUMENTS PROBLEM / RESOLUTION SRP REVISION. NONE ORIGINAL CURRENT ACTUAL M I LEST 0NE S DATE DATE DATE khhbkbbhTRkbhTbbhL bh/8h -
bh/hh RECLIVE DRAFT I4UREG/CR REPORT 07/83 --
07/83 FROM CONTRACTOR STAFF REVIEW OF DRAFT NUREG/CR 07/83 --
03/84 REPORT DRAFT STAFF POSITION (REVISED 07/84 --
08/84 SRP SECTION)
PREPARE draft VALUE/ IMPACT 08/83 --
05/85 STATEMENT EVALUATE PROPOSED RESOLUTION 03/89 --
09/87 0F USI A-45 AND EPRI/AIF
SUMMARY
PAPER PREPARE DTR CRGR PACKAGE FOR REVIEW 09/83 --
11/87 BY OTHER OFFICES DIVISION DEPUTY DIRECTOR REVIEW COMPLETED 12/83 05/88 --
REVISE REGULATORY ANALYSIS 04/88 04/88 --
REVIEW PACKAGE TO CRGR (29) 01/84 07/88 --
ACRS REVIEW COMPLETED 04/88 04/88 --
CRGR REVIEW COMPLETED 01/84 09/88 --
EDO APPROVAL 03/84 10/88 --
FRN OF ISSUANCE OF PROPOSED RESOLUTION 03/84 12/88 --
FOR PUBLIC COMMENT AS OF FY88 OUaG'ER 2 O O O
l... < '
i t
! RUN DATEi 05/11/84_ !
! I i GENERIC ISSUE MANAGFMENT CONTROL SYSTEM PAGE: 7 .
i l ISSUE NUMBER- 49 TITLE: BOLTING DEGRADATION OR FAILURE IN NUCLEAR POWER PLANTS' I i
ORIGINAL CURRENT ACTUAL l MILEST0NES DATE DATE DATE ~!
COMPLETE DE REVIEW OF PUBLIC COMMENTS AND 12/88 05/89 --
PREPARE FTR PACKAGE DIVISION DEPUTY DIRECTOR REVIEW OF FTR 01/89 06/89 -- '
COMPLETED ,
CONCURRENCE BY OTHER OFFICES & FTR PACKAGE 12/88 08/89 __
TO CRGR (53) r CRGR REVIEW OF FTR COMPLETED 05/89 10/89 -.
EDO APPROVAL OF FTR 06/89 11/89 --
FRN OF ISSUANCE OF FTR 03/89 03/90 --
f t
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.I AS OF FY88 OUARTER 2' i
i 3
I
- - - - _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - ___ - _ ~. :- - . _ - - - _ . _ - - _ _ _ _ - - - _ _ _ - - - _ _ _ . _ _ _ __ -- - ____
RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE- 3 ISSUE NUMBER- 43 TITLE: RELIABILITY OF AIR SYSTEMS IDENTIFICATION DATE: 09/82C PRIORITIZATION DATE 12/87C TYPE. GSI PRIORITY: H TASK MANAGER: G. BURDICK OFFICE / DIVISION / BRANCH RES /DRPS/RPSI ACTION LEVEL: ACTIVE STATUS; TAC NUMBERS: RESOLUTION DATE 04/89 WORK AUTHORIZATION. NRR FY-84 OPERATING PLAN ( APPENDIX G)
FIN CONTRACTOR CONTRACT TITLE A396F BNL AIR SYSTEMS RELIABILITY W 0R K SC0PE ASSESS THE RISK SIGNIFICANCE Of AIR SYSTEMS PROBLEMS. PROBLEMS AND DEVELOP A REGULATORY GUIDE FOR IMPLEMENTATION DEVISE A COST-EFFECTIVE APROACH FOR ALLEVIATING THOSE OF THE APPROACH
$TA T US PRELIMINARY RESOLUTION APPROACH PRESENTED BALLY TO PLANTS SHOW VERY LITTLE CONTRIBUTION TO RISK FROM AIR SYSTEM NRR. PROG. ASSUMPTION TO CONTRACTOR 12/22/87 1ASK FAULTS. THE TECH ASSISTANCE PROGRAM IS CN SCHEDULE WITH MAAAGER/ CONTRACTOR MEETING HELD 12/29/87. DRAFT 187 COMPLETION OF THE RISK ESTIMATE TASK BY 4/30/88. DECISION REVIEWED 1/6/87. ON PUBLIC MEETING WITH INDUSTRY PENDING OUTCOME OF RISK AN APPROACH TO RESOLUTION WAS AGAIN DISCUSSED WITH CONTRIBUTION ESTIMATE.
AEOD AND NRR ON 2/24/88. RESULTS FROM NUREG-1150 REFERENCE AFFECTED DOCUMENTS PROBLEM / RESOLUTION NRC INFORMATION NOTICE NO. 87-28 SUPPLEMENT J. *** N ONE ***
ORIGINAL CURRENT ACTUAL MI LEST ONF S DATE DATE DATE INITIAL RESOLUTION APPROACH DEFINED -- --
12/87 AS OF FY88 OUARTER 2 O O O
f
( - J RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 9 ISSUE NUMBER: 43 TITLE: RELIABILITY OF AIR SYSTEMS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE TECHNICAL ASSISTANCE PROG. START 01/88 --
02/88 TASK ACTION PLAN APPROVED 01/88 --
02/88 RISK ASSESSMENT COMPLETE 04/88 04/88 --
RECOMMENDATIONS OR FINAL TAP 05/88 05/88 --
TO NRR TECHNICAL ASSISTANCE, V/I STATEMENT COMPLETE 08/88 08/88 --
DRAFT REG. GUIDE COMPLETE 09/88 09/88 --
REG. GUIDE REVIEW BY DIVISIONS COMPLETE 10/88 10/88 --
(RES/NRR/AEOD)
RESOLUTION OF COMMENTS COMPLETE / SUBMITTED TO 11/88 11/88 --
CRGR (29) "
NRR/CRGR CONCURRENCE 11/88 11/88 --
TO ACRS SUBCOMMITTEE AND OGC 11/88 11/88 --
COMMENT RESOLUTION CL:MPLETE 12/88 12/88 --
CONCURRENCE BY NRR LEAD DIVISIONS 12/88 12/88 --
GUIDE ISSUED FOR USE.AND COMMENT 12/88 12/88 --
PUBLIC COMMENTS REVIEWED 03/89 03/89 --
NRR CONCURRENCE 04/89 04/89 --
FINAL REG. GUIDE ISSUED 04/89 04/89 --
i l
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'AS OF FY88 OUARTER 2 l
_ -_.. . ..[ .. . . . . . .
RUN DATE: 03/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 10 ISSUE NUMBER: 51 TITLE- IMPROVING THE RELIABILITY OF OPEN CYCLE SERVICE WATER SYSTEMS IDENTIFICATION DATE: 09/82C PRIORITIZATION DATE: 06/83C TYPE: GSI PRIORITY: M TASK MANAGER: J. JACKSON OFFICE / DIVISION / BRANCH: RES /DE /EIB ACTION LEVEL: ACTIVE STATUS:
TAC NUM3ERS: RESOLUTION DATE- 07/90 WORK AUTHORIZATION: MEMO TO R.J. MATTSON FROM H.R. DENTON DATED JUNE 3. 1983.
NRR FY-84 OPERATING PLAN. (APPENDIX G).
FIN CONTRACTOR CONTRACT TITLE 82977 PNL IMPROVING RELIABILITY OF OPEN-CYCLE WATER Sv5TEMS W0P K SC0PE
$HEbkhkkLkbWbRKbbbPkksPRbVkbkbhkkHkhkP kNb bbNhRbt MkhHbbS kNb b hhbPbbk THk bkk bF kHbbk FOR ISSUE 51 (MEMORANDUM FROM R. MATTSON ' . . T. SPEIS. METHODS WHICH WILL ASSURE THE CONTINUED RELIABILITY ET AL.. DATED 01/11/84). IN
SUMMARY
. THE SCOPE OF THIS OF OPEN CYCLE SERVICE WATER SYSTEMS AGAINST VARIOUS TASK WILL BE TO EVALUATE THE ADEQUACY OF SURVEILLANCE FORMS OF FOULING.
ST A T US THE TAP WAS REVISED AND ISSUED ON 10/3/84 MATERIALS TO OPEN CYCLE WATER SYSTEMS IN NUCLEAR POWER THE S0W WAS REVISED ON 5/9/85 TO INCORPORATE PLANTS.
RES PROJECT TASK V INTO NRR*S TECHNICAL TASKS 1 & 2 (OF 41 0F THE S0W WERE COMPLETED. WITH THE ASSISTANCE PROJECT. THE TAP WAS REVISED TO BE PUBLICATION OF NUREG/CR-4626 (VOLS 1 & 2) IN 9/86 AND CONSISTENT WITH THE S0W AND TO ASSURE THAT IT 3/87 RESPECTIVELY. COORDINATION OF THIS PROJECT WITH INCORPORATED MILESTONES NECESSARY TO PROCESS CRGR RES IS DOCUMENTED IN A MEMORANDUM FROM R. MATTSON TO F .
SRP PACKAGES THROUGH ISSUANCE AND USE. THE FIRST 4 ARSENAULT. DATED 01/23/84.
TASKS ASSOCIATED WITH THIS ISSUE ARE TIED TO RES DSRO REQUESTED MODIFICATION OF THE CONTRACT ON PROJECT B2463 AND ARE COMPLETE. BASED UPON THE 12/22/86 TO INCLUDE PREPARATION OF A GUIDANCE DOCUMENT RESULTS OF THIS RESEARCH WHICH DEALS WITH BI0 FOULING. (INTO TASK 4) AND PREPARATION OF THE PRA/VALUE IMPACT EIB WILL ADAPT WHERE POSSIBLE METHODS FOR ASSESSMENT AS A NEW TASK 5. THE RESULTING 189 IDATED SURVEILLANCE AND CONTROL OF BI0 FOULING TO FOULING 1/26/871. ALONG WITH THE FY-87 FUNDING. WAS APPROVED BY MUD. SILT AND CORROSION PRODUCTS. IN MARCH 1987.
A MODIFIED PNL PROPOSAL DATED 10/85 WAS TASK 4 (TECHNICAL FUNDINGS REPORT) AND TASK 5 APPROVED BY DSRO ON 5/15/86. THE CONTRACTOR WILL (REGULATORY ANALYSIS REPORT) ARE IN PROGRESS AND SHOULD DETERMINE THE APPLICABILITY OF BI0 FOULING SURVEILLANCE BE SUBMITTED DURING THE THIRD OUARTER OF FY-88.
AND CONTROL METHODS CONTAINED IN NRC-FURNISHED AS OF FY88 QUARTER 2 O O O
s A J -
L) i RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: II 4
ISSUE NUMBER: 51 TITLE: IMPROVING THE RELIABILITY OF OPEN CYCLE SERVICE WATER SYSTEMS AFFECTED DOCUMENTS PROBLEM / RESOLUTION MORE EXTENSIVE USE OF CHLORINATION THAN ORIGINALLY PLANNED. THEREFORE AN ENVIRONMENTAL IMPACT ASSE S? aiN T (EIA) WILL BE NECESSARY. A RFP TO PNL FOR THIS STf7Y HAS BEEN MADE THIS WORK WILL DELAY THE SCHEDULE BY APPROXIMATELY 4 MONTHS.
4
! ORIGINAL CURRENT ACTUAL
' MILEST0NES DATE DATE DATE
. TAP APPROVED BY DSI DIRECTOR 01/84 --
01/84 REVISED TAP APPROVED AND ISSUED 10/84 --
10/84 PROPOSALS SOLICITED 07/84 --
10/84 l PNL RESPONSE TO RFP AND S0W 12/84 --
12/84 I
REVISE S0W TO INCORPORATE RES TASK V 05/85 --
05/85 PROPOSAL EVALUATED AND ACCEPTED 02/85 --
08/85 CONTRACT SCHEDULE 03/85 --
10/85 DRAFT TECHNICAL FINDINGS REPORT FROM 07/86 04/88 --
CONTRACTOR STAFF REVIEW OF DRAFT TECHNICAL FINDINGS 08/86 05/85 --
REPORT STAFF REVIEW OF FINAL NUREG/CR TECHNICAL 09/86 06/88 --
FINDINGS REPORT ENVIRONMENTAL IMPACT ASSESSMENT (EIA). 06/88 06/88 --
WORK COMPLETED DRAFT REGULATORY ANALYSIS REPORT FROM 10/87 10/88 --
CONTRACTOR' AS OF FY88 QUARTER 2
RUO DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 12 ISSUE NUMBER: S1 TITLE: IMPROVING THE RELIABILITY OF OPEN CYCLE SERVICE WATER SYSTEMS ORIGINAL CURRENT ACTUAL M ILEST 0N E S DATE DATE DATE DTR PACKAG. COMPLETED 11/87 10/88 --
DIVISION DEPUTY DIRECTOR PEVIEW OF DTR 12/87 11/88 --
COMPLETED CONCURRENCE BY OTHER OFFICES 12/87 01/89 --
DTR FACKAGE TO CRGR (291 12/87 0I/89 --
ACRS REVIEW OF DTR COMPLETED 12/87 03/89 --
CRGR REVIEW OF DTR COMPLETED 01/88 03/89 --
FRN OF ISSUANCE OF PROPOSED RESOLUTION OS/88 06/89 --
FOR PUBLIC COMMENT COMPLETE DE REVIEW OF PUBLIC CCMMENTS 07/88 11/89 --
AND PREPARE FTR PACKAGE DIVISION DEPUTY DIRECTOR REVIEW OF FTR 08/88 12/89 _-
COMPLETED CONCURRENCE BY OTHER OFFICES 08/88 02/90 --
CRGR REVIEW OF FTR COMPLETED (53) 09/88 04/90 --
FRN OF ISSUANCE OF SRP 07/88 07/90 --
AS OF FY88 OUARTER 2 O O O
% r3 a
) (w) - (mw)
RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL S(STEM PAGE: 13 ISSUE NUMBER: F6 TITLE: STEAM GENERATOR REQUIREMENTS IDENTIFICATION DATE: 01/83C PRIORIIIZATION DATE. 11/83C TYPE: GSI PRIORITY:
TASK MANAGER: E. MURPHY OFFICE / DIVISION / BRANCH- NRR / DEST /EMTB ACTION LEVEL: INACTIVE STATUS: NR TAC NUMBERS: MS3338 RESOLUTICN DATE- 06/88 WORK AUTHORIZATION: MEMO TO D. EISENHUT FROM H. DENION DATED 11/16/83.
FIN CONTRACTOR CONIRACT TITLE
---------- ------------------ .-------------------------~~-----------------------
W0R K SC0PE CONSIDER PROPOSED GENERIC REQUIREMENTS STEMMING GENERATOR TUBE INTEGRTTY, FROM USI*S A-3 A-4 AND A-5 REGARDING STEAM STA TUS AS AFPROVED BY THE COMMISSION, ORIGINALLY PROPOSED LICENSEES TO IMPLEMENT THE STAFF"S RECOMMENDATIONS; AND (2)
GENERIC REQUIREMENTS WERE ISSUED AS RECOMMENDATIONS TO ALL REVISE TH7 SRP AND STS CONSISTENT WITH THE STAFF PWR LICENSEES AND APPLICANTS IN GL 85-02. THE STAFF"S RECOMMENDATIONS IN GL 85-02.
ASSESSMENT OF LICENSEE RESPONSES TO GL 85-02 WAS PROVIDED TO THIS GSI HAS BEEN CONDUCTED IN PARALLEL WITH THE THE COMMISSSION IN SECY-86-77 DATED 03/24/86. TWO STAFF'S PROGRAM FOR RESOLVING USI*S A-3, A-4 AND A-5. A ADDITIONAL TASKS ARE UNDER CONSIDERATION AS A RESULT OF THE DRAFT REPORT DOCUMENTING THE-STAFF'S PROPOSED RESOLUTION OF ABOVE ASSESSMENT. THESE TASKS ARE CURPENTLY INACTIVE WITH THE USI'S WAS ISSUED FOR PUBLIC COMMENT IN APRIL 1984.
NO SCHEDULED COMPLETION DATES: (1) PROVIDE PLAN T-SPECIF IC FINAL PUBLICATION OF NUREG-0844 WILL CONSTITUTE TECHNICAL ASSESSMENTS TO EACH LICENSEE IDENTIFYING AREAS WHERE RESOLUTION OF THE USI*S. DELA(S IN RESOLUTION OF USI'S A-3, LICENSEE PROGRAMS APPEAR TO FALL SHORT OF STAFF 4, 5 HAVE AFFECTED CLOSE OUT OF THIS ISSUE. NO RECOMMENDATIONS IN GL 85-02 AND TO CONTINUE TO ENCOURAGE REQUIREMENTS WILL RESULT FROM THE RESOLUTION OF THIS ISSUE.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION i GL 85-02, "STAFF RECOMMENDED ACTIONS NONE STEMMING FROM NRC INTEGRATED PROGRAM FOR THE RESOLUTION OF UNRESOLVED SAFETY ISSUE REGARDING STEAM GENERATOR
- TUBE INTEGRITY."
AS OF FY88 QUARTER 2-
. _ _ _ _ . _ _ _ _ _ _ _ _ _ ._________._______.____._________________________m ___ _ _ _ _ _ _ _ - _ _ _ _ ___ __ _ _ . __ __ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _
RUN DATE: 05/11/80 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 14 ISSUE NUMBER: 66 TITLE: STEAM GENERATOk' REQUIRCMENTS ORIGINAL C'tRRENT ACTUAL MI LES T ON ES DATE DATE DATE ACRS REVIEW COMPLETE (231 10/83 --
10/83 CRGR REVIEW COMPLETE 01/83 --
10/83 COMMISSION PAPER ON PROPOSED USI 01/84 --
01/84 RESOLUTION AND ISSUANCE OF GENERIC LETTER ISECY-84-131 REVISED COMMISSION PAPE R ON ISSUANCE 07/84 --
09/84 OF GENERIC LETTER (SECY-84-13Al COMMISSION MEETING 02/84 --
09/84 ISSUE SECY-84-138 11/84 --
11/84 ISSUE SECY-85-62 02/85 --
02/85 ISSUE GL 85-02 03/84 --
04/85 ISSUE REPORT TO COMMISSION REGARDING 02/86 --
03/86 RESPONSES TO GL 85-02 CLOSE CUT ISSUE 06/88 06/88 --
AS OF Fv88 OUARTER 2 9 9 .
9
i
( 3 v/
RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 15 ISSUE NUMBER: 67.5.1 TITLE: REASSESSMENT OF SGTR DESIGN BASIS
. t IDENTIFICATION DATE: 06/83C PRIORITIZATION DATE: 03/85C TYPE: LI PRIORITY:
TASK MANAGER: J. HOPENFELD OFFICE / DIVISION / BRANCH: RES /DRPS/RPSI ACTION LEVEL: ACTIVE STATUS: 5 i TAC NUMBERS: NONE RESOLUTION DATE: 03/89 4
WORK AUTHORIZATIUN: MEMO TO R. BERNER0 FROM H. DENTON DATED 3/25/85 FIN CONTRACTOR CONTRACT TITLE A6879 INEL RISK ASSOCIATED WITH A SPECTRUM OF SGTR ACCIDENTS B0832 ORNL STEAM GENERATOR TUBE RUPTURE 1
1
) WORK SCOPE COMPLETE THE EXPERIMENTS ON IODINE PARTITION REQUIREMENTS IN LIGHT OF RECENT DATA USING BEST ESTIMATE j COEFFICIENTS: EVALUATE THE VALIDITY OF SRP IODINE SPIKE MODELS. IDENTIFY MODIFICATIONS TO THE SRP, STA TUS i THE ORNL EXPERIMENTS TO DETERMINE THE IODINE PARTITION EVALUATE THE RISK ASSOCIATED WITH SGTR ACCIDENTS WAS
- COEFFICIENT ARE NEARLY COMPLETE. THE INEL CONTRACT TG ISSUED 2/10/88 AND T/A WORK IS NOW UNDER WAY.
1 1
1 AFFECTED DOCUMENTS PROBLEM / RESOLUTION-THAN ANTICIPATED PARTLY DUE TO TEMPORARY UNAVAILABITY OF
. INEL PERSONNEL TO RESPOND TO THE S0W. THE CONTRACT WAS i-ISSUED ON 3/10/88. THIS SHOULD HAVE NO EFFECT ON SCHEDULED DELIVERABLES.
i OR:GINAL CURRENT ACTUAL MILESi0NES DATE DATE DA1E i PREPARE DRAFT TAP 06/87 --
06/87 i
l
$ AS OF FY88 OUARTER 2' 1
RU1 DATF. OS/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 16 ISSUE NUMBER: 67.S.1 TITLE- REASSESSMENT OF SGTR DESIGN BASIS ORICINAL CURRENT ACTUAL M ILEST0N E S DATE DATE DATE FEVISE DRAFT TAP TO INCLUDE 10/87 --
12/87 PROBASILISTIC ASSESSMENT OF SGTR MANAGEMENT APPROVAL OF REVISED 11/87 --
12/87 TAP COMPLETE WORK PLAN AND CONTRACT PROPOSAL 11/87 --
12/87 ISSUE CONTRACT TO INEL 01/88 --
03/88 DRAFT REPORT FROM INEL AND ORNL TO RES 06/88 06/88 --
FINAL REPORT FROM INEL AND 08/88 08/88 --
ORNL TO RES DRAFT REGULATORY ANALYSIS PREPARED 09/88 09/88 --
CRGR PACKAGE ISSUED FOR COMMENT 10/88 10/88 --
ORGR PACKAGE REVISED. SENT TO RES 12/88 12/88 --
DIRECTOR FOR APPROVAL CRGR AND ACRS MEETINGS (29,S3) 02/89 02/89 --
ISSUE CLOSEOUT MEMO 03/89 03/89 --
AS OF FY88 OUARTER 2 9 -
9 9
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\/ v - U RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 19 ISSUE NUMBER: 70 TITLE: PORV AND BLOCK VALVE RELIABILITY IDENTIFICATION DATE: 06/83C PRIORITIZATION DATE: 05/84C TYPE: GSI PRIORTTY: M TASK MANAGER: R. KIRKWOOD OFFICE / DIVISION / BRANCH: RES /DE /EIB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: RESOLUTION DATE: 10/88 WORK AUTHORIZATION: MEMO TO R. MATTSON FROM H. DENTON DATED 5/14/84 FIN CONTRACTOR CONTRACT TITLE h80h bhl [S hkhkbhbhRkbK kkbbChkbhhRbhkkPRbVkhPbkVfbbhhbh 80828 ORNL OP. EXPER. REV. OF PORV* S & BLOCK VALVES F AILURES IN NUC. POWER PLANTS W0RK SC0PE IDENTIFY FUNDAMENTAL SAFETY REQUIREMENTS OF THE FOR INCREASED PLANT AVAILABILITY AND THE PRA RESULTS PORV*S AND BLOCK VALVES. PRA*S WILL DE USED TO DETERMINE WILL BE USED TO IDENTIFY THE AMOUNT OF MONEY THAT COULD CORE-MELT FREQUENCIES AND RISK CONTRIBUTED BY BE JUSTIFIED FOR PORV/ BLOCK VALVE IMPROVEMENTS.
MALFUNCTION OF PORV AND BLOCK VALVES ASSOCIATED WITH POTENTIAL IMPROVEMENTS WILL BE IDENTIFIED IN THE AREAS OF VARIOUS ACCIDENTS AND PLANT PROTECTION FEATURES DESIGN. EQUIPMENT QUALIFICATIONS. QA AND QC, MAINTENANCE INCLUDING SGTR EVENTS. LTOP. PORV-LOCA. RCS VENTS AND PROGRAMS. TECHNICAL SPECIFICATIONS AND TESTING BTP RSB 5-1. BASED ON THE RESULTS fnOM BNL PRA WORh. REQUIREMENTS.
MAXIMUM RISK REDUCTION WILL BE EVALUATED. THE POTENTIAL STA TUS TkP hkh khhbkh bh k b 85$ k kkPbRh hb kHk bbhbkkhhbN 9/h0/85$ hh FF bbbhkhhh HkVk bkkh RkhblVhh khb k FkhkL ON THE STATUS OF STAFF ' ARK WAS ISSUED ON 2/18/86. DRAFT VERSION OF THE REPORT WAS ISSUED IN THE 3RD QUARTER OF INFORMATION WITH RESPF1,I TO RADIATION LEVELS ANTICIPATED FY-87 AS NUREG/CR-4692. THIS REPORT WAS EXPANDED TO INCLUDE FUNDING. AND SCHEDULE CHANGES INDICATE THAT DATA FROM RESPONSES TO NRC QUESTIONS DURING INTERVIEWS WITH FOUR PORV DISASSEMBLY OF THE idRV FROM TMI-2 WOULD NOT BE AVAILABLE MANUFACTURERS CONDUCTED AT THEIR RESPECTIVE MANUFACTURING FOR APPROXIMATELY 12 MONTHS. IN ADDITION, THERE WAS FACILITIES TO DISCUSS PORV PROBLEMS. THE FINAL REPORT HAS CONSIDERABLE UNCERTAINTY AS TO WHETHER THE PORV IN ITS BEEN COMPLETED AND WAS ISSUED IN OCTOBER.1987. COMMENTS PRESENT CONDITION (SEVERELY CORRODED FROM EXPOSURE OF SEVEN WERE ALSO FURNISH D ON BNL DRAFT REPORT. "ESTIMATION OF RISK YEARS IN A HIGH HUMIDITY, HIGH RADIATIONI ENVIRONMENT WOULD REDUCTION FROM IMPROVED PORV RELIABILITY IN PWRS." DATED
' PROVIDE ANY CONCLUSIVE EVIDENCE AS TO THE CAUSE OF THE MARCH 9/85. STAFF COMMENTS HAVE BEEN RESOLVED AND A SECOND DRAFT 1979 FAILURE TO CLOSE. TAKING THESE FACTORS INTO ACCOUNT, VERSION OF THE REPORT WAS PREPARED IN THE SECOND QUARTER OF IT WAS CONCLUDED THAT THE RESOLUTION OF THIS ISSUE SHOULD BE FY-87. THE FINAL REPORT HAS BEEN COMPLETED AND WAS ISSUED COMPLETED WITHOUT THE DATA FROM THE TMI-2 PORV. COMMENTS AS NUREG/CR-4999 DATED DECEMBER 1987. WORK HAS COMMENCED ON WERE FURNISHED ON ORNL DRA T REPORT. "0PERATING EXPERIE9;E THE PREPARATION OF A NUREG TN LIEU OF A SERIES OF LETTER REVIEW AND ANALYSIS OF FAILURES OF PILOT-OPERATED RELIEF REPORTS. ONE FOR EACH COMPLETED TASK. AS WAS ORIGINALLY VALVES ANP BLOCK VALVES IN NUCLEAR POWER PLANTS." DATED SCHEDULED IN THE TAP. A DRAFT VERSION OF THIS NUREG HAS AS OF FY88 QUARTER 2
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RUN DATEi 05/11/88' GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE :- 21 -l
! ISSUE NUMBER: 70 TITLE: PORV AND BLOCK VALVE RELIABILITY -
I t t
t ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE ;
i' ESTIMATION OF RISK REDUCTION FROM 01/86 -
09/87 l IMPROVED PORV/ BLOCK VALVE RELIABILITY NUREG COMPLETED 05/87 04/88 --
PREPARE DTR PACKAGE 03/86 04/88 -- !
t DIVISION DEPUTY DIRECTOR REVIEW OF DTR 04/86 04/88 -- !
l COMPLETED I f CONCURRENCE ON DTR BY OTHER OFFICES 05/86 05/88 --
i DTR PACKAGE TO CRGR (29.53) 06/86 05/88 --
5 ACRS REVIEW OF DTR COMPLETED 06/86 07/88 --
?
CRGR REVIEW OF DTR COMPLETED 07/86 07/88 --
f EDO APPROVAL OF DTR 01/87 09/88 --
, ComISSION PAPER 12/87 10/88 --
CLOSE OUT ISSUE 10/88 10/88 l
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 22 ISSUE NUMBER: 7S TITLE: GENERIC IMPLICATIONS OF ATWS EVENTS AT SALEM - QA IDENTIFICATION DATE: 06/83C PRIORITIZATION DATE 10/83C TYPE: GSI PRIORITY:
TASK MANAGER: O. GORMLEY OFFICE / DIVISION / BRANCH RES /DRA /ARGI ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS:
RESOLUTION DATE 01/90 WORK AUTHORIZATION: MEMO FROM H. DENTON TO R DEYOUNG. "SCHEDULE FOR RESOLVING & COMPLETING GENERIC ISSUE NO. 75." 10/19/83 FIN CONTRACTOR CONTRACT TITLE NONE NONE NONE W0R K SC0P E THE RESOLUTION TO SUBTASK 1 OF GSI ------------------
7S IS TO BE ------------ SIDER BACKFITTING STAFF WILL CON THIS REG. GUIDE REVISION ADDR E SSE D - REVISE REG. GUIDE 1.33 OUALITY ASSURANCE THE WORK SCOPE OF TMI ITEMS I.B.I.116) AND I.B.1.1(7)
PROGRAM REQUIREMENTS (OPERATIONS)* TO CONTAIN MORE RELATIVE TO THE REVISION OF REG. GUIDE 1.33 HAS BEEN DETAILED GUIDANCE FOR OPERATIONAL QA PROGRAMS THE SUBSUMED BY THIS GENERIC ISSUE SUBTASK.
S T A T US --------------------------------------.---------
- ---- THE ORIGINAL PLAN WAS ----------------------------------------------
TO ISSUE A REG. GUIDE EXPANDING S VERSION DRAFT OFANDTHI RECEIVED A TOTAL OF 71 COMMENTS THE F ROM F OUR REGIONS. THIS PLUS OTHER PROBLEMS DISCUSSED BELOW ON THE REQUIREMENTS OF THE 1976 VERSION OF ANS 3.2 LED THE STAFF TO CONCLUDE THAT THE CURRENT SCHEDULE IS PLAN WAS LATER ALIGNED TO THAT OF ENDORSING THE 1982 VERSION UNREALISTIC IF IT IS TO BE TIED TO A NEW VERSION OF ANS 3.2.
WHICH FROVIDED MANY OF THE IMPROVEMENTS. ANS IS CURRENTLY THEREFORE. THE STAFF HAS CONCLUDED THAT GSI 75 SHOULD BE PLANNING TO ISSUE AN EVEN MORE COMPREHENSIVE AND SIGNIFICANTLY IMPROVED VERSION OF ANS 3.2 AT THE END OF DECOUPLED FROM THE ANS 3.2 REVISION EFFORT IN ORDER TO AVOID 1988 THE STAFF SOLICITED COMMENTS FROM THE REGIONS ON A FURTHER SCHEDULE SLIPS.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION ANS 3.2 (1982) .THE CONTINUED SLIPPAGE OF ANS-3.2 IS A PROBLEM IN ADDITION. THE DRAFT CURRENTLY IN PREPARATION RELIES ON NOA-2 WHICH HAS NEVER BEEN ENDORSED BY NRC, AS WELL AS VERSIONS OF OTHER STANDARDS EITHER NOT ENDORSED. E.G.. NOA-I 1986. OR NEVER REVIEWED BY NPC, E.G., ANSI /ANS-3 3 198X GSI 7S IS A SALEM ATWS ISSUE WITH TASKS SUBSUMED FROM TMI.
THE STAFF HAS CONCLUDED FROM AN EXAMINATION OF THE AS OF FY88 QUARTER 2 9 9 e
)
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RUN DATE: 05/11/88 l GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 23
} ISSUE NUMBER: 75 TITLE: GENERIC IMPLICATIONS OF ATWS EVENTS AT SALEM - QA AFFECTED DOCUMENTS PROBLEM / RESOLUTION
.--------------------------------------~~------ -----------------------------------------------------------.
SALEM ATWS TASK FORCE THAT ALL THE PERTINENT REQUIREMENIS AND GUIDANCE WERE IMPOSED ON OPERATING PLANTS BY NUREG-0737 AND GL 83-28. THEREFORE, THE STAFF IS WORKING ON THE MODIFICATION TO R.G. 1.33 REV. 2 TO MAKE THE PROVISIONS OF NUREG-0737 AND GL 83-28 APPLICABLE TO FUTURE REACTORS AS WELL AS THOSE CURRENTLY LICENSED. THIS WILL COMPLETE THE ACTIONS NECESSARY TO CLOSE OUT THIS GENERIC ISSUE AND WILL ALLOW THE STAFF TO APPROACH THE ENDORSEMENT OF QA RELATED REG GUIDES ON A SYSTEMATIC BASIS STARTING WITH NOA-2 WHICH IS AT THE MOST BASIC LEVEL.
ORIGINAL CURRENT ACTUAL l
MI LESTONES D%TE DATE DATE ISSUED MEMO TO EDO 07/84 --
07/84 SUBSUMING TMI ITEM I.B.1.1.
SUBTASKS 6 AND 7 ISSUE DRAFT R.G. 1.33 FOR DIVISION AND 02/85 --
02/85 REGION COMMENTS RE-ISSUE DRAFT R.G. 1.33 FOR DIVISION AND 01/86 --
02/86 REGION COMMENTS FINAL DRAFT REVISION OF ANS-3.2-1982 10/87 04/88 --
COMPLETED
, ISSUE DRAFT R.G. 1.33 FOR DIVISON 02/88 05/88 --
s AND REGION COMMENTS RESOLVE COMMENTS AND PREPARE 04/88 06/88 --
REGULATORY ANALYSIS PACKAGE FOR CRGR REVIEW CRGR REVIEW COMPLETED (29] 08/R8 08/88 --
} ACRS REVIEW COMPLETED 10/88 09/88 --
i 2 AS OF FY88 QUARTER 2 1
1 i
i
RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 24 ISSUE NUMBER: 75 TITLE GENERIC IMPLICATIONS OF ATWS EVENTS AT SALEM - OA ORIGINAL CURRENT ACTUAL M I LEST 0N E S DATE DATE DATE hhSbEFRNbN kVk Lkh LkTY bF 3hb 2/ h 0/hh --
PROPOSED R.G. 1 33 REV. 3 FOR COMMENT END OF 60-DAY PUBLIC COMMENT PERIOD 03/89 12/88 --
RESOLVE COMMENTS AND REVISE GUIDE 05/89 02/89 --
RE-ISSUE DRAFT R.G. 1.33 FOR 05/98 03/89 --
DIVISION AND REGION COMMENTS RESOLVE COMMENTS AND PREPARE 07/89 04/89 --
PACKAGE FOR CRGR REVIEW CRGR RE"IEW COMPLETED 153) 10/89 05/89 --
ACRS REVIEW COMPLETED 12/89 06/89 --
FINALIZE GUIDE 12/89 08/89 --
EDO APPROVAL 01/90 09/89 --
ISSUE FRN ON ISSUANCE AND 01/90 01/90 --
AVAILABILITY OF R G. 1.33 REV.3 ISSUE CLOSEOUT MEMO TO RES DIRECTOR 01/90 01/90 --
AS OF FY88 QUARTER 2 O O O
V" 'd -
v RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 25 ISSUE NUMBER: 79 TITLE- UNANALYZED RX VESSEL THERMAL STRESS DURING NATURAL CONVECT 73N COOLING IDENnIFICATION DATE: 06/83C PRIORITIZATION DATE. 07/83C TYPE: GSI PRIORITY: M TASK MANAGER: J. PAGE OFFICE / DIVISION / BRANCH: RES /DE /EIB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: RESOLUTION DATE- 08/88 WORK AUTHORIZATION: MEMO TO R.VOLLMER FROM H. DENTON DATED 7/25/83 NMR FY-84 OPERATING PLAN. (APPENDIX G),
FIN CONTRACTOR CONTRACT TITLE A3822 BNL UNANALYZED REACTOR VESSEL THERMAL STRESS W0R K SC0 PE l1) PWR NSSS WILL PROVIDE THERMAL-HYDRAULIC, HEAT [3) EIB WILL VERIFY ACCEPTABILITY OF STRESS ANALYSES.
CONDUCTION AND ASME III STRESS AN/: LYSIS OF THr EVALUATE RESULTS, AND DETERMINE RESOLUTION OF THE REACTOR VESSEL. ISSUE.
(2) BNL WILL VERIFY ACCEPTABILITY OF THERMAL ANALYSES.
STATUS CONTRACTOR IS PERFORMING THE REVIEW.
AFFECTED CJCUMENTS PROBLEM / RESOLUTION PbikkhkkbhkPhhhhbkkhhhhRhhkkhkkPbkhS$ hY Lkhhkkhbkhkh2hlkh8hkhh3hhh8h$kHkbhhhkkbTbR REQUESTED ADDITIONAL DETAILS TO COMPLETE THE REVIEW OF THE B&W ANALYSES (DOCUMENT NOS. 32-1151155-00 AND 77-1152846-00) WHICH WERE PROVIDED BY LETTER DATED 10/15/84 THIS REQUEST WAS TRANSMITTED TO THE B&W OWNERS GROUP (BWOG)
BY LETTER DATED 3/27/86. REQUESTED INFORMATION INCLUDED 12 REFERENCES. 4 0F WHICH WERE NOT RECEIVED IN EASILY REPRODUCIDLE FORM. ADDITIONAL HARD COPIES WERE RECEIVED FROM BWOG IN LATE JULY 198C AND FORWARDED TO THE CONTRACTOR.
DELAYS ENCOUNTERED IN OBTAINING NECESSARY REVIEW MATERIALS AND THE SUBSTANTIVE NATURE OF QUESTIONS GENERATED BY THE CONTRACTOR NECESSITATED THE ADDITION OF 1 MILESTONE AFTER THE COMPLETION OF THE CONTRACTOR AUDIT CALCS AND ALSO AS OF FY88 QUARTER 2
___ ___-___~_- - - - __ - ___ - _-_ _ ___ . - . _ _
RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 26 ISSUE NUMBER: 79 TITLE- UNANALYZED RX VESSEL THERMAL STRESS DURING NATURAL CONVECTION COOLING AFFECTED DOCUMENTS PROBLEM / RESOLUTION REQUIRED THAT THE SCHEDULE BE EXTENDED TO 4/88.
DURING THE 3RD QUARTER OF FY-87, ADDITIONAL DELAYS WERE ENCOUNIERED BY THE CONTRACTOR DUE TO DIVERSION OF ITS STAFF TO A HIGHER PRIORITY ISSUE FOR NRR. THE SHOREHAM CONTAINMENT FAILURE ANALYSIS (FIN A3772). THIS DELAY WAS COMPOUNDED BY COMPUTER MALFUNCTIONS RESULTING IN A 3-MONTH SLIPPAGE FOR THE COMPLETION OF THE AUDIT CALCULATIONS AND THE MEETING TO DISCUSS THE RESULTS WITH NRC, A 2-MONTH SLIPPAGE IN ISSUING THE RAI. AND A 3-MONTH SLIPPAGE OF 4 0F THE REMAINING 5 MILESTONES-. HOWEVER, THE FINAL MILESTONE REMAINED UNCHANGED (04/88)
DURING THE 4TH QUARTER OF 1987 A MEMO WAS ISSUED FROM G ARLOTTO TO F. MIRAGLIA DATED 7/28/87 REQUESTING THAT A MEETING BE ARRANGED WITH THE BWOG AS SOON AS POSSIBLE.
HOWEVER. DUE TO NUMEROUS DL PERSONNEL CHANGES. THE ATTACHED QUESTIONS WERE MISPLACED. THE TASK MANAGER SUPPLIED ADDITIONAL COPIES OF THE QUESTIONS TO DL ON 9/17/87 AND A
'AANSMITTAL WAS MADE TO BWOu ON 10/2/87. THESE DELAYS REQUIRED A 3-MONTH SLIPPAGE FOR ISSUING AN RAI/ MEETING REQUEST TO THE BWOG AND ALSO FOR THE REMAINING S MILESTONES.
DURING THE FIRST QUARTER OF FY-88, BWOG INFORMED DL THAT THEY WOULD BE AdLE TO SUPPORT A MEETING IN MID-JANUARY 1988 HOWEVER. HOLIDAY OUT-OF-COUNTRY ABSENCES BY TWO OF THE THREE COGNIZANT CONTRACTOR PERSONNEL PROHIBITED THIS AN ADDITIONAL COMPLICATION IS THAT ONE OF THESE PERSONS IS NO LONGER EMPLOYED BY THE CONTRACTOR. UPON HIS RETURN ON JANUARY 9. 1988 MEETJNG PLANS WERE COMPLETED. SINCE THE OTHER COGNIZANT CONTRACTOR PERSON DID NOT RETURN UNTIL 2/2/88 THE SCHEDULED MILESTONE FOR MEETING WITH THE BWOG.
AND SUBSEQUENT INTERIM MILESTONES. SLIPPED ONE MONTH. BNL WILL GENERATE PRELIMINARY TECHNICAL EVALUATION BASED ON INFORMATION PROVIDED AT 04/83 MEETING.
ORIGINAL CURRENT ACTUAL MI LEST0NE S DATE DATE DATE MEETING WITH B&W TO CLARIFY ISSUE 11/83 --
03/84 RECEIPT OF INITIAL B&W ANALYSES 08/84 --
12/84
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RUN DATE: 03/II/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGr: 23 ISSUE NUMBER: 82 (ITLE: BEYOND DESIGN BASES ACCIDENTS IN SPENT FUEL POOLS
~DENTIFICATION DATE: 08/83C PRIORITIZATION 9 ATE: 12/83C TYPE: GSI PRIORITY: M
's.SK MANAGER: E. THROM OFFICE / DIVISION / BRANCH: RES /DRPS/RPSI ACTION LEVEL: ACTIVE STATUS:
.AC NUMBERS: RESOLUTION DATE: 05/89 WORK AUTHORIZA'. ION: MEMO TO R. MAiTSON FROM H. DENTON DATED I2/7/83; NRP FY 84 OP PLAN ( APPE NDIX G)
FIN CONTRACTOR CONTRACT TITLE A08I4 LLNL EFFECTS OF BEYOND DSN BASIS EVENTS ON SPENT FUEL POOLS A3786 BNL STUDY BEYOND DESIGN BASES ACCIDENTS IN SPENT FUEL POOLS A3963 BNL ANAL. OF SPENT FUEL POOL STORAGE A: TERNATIVES W0R K SCU PE WbkK SCbPk kPPkbVkD hh h PI k bkE hEMb Fkbh NbbbNSkbERkh R. MATTSON TO T. SPEIS. DATED 2/2/84.1 THE RANGE OF FIXES WHICH APPEAR TECHNICALLY RESEARCH HAS VERIFIED THE POSSI3ILITY OF IGNITING FEASIBLE INCLUDE DELAYING STORAGE OF FRESH ASSEMBLIES.
ZIRCALOY CLADDING IN THE EVENT RELATIVELY FRESH SPENT OR THE PLACEMENT OF FRESH ASSEMBLIES ONLY NEAR OLDER FUEL IS UNCOVERED DUE TO POOL FAILURF. THE ONES. A NUREG/CR WILL BE PREPARED DESCRIBING SAFETY CIRCUMSTANCES OF IGNIsION AND PROPAGATION, AND THE ISSUES AND COST / BENEFIT ANALYSES ASSOCI4TED WITH CONSEQUENCES AND LIKELIHOCD OF A SEVERE SPENT FUEL POOL ALTERNATTV* FIXES. IF FIXES ARE WARRANTED, A REGULATORY ACCIDENT WILL BE ASSESSED. SHOULD THE RISX FROM SUCH AN REQUIREV ..(S PACKAGE WILL BE PREPARED FOR CRGR REVIEW ACCIDENT BE JUDGED UNACCEPTABLE ON A COST / BENEFIT BASIS. AND ISSUANCE.
THEN PREVENTIVE AND MITIGATING MEASURES MUST BE DEVISED STAT US
' NbRkb/bR-4982$"bkVkREkhbkbkhkbkhhPkhhFbklPbbLbkh khbbhbkhkkkbNWhH HkbbNbhbbkhbEhkVkLbkhkbb.kbbbhbkbkR SUPPORT OF GENE.IC ISSUE 82." WAS PUBLISHED 7/87. - A REGULATORY ANALYSIS WHICH JUSTIFIES NO ACTION (NO FRAGILITY ANALYSES ARE BEING PREFORMED BY LLNL, A BWR VALUE/ IMPACT PTUDY REQUIRED).
AND A PWR SPENT FUEL POOL WILL BE EVALUATED. LLNL WORK INDICATE 3 THAT THE SEISMIC MARGINS ARE ABOUT A RFP FOR A VALUE/ IMPACT ANALYSIS WAS SENT TO BNL ON THREE TIMES THE SSE. HIGH CONFIDENCE OF LOW PROBABILITY OF 9/25/87. AUTHORIZED 03/11/88. , FAILURE (HCLPF) VALUES OF 0.S TO 0.7 G. HOWEVER. COMBINED TAP WAS REVISED 8/87 TO REFLECT NEW NRC ?RG; 'ATION VITH SEISMIC HAZARD CURVES. ANNUAL FAILURE FREQUENCIES AND T/A WORK FOR VALUE/ IMPACT ANALYSIS. CONTAIN LARGE UNCERTAINTIES. THE MEAN VALUE FOR AN BNL AND LLNL WORK COMPLETED TO DATE INDICA ~C IHAT THE EXISTING POOL STRUCTURE IS ABOUT E-6 PER RY. MEDIAN VALUE LIKELIHOOD OF A POOL DRAINAGE EVENT MAY BE ACCEPTABLY LOW. E-8 PER RY.
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AS OF FY88 OUARTER 2
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, GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 29 l
ISSUE NUMBER: 82 TITLE: BEYOND DESIGN BASES ACCIDENTS IN SFfNT 1UEL POOLS AFFECTED DOCUMENTS PROBLEM / RESOLUTION SRP SECTIONS 9.1.2. 9.1.3 AND 15.7.4. PWR LICENSEE WITHDREW FROM COMMITTMENT TO PROVIDE PLANT REGULATORY GUIDE 1.25 AND STS DATA FOR TASM 6 FRt.GILITY STUDIES. WITH NRR ASSISTANCE.
ANOIHER LICENSEE HAS BEEN IDENTIFIED AND HAS COMMITTED TO PROVIDE DATA 2/88. THIS SLIPPED TASK 6 FROM 11/87 TO 3/88.
DELAY IN OBTAINING SEISMIC HAZARD CURVE FOR PWR FROM NRR HAS SLIPPED TASK 6 TO 4/88 (1 MONTH). NRR HAS EXPRESSED CONCERN WITH USE OF SHCS PRIOR TO THE COMPLETION OF THE PARALLEL EPRI/ UTILITY PROGRAM. 12/88. Mt" RECOMMENDS SHCS BE USED TO ADDRESS UNCERTAINTIES 'IN RISK, NOT QUANTITATIVE RISK (I E. MARGINS APPROACH). NRR MAY NGT ENDORSE SHCS PRIOR TO EPRI WORK. BUDGET DELAY HAS MOVLD BNL START DATE FROM 11/87 TO 1/88: BNL PROPOSAL FOR TASK 7 V/I STUDY BASED
. ON ONE STAFF MEMBER RESULTING IN PERIOD Or PERFORMANCE INCREASE FRCH S CALENDAR MONTHS TO 9 MONTHS. (RFP WAS BASED ON A MINIMUM OF TWO STAFF AVAILABLE). OVERALL SLIPPAGE 5 MONTHS. BNL HAS BEEN REQUESTED iO DETERMINE IF ADDITIONAL SIAFF RESOURCES COULD BE MADE AVAILABLE TO RECOUP 2 MONTHS FROM SLIPPAGE (1/88).
j 2/8/88 - DURING NORMAL MANUAL CHAPTER 1102 REVIEW OF A3963 NMSS MISUNDERSTANDS SOEW AND RECOMMENDS RES NOT FUND PROJECT. RES MEETING WITH NRR/NMSS 2/10/88. *"S MEETING
?
WITH DOE '/2/88 TO OBTAIN UPDATED SPENT FUEL INi NTORY DATA AND COORDINATE NRC EFFORTS WITH DOE EFFORT ON AT-REACTOR STORAGE COSTS. RES AMENDS SOEW AND AUTHORIZES WORK 3/11/88 i
OVERALL SCHEDULE SHOULD NOT CHANGE, HOWEVER. BNL START DATE
{ SLIPS FROM 1/88 TO 3/88.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE GSI 82 ASSIGNED TO DSI 12/83 --
12/83 i TENTATIVE AGREE. REACHED WITH RES TO INCLUDE 01/84 -- --
l A TASK TO DETERMINE WHETHER ZIRCALOY IGNITION i AND SOURCE TERM RELEASE ARE POSSIBLE 4
TAP APPROVED BY DSI DIRECTOR 02/84 --
02/84 RECEIVE RES CONTRACTORS
- ASSESSMENT 04/84 --
05/84 r l AS OF FY88 QUARTER 2 4
i f
- ~
RUN DATE: C5/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE 30 ISSUE NUMSER- 32 TITLE BEYOND DESIGN BASES ACr ~5 IN SPENT FUEL POOLS elGINAL CURRENT ACTUAL M I LES T 0NE S DATE DATE DATE RES CONTRACTORS
- ASSESSMENT SENT TO 05/84 --
05/84 DL, OST. DE AND DSI.CPB AND DSI ASB FOR REVIEW AND COMMENT COMPLETE PID FOR INCLUSION OF T/A 04/84 --
06/84 SUPPORT FOR G,I 82 IN FY-85 BUDGET ISSUE RFP 08/8t --
08/84 ISSUE T/A CONTRACT 09/84 --
11/84 COMPLETE TASKS 1 & 2A OF TAC AND RECEIVE CONT 04/85 --
05/85 PRELIMINARY ASSESSMENT OF LIMELIH000 AFD CONSEQUENCES OF LOSS OF POOL INTEGRITY PREPARE PRELIMINARY EXPANDED WORK -- --
11/85 SCOPE FOR RISK STUDY EVALUATE CONTRACT RESULTS/ -- --
11/85 DETERMINE WHETHER PROBABILITIES AND PHENOMENA WARRANT RISK STUDY TASK I - INITIATING EVENTS / FREQUENCIES -- --
08/86 TASK 2 - ZIRCALOY OXIDATION EVALUATION -- --
10/86 TASK 3 - CONSEQUENCES /RADIONUCLIDE -- --
02/87 INVENTORY TASK 4 - PRELIMINARY RISK PROFILE -- --
02/87 TASK 5 - EVALUATE ALTERNATIVES -- --
02/87 nUTHORIZE FRAGILITY STUDIES [LLNL) -- --
04/87 BNL NUREG/CR REPORT -- --
07/87 ISSUE RFP FOR TASK 7 09/87 --
09/87 AWARD TASK 7 T/A 11/87 --
03/88 A~ OF FY88 OUARTER 2 O O O
m RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 31 ISSUE NUMBER: 82 TITLE- BEYOND DESIGN BASES ACCIDENTS IN SPENT FUEL POOLS ORIGINAL CURRENT ACTUAL MILEST 0NES DATE DATE DATE TASK 6 - FRAGILITY STUDIES 11/87 04/88 --
DOE DRAFT REPORT ON AT-REACTOR SPENT FUEL 07/88 07/88 _-
STORAGE COSTS TASK 7 - VALUE/ IMPACT EVALUATION 06/R7 09/88 __
i DRAFT REG. ANAL. TO ACRS. TO CRGR AND 07/87 10/88 __
l OTHER OFFICES / DIVISIONS FOR COMMENT (29)
ISSUE CLOSEOUT MEMORANDUM IF NO 01/88 12/88 __
PUBLIC COMMENTS REQUIRED DRAFT REG. ANAL. FOR PUBLIC C0be4ENT 07/88 12/88 --
INCORPORATE PUBLIC COMMENTS 09/88 02/89 --
FINAL REPORT TO ACRS CRGR. OTHER 10/88 03/89 --
0FFICE/ DIVISIONS 153)
FINAL CLOSEOUT 12/88 05/89 --
l I
I AS OF FY88 QUARTER 2
l RUN DATE: 03/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 32 ISWJE NUMBER: 83 TITLE CONTROL ROOM HABITABILITY IDENTIFICATION DATE: 11/83C PRIORITIZATION DATE. 06/84C TYPE- GSI PRIORITY:
TASK MANAGER: C. FERRELL OFFICE / DIVISION /0 RANCH RES /DRAA/SAIB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS: RESOLUTION DATE- 04/90 WORK AUTHORIZATION: MEMO FOR H. DENTON FROM W DIRCKS, DATED 8/15/83 FIN CONTRACTOR CONTRACT TITLE A2328 ANL IN-PLANT REVIEWS ON CONTRCL ROOM HABITABILITY A2334 ANL IN-PLANT REVIEWS ON CONTPOL ROOM HABITABILITY W0R K SC0P E ASSESS ADEQUACY OF HABITABILITY CRITERIA. NRR REVIEW. OF ACRS CONCERN A FINAL REPORT WILL BE PREPARED PLANT SYSTEMS AND COMPONENTS. AND TESTING PROCEDURES SUMMARIZING RESULTS AND PROVIDING RECOMMENDATIONS.
RELATIVE TO CONTROL ROOM HABITABILITY. INCLUDING THOSE AREAS S TA T US A PROGRAM OF SURVEY VISITS TO A TOTAL OF 11 PLANTS WAS WITH ANTICIPATED ISSUANCE DATE OF 06/88. THE CONTRACTOR HAS INI T I A TED IN SE PTEMBER 1985. VISITS TO 11 OPERATING PLANTS INITI ATED WORK ON SOME OF THE OTHER ' ASKS OF THE CONTRACT HAVE BEEN COMPLETED. CONTRACTOR REPORT IS BEING WRITTEN WHICH WILL BE MONITORED BY RES.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION 10 CFR 50 APPENDIX A; 2.3.4.5.19.60 SRP 6.4 THE ORIGINAL TAP FOR GSI 83 CONTAINED A NUMBER OF 9 4 1 12.3 6.5.1. 23 2.2.1-2.2.3 18 9 5.1; SUBTASKS FOR IMPLEMENTATION OF THE RECOMMENDATIONS IN THE RGS 1 78, I 95 1.29 1.52. 1.101 1.140; NUREG-0737 JUNE 1984 CONTROL ROOM HABITABILITY [CRH) REPORT. WORK ON ITEM III D 3.4 II B 2. 10 CFR 50: 50 48. APPENDIX IMPLEMENTATION OF THESE RECOMMENDATIONS HAS BEEN HALTED DUE R TO 10 CFR 50; NUREG-0700 NUREG-0737 SUPPLEMENT I. TO MANAGEMENT CONCERNS OVER : (1) LACK OF RESOURCES TO PERFORM INDEPENDENT VERIFICATION OF ACCEPTABILITY OF APPLICANTS' SUBMITTALS AND DEGREE OF SAFETY GAIN TO BE ACHIEVED. (2) RELUCTANCE TO DEVOTE RESOURCES TO UPDATING SRP's AND PLANT ORDERS; AND (3) PERTINENT REG GUIDES IN lHE ABSENCE OF NEW IMPLEMENTATION RECDMMENDATIONS THAT MIGHT BE INTERPRETED AS BACKFITTING WITHOUT PROPER BACKFIT ANALYSIS AS OF FY88 QUARTE % 2 O O O
in
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% - '%d RUN DATE: 05/11/88 GENERIC ISSifE MANAGEMENT CONTROL SYSTEM PAGE: 33 ISSUE NUMBER: 83 TITLE: CONTROL ROOM HA8ITABILITY AFFECTED DOCUMENTS PROBLEM / RESOLUTION THE IMPLEMENTATION OF THE RECOMMENDATIONS IN THE JUNE 1984 REPORT WILL BE REEVALUATED IN LIGHT OF THE ABOVE CONCERNS. ADDITIONAL DELAY WAS ENCOUNTERED IN CONTRACTOR PROVIDING REPORT TO NRC. REPORT IS CURRENTLY BEING REVIEWED BY NRR.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE AWARD OF CONTRACT C2/84 --
01/84 VISIT TO INITIAL PLANT 03/84 --
05/84 REPORT ON CRH CRITERIA TO NRR DIRECTOR 06/84 --
06/84 COMPLETION OF CONTRACTOR VISITS TO 08/84 --
08/84 OPERATING AND NTOL PLANTS SDW 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 (S) 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 ISSUE REPORT (NUREG/CR) AND 01/87 06/88 --
( RECOMMENDATIONS l RES TO DEVELOP TAP BASED ON REEVALUATION 03/87 06/88 --
& PROVIDE MILESTONES INCL. INITIAL WORK ON GENERIC STATUS l
AS OF FY88 QUARTER 2 l
l l
, _ _ _ _ - _ _ ~ . . . .
> RUN DATE: 05/11/88 GENERIC ISSUE MANAGE t4 N T CONTROL SYSTEM PAGE: 34 ISSUE NUMBER: 83 TITLE- CON TROL RLs3M HABIT ABILITY l
ORIGINAL CURRENT ACTUAL
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RUM DATE: 05/II/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 3S ISSUE NUMBER: 84 TITLE: CE PORVS IDENTIFICATION DATE: 11/83C PRIORITIZATION DATE: 02/85C TYPE: GSI PRIORITY:
TASK MANAGER: H. WOODS OF F ICE / DIVI
RESOLUTION DATE: -
WORK AUTHORIZATION: MEMO TO R. BERNERO FR0ti H DENTON DATED 2/27/85 FIN CONTRACTOR CONTRACT TITLE W0R K SC0PE STATUS AWAITING FINAL RESOLUTION OF USI A-45 WITH RESPECT TO FIRST OUARTER FY-88.
POAV REQUIREMENTS. ISSUE TRANSFERRED FROM NRR TO RES DURING AFFECTED DOCUMENTS PROBLEM / RESOLUTION USI A-45 WORK, ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE DEVELOP TAP AFTER RESOLUTION Of USI A-45 '480 TED .-
AS OF FY85 QUARTER 2'
- - - - - _ - _ - - _ - - --- - - * - - -, u &
CUN DATE: C5/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 36 ISSUE NUMBER: 86 TITLE- *ONG RANGE PLAN DEALING WITH STRESS CORROSION CPACKING IN BWR PIPING IDENTIFICATION DATE: 12/83C PRIORITIZATION DATE 10/84C TYPE: GSI PRIORITY.
TASK MANAGER. W. KOO OFFICE / DIVISION / BRANCH NRR / DEST /EMTB ACTION LEVEL: INACTIVE STATUS: 3A TAC NUMBERS: RESOLUTION DATE 01/88C WORK AUTHORIZATION: MEMO TO R VOLLMER FROM H DENTON DATED 10/3/84 FIN CONTRACTOR CONTRACT TITLE WOR K SC0PE lbNb k hbk PL kFbkbkkLkkbhkkhPkPhhkkhkkkbkb h kkhbf bbkkb bhkh RkV 2 CONT AINE D IN SECY-84-301. JULY 1984- 13] ISSUE GENERIC LETTER INCORPORATING NUREG-0313 REV 2 (1) ISSUE NUREG-1061. VOL. 1 FOR COMMENT 14) PURSUE ASME CODE CHANGES ST A T US
-..........------- ..------...-------------------- ----- -- ------------~~--------.----------------------------------
GENERIC LETTER 88-01 AND ITS TECHNICAL BASIS DOCUMENT REACTOR LICENSEES AND CONSTRUCTION PERMIT HOLDERS IN NUREG 0313 REV. 2 WAS ISSUED TO ALL BWR OPERATING JANUARY 1988.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION NUREG-0313 REV. 1 NONE.
ORIGINAL CURRENT ACYUAL MILEST0NES DATE DATE DATE SECY 84-301, NUREG-1061 TO COMMISSION 07/84 --
07/84 PUBLISH NUREG-1061 VOL. I 09/84 --
09/84 END OF COMMENT PERIOD 11/84 --
11/84 AS OF FY88 QUARTER 2 O O O
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 37 ISSUE NUMBER: 86 TITLE: LONG RANGE PLAN DEALING WITH STRESS CORROSION CRACKING IN BWR PIPING ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE bbMPLhhhPkEPkkkhhbNbhbkkhh bl/8h --
b9/kh NUREG-0313. REV. 2 PROPOSED GL AND STAFF 09/85 --
02/85 POSITION IN DRAFT NUREG 0313 REV. 2 CIRCULATED FOR NRR DIV. SIR REVIEW PROPOSED GL AND STAFF POSITION IN DRAFT 10/85 --
04/86 NUREG-0313 REV. 2 REVIEWED AND ENDORSED BY CRGR (291 DRAFT NUREG-0313 REV. 2 AND GL 11/85 --
07/86 ISSUED FOR PUBLIC COMMENT DRAFT MUREG-0313. REV. 2 REVISED 02/86 --
05/87 TO REFLECT PUBLIC COMMENTS COMMISSION PAPER ON STAFF IMPLEMENTATION 03/86 --
06/87 plt.N AND STAFF POSITION (NUREG-0313 REV 21 REVIEWED AND ENDORSED BY CRGR (53)
COMMISSION PAPER ON STAFF IMPLEMENTATION PLAN 04/86 --
09/87 AND STAFF POSITION (NUREG-0313. REV.2)
SUBMITTED FOR APPROVAL PUBLISH NUREG-0313. REV. 2 05/86 --
01/88 ISSUE GL 88-01 05/86 --
01/88 AS OF FY88 QUARTER 2 8 e - -_
RUN DATE: 09/11/88 GENERIC ISSUE MANAGEMENT CONVROL SYSTEM DCGE: 38 ISSUE NUMBER- 47 TITLE- FAILURE OF HPCI STEAM LINE WITHOUT ISOLATION IDENTIFICATION DATE: 01/84C PRIORITIZATION DATE- 09/85C TYPE: GSi PRIORITY- H TASK MANAGER: R. WOODS OFFICE / DIVISION / BRANCH RES /DRPS/RPSI ACTION LEVEL: ACTIVE STATUS-TAC NUMBERS; RESOLUTION DATE 12/90 WORK AUTHORIZATION: MEMO TO R. BERNEPO FROM H. DENTON DATED 9/26/85 FIN CONTRACTOR CONTRACT TITLE NONE NONE NONE W 0R K SC0PE bkkkRhkNkkVPkkhbkZkb/hbbkLbbFVkLVEbkkhbtVkbkN bPhN PbbkD bkbVRbNM N BYb hkS HPCI. RCIC, RWCU [AND ANY OTHER) SYSTEMS WHERE VALVES OUALIFICATIONI DETERMINE CONSEQUENCES AND PISK DUE HIGHT NOT BE QUALIFIED TO CLOSE IN THE EVENT OF A TO FAILURE OF HIGH ENERGY LINE ISOLATION VALVES TO DOWNSTREAM BREAK AND WOULD CAUSE AN UNACCE PI ABLE CLOSE DEVELOF NEW LICENSING CRITERIA TO REDUCE RISK HIGH RISK OF CORE-MELT IF BREAK NOT ISOLATED (DUE TO AN ACL!PTABLE LEVEL. IF NEEDED.
TO INVENs0RY LOSS AND/OR OTHER SAFETY-RELATED STA TUS "LICENSING NEED LETTER SENT 3/11/86 TO R. MINOGUE FROM TWO REPRESENTATIVE VALVES IN THE RWCU SYSTEM. THESE WATER H DrNTON IDENTIFICATION OF VALVES /0PERATORS IN THE HPCI FLOW TESTS WILL BE CONDUCTED AT WYLE LABS IN HUNTSVILLE.
AND RCIC THE RES/DI/EFEB CONTRACTOR (INELI IS PLANNING ALABAMA VALVE-CLOSURE-DURING-F LOW TESTS AT FULL F LOW CONDI T IONS F OR AFFECTED DOCUMENTS PROBLEM / RESOLUTION IEB 85-03 POSSIBLE SUPPLEMENT. POSSIBLE GENEkIC LETTER SCHEDULE REFLECTS SLIPPAGE OF ONE YEAR TO ACCOMMODATE UNDER GSI II.E.6.I STEAM TESTS LIKELY TO BE NEEDED IN ADDITION TO THE SCHFDULED WATER TESTS PREVIOUS CONSIDERATION OF PERFORMING ALL TESTS AT ONCE ARE NOT POSSI3LE WITHIN THE BUDGET AND WOULD NOT BE AN EFFICIENT USE OF RESOURCES. AN ADDITIONAL FOUR MONTHS HAVE ALSO BEEN ADDED TO THE SCHEDULE TO ACCOMMODATE THE MOST RECENT INEL VALVE TESTING PROGRAM SCHEDULE . THIS ADDED F OUR MONTHS IS NEEDED TO ASSESS DATA BASE AND TRANSLATE TO A REGULATORY ANALYSIS.
AS OF FY88 QUARTER 2 O O O
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 39 ISSUE NUMBER: 87 TITLE: FAILURE OF HPCI STEAM LINE WITHOUT ISOLATION
, ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATL DATE SEND LICENSING NEED LETTER TO RES 03/86 --
03/86 RECEIVE REPLY 04/86 --
04/86 RECEIVE RES CONTRACTOR R E I'OR T 06/86 --
06/86 IDENf!FYING VALVES ,
MEET WITH RES CONTRACTOR TO 07/86 --
07/86 DETERMINE NEXT PHASE OF PROGRAM RES CONTRACT 0F RECEIVES VALVE 09/86 --
10/86 OUALIFICATION DATA FROM SELECTED LICENSEES RIS CONTRACTOR MAKES RECOMMENDATION 11/86 --
11/86 FOR NEXT PHASE OF PROGRAM DEVZLOP TAP TO CARRY OUT RECOMMENDATION 12/86 --
08/87 MIET WITH INEL TO FINALIZE 04/87 --
04/87 VALVE TESTING PROGRAM VALVE TESTING PROGRAM SUBMITTED BY INEL 07/87 --
10/87 CDNPLETE VALVE TESTING BY INEL 03/89 03/89 --
j CRGR PACKAGE (IMCLUDING REG. ANALYSIS) 10/87 08/89 --
SIGNED BY DIV. DIRECTOR CRGR PACKAGE TO RES DIRECTOR 12/87 10/89 --
PACKAGE TO ACRS AND CRGR 01/88 11/89 --
(29.53)
ISSUE GL OR IEB-85-03 06/88 12/90 --
SUPPLEME NT 4
AS OF FY88 OUARTER 2
CUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 40 ISSUE NUMBER: 93 TITLE STFAM BINDING OF AFW PUMPS IDENTIFICATTON DATE: 07/84C PRIORITIZATION DATE 10/84C TYPE. GSI PRIORITY: H TASK MANAGER: A. SPANO OFFICE / DIVISION / BRANCH RES /DRPS/RPSI ACTION LEVEL: INACTIVE STATUS: 3B TAC NUMBERS: RESOLUTION DATE- 02/88C WORK AUTHORIZATION: MEMO TO R. BERNERO FROM d DENTON DATED 10/19/84 FIN CONTRACTOR CONTRACT TITLE NONE NONE NONE W0R K SC0PE GENERIC PREVENTIVE MAINTENANCE 04 MONITORING LICENSING. ETC FOR RESOLVING THE IDENTIFIED CONCERNS MEASURES MAY HAVE Tfj BE IMPLEMENTED AT ALL PWR$ ?O EVALUATE PLAN 1-SPECIFIC INFORMATION OBTAINED FROM REDUCE THE POTENTIAL FOR BACKLEAKAGE OF STEAM AND HOT NRC TI-2515/67 AND IEB 85-01 WATER TO THE AFW SYSTEM FROM THE STE AM CONVERSION SYSTEM CONCERNING ACTIONS TAKEN BY INDIVIDUAL LICENSEES VIA ISOLATION VALVES IN THE AFW SYSTEM IT IS EXPECTED RELATING IO SURVEILLANCE PROGRAMS FOR MONITORING THE THAT THESE MEASURES WILL REDUCE IHE LIKELIHOOD OF ATW SYSTEM FLUID CONDITIONS AND CORRECTIVE OPERATOR STEAM BINDING OF THE AFW PUMP (S) AND POSSIBLE COMMON ACTIONS FOR RESTORING POTENTIAL STEAM BOUND AFW PUMPS PODE FAILURE OF THE AFW SYSTEM BY ENSURING THAT THE TO OPERABLE STATUS-VALVES PERFORM THEIR INTENDED FUNCTION BASED ON THE RESULT OF IEB 85-01. DEVELOP SOLICIT RECOMMENDATIONS FROM INTERESTED INTERAGENCY ADDITIONAL AND/OR ALTERNATIVE GENERIC OR PLANT STxFF SUCH AS RESIDENT I NS PE C T OR S . OEAB STAFF IN NRR. SPECIFIC MODIFICATION
S. PROCEDURE
S. AND REVISIONS TO ENGINEERING AND PLANT SYSTEMS STAFF IN THE DIVISIONS OF PLANT TS AS NECESSARY.
STA TUS FOLLOWING CRGR REVIEW, GENERIC LETTER 88-03 RESOLUTION THIS CLOSES OUT GENERIC ISSUE 93.
OF GENERIC SAFETY ISSUE 93. WAS ISSUED ON 02/17/88 AFFECTED DOCUMENTS PROBLEM / RESOLUTION LICENSEE F SAR ' S AWAITING NRR ISSUANCE OF GL TO CLOSE OUT THE ISSUE AS OF FY88 QUARTER 2 O O O
.- _ - -=
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ISSUE NUMBER: 93 TITLE: STEAM BINDING OF AFW PUMPS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE kbhbkIkh5bMEbTbbbk kbhh4 --
[bhh4 PREPARE DRAFT TAP 12/84 --
12/84 1
DRAFT TAP APPROVED BY DSI DIRECTOR 12/84 --
01/85 INCORPORATE COMMENTS BY VARIOUS 02/85 --
06/85 DIVISIONS REVISE AND REISSUE APPROVED TAP 07/85 --
06/85 j
. - NRR EVALUATION OF PLANT-SPECIFIC RESPONSE 04/86 --
06/86 TO IEB 85-01 EVALUATION OF IMPACT OF NSSS OWNERS GROUP 10/86 --
11/86 i
CHECK VALVE PROGRAM AS RELATED TO GSI 93
. CONCERNS IDENTIFY GENERIC OR PLANT-SPECIFIC PREVENTIVE 04/86 --
12/86 MAINTENANCE MEASURES. SURVEILLANCE l REQUIREMENTS AND CORRECTIVE ACTIONS EVALUATION OF STEAM BINDING CONTRIBUTION 07/86 --
01/87 3 TO AFW UNAVAILABILITY FOR REPRESENTATIVE I AFW PIPING CONFIGURATIONS i
i OBTAIN ADDITIONAL PLANT-SPECIFIC DATA ON 08/86 --
01/87 j MONITORING PROCEDURES ANALYSIS OF EFFECT OF CONTINUOUS MONITORING / 11/86 --
01/87
- CONTROL ROOM ALARM ON ESTIMATED AFWS A RELIABILITY i PREPARE INITIAt DRAFT OF VALUE/ IMPACT 12/86 --
02/87 l STATEMENT REG ANALYSIS APPROVED BY DRPS 07/86 --
05/87 1
DIRECTOR AND SENT TO RES DIRECIOR J
i FINAL RESOLUTION APPROVED 06/87 --
05/87 '
!. BY RES i -
AS OF FY88 QUARTER 2
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RUN DATE: 05/11/88 GEWERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 42 l
l ISSUE NUMBER: 93 TITLE- STEAM BINDING OF AFW PUMPS 4
I i CRIGINAL CURRENT ACTUAL
, MI LE S TONE S DATE DATE DATE j
- NRR CONCURS WITH FINAL RESOLUTION 06/87 --
06/87 i
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\d RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 43 ISSUE NUMBER: 94 TITLE: ADDITIONAL LOW-TEMP. OVERPRESSURE PROTECTION FOR LWRS IDENTIFICATION DATE: 08/84C PRIORITIZATION DATE- 07/85C TYPE: GSI PRIORITY: H TASK MANAGER: E. THROM OFFICE / DIVISION / BRANCH: RES /DRPS/RPSI ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: RESOLUTION DATE- 12/88 WORK AUTHORIZATION: MEMO TO R. BERNERO FROM H DENTON DATED 7/23/85.
FIN CONTRACTOR CONTRACT TITLE B2238 PNL LDW IEMP OVERPRESS PROT SYS EVAL FOR PWRS WORK SC0PE EVALUATE CURRENT OPERATING DATA. APPLYING STS SOLID. LIMITING START OF THE. REACTOR COOLANT PUMP. USING TO ALL SYSTEMS. UPDATING LTOP SET-POINTS TO CURRENT RHR RELIEF VALVES. REQUIRING THE LTOP TO BE "SAFETY-APPENDIX G CURVES. PROHIBITING OPERATION WITH EITHER LTOP GRADE" AND VALUE/ IMPACT OF THESE ALTERNATIVES.
TRAIN OUT OF SERVICE OR HPI PUMP IN SERVICE WHILE WATER STA TUS A REVIEW OF LER DATA. AND RECENT MEETING WITH TAP REVISED 8/87 TO REFLECT NEW NRR ORGANIZATION.
OWNERS
- GROUPS INDICATED THAT LICENSEES A'AE AWARE OF THE TASK 4 THROUGH 7 AND THE TASK 11 VISA CALCULATIONS NEED TO UPDATE LTOP SE T-POINTS TO ACCOl'4T FOR SHIFT IN REASSIGNED TO PNL. REQUEST FOR MODIFIED 189 ON 8/25/87, ,
APFINDIX G CURVES DUE TO VESSEL EMBRIr LEMENT. a AND AUTHORIZED 2/10/88. 1 REVISION 2 TO REG. GUIDE 1.99.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION
_--.--- ..-_---.-r----_-_----__ ._-_-_--_ --.-----.-_-_----- ....-....---------------.---------....----....-_--....-.....
SRP 5.2.2, BTP 5-2. STS I/19/88 MILLSTONE 3 LER-28-005 - BOTH PORVS AND BOTH RHR SRV'S UNAVAILABLE TO MITIGATE OVERPRESSURE EVENT.
OPERATING EXPERIENCE FOR 1987 AND THIS EVENT WERE REVIEWED BY CONTRACTOR TO DETERMINE IMPACT ON PREVIOUSLY COMPLETED WORK. COMPLETION OF TASK 10 AND 12 DELAYED SLIGHTLY TO 4/88. NET IMPACT OF UPDATING PREVIOUSLY COMPLETED ANALYSES WOULD BE ABOUT 10% DECREASE IN OVERALL RISK DUE TO LARGE NUMBER OF ACCUMULATED RYS EXPERIENCE WITH NO ADDITIONAL SIGNIFICANT EVENTS.
AS OF FY88 QUARTER 2
CUN DATE: 03/11/88 GENEDIC ISSUE MANAGFMENT CONTROL SYSTEM PACE: 44 ISSUE NUMBER: 94 T I T Lt_ . ADDITIONAL LOW-TEMP OVERPRESSURE PROTECTION FOR LWRS ORIGINAL CURRENT ACTUAL M I LE ST ON E S DATE DATE DATE GSI 94 ASSIGNED TO 07/85 --
07/85 RSB/DSI/NRR DRAFT OF TAP COMPLETED 11/85 --
05/86 FINAL TAP APPROVED BY DSRO DIRECTOR 02/86 --
06/86 ISSUE RFP 06/8E --
06/86 AWARD T/A CONTRACT 11/86 --
12/86 TASK - 1 UPDATE OPERATING DATA 11/86 --
12/86 D.TERMINE IF REGULATORY ANALYSIS FOR 01/87 --
02/87 TASKS 4 AND 5 SHOULD BE PERFORMED TASK 2 - CDiLATE PLANT DATA 03/87 --
04/87 TASK 3 - UPGRADE TO CURRENT STS 03/86 --
06/87 CSI-99 CONTRACTOR REPORT DUE 02/87 --
07/87 YASK 4 - LTOP SET-POINTS (APPENDIX G) 03/87 --
02/88 TASK 5 - STS FOR BOTH LTOP CHANNELS 04/87 --
02/88 TASK 6 - UPDATE SI STS REQUIREME N T S IF 04/87 --
02/88 STS DEFICIENT TASK 7 - UPDATE RCS TS REQUIREMENTS IF 04/87 --
02/88 STS DEFICIENT TASK S - EVALUATION OF E.!R MCDIFICATIONS 63/86 --
03/88 TASK 9 - PERFORMANCE EVALUATION FOR RHR 06/87 --
03/88 MODIFICATIONS TASK 11 - CORE-MELT FREQUENCY REDUCTION 09/97 --
03/88 YASK 10 - PERFORMANCE EVALUATION OF 06/86 04/88 --
SAFETY GRADE LTOP AS OF FY88 OUARTER 2 O -
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 45 ISSUE NUMBER: 94 TITLE: ADDITIONAL LOW-TEMP. OVERPRES$URE PROTECTION FOR LWRS ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE TASK 12 - VALUE/ IMPACT EVALUATION 12/87 04/88 --
DRAFT REG. ANAL. PREPARED. TO ACRS. TO 05/86 05/88 --
CRGR AND TO OTHER OFFICES / DIVISIONS FOR COMMENTS (29)
ISSUE CLOSEOUT MEMORANDUM IF NO 10/86 07/88 --
PUBLIC COMMENTS REQUIRED DRAFT REG. ANAL. FOR PUBLIC COMMENT 07/88 07/88 --
INCORPORATE PUBLIC COMMENTS 09/88 09/88 --
FINAL RESPONSE TO ACRS, CRGR, 10/88 10/88 --
OTHER OFFICES / DIVISIONS (53)
FINAL CLOSEOUT 12/88 12/88 --
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CUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE- 46 ISSUE NUMBFA: 99 TITLE: RCS/RHR SUCTION LINE INTERLOCKS ON PWRS IDENTif!LrtION DATE: 09/84C PRIORITIZATION DATE 08/85C TYPE: GSI PRIORITY. H TASK MANAGi< A. SPANO OFFICE / DIVISION / BRANCH RES /ORPS/RPSI ACTIOri LEVEL - ACTIVE STATUS.
TAC NUMBERS RES0tOTION DATE 08/88 WORK AUTHORIZATION: MEMO TO R. BERNERO FROM H. DENTON DATED 8/13/85 FIN CONTRACTOR CONTRACT TITLE A3849 BNL IMPROVED RELIABILITY OF RHR CAPAFILITY IN PWRS W0R K SC0PE OPERATING EXPERIENCE SHOWS THAT A CHANGE IN THE TO QUANTIF Y THE COST-BENEFIT ASPECTS OF- (A) REPLACING AUTOCLOSURE FEATURE OF THE RCS/RHRS ISOLATION VALVE THE EXISTING AUTOCLOSURE INTERLDCn BY ONE THAT INTERLOCKS IS NEEDED TO ELIMINATE A LEADING CAUSE OF FULFILLS ITS DESIGN BASIS SAFETY FUNCTION WHILE THE LOSS OF RESIDUAL HEAT REMOVAL DURING PLANT OUTAGE RED. THE PROBAB 0F FAILURE OF THE RHR SAFETY FUNCTICN, OPERATIONS. ADDITIONAL LOSS-OF-RHR EVENTS HAVE (31 IMPROVING THE RELIABILITY OF PROCEDURES AND RESULTED FROM INADEQUACIES IN THE RCS WATER LEVEL MONITORING DURING DRAINEO RCS OPERATIONS. (Cl ME ASUREMENT AND RELATED MONITORING BY THE OPERATOR IMPROVING RELIABILITY OF OPERATOR MONITORING AND AS WELL AS BY OTHER HUMAN ERROR RELATED INADEQUACIES MITIGATION OF LOSS OF RHR FLOW CONDITIONS, AND (D)
IN PLANT GUTAGE PROCEDURES. TRAINING AND IMPROVING THE RELIABILITY OF APPROPRIATE ADMINISTRATIVE CONTROLS ADMINISTRATIVE CONTROL AND OPERATOR PR GCEDURES THE SCOPE OF THIS TASK AS DEFINED IN 2/36 IS RELATED TO COLD SHUTDOWN OPERATIONS.
STA TUS PURSUANT TO THE DIABLO CANYON-2 LOS -OF- INFORMATION IMPORTANT TO THE RESOLUTION OF GSI $9.
RHR EVENT OF 4/10/81, NRC'S ISSUANCE OF A 50 SAF REVIEW OF RESPONSES INITIATED.
LETTER WILL PROVIDE A LARGE BASE OF PLANT-SPECIFIC AFFECTED DOCUMENTS PROBLEM / RESOLUTION NONE REPORT SUBMITTED ON SCHEDULE (1/88) BUT ADDRESSING ADDITIONAL NRC COMMENTS ON THE REPORT DELAYED ISSUANCE OF THE REPORT BY ABOUT 3 MONTHS WITH MINOR IMPACT ON THE FINAL COMPLETION DATES. THE MILESTONE REGAPDING THE PROPOSED NRR - INDUSTRY MEETING ON MID-LOOP ISSUES HAS BEEN AS OF FY88 CUARTER 2 O O O
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 47 ISSUE NUMBER: 99 TITLE: RCS/RHR SUCTION LINE INTERLOCKS ON PWRS AFFECTED DOCUMENTS PROBLEM / RESOLUTION DROPPED DUE TO UNCERTAINTY IN SCHEDULING. ALSO. THE MILESTONE ON REVIEW OF INDUSTRY PROGRAMS HAS BEEN DROPPED DUE TO UNCERTAINTY IN THEIR STATUS. BOTH MILESTONES WILL NOT SIGNIFICANTLY IMPACT THE COMPLETION SCHEDULE.
, ORIGINAL CURRENT ACTUAL
! MILESTONES DATE DATE DATE bhhh9khhbNEbTbhhhhbbkhNhh -
08h8h 4 - PRELIMINARY DISCUSSION OF WORK PLAN WITH BNL 02/86 --
04/86 DRAFT BNL WORK PLAN 03/86 --
05/86 FINAL BNL WORK PLAN APPROVED 04/86 --
05/86 ISSUE CONTRACT TO BNL 05/86 --
06/86 IDENTIFY ALTERNATIVE PATHS FOR RESOLUTION 08/86 --
10/86 0F IDENTIFIED CONCERNS (BASED ON INPO.
EPRI. AEOD AND OTHER STAFF RECOMMENDATIONS)
PRELIMINARY DISCUSSION WITH BNL ON 09/86 --
10/86
- MODIFICATION OF CONTRACT WORK PLAN TO ACCOMODATE EXPANDED SCOPE 1 FINAL BNL CONTRACT MODIFICATION APPROVED 11/86 --
11/86 DRAFT REPORT FROM BNL 03/87 --
03/87 REVISED DRAFT REPORT FROM BNL 06/87 --
07/87 NRC ISSUANCE OF 50.54F LETTER WITH 06/87 --
07/87 60-DAY RESPONSE TIME INITIATE REVIEW OF 50.54F RESPONSES 09/87 --
10/87 a
FINAL REPORT FROM BNL ?.N ACCORDANCE 04/87 04/88 --
l WITH EXPANDED WORK SCOPE i
AS OF FYE8 QUARTER 2 l'
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CUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 48 ISSUE NUMBER: 09 TITLE: RCS/RHR SUCTION LINE INTERLOCKS ON PWR$
ORIGINAL CURRENT ACTUAL MILEST 0N ES DATE DATE DATE PREPARE INITIAL PHASE OF REGULATORY ANALYSIS 09/86 --
J3/88 (STATEMENT OF PROBLEM. PROPOSED LICENSEE ACTIONS AND ALTERNATIVES)
INCORPORATE 50 54F INFORMATION AS PART OF 10/87 04/88 --
REGULATORY ANALYSIS INTERNAL DRPS REVIEW OF DRAFT CPGR PACKAGE 11/87 05/88 --
FINAL REPORT PREPARED /CRGR PACKAGE APPROVED 10/87 06/88 --
BY DRPS DIRECTOR AND SENT TO OTHER DIVISIONS FOR COMMENT COMMENTS FROM OTHER DIVISIONS / PACKAGE 01/88 06/88 --
SENT TO RES DIRECTOR PACKAGE SENT TO CRGR (29, 53) 08/87 07/88 --
ISSUE CLOSE00T MEMO 10/87 08/88 __
AS OF FY88 OUARTER 2 O O O
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 49 ISSUE NUMBER: 101 TITLE BREAK PLUS SINGLE FAILURE IN BWR WATER LEVEL INSTRUMENTATION IDENTIFICATION DATE: 09/84C PRIORITIZAiION DATE: 05/85C TYPE: GSI PRIORITY: H TASK MANAGER: A. SZUKIEWICZ OFFICE / DIVISION /BRANLH- RES /DE /EIB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: RESOLUTION DATE: 03/90 WORK AUTHORIZATION: MEMO TO R. BERNERO FROM H. DENTON DATED 5/6/85.
FIN CONTRACTOR CONTRACT TITLE D6020 INEL BWR WATER LEVEL REDUNDANCY W0R K SC0PE PERFORM A DETAILED SURVEY OF ALL BWR PLANTS TO DETERMINE WOULD HAVE PROBLEM WITH EXISTING WATER LEVEL TYPES OF WATER LEVEL INSTRUMENTATION. COMPILE FAILURE INSTRUMENTATION WHEN SUBJECTED TO AN INSTRUMENT LINE DATA FROM LER*S OF INSTRUMENT PIPING LEAKS / BREAKS AND BR[AK AND AN ADDITIONAL SINGLE FAILURE. EVALUATE RISK INSTRUMENT JAILURES FOR ALL BWR PLANTS. PE RF ORM REDUCTION AND COSTS OF VARIOUS FIXES AND PERFORM A SIMPLIFIED RISK ANALYSES POSTULATING INSTRUMENT PIPING VALUE/ IMPACT ANALYSIS. MAKE RECOMMENDATIONS TO RESOLVE LEAKS. SINGLE FAILURE IN INSTRUMENTS AND FEED WATER THIS ISSUE.
CONTROL SYSTEN FAILURE TO DETERMINE WHICH BWR PLANTS STA T US INEL PROPOSAL FOR T/A ON THIS PROJECT WAS ACCEPTED ON ARE CURRENTLY BEING ADDRESSED BY THE CONTRACTOR. THE 11/29/85 AND WORK BEGAN CN 3/1/86. A DRAFT TECHNICAL RESOLUTION OF THE COMMENTS WILL BE INCORPORATED IN THE EVALUATION REPORT WAS RESUBMITTED FOR REVIEW IN DEC. 1987. FINAL REPORT. THE REPORT INCLUDES THE TECHNICAL FINDINGS THE REPORT WAS REVIEWED BY THE STAFF. STAFF COMMENTS (PART I) AND THE REGULATORY ANALYSIS (PART II),
AFFECTED DOCUMENTS PROBLEM / RESOLUTION ;
DRAFT REPORT: GENERIC ISSUE 101 BOILING WATER REACTOR NONE LEVEL SENSING LINE BREAK AND N0ZZLE FAILURE DATED. DEC.
1987. -
AS OF FY88 QU#RTER 2 4
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RUN DATE: 05/11/8R GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 50 ISSUE NUMBER 101 TITLE- BREAK PLUS SINGLE FAILURE IN BWR WATER LEVEL INSTRUMENTATION ORIGINAL CURRENT ACTUAL M ILEST 0NE S DATE DATE DATE GSI-101 ASSIGNED TO RS8/DSI/NRR -- --
05/85 PRELIMINARY DISCUSSION OF WORK PLAN -- --
05/85 WITH INEL INEL PROVIDES PRELIMINARY COST 06/85 --
06/85 ESTIMATE OF WORK PLAN 3 DEVELOP WORK PLAN AND CONTRACT PROPOSAL 06/!5 --
07/85 DRAFT WORK PLAN TO DSI DIRECTOR 06/85 --
08/85 INCORPORATE COMMENTS INTO WORK PLAN 09/85 --
10/85 FINAL WORK PLAN APPROVED BY DSI DIRECTOR 09/85 --
10/85 AND FORWARDED TO DST ISSUE CONTRACT TO INEL 10/85 --
11/85 ASSEMBLE PLANT-SPECIFIC INSTRUMENTATICM 07/86 --
08/86 INFORMATION CATEGORIZE ALL BWRS INTO GROUPS 08/86 --
11/86 SINGLE FAILURE ANALYSIS 09/86 --
12/86 PROBABILISTIC RISK ASSESSMENT 10/86 --
03/87 VALUE/ IMPACT ANALYSIS 12/86 --
03/87 DRAFT REPORT FRDM INEL TO NRR 01/87 --
03/87 FINAL REPORT FRDM INEL TO NRR 03/87 --
12/87 DRAFT REGULATORY ANALYSIS 07/87 --
12/87 DTR ISSUED TO STAFF FOR TECHNICAL 04/88 04/88 --
R E VIEW / COMME NT S OTR PACKAGE ISSUED FOR DIVISION REVIEW 06/87 06/88 --
AND CONCURRENCE AS OF FY88 QUARTER 2 O O O
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ISSUE NUMBER: 101 TITLE: BREAK PLUS SINGLE FAILURE IN BWR WATER LEVEL INSTRUMENTATION I
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2 COMPLETED ISSUE DTR PACKAGE TO CRGR (29) 07/87 09/88 --
ACRS REVIEW OF DTR COMPLETED ,
02/88 11/88 --
' CRGR REVIEW COMPLETED 11/88 11/88 --
l 1 ;
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} COMMENT I REVISE RESOLUTION Pt.CKAGE TO 07/89 07/89 --
i REFLECT PUBLIC COMMENTS AND COMPLETE FINAL RESOLUTION PACKAGE.
f DIVISION DEPUTY DIRECTOR 08/89 08/89 ---
REVIEW COMPLETED CONCURRENCE SY OTHER 10/89 10/89 --
j l' OFFICES COMPLETE .
CRGR REVIEW OF FTR COMPLETED (53) 12/89 12/89 --
FRN OF ISSUANCE OF FTR 03/90 03/90 --
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l DUN DATE: 03/11/88 GENERIC ISSUE MANAGE MENT CONTROL SYSTEM PAGE: 52 ISSUE NUMBER- 102 TITLE: HUMAN ERROR IN EVENTS INVOLVING WRONG UNIT OR WRONG TRAIN IDENTIFICATION DATE: 09/84C PRIORITIZATION DATE O2/85C TYPE: GSI PRIORITY TT.SK MANAGER: R. FCKENRODE OF F ICE / DIVISION /BR ANCH NRR /DLPQ/LP[8 ACTION LEVEL. ACTIVE STATUS: NR TAC NUMBERS. M57269 RESOLUTION DATE. _-- -
WORK AUTHORIZATION: MEMO FOR R. BERNERO. ET Al FROM H DENTON DATED 2/13/35 FIN CONTRACTOR CONTRACT TITLE W0R K SC0PE IN JANUARY 1984 AEOD ISSUED A SPECI AL STUDY RE PORT THE MAINTENANCE AND SURVEILLANCE SECTION (HFMT)
DESCRIBING A NUMBER OF EVENTS THAT RESULTED FROM HUMAM ERROR IDENTIFIED EXISTING PRACTICES THAT MAY LEAD TO HUMAN ERRORS IN REMOVING EQUIPMENT FROM SERVICE OR R E S T OR I NG E QU I PME N T , INVOLVING WROMG UNIT / WRONG TRAIN AND RECOMMENDED FOLLOWING MAINTENANCE THAT INVOLVED WRONG UNIT OR WRONG IMPROVEMENTS THAT MAY BE APPROPRIATE. THE SCOPE OF THIS TRAIN OF EQUIPMENT BEING PENDERF.D UNAVAILABLE. ALTHOUGH THE PROJECT INCLUDED REVIEW OF OPERATING EXPERIE NCE . CO NC 'JC T ING SCOPE OF THE STUDY WAS NARROW, AEOD FOUND THAT 19 OUT OF 27 SITE VISI)S. INTERVIEWING LICENSEE PERSONNEL AT A SELECT EVENTS IDENTIFIED RESULTED F?OM HUMAN ERROR DURING NUMBER OF PLANTS TO DETERM'NE THE EXTENT AND NATURE OF LOSS MAINTENANCE AND SURVEILLANCE TESTING. AEOD CONSIDERED SUCH OF SAFETY FUNCTION RESULTING FROM ERRORS INVOLVING THE WRONG EVENTS TO BE EXAMPLES OF EVENTS THAT COULD HAVE HIGH SAFETY UNIT / WRONG TRAIN AND IDENTIFIED ACTIONS FOR RESOLUTION Of SIGNIFICANCE DUE TO POTENTIAL LOSS OF SAFETY SYSTEM THE GSI OR FOR FUPTHER INVESTIGATION.
FUNCTIONS.
STA T US A MEETING WITH THf INDUSTRY WAS HELD ON 8/I5/86 TO DIRECTION TO DEVELOP A POLICY STATEMENT ON MAINTENANCE-PRESENT NRC FIMDINGS AND RECOMMENDATIONS THE STAFF WILL FURTHER STAFF ACTION ON THIC ISSUE WILL BE ADDRESSED EVAlbATE INDUSTRY INITIATIVES AS A RESULT OF STUDY. IE FOLLOWING COMMISSION ACPROVal 0F THE POLICY STATEMENT ON INFORMATION NOTICE NO 87-25 ISSUED 9N 6/11/87 MAINTENANCE.
RESOLUTION OF THIS ITEM WAS INCORPORATED INTO STAFF NRR JNTENDS TO TRANSFER THIS ISSUE TO RES CONSISTENT EFFORTS ON HF-8, MAINTENANCE AND SURVEILLANCE PROGRAM. Hf-8 WITH COMMISSION DF. CISION TO DEVELOP A RULE ON MAINTENANCES IS CURRENTLY BEING REVISED TO ADDRESS JHE COMMISSION (SEE ISSUE HF8)
As nF FY88 CUARTER 2 O O O
_____....m.. ._m._.-..-.._.._ ___ _.....____... - =- ._.m._.. . ._m_ _..... ._ . _ _ __._. . . . _ - . _ . . . . ._
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L ISSUE NUMBER: 102 TITLE: HUMAN ERROR IN EVENTS INVOLVING WRONG t, NIT OR WRONG T2AIN t
i AFFECTED DOCUMENTS PROBLEM / RESOLUTION r NONE NONE i t
i ORIGINAL CURRENT ACTUAL i MILEST0NES DATE DATE DATE :
DEVELOP TAP 04/85 --
04/8s I DEVELOP PROTOCOL. CONDUCT SITE VISITS. 03/86 --
03/86 j AND WRITE TRIP REPORTS 1 ISSUE FINAL STUDY REPOR1 CONTAINIri 04/86 --
04/86 t RECOMMENDATIONS FIRST MEETING WITH INDUSTRY 08/86 --
08/86 SECOND MEETING WITH INDUSTRY 03/87 --
03/87 EVALUATE ErFECTIVENESS OF INDUSTRY 10/87 TBD --
INITIATIVES
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 54 ISSUE NUMBER: 103 TITLE. DESIGN FOR PROBABLE MAXIMUM PRECIPITATION IDENTIFICATION DATE: 10/84C PRIORITIZATION DATE 09/85C TYPE: GSI PRIORITY:
TASK MANAGER: R. KORNASIEWICZ OFFICE / DIVISION /0 RANCH RES /DE /EIB ACTION LEVEL- ACTIVE STATUS. NR TAC NUS.BERS: E RESOLUTION DATE 04/89 WORK AUTHORIZATIOH; MEMO TO J. KNIGHT F ROM H DENTON DATED 9/4/85 FIN CONTRACTOR CONTRACT TITLE NONE NONE NONE W0R K SC0PE REVISE SRP SECTIONS 2 4.2 AND 2.4 3 INCORPORATING DEVELOP RECOMMENDATIONS REGARDING BACKFIT NEW NATIONAL WEATHER SERVICE PROCEDURE S F OR DETERMINATION APPLICATION OF NEW PMP VALUES. OBTAIN OF PROBABLE MAXIMUM PRECIPITATION lPMP) PREPARE NECESSARY REVIEW AND APPROVALS. THEN PUBLISH REGULATuRY ANALYSIS (VALUE/ IMPACT) FOR USE OF NEW REVISION 3 OF SRP SECTIONS 2 4.2 AND 2 4 3 PMP VALUES PREPARE A PACKAGE FOR REVIEW BY CRGR S TA T as S NW LbENSkkN0hkFkbAkkbNLkkhERBkkNbbkVElbhkbBY NhR AFFECTED DOCUMENTS PROBLEM / RESOLUTION SRP SECTIONS 2.4.2 AND 2.4.3 DUE TO THE 11/85 NRR REORGANIZATION AND PRIORITY WORK.
A F IVE-MONTH E ELAY DCCURED, RE-REVIEW BY NEW NRR DIVISIONS AND OGC REQUIRED A 50.54(F) REQUEST TO BE ISSUED TO LICENSEES. DSRO ASKED FOR A STAFF PRA 0F THE MERIT OF THE 10 CFR 50.54lF) REQUEST BEFORE SENDING PACKAGE TO THE NRR DIRECTOR. NRC REORGANIZED IN 4/87 BEFORE PACKAGE WAS SENT TO THE NRR DIRECTOR AFTER THE REORGANIZATION, NRR DID NOT CONCUR WITH THE ISSUAdCE OF A 50 54(FI LETTER DGC WAS ASKED TO REASSESS THE NEED FOR A 50.54(FI LETTER THEY RESPONDED IN A 10/19/87 MEMORANDUM THAT THEY ~ BELIEVED THAT THERE IS SUFF ICIENT JUSTIFICATION TO ISSUE A 50 54(F)
LETTER - NRR IS DEVELOPING AN ALTERNATE PROPOSAL THAT WILL THE N HAVE TO BE NEGOTIATED WITH OGC. THIS SLOW PROCESS AS OF FY88 OUARTER 2 n
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE; 55 m s
ISSUE NUMBER: 10's TITLE DESIGN FOR PROBABLE ttAMIMUM PRECIPITATION '
AFFECTED DOCUMENTS C' -
. __________ .._______.....-_.._-.._..-------------..------. ------.-----------.--------------.- ICM PROBLEM /RESOLUT OF ------.------ ---------
s REACHING FURTHER DELAYS AGPEEMENT ON THE PROPOSED RESOLUTION HAS CAUSED .
IN RESGLUTION OF THIS ISSUE. IN MARCH. 1988 A PROPOSAL FOR A GENERIC INFORMATION LETTER WAS RECEIVED i
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m ADVISED THAT THEY HAVE NO OBJECTION AND WILL CONCUR ON "
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x M-! L E $ T 0 N E S ORIGINAL CURRENT ACTUAL s
DAIE DATE DATE IDENTIFICATION OF POTENTIAL GENERIC 05/84
.__....... s x RFOUIREMENT CONCERivING DESIGN FOR 05/84 N PMP/ MEMO V. STELLO TO H. TRENTON ,
^
v PREPARE DRAFT REVISIONS OF SRP SECTIONS 07/85 --
2.4.2 ALD 2.4.3 07/85
- CRGR PACKAGE SENT DST. DL. OSI. AND PPAS FOR GIVISION REVIEW i 07/85 :
07/85' -
CRGR PACKAGE REVIEWED BY DIVISIONS 08/85 -- '"
08/85_
DST COMMENTS ON CRGR PACKAGE _ 09/85 --
09/85 REVISi"D CRG$t PACKACC- 3Asi M N COMMENTS 10/85 10/85 g
REVISED CRGR PACKAGE REVIEk:0 BY 11/85 09/86 RECRGANIZED NRR DIVISION --
09/86
! -BASED CN DIVISION COMMENTS AND OGC 12/86 01/87 REVIEW. CRGR PACKAGE WILL INCLUDE 30.54tF) REQUEST TO LICENSEES
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7
, , _ - LE. ASSESSMENT T TE R TO LICENSEES OF MERIT OF 50.54(Fl 03/87
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RUN DATE: 05/11/88 PAGE: 56 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM ISSUE NLMdER: 103 TITLE: DESIGN FOR PROBA6LE MAXIMUM PRECIPITATION ORIGINAL CURRENT ACTUAL DATE DATE DATE MI LE ST ONE S -- ------- --.--- --- ----------
CRGR PACKA7E CONCURRENCE f. 'NC OFFICES 11/85 04/88 --
RESOLVE OFFICE DIFFERENCES P
- REVISE PACKAGE 09/87 04/88 --
PACKAGE CONCURRENCE BY NRC OFFICES AND OGC 10/87 04/88 --
REVIEW AND APPROVAL BY DIRECTOR DE/RES 11/87 05/88 --
PACKAGE SENT TO CRGR (29) 12/87 07/88 --
CRGR REVIEW AND APPROVAL 12/85 09/88 --
FRN OF ISSUANCE OF REV. 3 TO SRP SECTIONS 01/86 10/88 --
2.4.2 AND 2.4.3 FOR PUBLIC COMMENT CRGR PACKAGE REVISED INCORPORATING PUBLIC 04/86 01/89 --
COMMENT REVISED CRGR PACKAGE REVIEWED AND 05/86 03/89 --
APPROVED BY CRGR (53)
FRN ISSUING REV. 3 TO SRP SECTIONS 07/86 04/89 --
2.4.2 AND 2.4 3 GENERIC LETTER ISSUED TO LICENSEES 11/87 04/89 --
BY NRR LICENSING DIVISIONS 4
AS OF FY88 OUARTER 2 9 -
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RUN DATE: 05/II/88 GENERIC ISSUE MANAGEMENT CONTPOL SYSTEM PAGE: 57 ISSUE NUMBER: 105 TITLE: INTERFACING SYSTEMS LOCA AT LWRS IDENTIFICATION DATE: IO/84C PRIORITIZATION DATE: 06/85C TYPE GSI PRIORITY: H TASK MANAGER: O. ROTHBERG OFFICE / DIVISION /BRANC!I: RES /DE /EIB ACTION LEVEL- ACTIVE S TATUS :
TAC NUMBERS: RESOLUTION DATE: 08/88 VORK AUTHORIZATION: MEMO FOR R. BERNER0 FROM H. DENTON DATED 6/II/85.
FIN CONTRACTOR CONTRACT TITLE A3829 BNL INTERFACING SYSTEMS LOCA I
W0RK SC0PE PERFORM A DETAILED PRA FOR 3 BWR AND 3 PWR PLANTS TO INTERFACING SYSTEMS LOCA. DEVELOP NEW LICEt: SING CRITERIA IF DETERMINE CORE-MELT FPEQUENCIES AND RISK CONTRIBUTED BY NECESSARY FOR THE GENERIC RESOLUTION.
STA TUS
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l BblPRbPbbklFbRh/kbhTHkbPRbJkbhhSkbbkPTkbbh bhbkRhkY I2/2/85 AND MODIFIED ON I/24/86. THE WORK IS CURRENTLY l AFFECTED DOCUMENTS PROBLEM / RESOLUTION
- NUREG/CR-5124 NUREG/CR-5IO2 THE BNL CONTRACT HAS BEEN MODIFIED TO INCLUDE A MORE COMPLETE PRA AND AN ANALYSIS OF 3 PWRS, IN ADDITION TO 3 BWRS. THE SCHEDULE HAS BEEN EXTENDED TO RECOGN1ZE THE TIME THAT WILL BE NEEEED TO INCLUDE THE 3 PWRS AND TO DEVELOP ANY NEW LICENSING REQUIREMENTS THAT MAY BE INDICATED OR NECESSARY BY THE BNL PRA REPORTS. -8NL WORK HAS BEEN DELAYED ABOUT SIX MONTHS DUE TO CONCURRENT WORK ON THE SEABROOK ANALYSIS OF INTERSYSTEM '0CA'S. AND ABOUT 3 ADDITIONAL MONTHS DUE TO NECESS%RY CORRECTIONS TO EARLIER DRAFTS AND DUE TO REQUIREMENTS TO ADD CONSIDERATION OF PLANTS THAT 00 l NO PIV LEAK TESTING. COMPLETION OF THIS ISSUE ON SCHEDULE i- WAS DELAYED DUE TO A TEMPORARY LACK OF FUNDING DURING TdE LAST QUARTER OF FY-87 FOR AN ADDITIONAL 4 STAFF-MONTHS OF i
EFFORT (PER BNL'S LETTER TO THE TASK MANAGER ON 6/22/87).
!HE REQUESTED F UNDS WERE EVENTUALLY FOUND. BUT NOT BEFORE A AS OF FY88 OUARTER 2 i - _ . _ _ _ . - _ _ _ _ ___ _ - _ - - - _ _ _ _ -. _ - -
QUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 58 ISSUE NUMBER- 105 TITLE- INTERFACING SYSTEMS LOCA AT LWRS AFFECTED DOCUMENTS PROBLEM / RESOLUTION DELAY OF AT LEAST A MONTH HAD BEEN INCURRED GSI 105 WILL BE CLOSED OUT WITH THF P!V PORTION Or GSI II E6 1 ORIGINAL CURRENT ACTUAL M ILEST 0 net DATE DATE DATE GSI 105 ASSIGNED TO RS8/DSI/NRR -- --
06/85 PRELIMINARY DISCUSSION OF knRK PLAN WITH BNL -- --
06/85 BNL PRELIMINARY COST ESTIMATE OF WORK PLAN 09/85 --
08/85 DEVELOP WORK PLAN AND CONTRACT PROPOSAL 09/85 --
08/85 DRAFT WORK PLAN TO DIRECTORS. DSI. DE. DL. 09/85 --
08/85 DHFS. AND AEDD 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 C3/86 --
03/86 FINAL DRAFT REPORTS RECEIVED FRCH BNL 07/86 --
02/88 INCLUDING VALUE/ IMPACT ANALYSIS PUBLISH NUREG REPORTS 08/88 08/88 --
FOR ADDITIONAL MILESTONES RELATING TO THE -- -- --
TESTING OF PRESSURE ISOLATION VALVES. SEE GSI II E.6.1.
AS OF FY88 QUARTER 2 O O O
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 61 ISSUE NUMBER: 113 TITLE- DYNAMIC QUALIF. TESTING OF tARGE BORE HYDRAULIC SNUBBERS IDENTIFICATION DATE: 09/82C PRIORITIZATION DATE. 0//87C TYPE: GSI PRIORITY: H TASK MANAGER: J. PAGE OFFICE / DIVISION / BRANCH: RES /DE /EIB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: RESOLUTION DATE: 09/91 ,
WORK AU)HORIZATION: JULY 2, 1987 MEMO FROM E. BECKJORD TO G. ARLOTTO FIN CONTRACTOR CONTRACT TITLE TBD TBD TO BE DETERMINED t
W0RK SC0PE
- 1. SURVEY INDUSTRY TO DETERMINE TYPES AND NUMBERS OF AVAILABLE IN U.S. INDUSTRY. IMCLUDING PORTABLE LARGE BORE HYDRAULIC SNUBBERS (LBHS*S) USED IN U.S_ EOUIPMENT AND EQUIPMENT ONLY AVAILABLE AT TEST PLANTS, LABORATORIES.
- 2. OBTAIN DESIGN INFORMATION AND OPERATING LIMITS FROM 7 EVALUATE FEASIBILITY OF PERFORMING PERIODIC INSERVICE LBHS MANUFACTURERS. SURVEILLANCE / TESTS ON INSTALLED LBHS*S.
- 3. OBTAIN AND EVALUATE OPERATING EXPERIENCE DATA (NPROS, 8. ASSESS THE OVERALL IMPACT OF SNUBBER REDUCTION LERS. FEF. AEOD CASE STUDY AE00/E423. ETC.I INITIATIVES AND THE GDC-4 BROAD SCOPE RULE a
- 4. OBTAIN AND EVALUATE ENVIRONMENTAL AND DYNAMIC IMPLEMENTATION ON THE UTILIZATION OF LBHS S.
QUALIFICATION INFORMATION. 9. IDENTIFY POTENTIAL IMPROVEMENTS IN LBHS'S RELIABILITY S. ASSESS CURRENT LBHS TEST AND SURVEILLANCE REQUIREMENTS AND THE ASSOCIATED COSTS / BENEFITS.-
l AS CONTAINED IN PLANT TECHNICAL SPECIFICATIONS 10. DEVELOP STAFF RECOMMENDATIONS FOR ENVIRONMENTAL /
INCLUDING APPLICABLE ASME SECTION XI. DYNAMIC OUALIFICATION AND INSERVICE TESTING /
, 6. DETERMINE STATE-OF-THE-ART TESTING CAPABILITIES SURVEILI ANCE .
l STATUS DRAFT TAP APPROVED BY DE DIRECTOR AND SUBMITTED TO OTHER RES DIVISIONS AND NRR FOR COMMENT.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION (A) ASME SECTION XI NONE (B) ANSI /ASME OM-4 (C) SRP 3.9.3.
(D) STANDARD TECHNICAL SPECIFICATIONS
- lE) CUSTOM TECHNICAL SPECIFICATIONS AS OF FY88 QUARTER 2 h
RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 62 ISSUE NUMBEP: 113 TITLE: D.1AMIC QUALIF TESTING OF LARGE BORE HYDRAULIC SNUBBERS ORIGINAL CURRENT ACTUAL M ILEST0NE S DATE DATE DATE DRAFT TAP TO DE DIRECTOR 11/87 --
11/87 DRAFT TAP APPROVED BY DE DIRECTOR 12/87 --
12/87 AND FORWARDED TO OTHER RES DIVISION DIRECTORS AND NRR FOR COMMENT INCORPOPATE COMMENTS IN TAP 03/88 --
03/88 FINAL TAP APP!t0VED BY 04/88 04/88 --
DE DIRECTOR WITH CONTRACTOR ASSISTANCE. SURVEY 12/88 12/88 --
INDUSTRY TO DETERMINE TYPE AND NUMBERS OF LBHS'S IN U.S PLANTS WITH CONTPACTOR ASSISTANCE. OBTAIN 12/88 12/88 --
DESIGN INFORMATION AND OPERATING LIMITS FROM LBHS MANUFACTURERS.
WITH CONTRACTOR ASSISTANCE. CBTAIN 12/88 12/88 --
AND EVALUATE OPERATING EXPERIENCE DATA WITH CONTRACTOR ASSISTANCE. OBTAIN 12/88 12/88 --
AND EVALUATE ENVIRONMENTAL AND DYNAMIC CtaLIFICATION INFORMATION.
WITH CONTRACTOR ASSIS.*ANCE, ASSESS 12/88 12/88 --
CURRENT LBHS TEST AND SdRVEILLANCE REQUIREMENTS.
WITH CONTRACTOR ASSISTANCE. DETERMINE 03/89 03/89 --
STATE-OF-THE-ART TF_ STING CAPABILITIES AVAILABLE IN U.S INDUSTRY.
WITH CONTRACTOR ASSISTANCE. COMPLETE 04/89 04/89 --
FEASIBILITY EVAL. OF PERFORMING PERIODIC INSERVICE SURVEILLANCE / TESTS ON LBMS'S WITH CONTRACTOR ASSISTANCE. COMPLETE ASSESS. 05/89 05/89 --
OF IMPACT OF SNUBBER R EDUC T ION INITIATIVES AND GDC-4 BROAD SCOPE RULE ON USE OF LBHS'S AS OF FY88 CUARTER 2 O 1 O O _ . _ _ _ _ . _
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 63 ISSUE NUMBER: 113 TITLE: DYNAMIC QUALIF. TESTING OF LARGE BORE HYDRAULIC SNUBBERS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE WITH CONTRACTOR ASSISTANCE. IDENTIFY 06/89 06/89 --
POTENTIAL IMPROVEMENTS IN LBHS RELIABILITY AND 1HE ASSOCIATED COSTS / BENEFITS ,
COMPLETE DTR PACKAGE FOR COMMENT 08/39 08/39 --
DTR PACKAGE TO OTHER OFFICES FOR 04/89 09/89 --
CONCURRENCE DTR PACKAGE TO CRGR 12/89 12/89 -_
CRGR REVIEW (29) 02/90 02/90 --
DTR PACKAGE ISSUED FOR PUBLIC COMMENT 05/90 05/90 --
t PUBLIC COMMENTS RECEIVED 07/90 07/90 --
~
FTR PACKAGE PREPARED 10/90 10/90 --
FTR PACKAGE TO OTHER OFFICES 01/91 01/91 --
FTR PACKAGE TO CRGR 04/91 04/91 --
CRGR REVIEW 0F FTR (53) 06/91 06/91 --
FTR PACKAGE ISSUED 09/91 09/91 --
l AS OF FY88 QUt9TER-2 o
RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 64 ISSUE NUMBER: 115 TITLE ENHANCEMENT OF RELIABILITY OF W SOLID STATE PROT. SYSTEM IDENTIFICATION DATE: 04/85C PRIORITIZATION DATE- 07/86C TYPE: GSI PRIO7ITY: H TASK MANAGER. D. BASDEhAS OFFICE / DIVISION /6 RANCH- RES /DRPS/RPSI ACTION LEVEL- ACTIVE STATUS-TAC NUMBERS: RESOLUTION DATE 05/89 WORK AUTHORIZATION: MEMO 10 T. SPEIS FROM H DENTON DATED 7/7/86 FIN CONTRACTOR CONTRACT TITLE A6875 INEL GI-115 "ENHANCEMENT OF RELIAB 0F WEST SOLID STATE PROTECTION SYS" W 0R K SC0PE RkVkkWRkkPbkSkSTbbl8hk8 (bkN RhbkbPLb bksbF bbkkkhkhkF kNEbNbEkVbLhkbhbRkVkRbkRbRkLkIBkLkhYbkN SALEM ATWS EVENTS) TO ASSESS VENDOR-RELATED MODIFICATIONS OF BE IMPROVED BY INSTALLING A RELAY DRIVER AND ASSOCIATED THE WESTINGHOUSE SOLIO STATE PROTECTION SYSTEM (SSPS). RELAYS TO DUPLICATE THE FUNCTION OF THE UNDERVOLTAGE THEREBY THESE MODIFICATIONS INCLUDE THE RECOMMENDATIONS IDENTIFIED PROVIDING DIVERSITY FOR THE FUNCTION. ALSO. PERFORM A IN WESTINGHOUSE TECHNICAL BULLETIN NSID-TB-85-16 DATED VALUE/ IMPACT ANALYSIS FOR THOSE MODIFICATIONS THAT SHOW 7/31/85. PERFORM AN ENGINEERING ANALYS!S (SIMPLIFIED PRA) POTENTIAL FOR IMPROVEMENT.
STA TUS A SDW FIN A6875 FOR AN INEL PROPOSAL FOR T/A ON THIS PROJECT WAS ISSUED IN AUGUST 1987.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION TO BE DETERMINED. NONE ORIGINAL CURRENT ACTUAL MI LESTON ES DATE DATE DATE GSI 115 ASSIGNED TO RSIB/DSR0/NRR 07/96 --
07,86 PRELIMINARY DISCUSSION OF WORK PLAN 08/86 --
08/86 WITH INEL AS OF FY88 OUARTER 2 O O O
! ) O .
O RUN DATE: 05/11/88
{ GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 65 j
d ISSUE NUMBER: 115 TITLE: ENHANCEMENT OF RLLIABILITY OF W SOLID STATE PROT. SYSTEM ,
i I
ORIGINAL CURRENT ACTUAL
> MILEST0NES DAIE DATE DATE
~~------ ---------- ---------- ----------
4 INEL TO PROVIDE PRELIMINARY COST 10/86 --
07/87 j- ESTIMATE OF WORK PLAN 1
DEVELOP S0W AND CONidACT PROPOSAL 10/86 --
08/87 DRAFT TAP (ISSUED TO RES/NRR) 08/87 --
08/87 ISSUE CONTRACT TO INEL 12/86 --
08/87 a REVISE TAP (SEND 10 RPSID CHIEF) 10/86 --
09/87
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DRAFT REPORT FROM INEL TO RES 07/87 07/88 --
) ' FINAL REPORT FROM INEL TO RES 09/87 09/88 --
i FINAL REPORT PREPARED. CRGR PKG. .11/87 11/88 --
1 APPROVED BY DIV. DIRECTOR j SENT TO OTHER DIVISIONS FOR COMMENT COMMENTS FROM OTHER OIVISION 12/87 12/88 --
DIRECTORS INCORPORATED / PACKAGE SENT TO RES DIRECTOR j PACKAGE SENT TO CRGR/ACRS (29, 53) 01/88 02/89 --
1
! CRGR/ACRS REVIEW AND EDO APPROVAL 02/88 03/89 --
'IS7UE CLOSEOUT MEMO FROM RES 03/88 05/89 --
j DIRECTOR (GL TO LICENSEES) ;
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AS 0F FY88 QUARTER 2' a i
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RUN DATE: 03/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 66 ISSUE NUMBER: 179.1 TITLE- PIPE RbPTURE REQUIREMENTS IDENTIFICATION DATE: 07/85C PRIORITIZATION DATE. 09/85C TYPE- RI PRIORITY:
TASK MANAGER: TBD OFFICE / DIVISION / BRANCH NRW / DEST /EMTB ACTION LEVEL: ACTIVE STATUS: 5 TAC NUMBERS: RESOLUTION DATE 05/88 WORK AUTHORIZATION: MEMO TO R. MINOGUE FROM H DENTON DATED 9/10/85 FIN CONTRACTOR CONTRACT TITLE bk33 LLkL [bIbbbMbkNkkkbh5 W0R K $C0PE PREPARE REGULATORY ANALYS?S ASSOCIATED WITH RELATIVE TO DECOUPLING OF SSE AND LOCA LOADS PROPOSED SRP REVISIONS AND GDC-4 AMENDMENT. WILL BE ADDRESSED IN THE RESOLUTION OF GSI 119 1.
IN ACCORDANCE WITH A 01/08/87 MEMO FROM R. SUBSEQUENTLY. OtCOUPLING SSE AND LOCA EFFORTS WERE BOSNAK TO K. KNIEL, THE REMAINING PART OF GSI B-6 TERMINATED BASED ON INPUT FROM OGC.
S TA T US THE EDO APPROVAL TO BEGIN RULEMAKING (GDC-4) WAS GIVEN AUGUST 28. 1987. MANAGEMENT OF SRP 3.6.3 TRANSFERRED TO NRR IN 12/84. THE FRN OF PROPOSED LIMITED SCOPE RULE WAS MADE IN MEMO ARLOTIO TO SHA0 DATED SEPTEMBER 28. 1987 FRN OF IN 7/85 WITH THE FINAL RULE PUBLISHED IN 4/86. THE FRN OF SRP SECTION 3.6.2 REVISION AND ASSOCIATED GL WERE PUBLISHED.
PROPOSED BROAD SCOPE RULE WAS MADE IN 7/86. COMMISSIONERS ALL REMAINING ISSUES RELATE TO NRR - NO TASK MANAGERS APPROVED FINAL BROAD SCOPE RULE ON OCTOBER 1, 1987. ASSIGNED.
FRN SOLICITING PUBLIC COMMENT ON SRP 3.6.3 PUBLISHED ON AFFECTED DOCUMENTS PROBLEM / RESOLUTION I555bbFR 5b kPPkhbkk bbbk S[kPPEbhkbPbbLkbkTkbbbF PRbPbkkbbRbIbSbbPk (2) SRP SECTION 3.6.2 RULE DUE TO PREPARATION OF BACKFIT ANALYSIS AND (3) SRP SECTION 3.6.3 (NEW SECTION) INTEGRATION OF VIEWS FROM THE FEDERAL REPUBLIC OF GERMANY. StIPPAGE IN FINAL BROAD SCOPE RULE DUE TO DELAYS IN PROPOSED BROAD SCOPE RULE AND TO DIFFICULTIES IN RESOLVING TECHNICAL ISSUES, PARTICML3 R L*, RELATING TO HEAVY COMPONENT SUPPORT REDESIGN AS OF FY88 QUARTER 2 O O O .
- \
Y RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTR01 SYS;EM PAGE: 67 ISSUE NUMBER: 119.1 TITLE: PI?E RUPTURE REQUIREMENTS ORIGINAL CURRENT ACTUAL MILEST0NES OATE CATE DATE Pkb FkhkL hPT bbhTkkhhhb hEbbMMEbb Fbk bhhhh -
Ohhhh CECOUPLING LOCA. SSE & ARSITRARY INTERMED.
PIPE BREAKES ISSUED TO EDO (SKP 3.6.2) i SRP REVISION AND REGULATORY 04/8S --
04/86 ANALYSIS COMPLETE (SRP 3.6.2)
J DIVISION DIRECTOR REVIEW OF CRGR 06f86 --
07/86 PACKAGE COMPLETE (SRP 3.6.2)
! DIVISION DIRECTOR'S COMMENTS RESOLVED, 07/86 --
08/86 4
, FOR REVIEW (SRP 3.6.2)
' NRR DIRECTOR REVIEW COMPLETE. 08/86 --
09/86-5 PACKAGE SENT TO CRGR (SRP 3.6.2) i
- CRGR REVIEW COMPLETE. PACKAGE SENT I?/86 --
11/86 1-FRN ISSUED FOR PUBLIC COMMENT 01/87 --
12/86 l (SRP 3.6.2)
- f. ANALYSIS COMPLETE (SRP 3.6.2) 03/87 --
03/87 j DIVISION DIRECTOR REVIEW 04/87 --
01/87 j COMPLETE (SRP 3.6.2).
[ PUBLIC COMMENTS RESOLVED. FINAL 05/87 --
01/87 '
1 CRGR PACKAGE TO DIVISION DIRECTORS j FOR REVIEW (SRP 3.6.2)
COMMENTS RESOLVfD. FINAL CRGR PACKAGE 07/87 --
02/87 TO NRR DIR. FOR REVIEW (SRP 3.6.21 PACKAGE SENT TO CRGR (SRP 3.6.2) 08/87 --
03/87
. PACKAGE SENT TO ACRS (SRP 3.6.2) 10/87 --
03/87 AS OF FY88 CUARTER 2 i
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RUN DATE: 03/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 68 ISSUE NUMBER: 119.1 TITLE: PIPE RUPTURE REQUIREMENTS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE ACRS REVIEW COMPLETE (SRP 3.6.2) 12/87 --
06/87 FRN OF ISSUANCE OF SRP 3.6.2 01/88 --
06/87 SRP REVISION AND REGULATORY 03/87 --
03/87 ANALYSIS COMPLETE (SRP 3.6.3)
! CRGR PACKAGE TO DIVISION 04/87 --
04/87 DIRECTORS FOR REVIEW (SR P 3.6.3 )
DIVISION DIRECTOR REVIEW 04/87 --
05/87 COMPLETED (SRP 3.6.3)
06/87 DIRECTOR FOR REVIEW (SRP 3.6.3)
PACKAGE SENT TO CRGR (SRP 3.6.3) (29) 05/87 --
06/87 PACKAGE SENT TO ACRS (SRP 3.6.3) 06/87 --
06/87 ACRS & CRGR REVIEW COMPLETED (SRP 3.6.3) 06/87 --
08/87
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FRN ISSUED FOR PUBLIC COMMENT (SRP 3.6.3) 07/87 --
08/87 MANAGEMENT OF SRP 3.6.3 TRANFERRED TO NRR 09/87 FRN Of FINAL BROAD SCOPE RULE (GDC-41 02/87 --
10/87 PUBLIC COMMENTS RESOLVED, CRGR 11/87 04/88 --
PACKAGE SENT TO DIVISION DIRECTORS (SRP 3.6.3)
DIVISION DIRECTORS REVIEW COMPLETED 12/87 04/88 --
(SRF 3.6.3)
NRR OFFICE DIRECTOR REVIEW 02/88 04/88 --
COMPLETED (SRP 3.6.3)
PACKAGE SENT TO CRGR AND ACRS 03/88 04/88 --
(SRP 3.6.31 (53)
%S OF FY88 QUARTER 2 O O O
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I, ' GENERIC IS30E MANAGEMENT CONTROL SYSTEM PAGE: 69 '!
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i ISSUE NUMBER: 119.1 TITLE: PIPE RUPTURE REQUIREMENTS 1
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, ORIGINAL CURRENT ACTUAL
.' MILESTONES DATE DATE DATE-
..___...__.___________._.... . ..___._...___ _ ......____ _________. -_______ .. i
- ACRS AND CRGR REVIEW COMPLETE 04/88 04/88- ---
( (SRP 3.6.3) l FRN OF ISSUANCE OF SRP 3.6.1 05/88 05/88 --
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 70 ISSUE NUMBER: 119.2 TITLE: PIPE DAMPING VALUES IDENTIFICATION DATE: 07/85C PRIORITIZATION DATE: 09/85C TYPE: RI PRIORITY:
TASK MANAGER: D. GUZY OFFICE / DIVISION / BRANCH- RES /DE /SSEB ACTION LEVEL- ACTIVE STATUS' 5 TAC NUMBERS. NONE RESOLUTION DATE 06/88 WORK AUTHORIZATION- MEMU TO R MINOGUE FROM H. DENTON OATED 9/10/85 FIN CONTRACTOR CONTRACT TITLE A0457 LLNL PIPE DAMPIEG FOR TIME-HISTORY ANALYSIS A6316 INEL PIPE DAMPIP'i W0R K SC0PE bb((kbi b Tk Nb bbNbbbT kkhkkkMkNTk Tb PRbVkbE hkhkSFhR PkPEbkMPkN CRhThRkk OBTAIN PIPE DAMPING VALUES. USED aN TIME-HISTORY ANALYSIS.
S T A T US A MEETING WAS HELD 07/10/86 WITH RES. NRR. AND FURTHER ACTION ON d.G. 1 . 16 1 (THUS THE ESTABLISHMENT OF REPRESENTATIVES OF THE ASME AND PVRC DAMPING TASK AN NRC NON-SEISMIC AND TIME-HISTORY PIPE DAMPING WILL BE GROUPS THE DECISION WAS MADE TO DELAY WORK ON DROPPED AS A SEPARATE MILESTONE). PRDGRESS OF THE REGULATORY GUIDE 1.61 UNTIL THE ASME GROUP COMPLETES EPRI/BECHTEL PROJECT TO EVALUATE DAMPING DATA. DEVELOP ITS NEW EFFOPT. NEW DAMPING CURVES. AND PROVIDE STRAWMAN CRITERIA THE INEL STUDY OF HIGH FRECUENCY PIPE-DAMPING WAS CHANGES TO THE ASME APENDIX WORKING GROUP WAS REVIEWED COMPLETED WITH THE PUBLICATION OF NUREG/CR-4562 IN JULY IN SEPTEMBER 1987. MORE WORK IS NEEDED TO COMPLETE THIS 1986. TASK BUT IT APPEARS NOW THAT THIS IS TECHNICALLY RECOMMENDATIONS FROM THE INEL STUDY ON HIGH FEASIBLE.
FREQUENCY DAMPING WERE APPROVED BY THE PVRC PIPING SCHEDULE SLIPPAGES IN EPRI/BECHTEL PROJECT HAVE DELAYED COMMITTEES IN JANUARY 1987 BUT THEIR ACTION HAS BEEN TO ASME AND NRC STANDARDS DEVELOPMENT ACTIVITIES. THE WORK ON PASS THIS ALONG TO THE ASME TASK GROUP. THE ASME TASK LLNL FIN A0457 WAS PRESENTED TO THE NRC STAFF IN OCTOBER GROUP WILL CONSIDER ALL DAMPING ASPECTS, INCLUDING HIGH 1987. THE FINAL REPORT OF THIS STUDY SHOULD BE PUBLISHED IN FREQUENCY AND ANALYTIC APPLICATION AS A COMPLETE FEBRUARY 1988.
PACKAGE. THIS PACKAGE WILL BE CONSIDERED IN SCHEDULING AFF'CTED DOCUMENTS PROBLEM / RESOLUTION REGULATORY GUIDES 1.84 AND 1.61 SCHEDULE SLIPPAGES IN THE EPRI/BECHTEL PIPE DAMPING AS OF FY88 CUAPTER 2 O -
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I ISSUE NUMBER: 119.2 T1TLE: PIPE DAMPING VALUES l
1 AFFECTED DOCUMENTS PROBLEM / RESOLUTION
~
hkP bEbhkbb b$b52~ ~ Phbhhbh h5LL PkbbkbLh BEL hTbkkhhkbLkhkNh~bFk~
SCHEDULE TO REVISE R.G. 1. 61..
ORIGINAL CURRENT ACTUAL -
MILESTONES DATE DATE
.__.....__________..._...______ .........__._ _. __....- __........ __-DATE..__ ... ;
ISSUE REV. 24 0F R.G. 1.84 05/J6 --
06/86- ;
ENDORSING ASMt CODE N-411. j DEVELOP SCHEDULE TO REVISE R.G 11/87 06/88 '.- l 1.61 AND SRP SECTION 3.9.2. .]
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 72 ISSUE NUMBER: 119.3 TITLE: DECOUPLING OBE FRCM SSE IDENTICICATION DATE: 07/SSC PRIORITIZATION DATE 09/85C TYPE- RI PRIORITY:
TASK MANAGER: A. MpJRPHY OFFICE / DIVISION /8 RANCH RES /DE /SSE8 ACTION LEVEL: ACTIVE STATUS: 5 TAC NUMBERS: NONE RESOLUTION DATE _ _ _ _ _
WORK AUTHORIZATION: MEMO TO R. MINOGUE FROM H DENTON DATED 9/10/85 FIN CONTRACTOR CONTRACT TITLE WOR K SCOP E TO BE PROVIDED LATER.
STA T US RULEMAKING TO START IN 1988.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION
[bbfR kbb APPkkh k k k kb bF bhHkR bbbUMkhTS kbNk TO BE PROVIDED LATER ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE DEVELOP TAP TBD TBD --
AS OF FY88 OUADTER 2 O O O
t C/ - v RUN DATE: 05/11/88.
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 73 ISSUE NUMBER: 11G.4 TITLE: UWR PIPING MATERIALS
, IDENTIFICATION DATE: 07/85C PRIORITIZATION DATE: 09/85C TYPE: RI PRIORITY:
TASK MANAGER: A. TABOADA 0FFICE/ DIVISION / BRANCH: RES /DE /MEB ACTION LEVEL: ACTIVE STATUS: 5 TAC NUMBERS: NONE RESOLUTION DATE: 05/88 WORK AUTHORIZATION: MEMO TO R. MINOGUE FROM H. DENTON DATED 9/10/85.
FIN CONTRACTOR CONTRACT TITLE A2212 ANL ENVIRONMENTAL? Y ASSISTED CRACKING IN LWRS W0RK SC0PE DETERMINE TME ACCEPTABILITY OF PROPOSED FIXES TO MITIGATE INTERGRANULAR STRESS CORROSION CRACKING (IGSCC).
STATUS kb.* b b3kh kE 2 kEbHhbkhhkPbRhbN ERkkL bbbNbkRhPkPkhb khkPPkbVEbhhhHkbbhkkhkbN bEbh SELECTION AND PROCESSING GUIDELINES FOR BWR COOLANT PRESSURE 87-239) FOR IMPLEMENTATION AND ISSUANCE OF GENERIC LETTER.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION R.G. 1.44 AND NUREG-0312 "TECHNICAL REPORT ON MATERIAL NONE SELECTION AND PROCESSING GUIDELINES FOR BWR COOLANT PRESSURE BOUNDARY PIPING.*
ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE hEbhhkh01Tbbbb5hhkbh Oh/hk 7- Oh/8k PUBLISH NUREG-1061 VOL. 1 09/84 --
09/84 PUBLISH NUREG-1061. VOL. 5 04/85 --
'04/85 AS OF FY88 QUARTER 2
RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 74 ISSUE NUMBER: 119.4 TITLE. BWR PIPING MATEPIALS ORIGINAL CURRENT ACTUAL MILEST ONE S DATE DATE DATE COMPLETE DRAFT ON NUREG-0113 REV 2 09/85 --
09/85 0FFICE REVIEW 01/86 --
01/86 CRGR REVIEW 03/86 --
04/86 ISSUE FOR PUBLIC COMMENT G4/86 --
06/86 REVISION OF DFAFT TO REFLECT 07/86 --
02/87 PUBLIC COMMENTS ACRS REVIEW 03/87 --
03/87 CRGR REVIEW 09/86 --
06/87 COMMISSION PAPER FOR APPROVAL 12/86 --
09/87 ISSUE GENERIC LETTER-8801 04/87 --
01/88 DEVELOP SCHEDULE TO REVISE REGULATORY GUIDE 12/87 05/88 --
1.44 AS OF FY88 QUARTER 2 9 9 e
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RUN DATE: 05/II/88 4
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GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 75 I I
ISSUE NUMBER: 119.5 TITLE: LEAK DETECTION REQUIREMENTS IDENTIFICATION DATE: 07/85C PRIORITIZATION DATE: 09/85C TYPE: RI PRIORITY-1 TASK MANAGER: J. MUSCARA 0FFICE/ DIVISION / BRANCH: RES /DE /MEB ACTION LEVEL: ACTIVE STATUS: 5 '
TAC NUMBERS:
RESOLUTION DATE- 06/88 WORK AUTHORIZATION: MEMO TO R. MINOGUE FROM H DENTON DATED 9/10/85. I FIN CONTRACTOR CONTRACT TITLE hh5b Eht~ kV lbIkhbh bF bbRRkNh hb kbVkNhkb LhkK bkkkChkhh hYkTkMb DI658 BCL LEAK RATE EVALUATION W0R K SC0PE SURVEY EXISTING OPERATING PLANT PRACTICES AND LEAK DETECTION SYSTEMS. EVALUATE LEAK RATE ESTIMATION
( CURRENT ADVANCED METt?ODS TO DETERMINE THE ADEQUAC" 0F MODELS.
STATUS NUREG.0313. REV. 2 APPROVED BY THE COMMISSION AND IN PUBLICATION, l
AFFECTED DOCUMENTS PROBLEM / RESOLUTION (I) REGULATORY GUIDE 1.45 RESEARCH PROJECT ON LEAK DETECTION STARTED IN FY-86
{?) SRP SECTION 5.2.5 BUT DRASTICALLY REDUCED DUE TO BUDGET CUTS (GRAMM/
(3) NUREG-0313, "TECHNICAL REPORT ON MATERIAL RUDMAN). REPORT COMPLETED IN FY-86 ONLY ON LIMITED SELECTION AND PROCESSING GUIDELINES FOR BWR ASSESSMENT OF CURRENT PRACTICE IN PLANTS. FUNDING COOLANT PRESSURE BOUNDARY PIPING." RESUMED IN MID FY-87. REPORT TO BE EXPANDED AND UPDATED IN FY-1988. FINAL VALIDATION OF AN ADVANCED LEAK DETECTION SYSTEM TO BE COMPLETED IN FY-1988. RECOMMENDA-DATIONS FOR REVISION OF SRP AND REG, GUIDE 1.45 TO BE DEVELOPED IN FY-1988.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE
--.------------........------ ..------.----~~ ......---- .... ..... -.........
SECY-84-301 TO COMMISSION 07/84 --
07/84 AS OF FY88 QUARTER 2
RUN DATE: 05/11/d8 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 76 ISSUE NUMBER: 119.5 TITLE: LEAK DETECTION REQUIREMENTS ORIGINAL CURRENT ACTUAL MI LEST ONES DATE DATE DATE PUBLISH NUREG-1061 VOL 1 09/84 --
09/84 PUBLISH NUREG-1061, VOL 5 04/85 --
04/85 COMPLETE DRAFT OF NUREG-0313 REV. 2 09/85 --
09/85 CFFICE REVIEW 01/86 --
01/86 CRGR REVIEW 03/86 --
04/86 ISSUE FOR PUBLIC COMMENT 04/86 --
06/86 REVISE DRAFT TO REFLECT 07/86 --
02/87 PUBLIC COMMENTS ACRS REVIEW 03/87 --
03/87 CRGR REVIEW 09/86 --
06/87 COMMISSION PAPER FOR APPROVAL 12/86 --
09/87 GL ISSUED 04/87 --
01/88 DEVELOP SCHEDULE TO REVISE R.G. 1.45 01/88 06/88 --
DEVELOP SCHEDULE TO REVISE 01/88 06/88 --
SRP SECTION 5.2.5.
AS OF FY88 OUARTER 2 O -
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 77 ISSUE NUMBER: 121 TITLE: HYDROGEN CONTROL FOR LARGE. DRY PWR CONTAINMENTS IDENTIFICATION DATE: 08/85C PRIORITIZATION DATE: 09/85C TYPE: GSI PRIORITY: H TASK MANAGER: J. TELFORD OFFICE / DIVISION / BRANCH: RES /DRA /RDB ACTION LEVEL: ACTI'!E STATUS:
T AC NL'MBE RS : NONE RESOLUTION DATE-WORK AUTHORIZATION: MEMO TO F.GILLESPIE FROM T.SPEIS DATED 9/26/85.
i FIN CONTRACTOR CONTRACT TITLE NONE NONE NONE W0RK SC0PE ESTABLISH A TECHNICAL POSITION ON THE NEED FOR AND MAKE RECOMMENDATIONS TO THE COMMISSION REGARDING HYDROGEN CONTROL FOR LWR'S WITH LARGE. ORY CONTAINMENTS RULEMAKING.
STA T US ,
. AT THE COMMISSION MEETING ON 12/10/84 AND IN RESEARCH TASKS WERE SCHEDULED TO BE COMPLETED DURING THE SECY-83-3578. THE STAFF INDICATED THAT RECOMMENDATIONS FOR FIRST HALF OF CALENDAR YEAR 1986. A RECOMMENDATION WAS TO RULEMAKING RELATED TO LWR'S WITH LARGE, ORY CONTAINMENTS BE MADE TO THE COMMISSION DURING MID-1986.
WOULD BE PROVIDED AT THE CONCLUSION OF ONGOING RESEARCH IN ADDITIONAL RESEARCH WAS COMPLETED IN 10/87 WITH FINAL 1, MID-1986. WORK HAS BEEN PROCEEDING AND STAFF MEETINGS WERE REPORTS DUE IN 4/88. STAFF IS PREPARING RECOMMENDATIONS ON j HELD IN NOVEMBER 1985 TO REVIEW THE PROGRESS. THE VARIOUS REMAINING EFFORT REQUIRED TO ESTABLISH THE BASIS FOR A RULE.
, AFFECTED DOCUMENTS PROBLEM / RESOLUTION 1
l POSSIBLE NEW AMENDMENTS TO 10 CFR PART 50.44 NONE 4
i
) ORIGINAL CURRENT ACTUAL
- MILEST0NES DATE DATE DATE RESEARCH COMPLETE 06/86 04/88 --
TRANSMIT RECOMMENDATIONS 06/86 TBD --
i d AS OF FY88 OVARTER 2 l
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RUN DATE: 05/11/88 i GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 78 ISSUE NUMBER: 121 TITLE: HYDROGEN CONTROL FOR LfRGE. DRY PWR CONTAINMENTS ORIGINAL CURRENT ACTUAL M I LEST ONE S DATE DATE DATE kbbbkblbbEbbhhkhbbhPhbhkbhMhthkhbNkb bb/bb kbb
- NECESSARY TO IMPLEMENT RECOMMENDATIONS i
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(%a ) r Q ,l RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 79 ISSUE NUMBER: 122.2 TITLE: INITIATING FEED-AND-BLEED IDENTIFICATION DATE: 08/85C PRIORITIZATION DATE 01/86C TYPE: GSI PRIORITY: H TASK MANAGER- W. HODGES OFFICE / DIVISION /8 RANCH- NRR / DEST /SRX8 ACTION LEVEL- ACTIVE STATUS:
TAC NUMBERS: M61170 RESOLUTION DATE- 06/88 WORK AUTHORIZATION: MEMO FOR T. SPEIS AND W. RUSSELL FROM H DENTON DATED 1/28/86.
FIN CONTRACTOR CONTRACT TITLE i
W0R K SC0PE FEEb bb bLbEb (Fkbh bbbLkbb kb MEhikbbbF CbRE kbf bbhEbhkVkbhhHERhSbLbhkbNbhTHbkSbbE hShb COOLING FOLLOWING LOSS OF ALL FEEDWATER AT MOST PWRS. IDENTIFY WHAT. IF ANY, ADDITIONAL REGULATORY GUIDANCE IS IT IS AN OPTION OF LAST RESORT. DUT ONE WHICH CAN NEEDED FOR: III EMERGENCY OPERATING PROCEDURES, (2)
SIGNIFTCANTLY REDUCE THE CORE-MELT FREQUENCY PREDICTED OPERATOR TRAINING, AND/OR (3) INSTRUMENTATION FOR THE FOR MANY PWRS. F&B COOLING MUST BE MANUALLY INITIATED; MANUAL INITIATION OF F&B COOLING AT PWRS WITH THE IN NO PWR IS THIS AUTOMATIC. CAPABILITY TO COOL THE CORE BY F&B. TO DO THIS.
THE DAVIS-BESSE FEEDWATER TRANSIENT OF 6/9/85 IT IS NECESSARY TO: (I) IDENTIFY AND EVALUATE HUMAN CALLED INTO QUESTIOk THE ADEQUACY OF THE EMERGENCY PEEFORMANCE-SHAPING FACTORS AFFECTING OPERATOR OPERATING PROCEDURES CALLING FOR THE INITIATION OF RELIABILITY IN EFFECTING FSB CCOLING; (2) REVIEW THE FEB COOLING AND THE OPERATORS TRAINING ON THESE THERMAL-HYDRAULIC CRITERIA FOR COMMENCING FSB EMPLOYED PROCFDURES. WITHOUT BETTER PROCEDURES AND/OR TRAINING. IN THE EMERGENCY RESPONSE GUIDELINES (ERGS) FOR W. CE.
THE RELIABILITY WITH WHICH OPERATORS WILL INITIATE AND 8&W PLANTS: (4) REVIEW AVAILABILITY OF RELEVANT FAB. WHEN IT IS NECESSARY TO AVERT CORE-MELT. MAY INSTRUMENTATION; (5) FORMULATE RECOMMENDATIONS: AND(6)
BE SIGNIFICANTLY LOWER THAN IT COULD BE WITH BETTER AMEND THE REGULATIONS IF NECESSARY AND APPROPRIATE.
PROCEDURES AND TRAINING.
4 2 STATUS DETAILED PLANNING OF TECHNICAL RESOLUTION THE STAFF REVIEW AND APPROVAL OF VENDORS
- GENERIC UNDERWAY. THE MOST LIKELY TECHNICAL RESOLUTION IS THE PROCEDURE GUIDELINES. MECHANISMS ALREADY EXIST FOR IDENTIFICATION OF MODEST CHANGES NEEDED IN THE GENERIC LICENSEES TO INCORPORATE CHANGES IN THE GENERIC PROCEDURE GUIDELINES COVERING THE INITIATION OF PROCEDURE GUIDELINES INTO THEIR PLANT-SPECIFIC f&B COOLING. IF THE CHANGES NEED AND EMERGENCY OPERATING PROCEDURES THAT ARE EXPECTED WARRANT FORMAL IMPOSITION, A GENERIC LETTER SHOULD TO SUFFICE IN THIS CASE. TO CARRY THE GENERIC SUFFICE. RESOLUTION THROUGH TO PLANT-SPECIFIC IMPLEMENTATION.
I THERE ARE CURRENTLY A NUMBER OF OPEN ITEMS IN AS OF FY88 QUARTER 2 h
RUN DATE: OS/11/QP GEWERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 80 ISSUE NUMBER- 122.2 TITLE INITIATING FEED-AND-BLEED AFFECTED DOCUMENTS PROBLEM / RESOLUTION GENERIC ERG *S FOR W. CE. AND B&W PI_ ANTS NONE ORIGINAL CURRENT ACTrJAL MILE ST0N E S DATE DATE DATL IDENTIFY PERFORMANCE SHAPING FACTORS 07/8S --
01/87 REVIEW THE CRITERIA 07/86 --
02/87 REVIEW ERGS FOR W. CE. AND B&W 09/86 --
03/87 REVIEW RELEVANT INSTRUMENTATION 09/86 06/88 --
IDENTIFY RECOMMENDED IMPROVEMENTS TO ERG'S 10/86 06/88 --
AS OF FY88 OUARTER 2 O - -
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 81 ISSUE NUMdER: 124 TITLE AUXILIARY FEEDWATER SYSTEM RELIABILITY IDENTIFICATION DATE 12/85C PRIORITIZATION DATE- 02/86C TYPE: GSI PRIORITY:
l TASK MANAGER: J. WERMIEL OFFICE / DIVISION / BRANCH. NRR / DEST /SFLB ACTION LEVEL: ACTIW STAiUS: NR TAC NUMBERS: M60460 RFSOLUTION DATE: 08/88 WORK AUTHORIZATION: MEMO FOR T. SPEIS FROM H. DENTON DATED 2/5/86 FIN CONTRACTOR CONTRACT TITLE WORK SC0PE BECAUSE OF THE SIGNIFICANCE OF THE AFWS IN REDUCING (3) ANO-1 (7) RANCHO SECO CORE-MELT FREQUENCY. THE STAFF HAS DETERMINED THAT ALL I4) ANO-2 PWRS SHOULD MEET THE RELIABILITY CRITERION SPECIFIED IN THE FOLLOWING ISSUES WILL BE ADDRESSED IN THE SRP SECTION 10.4.9 WHICH WAS NOT APPLIED TO OPERATING RESOLUTION OF ISSUE 124 FOR THE ABOVE SEVEN UNITS:
REACTORS. IN ORDER TO ACHIEVE AND MAINTAIN A HIGH DEGREE (1) GSI 68 "POSTULATED LOSS OF AUXILIARY OF RELIABILITY FOR THE AFWS. THE FOLLOWING SHOULD BE FEEDWATER SYSTEM RESULTING FROM TURBINE-COMPLETED: (1) PWR LICENSEES AND APPLICANTS SHOUlO DRIVFN AUXILIARY FEEDWATER PUMP STEAM SUPPLY DEMONSTRAIE. USING dELIABILITY ANALYSES. THAT THE AFWS IS LINE RUPTURE."
OF HIGH RELIABILITY. E-4 TO E-5 UNAVAILABILITY PER (2) GSI 93 "STEAM BINDING OF AUXILIARY FEED-DEMAND. (2) THE STAFF IS TO REVIEW THE RELIABILITY WATER PUMPS."
ANALYSES AND/OR ANY NECESSARY SYSTEM MODIFICATIONS AND (3) GSI 122.1.A. "FAILURE OF ISOLATION VALVES PROCEDURAL OR MAINTENANCE CHANGES. BASED ON THE STAFF IN CLOSED POSITION."
EVALUATION OF W. CE AND B&W PLANT AFWS (NUREG-0611. (4) GSI 122.1.B. "RECOVERY OF AUXILIARY FEEDWATEd" NUREG-0635. B&W PLANT SERS). THE STAFF HAS DETERMINED (5) GSI 122.1 C. "INTERRUPTION OF AUXILIARY THAT THE AFWS OF THE FOLLOWING PLANTS MAY NOT BE FEEDWATER FLOW" SUFFICIENT 1Y RELIABLE: (6) GSI 125.II.1.B. "REVIEW OF EXISTING AFW (1) PRAIRIE ISLAND 1 (S) FT. CALHOUN SYSTEMS FOR SINCLE FAILURES" (2) PRAIRIE ISLAND 2 (6) CRYSTAL RIVER STA TUS THE REGULATORY ANALYSIS OF GSI 124 WAS DISCUSSED TEAM WILL COORDINATE ITS EFFORTS FOR THE B&W PLANTS WITH THE NRR DIRECTOR IN JULY 1986. IT WAS DECIDED WITH THE OURRENT RANCHO SECO RESTART PROGRAM AND THE l THAT THE RESOLUTION PLAN WOULO BE CHANGED FRCM DESIGN REEVALUATION BEING PE RFORMED BY THE B&W OWNERS REQUIRING A PRA FROM EACH LICENSEE TO THE GROUP. LIMITED PLANT VISITS TO ANO-1 AND RANCHO SECO PERFORMANCE OF AN OVERALL RELIABILITY ASSESSMENT AT ARE ANTIGIPATED IN VIEW OF PREVIOUS NRC INSPECTIONS THE SITE BY AN NRC REVIEW TEAM. SITE VISITS ARE OF THESE FACILITIES.
TENTATIVELY SCHEDULED AS SHOWN BELOW. THE REVIEW AS OF FY88 QUARTER 2
_______________________.____t_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . . . _ _ _ _ _ _ _ _ _ _ . _ _ _
RUN DOTE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 82 ISSUE NUMBER- 124 TITLE - AUXILIARY FEEDWATER SYSTEM RELI ABILITY AFFECTED DOCUMENTS PROBLEM / RESOLUTION TBD CANCHO SECO VISIT WILL BE CONDUCTED FOLLOWING RESTART ORIGINAL CURRENT ACTUAL MI LEST ONES DATE DATE DATE PRAIRIE ISLAND 1 & 2 PLANT VISIT 09/86 --
09/86 PRAIRIE ISLAND 1 & 2 DRAFT EVALUATION 11/86 --
11/86 REPORT ANO-2 PLANT VISIT 12/86 --
12/86 ANO-2 DRAFT EVALUATION REPCOT 01/87 --
03/87 CRYSTAL RIVER RELIABILITY ANALYSIS 03/87 --
03/87 REVIEW COMPLETED CRYSTAL RIVER PLANT VISIT 03/87 --
03/87 FORT CALHOUN RELIABILITY ANALYSIS 05/87 --
05/87 COMPLETED FORT CALHOUN PLANT VISIT 06/87 --
07/87 CRYSTAL RIVER EVALUATION REPORT 05/87 04/88 --
FORT CALHOUN EVALUATION REPORT 08/87 04/88 --
ANO-2 EVALUATION REPORT 04/88 04/88 --
ANO-1 PLANT VISIT [ LIMITED) 09/87 05/88 --
ANO-1 EVALUATION REPORT 10/87 06/88 --
RANCHO SECO PLANT VISIT (LIMITEDI 10/87 05/88 --
RANCHO SECO EVALUATION REPORT 11/87 06/88 --
PREPARE
SUMMARY
REPORT 02/88 08/88 --
AS OF FY88 QUARTL1 2 O O O
v RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 83
. I ISSUE NUMBER: 125.II.7 TITLE- REEVAL, PROV. TO AUTOMATICALLY ISOLATE FEEDWATER FPOM SG IN LINE BREAK IDENTIFICATION DATE: 12/8SC rRIORITIZATION DATE- 09/86C TYPE: GSI PRIORITY: H TASK MANAGER: D. BASDEKAS OFFICE / DIVISION / BRANCH: RES /DRPS/RPSI ACTION LEVEL: ACTIVE STATUS: '
TAC NUMBERS:
RESOLUTIOF 'DA E - 08/89 WORK AUTHORIZATION: MEMO FROM H. DENTON TO T. SPEIS. SEPTEMBER 10, 1986
FIN CONTRACTOR CONTRACT TITLE .
-E%
A6881 INEL GI 125.II.7 AU.0 ISGLATION OF FEEDWATER FROM S.G. IN LINE BREAK" *~~
my W0RK '
SC0PE -
OBTAIN PLANT INFORMATION RELEVAN', TO ISSUE.
INCLUDING IDENTIFICATION OF ISSUE- AFFECTED PL ANTS. TYPES ON BASIS OF EXPERIENCE AND/OR FAULT TREE RELIABILITY ANALYTIC METHODS. PERFORM RISK ANALYSES TO QUANTIFY ALL CHAPTER 15 ANALYSES OF STEAM AND FEEDWATER LINE BREAM SIGNIFICANT POSITIVE AND NEGATIVE SAFETY ASPECTS ACCIDENTS. PLANT-SPECIF IC CONTROL SYSTEMS FOR RELATING TO A PROPOSED ELIMINATION OF.THE PROVISION AUTOMATIC FEEDWATER ISOLATION AND ISSUE-RELATED FOR AUTOMATIC ISOLATION. A% A BASIS FOR A REGULATORY OPERATIONAL EXPERIENCE. OBTAIN ESTIMATE OF FREOUENCY OF VALUE-IMPACT RESOLUTION OF THE ISSbE.
INADVERTANT ACTUATION OF REPRESENTATIVE CONTROL SYSTEM y - .;
S TA TUS '
A S0W l FIN AS881) FOR AN INEL PROPOSAL WAS ISSUED IN AUGUST 1987.
AFFECTED DOCUMENTS PROBLEM /RtSOLUTION'
.........-...------_....--..-..--.------------- --------..- ...---------------................. ...-- -.. 2.
NONE NONE.
s s .. ,
ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE kkhbEkhhkbNEbTbbhRb 5 hhfh6 AS OF FY88 OUARTER 2 3 -<
e
CUN DATE: 05/11/88 GENEdIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 6 IS SUF. NUMBER. 125.11.7 TITLE. REEVAL. PROV TO AUTOMATICALLY ISOLATE TEEDWATER FROM SG IN LINE BREAK ORIGINf4L CURRENT ACTUAL M I LE sT Ot E S DATE DATE DATE MILESTONE SCHEDULE COMPLETF 10/80 --
10/86 PRELIMINARf DISCUSSION OF WORK PLAN WITH 05/87 --
07/87 CONTRACTOR ISSUE SDW FOR CONTR.TCTOR 06/87 --
08/87 ISSUE CONTRACT 07/87 --
08/B7 DRAFT TAP (ISSHED TO RES/NRR) e5/O --
09/87 2f vI" 'A. (SEND TO RPSIB CHIEF) 07/87 --
09,87 "9 AFT .ACTOP REPORT 10/87 06/88 --
C f'N T R AC T OR REPOPT 0~ 88 11/88 --
- At,UE/ IMPACT ANA'.YSIS 04/88 01/89 --
4.% . AGE TO DRPS DIRECTOR 0%/8b 02/89 --
, GR PACKAGE TO LICENSING DIVISIONS 05/88 0?/89 --
- COMMENTS 3G" PACKAGE TO RES DIRECTOR 07/89 03/89 --
" .' .c FINALIZED AND SENT TO CRGP (29, 53) 07/88 05/89 --
i adE CLOSEOUT MEMO rROM RES DIRECTOR 11/88 08/89 .-
TO LICENSING DIVISIONS (GL 10 RELEVANT LICENSEES)
AS OF FY88 OOARTER 2 9 9 9
m (% j%
RUN DATE: 05/11/88 GENERIC ISSUE MANAGCMENT CONTROL SYSTEM PAGE: 85 ISSUE F. UMBER: I?8 TITLE: ELECTRICAL POWER RELIABILITY IDENTIFICATION DATE 05/86C PRIORITIZATION DATE: II/86C TYPF: GSI PRIORITY: H TASK MANAGER: D. THATCHER OFFICE / DIVISION / BRANCH- RES /DE /EIR ACTION LEVEL: ACTIVE STATUS:
TAC MUMBERS: RESOLUTION DATE' 17/09 WORK AUTHORIZATION: MEMO FOR H. DENTON FROM T. SPEIS DATED 11/28/86 FIN CONiRACTOR CONTRACT TITLE b6hk5 kkk khTkbR TkbhbkkthbTRhbkl PbWER hSSbkb W0RK SC0PE INTEGRATION OF OTHER HIGH OR MEDIUM PRIORITY GENERIC THROUGH SUPPLEMENT 6 MARCH 1987 TO CONSIDER OTHER ISSUES: A-30 48, 49. DOCUMENTED GSI'S WHICH MAY HAVE AN IMPACT ON THE INTEGRATED TASK 1: IDENTIF ICATION OF ISSUES. APPROACH 10 THE ELECTRICAL POWER SYSTEM ISSUES AND CONCERNS.
THE CONTRACTOR REVIEWED THE DOCUMENTATION RELATED TO BASED ON THE REVIEW OF THE ABOVE-DISCUSSED MATERIALS. INEL THE ELECTRICAL ISSUES AND CONCERNS LISTED BELOW. A NUMBER PREPARED A DRAFT REPORT SUMMARIZING ALL THE RELATED ISSUES OF GSI S DIRECTLY RELATED TO ONSITE ELECTRICAL PCWER SYSTEMS AND RECOMMENDED A PLAN FOR PROCEEDING WITH RESOLUTION OF THE HAVE BEEN DOCUMENTEC (NUREG-0933) AND ARE IN VARIOUS STAGES RELATED ISSUES AND CONCERNS (TASKS 2 AND 3).
OF RESOLUTION. THESE ISSUES INCLUDE: A-30. "ADEOUACY OF TASK 2: EVALUATE THE ISSUES AND EXPECTED RESULTS BASED SAFETY-RELATED DC POWER SUP."LIES:" 48 "LCO FOR CLASS lE ON THE RESULTS OF TASK 1.
VITAL INSTRUMENT BUSES IN OPLEATING REACTORS"; 49 INEL WILL COMPLETE NESESSARY ANALYSIS AND DEVELOP
- INTERLOCKS AND LCOS FOR REPUNDANT CLASS 1E TIE BREAKERS" ALTERNATIVES FOR RESOLUTION OF THE ISSUES AND CONCERHS FOR A NUMBER OF OTHER ISSUES AVD CONCERNS CONCERN THE BOTH EXIMTING AND FUTURE PLANTS. A FINAL REPORT WILL BE ONSITE ELECTRICAL POWER SYSTEMS TO A SOMEWHAT LESSER PREPARED THAT INCLUDES THE RESULTS OF TASK 1 AND PROVIDES DEGREE SOME OF THESE ISSUES INCLUDE: USI A-17 THE RECOMMENDED ALTERNATE RESOLUTIONS DETERMINED IN TASK 2.
"SYSTENS INTERACTIONS," AND USI A-47, "SAFETY PRELIMINARY CONSIDiRATION OF POTENTIAL SAFE 1Y BENEFITS AND IMPLICAIIONS OF CONIROL SYSTEks." COSTS OF EACH ALTERNATIVE WILL ALSO BE PROVIDED.
VITH RESPECT TO POSSIBLE RESCLUTION FOR FUTURE TASK 3: DEVELOP REGULATORY ANALYSIS BASED ON THE PLANTS. CONSIDERATION WAS GIVEN TO THE IEEE STANDARDS AND PRELIMINARY ANALYSES PERFORMED IN TASK 2.
NRC ENDCRSEPENTS BY REGULATORY GUIDES. SPECIFICAL(Y, THE INEL WILL COMPLETE NECESSARY ANALYSIS AND PREPARE DRAFT FOLLOWING wtRE CONSIDERED: IEEE 603 AND ITS REFERENCED DOCUMENTS FOR NRC STAFF SUBMISSION TO CRGR. THE DRAFT STANDARDS. AND IEEE 308 AND ITS REFERENCED STANDARDS. REGULATORY ANALYSIS TO BE PREPARED SHALL BE BASED ON THE TO OBTAIN AN UP-TO-DATE ASSESSMENT OF ONGOING h0ST COST-EFFECTIVE ALTERNATIVES EVALUATED IN TASK 2. THE ELECTR7 CAL POWER CONCERNS, AEOD AND NRR WERE CONTACTED. NRC-WIDE GUICZLINES, AS CONTAINED IN NUREG/BR-0058, RELEVAP: AEOD CASE STUDIES WERE REVIEWED ALONG WITH "REGULAIORY ANALYSIS CtilDELINES Gi THE U.S. NUCLEAR BULLE TINS AND NOTICES. IN ADDITION. INEL REVIEWED REGULATORY COMMISSION," JANUARY 1983. WILL BE FOLLOWED IN NUREG-0933, "A PRIO*ITIZATION OF GENERIC SAF ETY ISSUES." PREPARING THE DRAFT DOCUMENTS.
ST A T US THE OBJECTIVE OF THIS EFFORT IS TO DEVELOP A SINGLE PROGRAM WHICH ADDRESSES THE ISSUES IN AN INTEGRATED MANNER.
AS OF FY88 OUARTER 2
RUN DATE: 05/11/88 GENrRIC I'. SUE MANAGEMENT CONTROL SYSTEM FAGE: 86 ISSUE NUMBER: 128 TITLE ELECTRICAL POWER RELIABILITY AFFECTED E'OCUMENTS PROBLEM / RESOLUTION ThE FbLIbWkhb hEbHN bL RkPbRh5 hkVk bkkh PbbtISHEb bR L bbbbH hN PRbbRkMHkhhhhN kDhREhh5Nb HEkh ARE SCHEDbtED TO BE PUBLISHED- ISSUES. THE DRAFT TECHNICAL RESOLUTION FOR GSI'S 48 AND NUREG-0305 TECHNICAL REPORT ON DC POWER SUPPLIES 49 WERE DRAFTED SEPARATEtt FROM A-30. IT IS EXPECTED IN NUCLEAR POWER PLANTS." JULY 1977. THAf THE RESOLUTIONS WILL BE MERGED PRIOR TO SUBMISSION NUREG-0666 "A PROBAOILISTIC SAFETY ANALYSIS OF TO C9GR.
DC POWER SUPPLY REQUIREMENTS FOR NUCLE AR POWER PLANTS. APRIL 1981.
UCID-19469 120 VAC VITAL INSTRUMENT BUSES AND INVERTER TECHNICAL SPECIFICATIONS," 1982 Is IS ANTICIPATED THAT THE PROPOSED RESOLUTION OF THE ELECTRICAL POWER ISSUES WILL INCLUDE A REGULATORY ANALYSIS AND SUPPORTING
SUMMARY
ORIGINAL CURRENT ACTUAL MI LEST 0N ES DATE DATE DATE PRELIMARY RESOLUTION PACKAGE SENT TO STAFF 12/87 04/88 --
FOR TECHNICAL REVIEW /COMMFNTS (GSI'S 48 & 49)
PREPARE DTR PACKAGE (GSI'S 48 & 49) 04/88 04/88 --
DIVISION DEPUTY DIRECT 0ft 05/88 05/88 -
REVIEW OF DTR COMPLETED MANAGEMfNT C9NCURRENCE EY 07/88 07/88 --
OTHER OFFICiS OTR PACKAGE T" PRGR (29) 07/88 07/88 --
ACRS REVIEW OF DTR COMPLETEE 09/48 09/88 --
CRGR REVIEW OF DTR COMPLETED 09/88 09/88 --
FRN OF ISSUANCE OF PROPOSED RESOLUTION 12/88 12/88 --
FOR PUBLIC COMMENT COMPLETE DE REVIEW bf PUBLIC S4'89 04/89 --
COMMENTS AND PREPARE FTR PASAAGE AS OF FY88 QUARTER 2 O O O
' N
\ -
N RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE; 89 ISSUE NUMBER: 130 TITLE: ESSENTIAL SERVICE WATER PUMP FAILURES AT MULTIPLANT SITES ORIGINAL CURRENT ACMIAL MILEST0NES DATE DATE DATE
-.---------.-~~------------------------------
ASSIGN TASK MANAGER 05/87 --
06/87 DEVELOP TAP 01/87 --
08/87 i, ASSEMBLE INFORMATION ON SYSTEM LAYOUT 11/87 --
12/87 FOR MULTI-PLANT SITES PRELIMINARY DISCUSSION OF WORK PLAN WITH 12/87 .--
01/88 CONIRACTOR ISSUE S0W FOR CONTRACTOR 02/88 --
03/88 L 1 SEARCH FOR SERVICE WATER SYSTEM 12/87 --
03/88
-MALFUNCTa'1NS DRAFT REGULATORY ANALYSIS FOR TECH SPEC 05/88 05/88 --
CHANGE 4 SUBMIT DTR FOR TECH SPEC CHANGE TO RES 96/88 06/88 --
DIRECTOR CRGR REVIEW (TECH SPLC CHANGE) 07/88 07/88 --
ISSUE GENERIC LETTER ON TECH SPEC CHANGE 08/88 08/88 --
PRELIMINARY CONTRACTOR REPORT 09/88 09/88 --
FINAL REPORT 11/88 12/88 --
PREPARE VALUE/ IMPACT ANALYSIS 11f88 12/88 --
SUBMIT DTR TO RES DIRECTOR 02/89 03/89 --
ACRS REVIEW 05/83 04/89 --
CRGR REVIEW (29,53) 06/89 04/8C --
AS OF FY88 OUARTER 2
RUN DATE: CS/II/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 90 ISSUE NUMBER: 133 TITLE. UPDATE POLICY STATENENT ON NUCLEAR PLANT STAFF WORKING HOURS IDENTIFICATION DATE: 07/86C PRIORITIZATION DATE II/86C TYPE. LI PRIORITY:
TASK MANAGER: D. MORRISEAU OFFICE / DIVISION / BRANCH- NRR /DLPQ/LHFB ACTION LEVEL: ACTIVE STATUS- S TAC NUMBERS: M40402 RESOLUTION DATE 04/88 WORK AUTHORIZATION: SRM DATED 9/30/85 FIN CONTRACTOR CONTRACT TITLE W0R K SC0P E SINCE COMMISSION POLICY IS STATED IN SEVERAL ON THE CURRENT GUIDELINES OlJ OVERTIME AND NORMAL WORKING DOCUMENTS. REVISION OF NRC"5 PRESENT POLICY GUIDANCF HOURS IS BEING DEVELOPED. A REVISED POLICY STATEMENT ON ON LIMITS ON OVEATIME AND SHIFT SCHEDULING IS NEEDED TO SHIFT AND SCHEDULING HOURS OF WORK WOULD ELIMINATE CONSOLIDATE CURRENT GUIDANCE INTO A SINGLE DOCUME NT LICENSEE CONFUSION RESULTING FROM MULTIPLE POLICY AND A'SO. THE RECENT ALLEGATIONS OF OPERATORS SLLE PING ON REQUIREMENT DOCUMENTS AND WOULD CLEARLY IDENTIFY SHIFT AT PEACH BOTTOM. AS WELL AS SIMILIAR OCCURENCES. L ICE NSE E MANAGEMENT *S RESPONSIBILITY TO ASSCPE THAT POINT TO THE NtED FOR A MORE DEFINITIVE POLICY. FOR NUCLEAR POWER PLANT STAFF FATIGUE RESULTING FROM EXAMPLE. THERE IS NO SPECIFIC GUIDANCE RELATING TO THE EXCESSIVE WORKING HOURS DOES NOT ADVERSELY A*FECT PUBLIC USE OF 12-HOUR SHIFTS IN THE CURRENT POLICY STATEMENT HEALTH OR SAFETY.
THE STAFF HAS REVIEWED AND APPROVED CASE-BY-CASE 8 THE REVISED POLICY STATEMENT WILL AID THE NRC LICENSEE PROGRAMS FOR ROUTINE 12-HOUR SHIF1s FOR 7 STAFF IN CONDUCTING REVIEWS OF LICENSEE PROGRAMS AND UTILITIES. IN ADDITION, THE CUMULATIVE EFFECTS OF FAT (GUE IN MONITORING LICENSEE IMPLEMENTATION.
HAVE NOT BEEN ADDRESSED. A POLICY STATENENT WHICH BUILDS ST ATUS
.---------------------------------------------------------------------------------------------~~-. .---. --------------
CRGR REVIEWED A DRAFT POLICY STATEMENT ON 12/4/86 FACTORS EFFECTS OF ROTATING SHIFTS ON OPERATOR CRGR RECOMMENDATIONS HAVE RESULTED IN SEVERTL REVISIONS. ALERTNESS WHICH WAS SURMITTED BY THE STAFF ON L/?3/87.
ALSO. THE COMMISSION REQUESTED INFORMAT.'ON ON THE HUMAN AFFECTED DOCUMENTS PROBLEM / RESOLUTION
~ 'THk PRbPbbkb~PblkbY bT TkhkNh WbbLb bbPERbhDh hHk N N DOCUMENTS OR SECTIONS OF THE F OLLOWING DOCUME NTS THAT DE AL WI TH SHIF T SCHEDULING AND OVERTIME- POLICY STATE-AS OF FY88 OUARTER 2 O O O
l -!
t i
l RUN DATE: 05/11/88 r
GENERIC TSSUE MANAGEMENT CONTROL SYSTEM PAGE: 91 l ISSUE NUMBER: 133 TITLE: UPDATE POLICY STATEMENT ON NUCLEAR PLANT STAFF WORKING HOURS l
i i
i AFFECTED DOCUMENTS PROBLEM / RESOLUTION ,
HENT OF 2/18/82. 147FR7352), REVISED POLICY STATEMENT OF 6/1/82 (47FR23836). NUREG-0737 (ITEM I.A.1.3.1, AND GENERIC LETTERS 82-12, 82-16, 83-02 AND 83-14 l
< ORIGINAL CURRENT ACTUAL 3 MILEST0NES DATE DATE 'DATE j SUBMIT PAPER TO COMMISSION ON HUr!AN 06/87 --
'06/87 3
FACTORS EFFECTS 07/87 07/87 BRIEF NRR MANAGEMENT ON STAFF POSITION --
1 i SUBMIT DRAFT POLICY STATEME N'T TO NRR DIFECTOR 03/87 04/88 __
1 i SUBMIT DRAFT POLICY STATEMENT TO CRGR FOR 04/87 04/88 ..
l REVIEW s.
SUBMIT ORAFT POLICY STATEMENT TO EDO 05/87 04/88 --
l i
i -
4 1
i i
(
4 AS OF FYS8 OUARTER 2 4
1 4
4
- 1. -
CUN DT.TE: 05/11/88 GENERIC ISSUE MANAGEME NT CONTROL SYSTEM PAGE: 92 ISSUE NUMBER 134 TITLE RULE 04 DEGREE AND E XPE RIE NCE REO FOR SENIOR OPERATORS IDENTIFICATION DATE: 07/86C PRIORITIZATION DATE 07/86C TYPE GSI PRIORITY H TASM MANAGER. M. FLEISHMAN OFFICE / DIVISION / BRANCH RES / ORA /RDB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS- RESOLUTION DATE G8/89 WORK AUTHORIZATION: MEMO (CCMLZ-85-61FROM S CHILK TO V STE LLO DATED 1/23/86 FIN CONTRACTOR CONTRACT TITLE MONE NONE NONE W0R M SC0P E THIS CONTEMPLATED RULEMAKING ACTION IS DUE TO A CCMME RC I AL NUCLEAR REACTOR OPERATING AT GREATER THAN TWENTY COMMISSION DECISION TO ENHANCE THE LEVELS OF E NGINE E R ING AMD PERCENT POWER SO'S LICENSED PRIOR TO 4 YEARS AFTER ACCIDENT MANAGEMENT EXPERTISE ON SHIFT THIS IS BEING DONE EFFECTIVE DATE OF RULE WHO DO NOT HOLD DEGREES IN TO F URTHER ENSURE THE PROTECTION Of THE HEALTH AND SAFETY OF ENGINEERING OR PHYSICAL SCIENCE WOULD BE ~GRANDFtTHERED -
THE PUBLIC BY HAVING PERSONNEL ON SHIFT WITH ENHANCED ONLY ONE REEKAMINATION ALLOWED FOR SO APPLICANTS WHO APPLY QUA L IF ICA T IONS BEFORE 4 YEARS AFTER EFFECTIVE DATE OF RULE. NO DEGREE THE CONTEMPLATED RULE WOULD REQUIRE (1 YEARS AFTER EQUIVALENCY WOULD BE ACCLPTABLE 4 YEARS AFTFR EFFECTIVE DATE EFFECTIVE DATE OF RULE) THAT APPLICANTS F OR LICENSES AS A 0F RULE SENIOR OPERATOR 1S01 0F A NUCLEAR POWER PLANT HOLD A THE CONTEMPLATED DEGREE RULE IS RELATED TO THE BACCALAUREATE DEGREE IN ENGINEERING OR PHYSICAL SC IE NCE FRDM COMMISSION POLICY STATEMENT ON ENGINEERING E XPER T ISE ON AN ACCREDITED INSTITUTICN OTHER BACCAL AURE ATE DEGRE E S F ROM SHIFT (50 FR 43621. 10/28/851 THIS POLICY STATEMENT IS AN INSTITU'. ION MAY BE ACCEPTED ON A CASE-BY-CASE 8 ASIS THE SATISFIED By PROVIDING ENGINEERING AMD ACCIDENT MANAGEMENT CURRENT REQUIREMENT (FOR CANDIDATES WiTH A BACCALAUREATE E XPERTISE ON SHIF T THROUGH THE SEPARATE SHIFT 1ECHNICAL DEGREEl 0F TWO YEARS OF RESPONSIBLE MUCLEAP PCWER PLANT ADVISOR ISTAI OR BY CCMBINING THE STA/SO FUNCTIONS THE EXPERIENCE. WOULD BE AMENDED TO REQUIRE AT LEAST ONE OF THE POLICY STATEMENT CLOSED OUT ISSUE HF I 2. ENGINEERING TWO YEARS OF OPERATING EXPERIENCE BE WITH A SIMILAR EXPERTISE ON SHIFT ~
STA T US ANPRM PUBLISHED IN THE FEDERAL REGISTER CN 5/30/85 AN SRM DATED 6/24/87 DIRECTED THE STAFF TO PREPARE A THE COMME NT PERICD ENDED OM 9/29/86 PUBLIC COMMENTS PR000 SED RULE FOLLOWING THE NRC REORGANIZATION OF 4/12/87, PROVIDED IN RESPONSE TO THE ANPRM WERE RESOLVED AND RES NOW HAS THE RESPONSIBILITY FOR DEVELOPING THE RULE RECOPENDATIONS MADE TO THE COMMISSION THE CU NISSION IN AS OF FY88 OUARTER 2 O .
O O
.~c.._.- ._ . .+ -. __ . . - .~ -- . _ . _. . - _ _ _ _ . - -. -
4
, RUN DATE: 05/11/88 4
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 93 ,
i
! ISSUE NUMBER: 134 TITLE: r.sLE ON DEGREE AND EXPERIENCE REO. ~0R SENIOR OPERATORS i AFFECTED DOCUMENTS PROBLEM / RESOLUTION
- j. 10 CFR PARTS 50 AND 55. NONE.
i
! ORIGINAL CURS ~MT ACTUAL 1
MILEST0NES DATE DATE 'DATE
} - - - _ - - _ - - - - - - - - - - - - - - _ - - - - - - - - - - - - - - - - - - - - . - ---------- ---------- ----------
j ANPRM 151 FR 19561)., COMMENT BEGINS 05/86 --
05/86
! ANPRM (51 FR 19561). COMMENT ENDS 09/86 --
09/86 ~I
, ANPPM (51 FR 19561). RESOLUTION OF 02/87 --
03/87 j PUBLIC COMMENTS l
} SUOMIT OPTIONS TO NRR DIRECTOR IN 03/87 --
04/87 i SECY PAPER i '
j SUBMIT SECY PAPER TO EDO 04/87 --
04/87 SUBMIT SECY PAPER TO COMMISSION 04/87 --
04/87
! COMMISSION REVIEW 06/87 --
06/87 i
PROPOSED RULE TO CRGR/ACRS (29) 05/88 05/88 .--
1 PROPOSED RULE TO ECO 05/88 06/88 --
I t
- PROPOSED RULE ISSUED 10/88 08/88 --
-l f FINAL RULE FOR CRGR/ACRS REVIEW (53) 04/89 04/89 --
j FINAL RULE FOR EDO REVIEW 04/89 05/89 --
-l 1
4 FINAL RULE ISSUED 09/89 08/89 '
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1 Q , - J RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 95 ISSUE NUMBER: 135 TITLE: STEAM GENERATOR AND STEAM LINE OVERFILL ISSUES W0RK SC0PE
~
h khPkbVEb bbkbkhk hbhihbkkhb ikkbEhfhbRkbh9hhkhbbbkkbOhkkh T. REACTOR VESSEL INVENTORY MEASUREMENT TASK 4: REVIEW EFFECTS OF WATER HAMMER,
- 8. REACTOR COOLANT PUMP (RCP) TRIP OVERFILL AND WATER CARRYOVER ON SECONDARY SYSTEM
- 9. CONTROL ROOM DESIGN REVIEW AND CONNECTING SYSTEMS AND DEVELOF PROPOSALS FOR
- 10. EMERGENCY OPERATING PROCEDURES MITIGATING THE CONSEQUENCES. CONSIDER THE EFFECTS
- 11. ORGANIZATIONAL RESPONSES OF SAGGING DUE TO WATER WEIGHT, OPERABILITY OF VALVES
- 12. REACTOR COOLANT SYSTEM PRESSURE CONTROL AND OTHER COMPONENTS WHEN SUBJECTED TO TWO-PHASE THIS TASK WILL ENTAIL REVIEW OF THE FLOW OF LIOUID.
PRIORITIZATION AND RELATIONSHIP TO OTHER GENERIC STATUS TECHNICAL CONTRACT HAS BEEN AWARDED TO SCIENTECH 4 SATISFACTORILY. DRAFT REPORTS HAVE BEEN RECEIVED FROM INC. THE CONTRACTOR IS PROGRESSING ON TASKS 1 2 3 AND THE CONTRACTOR ON TASK 3 AND TASK 4.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION ISSUE NUREG/CR- NONE REVISE AND ISSUE SRP SECTION 15.6.3 ISSUE DRAFT REGULATORY GUIDE ON EDDY CURRENT TESTING ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE Shkkh~Phkhkhhkhkbhhbkbh5 bkh8h --
hhhhh STAFF / CONTRACTOR MEETING WITH ACRS 07/87 --
08/87 CONTRACTOR COMPLETES TASKS 1,2,3 & 4 10/88 10/88 --
STAFF COMMMENTS ON DRAFT 11/88 11/88 --
CONTRACTOR'S REPORT FINAL CONTRACTOR'S REPORT 12/98 12/88 --
AS OF FY88 OUARTER 2
RUN DATE: 05/11/88 GENERfC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 96 ISSUE NUM3ER- 135 TITLE STEAM GENERAT9R AND STEAM LINE OVERFILL ISSUES ORIGINAL CURRENT ACTUAL M ILES T ON E S DATE DATE DATE STAFF PREPARE DTR PACKAGE 02/89 02/89 --
DIVISION DEPUTY DIRECTOR 03/89 03/89 --
RE'JIEW OF DTR COMPLETED CONCUPRENCE ON DTR BY OTHER OFFICES 05/8) 05/89 --
DTR PACKAGE TO CRGR (29) 05/89 05/89 --
ACRS REVIEW OF DTR COMPLETED 07/89 07/89 --
CRGR REVIEW OF DTR COMPLETED 07/89 07/89 --
FRN OF ISSUANCE OF DTR 10/89 10/89 --
FOR PUBLIC COMMENTS COMPLE TE DE REVIEW PUBLIC COMMENTS AND 03/90 03/90 --
PREPARE FTR PACKAGE DIVISION DEPUTY DIRECTOR 04/90 04/90 --
FTR REVIEW COMPLETED CONCURRENCE ON FTR BY OTHER OFFICES 06/90 06/90 --
REVIEW FTR PACKAGE TO CRGR [53) 06/90 06/90 --
CRGR PEVIEW OF FTR COMPLETED 08/90 05/90 --
FRN OF ISSUANCE OF FTR I/90 11/90 --
AS OF FY88 CUARTER 2 9 9 e
- y. -
f% ,f
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l RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 97 ISSUE NUMBER- A-3, 4 AND 5 TITLE STEAM GENERATCR TUBE INTEGRITY IDENTIFICATION DATE: 01/78C PRIORITIZATION DATE- 01/78C TYPE: USI PRIORITY: U TASK MANAGER: E. MURPHY OFFICE / DIVISION / BRANCH NRR / DEST /EMTB ACTION LEVEL ACTIVE STATUS:
TAC NUMBERS-. M06114 RESOLUTION DATE 06/88 WORK AUTHORIZATION: COMMISSION APPROVAL OF ISSUES A-3 A-4 AND A-S AS USI*S IN IS78.
FIN CONTRACTOR CONTRACT TITLE B2314 PNL LATER B2315 PNL LATER LATER SAI VALUE-IMPACT ANALYSIS OF REC ON SG TUBE DEGRAD.
W0RK SC0PE RhPbRhhShbbE PREPkbbbbhkhE NRb b kbRkhhb H RkPbRh hS kb kbENhhhh kbhhbNh Hkh Wbbib hh hhhhbhkVh )N PROGRAM FOR THE RESOLUTION OF USI'S A-3. A-4 AND A-5 TO SIGNIFICANTLY REDUCING THE INCIDENCE OF STEAM GENERATOR TUBE ADDRESS THE AREAS OF STEAM GENERATOR INTEGRITY. PLANT DEGRADATION. THE FREQUENCY OF TUBE RUPTURES AND THE SYSTEMS RESPONSE, HUMAN FACTORS. RADIOLOGICAL CONSEQUENSES CORRESPONDING POTENTIAL FOR SIGNIFICANT NON-CORE MELT AND THE RESPONSE OF VARIOUS ORGANIZATIONS TO A STEAM RADIOLOGICAL RELEASES, AND OCCUPATIONAL RADIOL UGICAL GENERATOR TUBE RUPTURE. A GENERIC RISM ASSESSMENT IS TO BE EXPOSURES AND WHICH WOULD BE EFFECTIVE IN MITIGATING THE PROVIDED ON THE RISK FROM STEAM GENERATOR RUPTURE EVENTS. CONSEQUENCES OF SGTR EVENTS.
STA TUS A PACKAGE HAS BEEN PREPARED THAT CONSISTS OF A STAFF 'S TECHNICAL RESOLUTION OF USI'S A-3. A-4 AND A-S.
COMMISSION PAPER TRANSMITTING NUREG-0844 WHICH DOCUMENTS THE THE PACKAGE WAS DELAYED TO RESOLVE CGC COMMENTS.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION NUREG-0844 MAJOR FINDINGS EMERGING FROM THIS DROGRAM HAVE INCLUDED THE FOLLOWING:
SGIR'S DO NOT CONTRIBUTE A SIGNIFICANT FRACTION OF THF EARLY AND LATENT CANCER FATALITY RISKS ASSOCIATED WITH OTHER REACTOR EVLNTS AT A GIVEN SITE. THE INCREMENT OF RISK ASSOCIATED WITH SGTR EVENTS IS A SMALL FRACTION OF THE ACCIDENTAL AND LATENT CANCER FATALITY RISKS TO WHICH THE AS OF FY88 QUARTER 2 i
._ . _ _ _ - _ - _ - - . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ - - _ _ _ _ - . _ - _ _ _ _ - _ e
RUN DATE: 05/11/88 GENERIC ISSUE MANAuEMENV CONTROL SYSTEM PAGE: 98 ISSUE NUMBE9. A-3, 4 AND 5 TITLE STEAM GENERATOR TUBE INTEGRITY AFFECTED DOCUMENTS PROBLEM / RESOLUTION GENERAL PUBLIC IS ROUTINELY EXPOSED.
THE STAFF HAS RECCMMEh0ED ACTIONS WHICH HAVE BEEN FOUND TO BE EF FECTIVE ME ASURES F OR SIGNIFICANTLY REDUCING (A) THE INCIDENCE OF TUBE DEGRADATION, (81 THE FEEQUENCY OF TUBE RUPTURES AND THE CORRESPONDING POTENTIAL FOR SIGNIFICANT NON-CORE MELT RELExSES. AND (C) OCCUPATIONAL EXPOSURES AND WHICH WOULD BE EFFECTIVE IN MITIGATINS THE CONSEQUENCES OF SGTR'S THESE ACTIONS ARE CONSISTENT WITH GOOD OFERATING AND ENGINEERING PRACTICES AND ARE COST EFFECTI"E. ADOPTION OF THESE ACTIONS BY LICENSEES WOULD FURTHER REDUCE PUBLIC RISK AND PROVIDE ADDED ASSURANCE THAT RISK WILL CONTINUE TO BE SMALL.
THE STAFF HAS ISSUED GL 85-02 TO INFORM LICENSEES AND APPLICANTS OF THE STAFF RECOMMENDED ACTIONS. RE SPONSF.S TO THE GENERIC LETTER INDICATE THAT THE LARGE MAJORITY OF LICENSEES AND APPLICANTS ARE POLLOWING PRDGRAMS. PRACTICES.
AND/OR PROCEDURES WHICH ARE PANTIALLY TO FULLY LONSISTENT OR EQUIVALENT TO THE STP'F RECOMMENDED ACTIONS IT APPEARS IHAT BOTH INDUSTRY INITIATIVE AND THE STAFF RECOMMENDATIONS HAVE BEEN RESPONSIBLE FOR SIGNIFICANT IMPWOVEMENTS TO PLANT PROGRAMS OVER THE PAST FEW VEARS.
LOW RISK FROM SGTR .1 ELATED CAUSES CAN CONTINUE TO BE ASSURED THROUGH IMPLEMENTATION OF PROGRAMS WHICH ARE EFFECTIVE IN ENSURING STEAM GENERATOR TUBE INTEGWITY AND SGTR MITIGABILITY IN ACCORDANCE WITH 10 CFR 100 APPENDICES A AND 8. AS HAS BEEN TRUE IN THE >AST. UTILITIES MUST BE VIGILANT AGAINST NEW OP C,;*% L PROBLEMS WHICH MAY NECESSITATE PREVENTIVE. DIAGNOSTIC AND/OR CORRECTIVE ACTIONS BEYOND NORMAL UTILITY PRACTICES AN9/OR REGULATORY REQUIREMENTS. TtfE S'AFF WILL CONTINUE TO MONITOR STEAM GENERATOR OPERATING EXPERIENCES AS AN INDICATOR OF THE EFFECTIVENESS OF UTILITY PROGRAMS.
FINAL PUBLICATION OF NUREG-0844 WILL CONSTITUTE RESOLUTION Of USI'S A-3. A-4. AND A-5.
ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE DTR ISSUED BY DSRO FOR STAFF COMMENT 11/82 --
11/82 AS OF FY88 CUARTER 2 O O O
. m_ .. - __- - . _ _ ____m-- __ m_._ _ _s .m .- . . . - . _ _ _ _ _ _ . _ _ _ . . _ _ . . _ _
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RUN DATE: 05/1I/88, GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 99 1
i j ISSUE NUMBER: A-3, 4 AhD 5 TITLE: STEAM GENERATOR TUBE INTEGRITY i
i I ORIGINAL CURRENT ACTUAL NES DATE DATE DATE :t 1 MILESi ....--..-- -.....-... -----.....
] - . . . - - . . - . . . . - - . . _ . . . . . ..-----------.......
1 eTAFF COMMENTS TO DSRO 12/82 --
12/82
}' 06/83 DTR COMPLETED PACKAGE TO NRR DIRECTOR 06/83 --
l '
d DTR PACKAGE TO CRGR (29.53) 09/83 -.
09/83 CRGR REVIEW OF DTR COMPLETE 10/83 --
LO/83
)
! ISSUE DTR FOR PUBLIC COMME NT 04/85 --
04/85 f ISSUE STAFF DTR RECOMMENDED ACTION 04/85 --
04/85 4 GENERIC LETTER 85-02)
FTR COMMISSION PAPER APPROVED BY NRR DIRf 02/86 --
02/86 l (EVALUATION OF RESPONSFS TO GL 85-02).
! EDO RETURNED COMMISSION PAPE R WITH 03/86 --
03/86 f
COPSTNTS ON FTR t
1 I COMrtISSION PAPER TO EDO WITH FTR 03/86 --
03/86 .;
k, EDO APPROVAL OF FTR 04/86 --
03/86
} SUSIIIT FTR PACKAGE TO NRR DIRECTOR 04/87 --
04/87 N
i SUBP1IT FTR PACKAGE TO EDO 12/87 06/18 -- i 4
. ISSL'E FTR PACMAGE TO COMMISSION 12/87 06/88 --
f PUS 11SH NUREG-0844 12/87 06/88 --
a AS OF F Y B 8 ' OUAR TER 2 -
l I
I 1
l- ._ _ - - _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . . __.. _
CUN DATE: C3/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PA.GE : 100 ISSUE NUMBER- A-1r TITLE SYSTEM INTERACTIONS IN NUCLEAR POWER PLANTS IDENTIFICATION DATE: 01/78C PRIORITIZATION DATE 01/78C TYPE: USI PRIORITY: U TASK MANAGER D. THATCHER OFFICE / DIVISION / BRANCH RES /DE /EIB ACTION LEVEL- ACTIVE STATUS.
TAC hlEBERS RESOLUTION DATE 09/89 WORK AufMORIZATION. COMMISSION DESIGNATION OF SYSTEM INTERACTIONS AS A USI FIN CONTRACTOR CONTRACT TITLE 80h89 Okhl bbRVkY k kVkL bF bYbhfM kN b bN kVkNSkbbbRbES WOR K SC0P E THE SCOPE OF WORK TO RESOLVE THE ISSUE INCLUDES. COMPARISON: 14) SCREEN EVENTS FOR SAFETY SIGNIFICANCE (1) SEARCH FOR COMMON CAUSE EVENTS. (2lTREMDS/ 151 REVIEW-DEFINE SEARCH METHODS. AND (6 ) COMPARE /
PATTERNS OF COMMON CAUSE EVENTS; l3) INDIAN POINT E VALUATE ME THODS S T A T US MEETINGS WERE HELD WITH CRGR IN 4/86 AND WITH N0i AGAEE WITH THE PROPOSED RESOLUTION AND IN A S/13/86 THE ACRS IN 6/86 TO REVIEW THE DRAFT OF THE PROP. LE TTE R TO THE EDO OUTLINED RATHER BROAD CONCERNS.
RESOLUTION CRGR BASICALLY AGREED WITH THE APPROACH THE STAFF ADDRESSEb THE ACRS LETTER. BECAUSE OF BUT CONCLUDED THAT THE PACKAGE NEEDED TO BE REVISED THT NATURE OF THE ACRS CONCERNS. THE STAFF HAS INITIATED TO REFLECT THE DISCUSSIONS AT THE MEETING. ACRS DID A ScPARATE ACTION TO ADDRESS THEIR CONCERNS.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION THE FOLLOWING TECHNICAL REPORTS HAVE BEEN OR WILL THE ACRS S/13/86 LETTER OUTLINED A NUMBER OF BROAD BE PUBLISHED CONCERNS SEE ABOVE.
- 11) NUREG/CR-1321. ~ FINAL REPORT - PHASE I. SYSTEMS A PROPOSED RESOLUTION PACKAGE HAS BEEN DEVELOPED. AND INTERACTION METHODOLOGY APPLICATIONS PROGRAM.* AN ADVANCED COPY WAS SENT TO OTHER OFFICES IN JULY 1987 SNL (SAND 80-08841. APRIL 1980. OGC CONCURRED BUT NRR HAS NOT A MEETING WAS HELD WITH NRR (2) NUREG/CR-1859 SYSTEMS INTERACTIONS STATE-OF- IN NOVEMBER 1987 AND NRR COMMITTED TO SUPPLY COMMENTS BY THE-ART REVIEW AND METHCDS OF EVALUATION." DECEMBER 31. 1987 THE CRGR PACKAGE WAS REVISED TO ADDRESS LLNL. JANUARY 1981. NRR COMME N T S . NRR CONCURRENCE IS EXPECTED 4/88 (3) NUREG/CR-1896 REVIEW OF SYSTiMS INTERACTION MLIN000LOGIES." PNL JANUARY 1981 AS OF FY88 OUARTER 2 9 9 9
A RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTE*4 PAGE: 101 ISSUE NUMBER: A-17 TITLE: SYSTEM INTERACTIONS IN NUCL(AR POWER PLANTS 1
AFFECTED DOCUMENTS PROBLEM / RESOLUTION (4) NUREG/CR-IS01, "REVIEW AND EVALUATION OF SYSTEMS INTERACTION METHODS." BNL 1981.
(5) NUREG/CR-2915 "INITIAL GUIDANCE ON DIGRAPH MATRIX ANALYSIS FOR SYSTEMS INTERACTION STUDIES."
LLNL (UCID-19457). MARCH 1983. '
(6) NUREG/CR-3593 "SYSTEMS INTERACTION RESULTS FROM THE DIGRAPH MATRIX ANALYSIS OF A NUCLEAR POWER PLANT *S HTGH PRESSURE SAFETY INJECTION SYSTEMS "
ANALYTIC INFORMATION PROCESSING AND 4.LNL, JULY 1984.
(7) NUREG/CR-3922, "SURVEY AND EVALUATION OF SYSTEM INTERACTION EVENTS AND SOURCES." ORNL, t , JANUARY 1985.
(8) NUREG/CR.4179, "DIGRAPH MATRIX ANALYSIS FOR SYSTEMS INTERACTIONS AT INDIAN POINT UNIT 3 ABRIDGED VcRSION," (VOL.1, TO BE PUBLISHED; VOLS.
2=6 WILL 8E AVAILABLE IN THE NRC PUBLIC DOCUMENT ROOM, 1717 H STREET. N.W., WASHINGTON, DC 1 LLNL j (9) NUREG/CR-4207, "FAULT TREE APPLICATION TO THF 4
STUDY OF SYSTEMS INTERACTIONS AT IN3IAN POINT 3,"
t BNL, APRIL 1985.
! (10) NUREG/CR-4261, "ASSESSMENT OF SYSTEM INTERACTION
. EXPERIENCE IN NUCLEAR POWER PLANTS, " OPNL,
- JUNE 1986.
(11) NUREG/CR-4306, "REVIEW AND EVALUATION OF SPATIAL SYSTEM INTERACTTION PROGRAMS, ORNL, DECE MBER 1986.
A PROPOSED RESOLUTION OF SYSTEM INTERACTIONS CONSISTING OF A RFGULATORY ANALYSIL AND SUPPORTIK3 NUREG WILL BE ISSUED FOR PUBLIC COMMENT.
i
- ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE DTR ISSUED BY DSRO FOR STAFF COMMENT 03/85 --
08/85 STAFF COMMENTS TO DSRO ON DTP 04/85 --
11/85 DTR PACKAGE TO NRR DIRECTOR 12/85 --
03/86 i
AS OF FY88 OUARTER 2 i
1
i l KUN DATE: 03/11/88 1
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: IOP ISSUE NUMBER: A-17 TITLE: SYSTEM INTER ACT IONS IN MtCLE AR POWER PLANTS ORIGINAL CURRENT ACTUAL
.____.__..__ N !_b.b_E I_9_U b_h___________,__
_ - ___90lb___ __ 901b___ .__96!b___
03/86 PREPARE DTR PACKAGE 07/87 --
07/87 CIVISION DE PUTY DIRECTOR 08/87 --
08/87 REVIEW COMPLETED CONCURRENCE BY OTHER OFFICES (OGC CONCURRED. 10/87 04/88 --
NRR REVIEW NOT COMPLETEDI REVIEW PACKAGE TO CRGR (29) 10/87 04/88 --
i ACRS REVIEW OF DTR COMPLE TED 12/87 06/88 _-
CRGR REVIEW OF DTR COMPLETED 05/86 06/88 --
FRN NOTICE OF ISSUANCE OF PROPOSED 0%/86 09/88 --
RESOLUTION FOR PUBLIC COMMENT COMPLETE DE REVIEW OF PUBLIC COMMENTS 08/86 02/89 --
AND PREPAnZ FINAL RESOLUTION PACKAGE DIVISION DEPUTY DIRECTOR 09/88 03/89 --
REVIEW OF FTR COMPLETED CONCURRENCE BY OTHER OFFICES AND 10/86 04/89 -.
PACKAGE TO CRGR (s3)
CRGR REVIEW OF FTR COMPLETED 01/89 06/89 --
FRN OF ISSUANCE OF FTR 12/86 09/89 --
AS OF FY88 QUARTER 2 i
i O O O
7- .
N RUN DATE: 05/II/88 GENERIC ISSUE MANAGEMENT CONTROL SYSIEM PAGE: 103 ISSUE NUMBER: A-29 TITLE: NUCLEAR POWER PLANT VULNERABILITY TO SABOTAGE IDENTIFICATION DATE: 06/78C PRIORITIZATION DATE- II/83C TYPE GSI PRIORITY: M TASK MANAGER: A. SERKTZ OFFICE / DIVISION / BRANCH. RES /DRPS/RPSI ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE: 06/88 WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN FIN CONTRACTOR CONTRACT TITLE B2995 PNL EVALUATE PROBABILITY OF NUCLEAR PLANT SABOTAGE W0RK SC0PE l GSI A-29 DEALS WITH THE VULNERABILITY OF NUCLEAR POWER PLANT SYSTEMS TO INSIDER TAMPERING OFFSET SUCH POTENTIAL SABOTAGE (TASK 2): AND (C) l AND SABOTAGE. AND THE RISK RESULTING FROM SUCH AN ESTIMATE OF CMF AND RISKS FOR THE MOST IMPORTANT ACTIONS. SYS TEMS (TASK 31 THE RESULTS OF THESE TASKS I
k THE CURRENTLY PLANNED EFFORT EXTENDS (IE.. ESTIMATED CMF*S AND RELEASES) WILL BE A MEY THE PRIOR WORK TO OBTAIN: (Al A BETTER ESTIMATE FACTOR IN ESTABLISHING THE NEED FOR A DETAILED OF THE PROBABILITY OF SABOTAGE UTILIZING FIELD REGULATORY ANALYSIS WHICH WOULD INCLUDE AN EXTENSIVE
, EXPERIENCE (TASK 11; (B) A MANKING OF THOSE COST ESTIMATING EFFORT.
SYSTEMS MOST VULNERABLE AND POSSIBLE METHODS TO i
STA TUS DROPPED AND NOT SCHEDULED DUE TO UNAVAILABILITY OF ARE RFPORTED IN NUREG/CR-4392 AND NUREG/CR.4462 TASK MANAGER THE RESULTS OF PRIOR STUDIES BY BNL AND PNL RESPECTIVELY.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION TO BE DETERMINED PLANNED FY-86 FUNDING WAS CANCE' LED: PROJECT START WAS DEFERRED TO FY-87. RESOLUTION WILL BE PACED BY AVAILABILITY AND OBLIGATION OF FUNDS. FY-87 FUNDING WAS NOT MADE AVAILABLE. TASK VANAGER UNAVAILABLE. CURRENT TASK MANAGER WORKING ON A-44 B-56. AND II.E.4.3. NO OTHER TASK MANAGER AVAILABLE.
AS Of FY88 OUARTER 2
_._C
RUN DATE: 03/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 104 ISSUE NUMBER: A-29 TITLE- NUCLEAR POWER PLANT VULNERABILITY TO SABOTAGE ORIGINAL CURRENT ACTUAL MILEST0N ES DATE DATE DATE hkP khbbhh fhR bbbkN --
/ 3 FINAL TAP ISSUED 04/84 --
02/84 CONTRACTOR SUPPORT (A) PROPOSAL SOLICITED 02/84 --
02/84 (D) PROPOSAL EVALUATED 03/84 --
08/84 (C) CONTRACT ISSUED 04/84 --
08/84 DFVELOP METHOD TO EVALUATE SABCTAGE 04/85 --
04/85 VULNERABILITY REDUCTION MLASURES NUREG/CR-4392 EVALUATE ALTERNATIVF MEANS OF 11/85 --
11/85 SABOTAGE REDUCTION NUREG/CR-4462 RECEIVE 198A PROPOSAL 05/86 --
05/86 ISSUE CLOSE00T MEMO 06/88 06/88 --
AS OF FY88 QUARTER 2 9 -
9 - - -
9
\j (. '
ks RUN DATE: 05/II/88 GENERIC ISSUC P ANAGEMENT CONTROL SYSTEM PAGE: IOS ISSUE NUMBER: A-40 TITLE. SEISMIC DESIGN CRITERIA IDENTIFICATION DATE: 01/79C PRIORITIZATION DATE- OI/79C TYPE: USI PRIORITY: U TASK MANAGER: K. SHAUKAT OFFICE / DIVISION / BRANCH- RES /DE /EIB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: RESOLUTION DATE - 06/89 l WORK AUTHORIZATION: COMMISSION DESIGNATION OF SEISMIC DESIGN CRITERIA AS A USI l
1 FIN CONTRACTOR CCNTRACT TITLE A044I LLNL VALUE/ IMPACT ASSESSMENT FOR SEISMIC DESIGN CRITERIA l
l W0RK SC0PE kHk PRbbkkM FbR RkbbLb bh bh bh k 4b bb hkh b b khCbRPbRNhEb 5hhb kHk kRP hh k bkbkR LRkVkhkbhkhk98k TWO PHASES: (Il TASKS CONCERNING SEISMIC INPUT A VALUE / IMPACT ANALYSIS HAS BEEN COMPLE TED F OR THE DEFINITIONS. AND (2) TASKS CONCERNING THE RESPONSE OF ASSESSMENT OF THE SAFETY IMPACT OF IMPLEMENTING THE STRUCTURES. SYSTEMS. AND COMPONENTS. ALL TECHNICAL SRP CHANGES PROPOSED AS A RESULT OF THE TECHNICAL WORK HAS BEEN COMPLETED ON BOTH PHASES. THE TECHNICAL FINDINGS (NUREG/CR-3480). THE SUPPORTING DOCUMENTS I WORK ACCOMPLISHED ON EACH OF THE TASKS DESCRIBED BELOW REQUIRED FOR REVIEW BY !HE CRGR HAVE BEEN PREPARED AND l IS SUMMARIZED AND EVALUATED IN NUREG/CR-II61 INCLUDE ALTERNATIVES TO THE STAFF POSITION ON SOIL-
"RECOMMENDED REVISIONS TO NOCLEAR REGULATORY COMMISSION STRUCTURE INTERACTION (SSI). A WORKSHOP ON THE SUBJECT SEISMIC DESIGN CRITERIA.",THIS REPORT WAS PREPARED BY OF SSI WAS HELD IN JUNE 1986 BY RES WITH COORDINATION LLNL FOR THE NRC, REFERENCE TO TECHNICAL REPORTS BY NRR IN THE WASHINGTON. D.C. METROPOLITAN AREA. THE DOCUMENTING COMPLETION OF A-40 TASKS AND OTHER PERTINENT OBJECTIVES OF THIS SSI WORKSHOP WERE TO REVIEW THE TECHNICAL WORK IS INCLUDED IN NUREG/CR-II61. IN ALTERNATIVES SUGGESTED BY THE STAFF ON SSI AND RELATED DEVE LOPING THE SPECIF IC RECOMMENDATIONS. THE LLNL STAFF LICENSING CONCEPNS JOINTLY BY REGULATORS. PRACTITIONERS.
AND THEIR TEAM OF EXPERT CONSULTANTS CONSIDERED ALL RESEARCHERS. UTILITIES AND OTHER INTERESTED GROUPS, AND i AVAILABLE AND APPROPRIATE TECHNICAL LITERATURE IN TO DISCUSS SUGGESTIONS TO IMPROVE THE LICENSING CRITERIA l ADDITION TO THE RESULTS OF USI A-40 TASKS. IN SOME ON SSI. THE OUTCOME OF THE SSI WORKSHOP HELPED THE CASES. RECDMMENDATIONS WERE DEVELOPED BY CONSENSUS OF STAFF DECIDE THE LICENSING CRITERIA TO BE INCLUDED IN E APERT OPINION AND STEMMED FROM UNPUBLISHED DATA. )HE PROPOSED REVISION TO THE SRP. THE CRGR PACKAGE RESE ARCH AND EXPERIENCE . WHICH INCLUDES THE TECHNICAL FINDINGS (NUREG/CR-3480).
l A REVIEW OF THE RECOMMENDATIONS BY THE NRC $TAFF AND THE PROPOSED SRP CHANGES WILL BE SUBMITTED TO CRGR HAS BEEN MADE AND A PROPOSED STAFF POSITION DEVELOPED FOR REVIEW AND APPROVAL. FOLLOWING APPROVAL BY CRGR.
IN A FORM OF RECOMMENDED CHAhGES IN SRP FOR REVISION. IN THE PROPOSED AMENDMENTS WILL BE SUBMITTED FOR PUBLIC SOME CASES. THE RECOMMENDATIONS HAVE ALREADY BEEN COMMENT PRIOR TO IMPLEMENTING.
I STA TUS BASED ON THE OUTCOME OF AN SSI WORKSHOP. JUNE 1986 AND NRR STAFF COMMENTS. THE CRGR PACKAGE HAS BEEN REVISED TO l
AS OF FY88 OUARTER 2 l
l 1
CUN DATE 05/11/88 GENERIC ISSUE MANAGEMENT CONTPOL SYSTEM PAGE- ICS ISSUE NUMBER- A-40 TITLE SEISMIC DESIGN CRITERIA S T A T US INCLUDE MODIFIED SRP REQUIREMENTS WITH SUGGESTED OPTIONS AND LARGE ABOVE-GROUND TANKS IN THEIR FACILITIES.
ACCE PT ANCE CRITERIA FOR SSI ANAiVSIS IN ADDITION THE STAFF THE PROPOSED RESOLUTION WAS REVIEWED BY CRGR IN FT E T ING IT PROPOSING A REVISED POSITION ON SE'SMIC DESIGN OF TANMS NO 130 ON MARCH 9. 1988 CRGR RECOMME NDE D ISSUING THE WHICH IS INCLUDED IN THE PROPOSED SRP THE CRGR PACKAGE PACMAGE FOR PUBLICATION FOLLOWING CLARIFICATION OF ALSO INCLUDES A PROPOSED 10 CFR SO S4fF) LETTER TO BE SENT IMPL E ME N T A T ION SCHEDULE.
TO SELECTED LICENSEES ASKING FOR 'NFORMATION ON DESIGN OF AFFECTED DOCUMENTS PROBLEM / RESOLUTION THE FOLLOWING IECHNICAL RE PORTS HAVE BEEN PUBLISHED NONE (1) NUREG/CR-1161. RECOMMEND REVISIONS TO NUCLEAR RfG-ULATORY COMMISSION SEISMIC DESIGN CRITERIA.- MAY 1980 (2) NUREG/CR-1717 SOIL-STRUCTURE INTERACTION METHODS SIM CCDE. SEPTEMBER 1979.
(3) NUREG/CR-4182 VERIFICATION OF SOIL-STRUCTURE INTERACTION METHCDS." MAY 1985.
(4) NUREG/CR-4329. ~ RELIABILITY EVALUATION OF CONTAINMENTS INCLUDING SOIL-STRUCTURE INTERACTION."
DECEMBER 1985.
(S] NUR E G/CR - 3 4 8 0 VALUE/ IMPACT ASSESSMENT FOR SEISMIC DESIGN CRITERIA. USI A-40.* AUGUST 1984
{6) NUREG/CP-0054 "PROCEEDINGS OF THE WORKSHOP DN SSI'. BETHESDA. MD. 6/16-6/19/86.
(7) REVISIONS TO SRP SECTIONS 2.5 2. 3.7.1 3 7.2.
AND 3 7.3. WILL BE ISSUED AS THE FINAL RESOLUTION OF USI A-40.
ORIGINAL CURRENT ACTUAL MILEST 0N E S DATE DATE DATE DTR ISSUED BY DST r0R STAFF COMMENT 09/83 --
03/83 STAFF COMMENTS ON DTR TO DST 10/83 --
10/83 COMPLETED DTR PACKAGE TO NMR DIRECTOR 11/83 --
12/84 REVISED DTR STAFF POSITION 03/86 --
04/86 AS OF TY88 QUARTER 2 9 9 e
RUN DATL: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 107 ISSUE NUMBER: A-40 TITLE- SEISMIC DESIGN CRITERIA ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE SSI WORKSHOP TO SUPPORT DTR 06/86 --
06/86 .;
ISSUE DTR FOR STAFF COMMENT 08/86 --
08/86 SUSMIT PROPOSED RESOLUTION PACKAGE 08/86 --
08/87 FOR MRC OFFICES REVIEW PROPOSED RESOLUTION PACKAGE 09/86 --
01/88 TO CRGR (29l i CRGR REVIEW OF DTR COMPLETE 10/46 --
03/88 ISSUE PROPOSED RESOLUTION FOR 11/86 06/88 -~
PUBLIC COMMENT END OF PUBLIC COMNENT PERIOD 02/87 08/88 --
ISSUE FINAL RESOLUTTON PACKAGE FOR 04/87 II/88 --
,l COMCL*ENCE BY OTHER OFF ICES i I
FINAL PACKAGE TO CRGR (53) 07/87 02/89 --
CRGR REVIEW OF FINAL RESOLUTION 08/87 04/89 ..
COMPLETE
, ISSUE FINAL RESOLUTION 10/87 06/89 --
i I '
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AS OF FY88 OUA*TER 2 i
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RUN DATE: G5/II/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 108 ISSUE NUMBER: A-44 TITLE STATION BLACMOUT PRIORITIZATION DATE 01/19C TYPE. USI PRIORITY. U IDENTIFICATION DATE: 01/79C OFFICE / DIVISION /8 RANCH. RES /DRPS/RPSI ACTION LEVEL: ACTIVE STATUS:
TASK MANAGER: A. SERKIZ RESOLUTION DATE 05/88 TAC NUMBERS:
WORK AUTHORIZATION: COMMISSION DESIGNATION OF STATION BLACKOUT AS A USI FIN CONTRACTOR C1NTRACT TITLE A1302 LLNL STATION BLACKOUT ACCIDENT ANALYSIS.
80744 LLNL RELIABILITY OF AC POWER SUPPLIES W0R K SC0PE kHE ShbPkbhWbRK b hkkblVk Hh kbbbE NblbbES kNklYb bh b kbkl bkNkhk bR RbLkkbkLkhYbkk AND LOSSES OF OFFSITE POWER DATA (1) EVALUATING THE EXPECTED FREQUENCY AND DURATION (4) E VALUA TIPlG ElSKS POSED BY ST ATION BLACKOUT 0F OFFSITE POWER LOSSES AT NUCLEAR POWER PLANTS. ACCIDF_ NTS AND ASSESSING THE EFFECTIVENESS OF (2) ESTIMATING THE RELIABILITY AND EVALUATING THE SAF E T Y IMPROVEMENTS IN REDUCING THOSE RISKS.
DOMINANT FACTORS AFFECTING THE RELIABILITY OF ONSITE EMERGENCY AC POWER SUPPLILS. (5) EVALUATING RISK REDUCTION AND COSTS OF VARIOUS FIXES TO PERFORM VALUE/ IMPACT ANALYSIS.
(3) PERF ORMING STATISTICAL CORRELATION AND TREND STA TUS THEbhMMhhhhNWkhhR EFEDhNh31/88 AFFECTED DOCUMENTS PROBLEM / RESOLUTION THE FOLLOWING TECHNIAL REPORTS HAVE BEEN COMMISSION DELAY OF AT LEAST 'NE FONTH MAY PULLISHED- AFFECT DATE OF ISSUING RULE.
(1) NUREG/CR-2989 "RELIABILITY OF EMERGENCY JULY AC POWER SYSTEMS AT NUCLEAR POWER PLANTS.
1983 (2) NUREG-CR/3992, "COLLECTION ANO EVALUATION OF COMPLETE AND PARTIAL LOSSES OF OFFSITE POWER AT NUCLEAR POWER PLANTS.~ FEBRUARY 1985 (3) NUREG-CR/3226 "SiATION BLACKOUT ACCIDENT ANALYSES.- MAY 1983.
AS OF FY88 OUARTER 2 O O O
L >
- J RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE. 109 ISSUE NUMBEP: A-44 TITLE: STATION BLACK 00T J
AFFECTED DOCUMENTS PROBLEM / RESOLUTION (4) NUREG-CR/4347 "EMERGENCY DIESEL GENERATOR OPERATING EXPERIENCE. 1981-1983." DECEMBER 1985.
(5) NUREG-1032 "EVALUATION OF STATION BLACKOUT ACCIDENTS AT NUCLEAR POWER PLANTS. TECHNICAL FINDINGS RELATED TO USI A-44." DRAFT REPORT FOR COMMENT, MAY 1986.
1
- 46) NUREG-1109,
- REGULATORY ANALYSIS FOR THE RESOLUTION OF UNRESOLVED SAFETY ISSUE A-44, STATION BLACKOUT." DRAFT REPORT FOR COMMENT. -
JANUARY 1986.
A PROPOSED RULE AND A DRAFT REGULATORY GUIDE ON STATION BLACKOUT WERE PUBLISHED FOR PUBLIC COMMENT
, IN THE FEDERAL REGISTER ON MARCH 21 AND APRIL 3.
1986 RESPECTIVELY. THE REGULATORY GUIDE PPOVIDES .
GUIDANCE ON ACCEPTABLE MEANS TO COMPLY WITH THE PROPOSED RULE.
GRIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE DTR ISSUED BY DST FOR STAFF COMMENT 10/83 --
12/83 STAFF COMMENTS ON DTR TO DST 11/83 --
12/83 COMPLETED DTR PACKAGE TO NRR DIRECTOR 11/83 --
12/83 DTR PACKAGE TO CRGR (29) 12/83 --
03/84 CRGR REVIEW OF DTR COMPLETED 01/84 --
05/84
~
PROPOSED RULE TO COMMISSION 02/85 --
05/85 EVALUATION OF NUGSB0 PROPOSAL -- --
09/85 COMMISSION MEETING ON LTR 04/85 --
09/85 COMMISSION MEETING ON DTR 04/85 --
11/85 COMPLETE DTR BACKFIT ANALYSIS -- --
01/86 AS Of FY88 OUARTER 2
RUN DATE. 05/11/88 GE NE P IC ISSUE MANASEMENT CONTROL SYSTEM PAGE- 11G ISSUE NUMP,ER A-44 TITLE STATION ELACFOUT ORIGINAL CURRENT ACTUAL M ILEST oN E S DATE DATE DATE COMMISSION DECISION TO ISSUE PULE 08/85 --
03/86 ISSUE PROPOSED RULE FOP PUB L I C C OMPE N T 09/85 --
03/86 E ND OF PUBLIC COMMENT ON FTR 12/85 --
06/86 FTP ISSUED BY DSRO FOR STAFF COMMENT 03/86 --
02/87 STAFF COMMENTS ON FTR TO DSPD 12/86 --
03/87 CCMPLETED FTR PACKAGE TO NoR DIRECTOR 03/86 --
04/87 FTR PACKAGE TO CPGR AND ACPS [53] 05/86 -
04/87 CDGR AND ACRS FTR PEVIEW CCMPLETED 06/86 --
06/87 i
l FINAL PULE TO CCMMISSION 08/*6 --
01/88 '
1 COMMISSION DECISION ON RULE 11/86 04/88 --
1 ISSUE FINAL RULE 12/86 05/88 --
l
! I AS OF FY88 CUAPTEP 2 O O O
LJ M V M V O O -
O RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 111 ISSUE NUMBER: A-45 TITLE SHUIDOWN DECAY HEAT REMOVAL REQUIREMENTS IDENTIFICATION DATE: 12/80C PRIORITIZATION DATE 12/20C TYPE. USI PRIORITY: U TASK MANAGER: R. WOODS OFFICE / DIVISION / BRANCH' RES /DRPS/RPSI ACTION LEVEL- ACTIVE STATUS TAC NUMBERS.
RESOLUTION DATE 04/90 l WORK AUTHORIZATION: COMMISSION APPROVAL OF USI A-45 IN 12/80 l
i FIN CONTRACTOR CONTRACT TITLE 1 .---- --- ----..
l A1309 $NL SHUTDOWN DECAV HEAT REMOVAL (DOE INTERAGENCY) l l
W0R K SC0PE '
h/kbbhkRkbhhbPRbVkbEbVhRkL PRbhEbhMkN Nk 5 PbbRkM kNbbbNbbE[kbkkbbkkbhkkkbbMhbhbh TECHNICAL DIRECTION AND INTEGRAIION FOR THE ENTIRE USI SUBCONIRACTORS ST A T US kPhbPbShhRhbbLbkkhbPkbKkbk N PkE PkRkh kbN k PLkN hPkbkhkbPkkkbBkkNbPkbPbkEbTbhhkbH GENERAL AGREEMENT HAS NOW BEEN REACHED THAT RESOLUTION WILL INDIVIDUAL PLANT TO DETERMI!;E WHAT IMPROVEMLNTS ARE NOT BE ACCOMPLISHED BY THE. GENERIC REQUIREMENT TO INSTALL A NEEDED AS PART OF THF IPE PROGRAM.
DEDICATED DECAY HEAT REMOVAL SYSTEM ON ALL PLANTS. RATHER.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION (I) NUREG/CR-2883 STUDY GF IMPACT AND VALUE OF IF PUBLIC COMMENTS ARE NOT REQUIRED. SCHEDULE ALTERNATIVE DECAY HEAT REMOVAL CONCLPIS FOR LWR'S IMPROVEMENT WOULD BE EXPECTED (EST. FTR 2/89).
(SANDIA)
(2) SECY 84-134 PORV*S FOR CE PLANTS (3) RE LATED REG GUIDES. SRP. AND SEVERE ACCID POLICY (4) SIX INDIVIDUAL PLANT CASE STUDIES (NUREG/CRS -
4458 4713, 4767 4710 4767 AND 4762)
ORIGINAL CURRENT ACTUAL M I LESTONE S DATE DATE DATE FINAL VALUE/ IMPACT REPORT FOR QUAD 07/85 --
08/85 CITIES AS OF FY88 OUARTER 2
CUN DATE 05/11/88 CENE2IC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 112 ISSUE NU"BER: A-45 TITLE SHUTDOWN DECAY HEAT REMOVAL REQUIPEMENTS ORIGINAL CURRENT ACTUAL M I LEST 0N E S DATE DATE DATE FINAL VALUE/ IMPACT REPORT FOR POINT BEACH 10/85 --
11/85 DRAFT VALUE/ IMPACT REPORT FOR COOPER 11/85 --
12/85 DRAFT VALUE/ IMPACT REPORT FOR TURMEY POINT 11/85 -
12/85 DRAFT VALUE/ IMPACT REPORT FOR TROJAN 01/86 -- --
(DELETEDI DRAF T VALUE/ IMPACT REPORT F02 ST LUCIE 04/86 --
08/86 DRAFT VALUE/ IMPACT REPORT FOR ANO-1 05/86 --
10/86 CONTRACTOR DRAFT
SUMMARY
REPORT OF ALL 06/86 --
12/86 PL At:T S DSRO DRAFT REGULATORY ANALYSIS ISSUED 08/36 --
09/86 FOR STAFF COMMENTS STAFF COMMENTS ON REG ANALYSIS TO DSRO 09/86 --
12/86 DTR ISSUED FOR STAFF COMMENTS 08/86 --
02/87 COMPLETE REVIEW OF NUMARC PRA CRITIQUE 03/88 03/88 --
COMPLETED REGULATORY ANALYSIS PACKAGE 10/86 04/88 --
TO MES DIRECTOR REVIEW BY ACRS SUBCCMMITTEE 05/88 05/88 --
REVIEW BY FULL ACRS COMMITTEE 06/88 06/88 --
DTR TO CPGR 11/86 07/88 --
ACRS LETTER 02/87 09/88 --
CRGR REVIEW COMPLETE 01/87 10/88 --
DTR ISSUED FOR PUBLIC COtHENT 03/87 12/88 --
l AS OF FY88 OUARTER 2 O _
O O
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GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 113 i -j ISSUE NUMBER: A-45 TITLE: SHUTDOWN DECAY HEAT REMOVAL REQUIREMENTS i
-l j ORIGINAL CURRENT ACTUAL 'l j -MILEST0NES DATE DATE DATE
, __.._ ......._....._______.______.___________ .._..___._ ..._____.. ...__...__ i j FTR TO RES DIRECTOR '
04/88 08/89 --
i l FTR TO CRGR/ACRS (53) 09/88 11/89 - - -
l ACRS LETTER 08/88 12/89 -- l t TR TO COMMISSION 12/88 01/90 -- i i
ISSUE FTR 02/89 04/90 -- !
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O RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 115 ISSUE NUMBER: A-47 TITLE- SAFETY IMPLICATION OF CONTROL SYSTEMS AFFECTED DOCUMENTS PROBLEM / RESOLUTION (1) NUREG/CR-4262. EFFECTS OF CONTROL SYSTEM F AILURES ON HAS BEEN COMPLETED. THE REASSESSMENT OF THE INTEGRATED TRANSIENTS AND ACCIDENTS AT A GENERAL ELECTRIC CONTROL SYSIEMS WAS COMPLETED ON MARCH 31 1988.
BOILING WATER REACTOR " VOLUMES 1 AND 2 MAY 1985. CUMPLE TION OF THESE ACTIVITIES AND ANY RESULTING (2) NOREG/CR-4326, "EFFECTS OF CONTROL SYSTEM F AILURES RECOMMENDATIONS ARE HANDLED INDEPENDENTLY OF JSI A-47.
ON TRANSIENTS AND ACCIDENTS AT A 3-LOOP WESTINGHOUSE THE PROPOSED RESOLUTION PACKAGE HAS BEEN REVISED TO PRESSURIZED WATER REACTOR." VOLUME 1 AUGUST 1985, REFLECT CRGR COMMENTS SUBJECT TO RESOLUTION OF CRGR VOLUME 2 OCTOBER 1985 COMME N I S , THE PACKAGE WILL BE ISSUED FOR PUBLIC (3) NUREG/CR-4047, "AN ASSESSMENT OF THE SAFETY COMMENTS IN APRIL. A REVISED SCHEDULE HAS BEEN IMPLICATIONS OF CONTROL AT THE OCONEE 1 PROVIDED NUCLEAR PL ANT FINAL RE PORT ," MARCH 1986.
(4) NUREG/CR-3991, "FAILURE MODES AND EFFECTS ANALYSIS lFMEA) 0F THE ICS/NNI ELECTRIC POWER DISTRIBUTION CIRCUITRY AT THE OCONEE 1 NUCLEAR PLANT," 10/85 (5) NUREG/CR-3692, *POSSIBLE MODES OF STEAM GENERATOR OVERFILL RESULTING FROM CONTROL SYSTEM MALFUNCTIONS AT OCONEE-1 NUCLEAR PLANT." JULY 1984.
(6) NUREG/CR-4449, "A PWR HYBRID COMPUTE R MODE L FOR ASSESSING THE SAFETY IMPLICATIONS OF CONTROL SYSTEMS," MARCH 1986.
(7) NUREG/CR-4265 "AN ASSESSMENT OF SAFETY IMPLICATIONS OF CONTROL AT THE CALVERT CLIFFS 1 NUCLEAR PLANT "
VOLUME 1 APRIL 1986, VOLUME 2 JULY 1986 (8) NUREG/CR-4387, "EFFECTS OF CONTROL SYSTEM F AILURE ON 1RANSIENT. ACCIDENT AND CORE-MELT FRFOUENCIES AT A GENERAL ELECTRIC BOILING WATER REACTOR." DECEMBER 1985.
(9) NUREG/CR-438S. "EFFECTS OF CONTROL SYSTEM FAILURES ON TRANSIENTS, ACCIDENTS, AND CORE-MELT FREQUENCIES AT A WESTINGHOUSE PWR, "NOVEMBER 1985.
l (10) NUREG/CR-4386, "EFFECTS OF CONTROL SYSTEMS FAILURES CORE-MELT FREQUENCIES AT A BABCOCK AND WILCOX PRESSURIZED WATER REACTOR," DECEMBER 1985 (11) NUREG/CR-3958, "EFFECTS OF CONTROL SYSTEM FAILURES CORE-MELT FREQUENCIES AT A COMBUSTION ENGINEERING PRESSURIZED WATER REACTOR," MARCH 1986.
(12) ORNL/NRC/LTR-86119. "GENERIC EXTENSIONS TO PLANT-SPECIFIC FINDINGS OF THE SAFETY IMPLICATIONS OF CONTROL SYSTEMS" (ORNL PROGRAM).
l A DRAF T STAFF REPORT ON THE TECHNICAL FINDINGS RELATED TO USI A-47 AND THE REGULATORY ANALYSIS REPORT WILL BE i i
ISSUED FOR PUBLIC COMMENT j AS OF FY88 OUARTER 2
C U) DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 116 ISSUE NUMBER- A-47 TITLE. SAFETY IMPLICATION OF CONTROL SYSTEMS ORIGINAL CURRENT ACTUAL M ILES T ON f S DATE DATE DATE DTR ISSUED BY DSRO FOR STAFF COMMENT 09/86 --
09/86 STAFF COMMENTS ON DTR TO DSRO 10/86 --
01/87 ISSUE DTR PACMAGE FOR DIVISION 11/86 --
05/87 REVIEW AND CONCURRENCE DIVISION DEPUTV DIRECTORS REVIEW OF DTR 05/87 --
05/87 COMPLETED CONCURRENCE BY OTHER OFFICES CCMPLETED 10/87 --
11/87 ISSUE DTR PACKAGE TO CRGR (79) 01/87 --
11/87 ACRS REVIEW OF DTR COMPLE TE 01/87 --
11/87 CRGR REVIEW OF DTR COMPLETE 02/87 --
12/87 FRN OF ISSUANCE OF PROPOSED 03/87 04/88 --
RESOLLITION FOR PUBLIC COMMENT REVISE DTR TO REFLECT PUBLIC COMMENTS 06/87 09/88 --
AND COMPLETE FTR PACKAGE DIVISION DEPUTY DIRECTOR 06/87 10/88 --
REVIEW COMPLETED CONCURRENCE BY OTHER OFFICES COMPLETE 07/87 11/88 --
CRGR REVIEW COMPLETED (53] 10/87 01/89 --
FRN OF ISSUANCE OF FINAL RESOLUTION 11/87 04/89 --
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- GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 117 ISSUE NUMBER: A-48 TITLE. HYDROGEN CONTROL MEASURES AND EFFECTS OF HYDROGEN BURNS IDENTIFICATION D' ATE: 12/kOC PRIORITIZATION DATE' 12/80C TYPE: USI PRIORITY: U TASK MANAGER: C. FERRELL OFFICE / DIVISION / BRANCH: RES /DRAA/SAIB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: RESOLUTION DATE 06/88 WORK AUTHORIZATION: COMMISSION DESIGNATION OF HYDROGEN CONTROL AS A USI IN DECEMBER 1980.
FIN CONTRACTOR CONTRACT TITLE B8686 NAS REVIEW & ANALYSIS OF NUCLEAR ENERGY & REG. ISSUES t WORK SC0PE THIS ISSUE WAS ORIGINALLY RELATED TO ALL TYPES OF WHETHER ALL IMPORTANT AREAS HAVE BEEN PROPERLY LWR AND CONTAINMENT COMBINATIONS. WITH PUBLICATION OF COVERED.
RULE CHANGES (10 CFR 50) RELATED TO DEGRADED CORES. THE (3) DETONATION ISSUE WAS REDEFINED TO BE ONLY RELATED TO BWR/ MARK III A. COMMENT ON THE NEED FOR EXTENDING EXPERIM2NTAL AND ICE CONDENSER PLANTS. WORK TO INCLUDE EFFECTS OF DETONATION ON GSI 121 RELATES TO HYDROGEN ISSUES FOR LARGE. EQUIPMENT RECOGNIZING THAT MOST WORK TO DRY CONTAINMENTS THAT AROSE AFTER THE RULE CHANGES WERE DATE HAS CONCENIRATED ON DEFLAGRATION. IN ISSUED TMI ITEM II.B.5(3) HAS GENERALLY BEEN VIEW Of THE DIFFICULTY OF DETONATION WORK AND CONSIDERED A RESEARCH (PHEHOMENOLOGY) ISSUE. NOT A THE LOW PROBABILITY ASCRIBED TO SUCH AN EVENT REGULATORY DECISION-MAKING ITEM. B. PROVIDE AN INDEPENDENT ASSESSMENT OF THE THE ENERGY ENGINEERING BOARD OF THE NATIONAL FOLLOWING RESEARCH: RECENT RESEARCH BY SNL ACADEMY OF SCIENCES ASSESSED THE TECHNICAL ISSUES RELATED HAS ESTABLISHED LOWER LIMITING CONCENTRATIONS TO THE FATE AND CONTROL OF HYDROGEN GENERATION IN LWR OF HYDROGEN (APPROX. 13.5%l IN AIR WHICH ACCIDENTS. THE EVALUATION INCLUDED THE FOLLOWING: WOULD SUPPORT A DETONATION. FURTHERMORE.
(I) SCALE-UP ADDITIONAL TESTING WITH STEAM IN THE A. EVALUATE EXPERIMENTAL DATA FROM VARIOUS TEST DEBATED DETONATION TUBE FACILITY HAS FACILITIES (FITS. %EGES, NTS) WITH RESPECT TO PROVIDED RESULTS INDICATING THAT STEAM ADDITION THE FOLLOWING OUESTIONS: (I) HOW TYPICAL ARE TO HYDROGEN-AIR MIXTURES HAD LITTLE EFFECT ON THE COMBUSTION MECHANISMS IN SMALL ENCLOSURES THE DETONABILITY OF MIXTURES.
AS COMPARED WITH FULL-SIZE CONTAINMENTS? (2) (4) JET FLAMES HOW WELL CAN THEY BE SCALED TO FULL-SIZE DEVELOP INFERENCES AND COMMENT ON THE QUALITY OF CONTAINMENTS? THE INFERENCES WITH RESPECT TO THE FOLLOWING B. EVALUATE THE ABILITY TO SCALE THE INSTRUMENT QUESTION: WHAT ARE TKi CONDITIONS UNDER WHICH TEMPEPATURES OBTAINED FROM SMALL-SCALE TESTS AUTO IGNITION OF FLAMES MIGHT OCCUR F OR RELEASE THROUGH ANALYTIC CODES TO THE TEMPERATURES OF A STEAM-HYDROGEN OR HYDROGEN JET INTO AN PREDICTED FOR FULL-SIZE REACTOR CONTAINMENTS. AMBIENT MIXTURE 7 (2) COMPLETENESS (5) SUSPENDED WATER EVALUATE SNL'S PROGRAM AND THE PROGRAMS SPONSORED EVALU4TE THE INFLUENCE OF SUSPENDED WATER DROPLETS BY THE INDUSTRV WITH RESPECT TO THE QUESTION OF ON HYDROGEN COMBUSTION IN A HYDROGEN-NITROGEN-AS OF FY88 OUARTER 2
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GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 119
^!
a ISSUE NUMBER: A-48 TITLE: HYDROGEN CONTROL MEASURES AND EFFECTS OF HYDROGEN BURNS i
ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE
'L j ISSUE HYDROGEN RULE 07/83 --
02/85 NATIONAL RESEARCH COUNCIL HYDROGEN 09/86 --
09/86 4 REPORT ON FINDINGS RECOMMENDATIONS RES ISSUE NOTICE OF PROPOSED COURSE OF ACTION 01/88 --
01/88 < l FOR STAFF REVIEW 3 NRR RESPONSE TO PROPOSED COURSE OF ACTION 02/88 --
03/88
- l ISSUE GENERIC
SUMMARY
REPORT FOR STAFF 06/87 --
03/88 i!
C0tNENT i
! STAFF COPMENTS TO RES/SAIB 07/87 -04/88 --
COMPLETED PACKAGE TO RES DIRECTOR 08/87 04/88 -- l j ISSUE
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REPORT 09/87 06/88 --
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 121 ISSUE NUMBER: 8-5 TITLE BUCKLING BEHAVIOR OF STEEL CONTAINMENTS AFFECTED DOCUMENTS PROBLEM / RESOLUTION TO ENABLE THE STAFF TO CONCLUDE THAT ALL EXISTING CONTAINMENTS ARE ADEOUATE REGARDING BUCKLING BEHAVIOR.
BY LETTER FROM S. BAGCHI TO R, BAER DATED 3/1/88 NRR STATED ITS CONCLUSION THAT:
(1) ALTHOUGH THE REVISED SRP DID REFLECT CURRENT STAFF PRACTICE. THERE WAS A LACK OF CONSENSUS AMONG THE NRR REVIEW STAFF REGARDING THE VALUES OF FACTORS OF SAFETY,.THAT BASES FOR THE PROPOSED CHANGES WERE LACKING. AND THERE WAS LITTLE SAFETY
- MPROVEMENT TO BE DERIVED FRDM THE PROPOSED LHANGES.
(2) 8ASED ON A QUALITATIVE REVIEW. NRR HAD CONCLUDED THAT EXISTING CONTAINMENT DESIGNS HAD ADEOUATE MARGINS AGAINST BUCKLING.
(3) ITEMS (1) AND (2) SHOULD BE USED AS THE TECHNICAL BASIS FOR RESOLVING THIS ISSUE .
RES HAS ACCEPTED THE NRR RECOMMENDATIONS AND A CLOSEOUT MEMORANDUM AND MEMORANDUM DOCUMENTING HISTORY AND CONTENT OF THE PROPOSED SRP REVISIONS ARE IN PREPARATION. IT IS EXPECTED THAT THESE MEMORANDA WILL BE ISSUED IN APRIL. 1988.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE LOS ALAMOS DRAFT REPORTS RECEIVED BY RES 07/86 --
11/86 RESULTS RECEIVED FROM RES 07/86 --
11/86 PROPOSED SRP REVISION PREPARED , 08/87 --
08/87 VALUE/ IMPACT STATEMENT PREPARED 07/85 --
08/87 DTR PACKAGE TO OTHER OFFICES FOR 07/87 --
09/87 REVIEW AND CONCURRENCE REQUEST NRR INPUT MEMO FOR CRGR PACKAGE 10/87 --
11/87 RECEIVE NRR RECOMMENDATION FOR ISSUE 03/88 --
03/88 RESOLUTION AS OF FY88 QUARTER 2 J
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v RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 123 ISSUE NUMBER: 8-17 TITLE- CRITERIA FOR SAFE TY-RELATED OPERATOR ACTIONS IDENTIFICATION OATE: 06/78C PRIORITIZATION DATE. II/83C TYPE: GSI PRIORITY:.M TASK MANAGER: C. GODDMAN OFFICE / DIVISION / BRANCH- RES /DRPS/RHFD ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: RESOLUTION DATE __
WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN (APPENDIX G)
FIN CONTRACTOR CONTRACT TITLE NONE NONE NONE W0R K SC0PE THE WORK SCOPE INCLUDES: (Il DEVELOP TIME CRITERION MANUAL OPERATOR ACTION OR AUTOMATIC ACTION. THE SCOPE OF FOR SAFETY RELATED OPERATOR ACTIONS: (2) DETERMINE WHi.NER THIS GENERIC ISSUE COVERS DESIGN BASIS ACCIDENTS OR EVENTS.
OR NOT AUTOMATIC ACTUATION WILL BE REQUIRED; AND (3) LEVELOP CRITERI A FOR SAFE TY RELATED OPERATOR ACTIONS DURING SEVERE GUIDANCE AND REVIEW CRITERIA FOR LICENSEE PROPOSALS TO USE ACCIDENTS WILL BE COVERED UNDER THE SEVERE ACCIDENT PROGRAM.
STATUS THIS ISSUE WAS TRANSFERRED FROM NRR TO RES WITH THE 4/87 NRC RESPONSE TIMES. ANSI /ANS 58.8 WAS PUBLISHED IN SEPTEMBER REORGANIZATION ( 4 /13/ 87 MEMO F ROM W RUSSELL TO T. SPEIS). 1984. THE GENERIC ISSUE WAS LATER TRANSFERRED TO NRR NO NO WORK HAD BEEN COMPLETED ON THE ISSUE PRIOR TO TRANSFER. WORK WAS COMPLETED BY NRR ON THIS ISSUE. WORK HAS BEGUN ON DURING 1983 AND 1984 RES WORKED ON THIS ISSUE. DURING DEFINING THE SCOPE OF THE PROBLEM AND DECIDING ON AN THAT TIME DATA WERE COLLECTED BY RES CONCERNING OPERATOR APPROACH FOR RESOLUTION OF THIS ISSUE.
- AFFECTED DOCUMENTS PROBLEM / RESOLUTION TO BE PROVIliD LATER LACK OF RESOURCES PREVENTED WORK DN THIS ISSUE BY RES.
RES IS CURRENTLY ATTEMPTING TO FILL A POSITION WHICH WILL MAKE MORE RESOURCES AVAILABLE FOR THE RESOLUTION OF GENERIC ISSUES. WHEN RESOURCES BECOME AVAILABLE. RES WILL PLAN AND SCHEDULE RESOLUTION OF THIS ISSUE CONSISTENT WITH ITS PRIORITY.
AS OF FY88 QUARTER 2 i - __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _
i PUM DATE: C5/11/88
,I GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 124 i
1 i IS0UE NUtdBER B-17 TITLE CRITERIA rce SAFETY-9 ELATED CPERATOR ACTIONS l
l OPIGINAL CURRENT ACTUAL I M I L EST 0N E 5 DATE DATE DATE i _____________________________________________ __________ ________ __________
l DEVELOP TAP 08/87 05/88 --
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TAC NUMBERS. RESOLUTION DATE 03/89 l WORK AUTHORIZATION; NRR FY-84 OPERATING PLAN. (APPENDIX G) l l FIN CONTRACTOR CONTRACT TITLE NONE NONE NONE l
I
, W0R K SC0PE REVIEW BWR UTILITY APPROACHES TO INCREASING SRV CONFORMANCE TO NSSS VENDOR INSTRUCTIONS: (2)
RELIABILITY TO OBTAIN SUFFICIENT DATA BASE TO SUPPORT DEMONSTRATING SUFFICIENT RELIABILITY OF 2-STAGE VALVES THE CONCLUSION THAT THIS ISSUE HAS BEEN RESOLVED. AFTER DESIGN AND/OR SYSTEM MODIFICATIONS, AND (3)
THE UTILITY APPROACHES MAY INCLUDE: (1) DEMONSTRATING USING DIFFERENT VALVES AND DEMONSTRATING THEIR SUFFICIENT RELIABILITY OF 3-STAGE VALVES BY STRICT RELIABILTY, STA TUS A REPORT WAS SUBMITTED BY THE OWNERS GROUP (OG) TAMING THE LARGE SETPOINT DRIFT INTO ACCOUNT FOR THE 06/08/85 THAT WAS EXPECTED TO RESOLVE THE ISSUE. A WORST CASE DESIGN BASIS TRANSIENT. BRUNSWICK 2 WOULD SUBSEQUENT BOSTON EDISON REPORT ON EXPERIENCE AT PILGRIM STILL HAVE MET THE APPLICABLE ASHE PRESSURE LIMIT. THE INDICATED THAT THE RECOMMENDATIONS OF THE OG REPGRT WERE NRR STAFF IS IN AGREEMENT WITH THE OG THAT THE SELECTION NOT SUFFICIENT TO RESOLVE THIS ISSUE. THE OG HAS OF NEW PILOT DISK MATERIAL IS AN ACCEPTABLE WAY TO RECOGNIZED THE NEED TO PURSUE THIS PROBLEM FURTHER AND RESOLVE THE STUCK PILOT DISK CONCERN, BASED UPON THE HAS EVALUATED SEVERAL POTENTIAL NEW PILOT DISK MATERIALS ASSUMPTION THAT PH 13-8MO PILOT DISKS WILL ELIMINATE THE THAT COULD ELIMINATE EXCESSIVE SETPOINT DRIFT RESULTING STUCK PILOT DISK CONCERN, A DRAFT RESOLUTION MEMO WAS FROM PILOT DISKS. THEY HAVE ASSEMBLED A MATERIAL PREPARED AND DISTRIBUTED TO NRR AND IE FOR COMMENTS ON SELECTION PANEL COMPOSED OF EXPERTS IN BOTH MATERIALS 6/4/86. THE CLOSEOUT MEMO WAS FORWARDED TO DSRO UPPER TECHNOLOGY AND NUCLEAR VALVE DESIGN. THE PANEL HAS MANAGE ME N T FOR CONCURRENCE IN MID-JUNE 1986. COMMENTS SELECTED PH 13-SM STAINLESS STEEL AS THE CANDIDATE WERE RECEIVED FROM THE DSRO DEPUTY DIRECTOR. IN ORDER MATERIAL 70 BE TO BE TESTED IN SEVERAL PLANIS DURING TO RESPOND TO ALL COMMENTS. A LETTER WAS REQUESTED FROM UPCOMING FUEL CYCLES. IN JANUARY 1986 CAROLINA POWER THE BWROG THAT FORMALLY DOCUMENTED THE TRIAL DISK AND LIGHT (CP&L) REPORTED THE CONTROVERSIAL RES'JLTS OF REPLACEMENT PROGRAM AND ITS SCHEDULE .
RECENTLY COF9LETED 2 BRUNSWICK SRV TESTS. SIX OF ELEVEN THE TASK MANAGER RECEIVED A LETTER FROM THE BWROG SRVS FAILED (0 OPEN AT 10 PERCENT OR MORE ABOVE NORMAL DATED 4/2/87, THE LETTER INCLUDED THE FOLLOWING:
SETPOINT. ON MAY 7, 1986, CP&L SUBMITTED AN LER WHICH A) BACKGROUND AND DESCRIPTION OF THE STUCK PILOT DOCUMENTED THE SRV FAILURE DATA. IN ADDITION, THE LER DISK CONCERN.
INCLUDED THE RESULTS OF ANALYSES THAT INDICATE THAT. B) DESCRIPTION OF ONGOING BWR OG PROGRAM OF BOTH AS OF FY88 OUARTER 2 l
_ _ - _ _ . _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ . _ - _ . . _ _ _ _ _ _ . _________.________c m__- ,-__4 -.__--_u_____= _ _ _ _- __ _ -__ _ - _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ . _ _ _ _ . _ . _ _ _ . _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _
CUM DATE: CS/11/83 GEME9IC ISSUE MANAGEME NT CO*TPCL SYSTEM PAGE 126 ISSUE NU*"BER. B-55 TITLE IFP80VE DELIABILITy or TADGET 80CK SArETf-PELIEF VALVES S T A T US IN PEACTCP AC ACCELERATED CCCSIC% TESTI%G ADDITIC4 ALLY THE $[TPOINT DWIFT COP 94ITTEE CHAIPwAN OF PM 13-t MO DISK MATERIAL HAS ADVISED THAT A PPOGPAM OF ACCELEPATED C0'R00104 Cl 8ESULTS OF Im SE RVICE EXPERIEEE IE VALVE TE ST I%G IS BEI%G PLA4%ED ACTUATIO%S IN RESPONSE TO PLAMT PRESSU*E AF TE R THE 4/12/87 h8C PECPGANIZATIC4 THIS ISSUE WAS TPAMSIENTS UP TO 1/87 TFAMSFEPPED WITH EIB TO DE/ PES IN MAY. 1937 A DECISIO4 ADDITIO4 ALLY. RE PCpTS wERE PECE IVED F 8 0+' N*C *E SION WAS Mt-DE BV R E S MANAGE ME N T TO POSTPCME ISSUAMCE OF THE II A C AECD C4 THE RESULTS OF SURVEILLA%CE T E S T I 5G OF PESOLUTION t'EF3 UNTIL ADOITICMAL TEST DAT A E X PECTED OVE R 2-STAGE 08V S PEMOVED FROM MATCH I AND TESTED AT THE APPPOXIMATELY THE NEXT lt McMTHS COULD BE EVALUATED WYLE LAS FIVE OF E LE VE N SpV S TESTED **AD PH 13-t*3 ASS',*4I%G THAT TEST DATA IS FAVCRABLE. IT IS (XPECTED THAT PILOT DISFS 404E OF THESE EXHIBITED PILCT D I S r. TO SEAT THE RESCLUTIGN PEMO CCULD BE ISSUED IM THE 2 ND Q8 JAP T E R OF STICRI%G THE SIX OTHEP SPV S TESTED HAD STEL'.ITE Fv-90 A DETAILED STATUS REPCRT DISCUSSING THE INDUSTPY DISKS. A C CEE GF THESE DID EXHIBIT ST I CF.1% AS F OUC . EFFOeT WAS PREPAPED IN DECEMBER 1987 A FEW CHAMGES WEPE 0ET P*ESSUPi FCR ALL OF THE PH-13 EMO SPV S DID %OT SEEDED TO PESPOND TO MANAGEME NT CC**"JE NTS AND THE STATUS DEVIATE F#CM THE NOMINAL VALUE BY M08E THA% PLUS/MINUS REpoPT WILL BE ISSUED IN JANUARf 1938 IT IS ANTICIPATED Two PE PCENT THAT THEPE WILL NOT BE FU97HER UPDATES IN GIPCS UMTIL THE THE % EXT PLANT WITH PH13-IMO PILOT DIS *S SCHEDULED Ek# 0G F INA L D E CO't"E CA T IO N 04 PILOT DISK MATEPIAL IS TO BE SHUT DLb4 IS BRUNSWICR 2- DATA FPCw THE $8v TESTS *ECEIVED SHOULD BE A(AILABLE 14 JA4UARY- 1988.
AF FECTED DDCL*ENTS PPCBLEM/DESOLUTION wnE THE RESOLUTICN OF THIS ISSUE IS AIFED AT IMCPEASIM THE RELIABILITY OF THESE VALVES TO MEET THE CURRENT PLANT TECHNICAL SPECIFICATIOTS. PILOT DISMS OF PH 13-M0 WILL BE TESTED Im CEPTAI4 PLANTS WITH THE OBJECTIVE Cr ELIMIMATING EXCESSIVE SETPCINT D*IFT T HE ACT IOMS T AP.E N T HUS F A9 BY THE OG AMD TME OG PROGFAM APE RESPOMSIVE TO ISSUE VE E*PECT THAT THIS ISSUE WILL BE RESOLVED WITH MINIMUM STAFF EFFCET NEEDED ONLY TO MCMITO8 THEIR PROG 2AM VE wtLL WGPK WITH THE CG A%D PROVIDE THEM WITH OUR EVALUATIGN OF THEIS PROGR Aw AND ICICATE CU5t INTENT TO PELY C4 THEIP PPGG8AM TO DESOLVE THE ISSUE A GEuE8IC ISSUE CLOSEDUT FEMO WAS ISSUED THAT PEF LECTED THIS UCEPSTACIMS AT THE COMPLETIOM OF THE OG P1t0GPAM. THE STAFF WILL PEVIEw THE I CUS T R Y PESOLUTIow AMD ISSUE A CLOSE 0UT MEMO IF *HE STAFF CONCUPS WITH THE PESOLUTICs AS Cr FVft CUAPTEP 2 O O O
_ _. _. _. . . _ . . _. ._ m . . _ _ . _ ___ .m _._ _ _ _.
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j ISSUE NUMBER: B-55 TITLE: IMPROVE RELIABILITY OF TARGET ROCK SAFETY-RELIEF VALVES i
ORIGINAL CURRENT ACTUAL j
M ILESTONES DATE DATE DATE I MEETING WITH BWR OWNERS SETPOINT DRIFT 12/83 --
11/83 i
! COMMITTEE a
l BWR OWNERS REPORT SUBMITTED 07/84 --
06/84 ;
4 BOSTON EDISON REPORT SUBMITTED -- --
08/84 t
, COMPLETION OF NRR EVALUATION OF OWNERS 10/84 -- <
10/84 '
1 GROUP AND BOSTON EDISON REPORTS 1
e COMMUNICATION TO OG RE: NRC -- --
03/85
!, COMMENTS / CONCERNS i
l OG PRESENTATION TO THE STAFF 10/85 --
10/85
! STAFF RECEIVES OWNERS' PROGRAM FOR 10/85 --
10/85
! ELIMINATING SET POINT DRIFT t
j OWNERS BEGIN TO INSTALL NEW PILOT DISKS 01/86 --
01/86 A TO TEST IN PLANT FOR ONE FUEL CYCLE !
4 .
l ISSUE STATUS REPORT ON INDUSTRY EFFORTS '12/87 -. '
01/88 4 EVALUTE INDUSTRY DATA & RECOMMENDATIONS 10/85 03/89 --
- AND ISSUE CLOSEOUT MEMO ,
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CUN DATE- CS/II/88 GE NE R IC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 128 ISSUE NUMBER. B-56 TITLE D.ESEL GENERATOR RELIABILITY IDENTIFICATION DATE: 06/78C PRIORITIZATION DATE II/83C TYPE GSI PRIORITY. H TASK MANAGER- A. SERKIZ OFFICE / DIVISION /8 RANCH RES /DRPS/RPSI ACTION LEVEL ACTIVE STATUS-TAC NUMBERS. RESOLUTION DATE 04/89C WORK AUTHORIZATION- NRR FY-83 OPERATING PLAN ( APPE NDI X G]
FIN CONTRACTOR CONTRACT TITLE A1806 SNL GUIDELINES FOR EMERG DIESEL GENERATOR (EDG) RELIABILITY PROGRAMS W0R K SC0P E THk hbRK bbbPk bF b 56 kSb[bSE[Y bbbRbkNkT[b THE bbNCLbbkN EFFbRhbN BSkWk((bkbkRkbkkb WITH THE PESOLUTION OF USI A-44 STATION BLACKOUT THE AT DEFINING THE PRINCIPAL ELEMENTS OF AN EDG PROPOSED RESOLUTION OF USI A-44 INCLUDES. AMONG OTHER RELIABILITY PROGRAM AND TECHNICAL GUIDELINES FOR THINGS. A RECOMMENDATION THAT THE RELIABILITY LEVEL OF NRC TO USE IN THE REVISION OF REGULATORY GUIDES.
EMEPGENCY DIESEL GENERATOR (EDG) BE MAINTAINED AT OR INSPECTION MODULES AND SRP SECTIONS DEEMED ABOVE SPECIFIED ACCEPTABLE RELIABILITY LEVELS APPROPPIATE STA TUS kbfPRkN Pkt kHkbhkFbR kHkkkhbtbhkbbbF PLkkkh PRbbRkkShkbbhbRk"MkRCH IhkB Hkh B-36 IS TO DEVELOP GUIDELINES FOR AN ACCEPTABLE EDG BEEN PREPARED AND WILL BE PUBLISHED THIS TECHNICAL RLLIABILITY PROGRAM TO ENSURE CONFORMANCE WITH THE EDG F INDIPGS REPOR T WILL BE UTILIZED BY THE STAFF IN TARGE T RE LIABILITY (0 95 TO 0.975) IDENTIFIED IN THE UNDERTAKING THE REVISIONS NOTED ABOVE. A SECOND PROPOSED RESOLUTION OF USI A-44. VOLUME. WHICH DEALS IN MORE DETAIL WITH UNDERLVING NUREG/CR-5078 VOL. I. "A RELIABILITY PROGRAM CAUSES AND PERFORMANCE MONITORING. IS SCHEDULED FOR EMERGENCY DIESEL GENERATORS AT NUCLEAR POWER FOR THE THIRD QUARTER OF FY-88.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION REGULATORY GUIDES (E.G. RG I 108 I 91. SRP THE SCHEDULE FOR RESOLUTION OF GSI B-56 HAS SLIPPED SECTIONS WILL BE REVISED AS REQUIRED REVISIONS DUE TO APPLICATION OF STAFF RESOURCES TO RESOLVE USI A-44 TO TECH SPECS. INSPECTION GUIDANCE AND PREPARATION IN FY-87 OTR 4 AND FY-88. QTR. I. THE REVISED CURRENT OF A GENERIC LETTER WILL ALSO BE NEEDED. NRR HAS DATES REFLECT THIS SLIPPAGE.
THE LEAD ON REVISING SUCH DOCUMENTS. THE CONCLUDING ACTIVITIES (I E.. CHANGES TO AS OF FY82 QUARTER 2 O O O
__.-__ ___ - _ = _ _ . _ _ =_ _ . _ . _ _ _ . _ _ _._____m__ 1 ... . _ _ _ ,_. . _ _ . ~ . _ . . . . - ..
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AFFECTED DOCUMENTS PROBLEM / RESOLUTION REGULATORY GUIDANCE AND RELATED REQUIREMENTSI WILL BE l PACED BY NRR INPUT. WHICH IS SCHEDULED FOR 4/88 BY l GILLESPIE TO SPEIS MEMO OF 2/23/88,
}
l I ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE
-i ----------------.....-------------.---------. ---------- ------.--- -------- -
DTR IDENTIFIED 02/83 --
02/83 i ISSUED BY DSI DIRECTOR FOR STAFF COMMENT 02/83 --
02/83 1
- PACKAGE TO NRR DIRECTOR 04/83 --
03/83 I PACKAGE TO CRGR (29) 05/83 --
07/83 CRGR REVIEW COMPLETE 06/83 --
07/83
, SCOPE OF ISSUE MODIFIED TO C00RDINATE 09/83 --
09/83
- TECHNICAL RESOLUTION OF B-56 WITH USI i A-44 SCOPE OF ISSUE MODIFIED TO CONSIDER 11/83 --
11/83 NUMBER OF COLD FAST START SURVEILL.ANCE TESTS h
4 COORDINATED GSI B-56 AND USI A-44 CRGR _02/84 --
01/84 j PAchAGE SENT TO NRR DIRECTOR I REVISED PACKAGE TO CRGR 04/84 --
03/84 j CRGR REVIEW COMPLETE 05/84 --
05/84 i ISSUED S0.54tF) GL 84 15 TO LICENSEES 06/84 --
07/84 1
{ RECEIVED PUBLIC COMMENTS 09/84 --
11/84 t
j ISSUED T/A CONTRACT TO BNL 06/85 --
06/85 l PUBLISH CONTRACTOR REPORT ON LICENSEE 04/86 -. 04/86 ;
.j RESPONSE TO 50.54tF]
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i AS OF FY88 OUARTER.2 i
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1 PUN DATE. 05/11/88 i
GE%E8IC IS0UE MA%AGEMENT CCNTROL SYSTEM PAGE 130 1 ISSUE E'MER - B-56 TITLE DIESEL GENE 8AT08 PELIABILITv C8IGINAL CURRENT ACTUAL M I LE ST CN E S DATE DATE DATE PEVISE ssPS AND PEG GUICES 1%P*) 03/88 04/88 --
DE VE L O P DIESEL GENE 8 ATOP #ELIABILITY 10/t5 08/38 --
I PROG 8AM GUIDELI%ES FT* TO DIVISICMS FC# CO**"E N T 11/t6 05/88 --
j STAFF CGMMENTS TO CR PS 12/85 C6/tt --
! C8GR W AGE TO #ES DIPE T08 01/27 07/88 --
1
! FImA. PACFAGE TO C8GP 153) 03/E7 08/81 --
i CPGs *EVIEW C & pLETE 05/17 09/18 --
! ISSUE F0# PUBLIC COMP"F=T 05/87 10/E8 --
1 PECEIVE PUBLIC CC***ENTS 09/87 11/88 --
FTP TO #ES DIRECTOR C9/a7 12/88 --
l FTP TO CSGR 10/27 01/89 --
ISSUE FEG GUICE A C S*P G4/23 04/89 --
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 131 ISSUE NUMBER: 8-61 TITLE: ALLOWABLE ECCS EQUIPMENT OUTAGE PERIODS IDENTIFICATION DATE: 06/78C PRIORITIZATION DATE- 11/83C TYPE: GSI PRIORITY; M TASK MANAGER: R. BUSLIK OFFICE / DIVISION / BRANCH: RES /DRAA/PRAB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: RESOLUTION DATE: 04/90 WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN [ APPENDIX G)
FIN CONTRACTOR CONTRACT TITLE NONE NONE NONE WORK SCOPE IN GENERAL, PLANTS WILL BE CLASSIFIED SUCH THAT CHANGES IN ALLOWABLE ECCS OUTAGE PERIOD. CONSIDERATION IN EACH CLASS SIMILAR ECCS OUTAGE UNAVAILABILITIES OF SUPPORT SYSTEM OUTAGES MUST BE INCLUDED. DETAILS WILL HAVE SIMILAR IMPACTS ON RISK. THE EFFECT OF A OF THE WORK SCOPE ARE CONTAINED IN THE DRAFT ACTION GIVEN ECCS AVAILABILITY ON RISK WILL BE DETERMINED. PLAN.
FOR EACH CLASS OF PLANT. AS WELL AS THE IMPACTS OF ANY STATUS TASK I HAS BEEN CDMPLETED.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION TECHNICAL SPECIFICATION CHANGES ARE POSSIBLE. ALTHOUGH TASK I. METHODOLOGY REVIEW AND DEVELOFMENT. IS LISTED AS COMPLETED. NO METHODOLOGY FOR THE ANALYSIS OF THE COSTS TO THE UTILITY OF THE IMPLMENTATION OF A CUMULATIVE OUTAGE REQUIREMENT HAS BEEN DEVELOPED. ALSO. THE FINAL REPORT FROM BNL ON THIS TASK HAS NOT SEEN RECEIVED. ALTHOUGH A DRAFT REPORT HAS BEEN RECEIVED. THE MAJOR PROBLEM ASSOCIATED WITH B-61 RESOLUTION IS THE ANALYSIS OF THE COSTS AND BENEFITS OF THE IMPOSITION OF A CUMULATIVE OUTAGE i REQUIREMENT. THE CONSIDERATION OF ANALYTICALLY BASED -
CUMULATIVE OUTAGE REQUIREMENTS WAS INCORPORATED INTO B-61 AS PART OF THE RESOLUTION OF TMI ACTION ITEM IIRK.3.17. ISEE MEMOR ANDUM F OR G . C. LAINAS FROM F. H. ROWSOME DATED JUNE
- 17. 1983.) NO WORK HAS BEEN PERFORMED ON TASK II OF THIS AS OF F)$8 QUARTER 2
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i i j GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 133 ISSUE NUMBER: 8-61 TTILE- ALLOWABLE ECCS EQUIPMENT 0UTAGE PERIODS ORIGINAL CURRENT ACTUAL f l MILESTONES DATE DATE DATE ;
i RES DIRECTOR REVIEW COMPLETE / 08/86 08/89 --
!, PACKAGE TO CRGR ;
1 j.
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6 l ISSUANCE OF FRN FOR PUBLIC COMMENT 11/86 10/89 -. !
4
! SI TY-DAY COP 99ENT PERIOD ENDS 01/87 12/89 . -- !
DIVISION REVIEW OF PUBLIC COMMENTS 02/87 0I/90 -.
COMPLETED. AND FINAL CRGR PACKAGE COMPLETED RES REVIEW OF CRGR PACKAGE COMPLETED 04/87 02/90 --
{ (DIVISION REVIEW AND RES DIRECTOR REVIEW) [
l L CRGR REVIEW AND EDO APPROVAL COMPLETED 05/87 03/90 .- i 1, i i ISSUANCE OF PROPOSED CHANGES TO 07/87 04/90 -.
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 135 ISSUE NUMBER: 8-64 TITLE: DECOMMISSIONING Or REACTORS ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE EDO APPROVAL OF DECOMMISSIONING - SECY - 09/84 --
09/84 34-354 COMMISION APPROVAL OF SECV-84-354 12/84 --
12/84 ISSUANCE OF DRAFT RULE CHANGE FOR 02/85 --
02/85 PUBLIC COMMENT I FORMAT AND CONTENT FOR DECOMMISSIONING 02/84 --
06/85 l
EXTENDED PUBLIC COMMENT PERIOD ON RULE 07/55 --
07/85
, COMPLETE ISSUE ThANSFER MEMO TO RES (SRP) 01/86 --
01/86 l REVISE DRAFT RULE INCORPORATING PUBLIC 02/86 --
11/86
, COMMENTS PREPARE FOR RES MANAGEMENT REVIEW l
l REVISE DRAFT RULES /PUBLIC COMMENTS 08/86 --
08/87 REVIEWED AND APPROVED BY CRGR 1535 FTR TO EDO FOR TRANSMITTAL TO COMMISSION 10/86 --
12/87 FRN OF FINAL RULE 01/87 06/88 --
ISSUE MEMO TO WRR TRANSFERRING 11/87 07/88 --
RESPONSIBILITY FOR SRP CHANGE DEVPLOP MILESTONES FOR SRP CHANGE 12/87 08/88 --
ISSUE SRP CHANGE 01/89 04/89 --
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J v . J RUN DATE: 05/II/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: I37 ISSUE NUMBER: C-8 TITLE: MAIN STEAM LINE LEAKAGE CONTROL AFFECTED DOCUMENTS PROBLEM / RESOLUTION (4) STS CHANGES (TBD) FOR ANALYSIS AND/OR DISCUSSION OF CONTROL ROOM DOSES. THE NEED FOR INCLUSION OF SEISMIC EVENTS IN THE RISK ANALYSIS.
AND CONSIDERATION OF THE EFFECTS OF HYDROGEN DETONATION IN THE COMPONENTS DOWNSTREAM OF THE MSIV*S ON THE USE OF THE VARIOUS MITIGATION PATHS. THERE IS ALSO A NEED FOR SOME PART I00 AND PART 50 DOSE CALCULATIONS WITH TACT III INSTEAD OF CRAC2 TO PROVIDE GUIDANCE FOR THE REGULATORY APPROACH.
PROBLEMS INVOLVING THE REGULATORY APPROACH ARE Il THE CREDIT TAKEN FOR NON SAFETY-GRADE COMPONENTS TO MITIGATE THE CONSEQUENCES OF MSIV LEAKAGE AND 2) THE USE OF A TID I4844 SOURCE TERM WITH THE IODINE CONTRIBUTION MODIFIED FROM THAT GIVEN IN RG I.3. RECENT WORK TO RESOLVE SOME OF THESE PROSLEMS INCLUDES USC OF NEW DA A FROM THE BWROG ALONG WITH A NEW MONTE CARLO TREATMENT OF vfULTIPLE VALVE LEAKAGE.
REVIEW OF EXTERNAL EVENT ANALYS"S FOR BWR*S FROM TWO USI A-45 RISK ANALYSES AND DISCUSSIONS WITH PERSONNEL INVOLVED WITH USI A-M6 ON APPLICABILITY OF THE USI A-46 APPROACH FOR QUALIFICATI0W OF NON-SEISMIC EQUIPMENT TO GSI C-8. WORK ON l THESE PROBLEMS IS LIMITED BY LACK OF FUNDS (APPROXIMATELY l SI6.000 CURRENTLY AVAILABLE). THE PLAN AND SCHED',LE FOR ' t RESOLUTION OF THIS ISSUE WILL BE RECONSIDERED AS 'tRT OF THE MANAGEMENT REVIEW.
ORICINAL CURRENT ACTUAL MILESTONES DATE DATE DATE TAP APPROVED CY DSI DIRECTOR IO/83 --
10/83 DEVELOP MINIMUM DESIGN CRITERIA FOR 03/84 --
04/84 ALTERNATIVE EQUIPMENT 'OR LOCA MITIGATION RECEIVE INITIAL BWROG SUBMITTAL 04/84 --
04/84 REVISE WORK PLAN BASED ON SUBMITTAL 05/84 --
05/84 REVISED WORK PLAN APPROVED BY DD 06/84 --
06/84 REVISED TA REQUEST APPROVED BY DD 08/84 --
07/84 AS OF FY88 QUARTER 2
OUN DATE: 05/11/80 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 138 ISSUE NUMBER: C-8 TITLE MAIN STEAM LINE LEAKAGE CONTROL ORIGINAL CURRENT ACTUAL M I LE STON E S DATE DATE DATE COMPLETE REVIEW OF LITERATULE SEARCH 08/84 --
08/84 COMPLETE REVIEW OF BWROG RECOMPENDATIONS 09/84 --
06/85 REVIEW PNL MODEL FOR FILLING. DEPOSITION 07/85 --
08/85 AND RELEASI PROCESSES IN EWR STEAM LINES UNDER LEAKING MSIV CONDITIONS COMPLETE REVIEW OF EFFECTIVENESS OF 10/84 --
11/85 BWROC RECOMMENDATIONS COMPLETE REVIEW OF PRA STUDY OF DIFFERENT 11/84 --
11/85 ALTERNATIVES COMPLETE REV. OF: (1) BASELINE OFFSITE DOSE 03/85 --
11/85 CALCS. (2) THERM-HYD MCDEL., 13) ALT OFF SITE DOSE CALCS TO DETER EFFECTS OF LOCA COMPLETE REVIEW OF COMPARTMENT 10/85 --
11/85 CONTAMINATION COMPLETE NUREG 12/85 --
06/86 ISSUE MEMORANDUM TO NOTIFY CRGR OF INTENT 07/86 --
08/86 TO ?UBLISH NUREG-1169 AND ISSUE A GENERIC LETTER FOR INFORMATION ONLY ISSUE TRANSFER MEMO TO DSRO (EFFECTIVE 08/86 --
08/86 AFTER ISSUANCE OF GENERIC LETTER)
COMPLETE REVIEW OF LITERATURE SEARCH 08/84 --
08/84 CRGR RESPONSE TO ISSUE GENERIC LETTER 09/86 --
09/86 AND PUBLISH NUREG-1169 NUREG-1169 ISSUED 09/86 --
09/86 CRGR BRIEFING 09/86 --
09/86 INCORPORATE CRGR COMMENTS AND ISSUE 10/86 --
10/86 GENERIC LETTER TO BWR LICENSEES FOR INFORMATION AS OF FY88 CUARTER 2 O O O
e
~ ] #%
RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 139 j ISSUE NUMBER: C-8 TITLE: MAIN STEAM LINE LEAKAGE CONTROL i
ORIGINAL CURRENT ACTUAL
- MI LEST0NES DATE DATE DATE PNL DRAFT REG. ANALYSIS TO RES FOR 10/86 --
11/86 COMMENT RES COMMENTS TO PNL 11/86 --
11/86 j PNL FINAL REG. ANALYSIS TO RES 12/86 --
01/87 1
j RES COMMENTS TO PNL 02/87 --
. 02/87 j ON FINAL REGULATORY ANALYSIS f RES REQUESTED BWR OWNERS GROUP 02/87 --
02/87 j, PROVIDE MSIV LEAKAGE DATA
- MEETING WITH BWROG 08/87 --
08/87 l BWR OWNERS GROUP MSIV DATA TO DSRO 05/87 --
02/88 MEET WITH BWR OWNERS GROUP 05/87 04/88 --
4 TO DISCUSS MSIV LEAKAGE DATA FINAL REGULATORY ANALYSIS TO RES 01/87 04/88 --
FROM PNL 1
- i. DRAFT CRGR PACKAGE 03/87 04/as __
1 CRGR PACKAGE APPROVED BY RES DIRECTOR. SENT 01/86 05/88 --
TO DIVISION DIRECTORS FOR COMMENT
! COMMENTS INCORPORATED. CRGR PACKAGE SENT 02/86 07/88 --
i TO RES DIRECTOR t RES DIRECTOR REVIEW COMPLETE. PACKAGE 03/86 08/88 --
SENT TO CRGR (29) l CRGR REVIEW COMPLETED 04/86 09/88 --
i ACRS REVIEW COMPLETED 04/86 09/88 --
, EDO APPROVAL 05/86 10/88 --
4 I
,i I
j AS OF FY88-OUARTER 2 l
I -
4 1
- _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ ______,_______u__ ?__
i RUN DATE: 05/11/88
, GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 140 ISSUE nut 4BER. C-8 TITLE MAIN STEAM LINE LEAKAGE CONTROL ORIGINAL CURRENT ACTUAL M I LEST 0N E S DATE DATE DATE FRN ISSUED FOR PUBLIC COMMENT 05/86 11/88 --
INCORPORATE COMMENTS AND SEND PACKAGE 09/86 02/89 --
TO RES DIRECTOR RES DIRECTOR REVIEW COMPLETE. PACKAGE 10/86 02/89 -
SENT TO CRGR 153)
CRGR REVIEW COMPLETED 11/86 03/89 --
EDO APPROVAL 12/86 03/89 --
FRN NOTICE ISSUED 12/86 04/89 --
4 e
4 4
AS OF FY88 CUARTER 2 1
l 0 -_ _ -
e e
) j^ %
RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONIROL SYSTEM PAGE: 141 ISSUE NUMBER: HF 1.1 TITLE: SHIFT STAFFING IDENTIFICATION DATE- 08/83C PRIORITIZATION DATE: 10/84C TYPE: GSI PRIORITY: H TASK MANAGER: D. SERIG OFFICE / DIVISION / BRANCH: RES /DRPS/RHFB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: RESOLUTION DATE 06/88 WORK AUTHORIZATION: MEMO TO H. THOMPSON FROM H. DENTON DATED 10/1/84 "HUMAN FACTORS PROGRAM PLAN" FIN CONTRACTOR CONTRACT TITLE NONE NONE NONE i
W0R K SC0PE THE ISSUE CONSISTS OF TWO SUBISSUES: (1) THE "STAFFING CONFORMING AMENDMENTS TO R.G. 1.114 AND SRP 13.1 2 RULE. WHICH BECAME EFFECTIVE IN 1934; AND (2) THE WHICH ARE PE NDI NG j
STA TUS THE "STAFFING RULE" WHICH IS KNOWN OFFICIALLY AS "LICENSE THE GENERAL COUNSEL (OGC) FOR REVIEW. UPON OGC APPROVAL THE OPERATOR STAFFING AT NUCLEAR POWER UNITS' WAS ISSUED IN THE FINAL DRAFT OF REG. GUIDE 1.114 REV. 2 WILL BE SENT TO THE FEDERAL REGISTER (48 FR 31611) ON 7/11/63. WITH AN EFFECTIVE CRGR AND ACRS FOR FINAL REVIEW / APPROVAL.
DATE OF 1/1/84 REG. GUIDE 1.114 REV. 2 WAS PUBLISHED AS A PROPOSED REVISION TO SPP SECTION 13.1.2 WILL BE DEVELOPED AND FORWARDED TO NRR CONCURRENT WITH THE FINAL A DRAFT FOR COMMENT IN 1/87: THREE COMMENTS WERE RECEIVED.
THESE COMMENTS HAVE BEEN RESOLVED AND THE FINAL DRAFT ON REVIEW / APPROVAL PROCESS FOR REG. GUIDE 1.114.
REG. GUIDE 1.114 REV. 2 HAS BEEN FORWARDED TO THE OFFICE OF i
AFFECTED DOCUMENTS PROBLEM / RESOLUTION g (1) RULE: LICENSED OPERATOR STAFFING AT NUCLEAR NONE 1
POWER UNITS (48 FR 31611)
(2) R.G. 1.114 (3) SRP SECTION 13.I.2 k
t AS OF FY88 OUARTER 2 e
RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 142 ISSUE NUMBER: HF 1.1 TITLE: SHIFT STAFFING ORIGINAL CURRENT ACTUAL M ILEST0N ES DATE DATE DATE DTR COMPLETED 11/84 --
11/84 CRGR REVIEW OF DTR 02/8S --
02/85 ACRS REVIEW OF DTR 08/86 --
08/86 PUBLISH FRN OF PROPOSED REV. 2 0F RG 1 114 01/87 --
01/87 FOR PUBLIC COMMENT PUBLIC COMMENT RESOLVED 04/87 --
03/88 FINAL REG. GUIDE PUBLISHED 06/87 06/88 --
AS OF FY88 QUARTER 2 O O O
2 Y -
J RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 143 4
8 ISSUE NUMBER: HF 4.1 TITLE: INSPECTION PROCEDURE FOR UPGRADED EMERGENCY OPERATING PROCEDURES (EOPS IDENTIFICATION DATE: 08/83C PRIORITIZATION DATE: IO/84C TYPE: GSI PRIORITY: H TASK MANAGER: J. BONGARRA OFFICE / DIVISION / BRANCH: NRR /DLPQ/LHFB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:- RESOLUTION DATE: 07/88 J-WORK AUTHORIZATION: MEMO TO H. THOMPSON FROM H. DENTON DATED 10/1/84 "HUMAN ,
FACTORS PROGRAM PLAN" i FIN CONTRACTOR CONTRACT TITLE NONE NONE NONE WOR K SCOPE TO DEVELOP AN INSPECTION PROCEDURE TO GUIDE PLANT-REVISED EMERGENCY OPERATING PROCEDURES.
2 INSPECTORS IN THE REVIEW AND INSPECTION OF
' $1 r
l STATUS WALK-DOWN INSPECTIONS BEING CONDUCTED. EXPECTED REQUIREMENTS ON QUIDANCE EXPECTED.
COMPLETION IN 6/88. FINAL REPORT IN 7/88 WITH NO NEW i
AFFECTED DOCUMENTS PROBLEM / RESOLUTION NONE NONE ORIGINAL CURRENT ACTUAL M ILEST ON ES DATE DATE DATE
. ISSUE REVISED INSPECTION PROCEDURES 06/86 --
06/86 (TEMPORARY INSTRUCTION)
I IMPLEMENT REVISED INSPECTION 08/86 --
08/86
, PROCEDURES ON TRIAL BASIS
' h AS OF FY88 QUARTER 2 i
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RUN DATE: 05/11/88 q GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 145 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: D. SERIG OFFICE /DIVIS' ION / BRANCH: RCS /DRPS/RHFB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: RESOLUTION DATE: 06/89 WORK AUTHORIZATION: MEMO FOR H. THOMPSON FROM H. DENTON DATED 10/1/84 "HUMAN FACTORS PROGRAM PLAN" FIN CONTRACTOR CONTRACT TITLE b236b Phl hkVktbP bbfb hbk kNb RkbbLkhbRY kbTkbN FbR BPS k kbPS .
82966 PNL DEVELOP GUIDANCE & REGULATORY ACTION FOR OPS & AOPS I2005 PNL DEVELOP GUIDANCE & REGULATORY ACTION FOR OPS & AOPS WOR K SC0PE RECOMMEND IMPROVEMENTS IN NUCLEAR POWER PLANT NECESSARY FOR EACH 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 BENEFITS..
WILL DETERMINE THE AMOUNT OF UPGRADE EFFORT ST A T US HS ShbhhkSTRkhhFERREbFRbMNRR kbkEShkhH Hk hRR WkRbEb kN kbbkhkbhkL CbN R Ch Tb Phl kh 3bNh [98h hb 4/12/87 NRC REORGANIZATION (4/10/87 MEMO FROM W. RUSSELL CONDUCT THAT ANALYSIS UNDER FIN I-2005. RESPONSIBILITY FOR TO T. SPEIS). CONTRACTOR EFFORTS ON FIN B2360/PNL AND THAT CONTRACT WAS TRANSFERRED TO RES BY NOVEMBER 16 1987 FIN 82966/PNL WERE COMPLETED AT THAT TIME. NUREG/CR'S- MEMORANDUM FR0f t L . RUTH TO H. KALTMAN. RES IS IN THE 3968 AND -4613 WERE PUBLISHED IN FEBRUARY 1987 AS A PROCESS OF DETERMINING ANY NECESSARY SCHEDULE AND BUDGET i
RESULT OF WORK UNDER THESE FINS. REVIEW OF NUREG/ ADJUSTMENTS. PLANS FOR ACTIVITIES BEYOND THE REGULATORY CR'S-3968 AND -4613 PRIOR TO THE NRC REORGANIZATION ANALYSIS WILL BE DEVELOPED WHEN THE NEED FOR THEM IS INDICATED THE NEED FOR A REGULATORY ANALYSIS OF TH'IS ISSUE. CONFIRMED.
. AFFECTED DOCUMENTS PROBLEM / RESOLUTION POSSIBLE REVISION TO SRP SECTION 13.5.2 PNL SCOPING ANALYSIS INDICATED NEED FOR GREATER SCOPE.
RHFB INVESTIGATING PEANS OF PREVENTING OR MINIMIZING i SLIPPAGE DUE TO INCREASED SCOPE.
TASK MANAGER DIVERTED TO PJMAN FACTORS RESEARCH PROGRAM AS OF FY88 QUARTER 2
RUN DAYE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 146 ISSUE NUMBER: HF 4.4 TITLE: GUIDELINES FOR UPGRADING OTHER PROCEDURES AFFECTED DOCUMENTS PROBLEM / RESOLUTION PLAN RHf B INVESTIGATING WHETHER DEDICATED TM CAN BE ASSIGNED ORIGINAL CURRENT ACTUAL M I LESTONE S DATE DATE DATE PUBLISH FINAL REPORT ON OPERATING 12/85 --
02/87 PROCEDURES PROJECT AS NUREG/CR PUBLISH FINAL REPORT ON PROCEDURES 05/R6 --
02/87 INTERFACE PROJECT AS NUREG/CR CONDUCT REGULATORY ANALYSIS FOR 02/87 09/S3 _-
OPERATING PROCEDURES, ABNORMAL GPERATING PROCEDURES CLOSE OUT ISSUE 06/89 06/89 --
i AS OF FY88 QUARTER 2 f
9 O O
l \ f \
G J 'wJ - ;
RUN DATE: 05/II/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: I47 ISSUE NUMBER: HF 5.1 TITLE. LOCAL CONTROL STATIONS IDENTIFICATION DATE: 08/83C PRIORITIZATION DATE: 10/84C TYPE: GSI PRIORITY: H TASK MANAGER: L. BELTRACCHI 0FFICE/ DIVISION / BRANCH: RES /DRPS/RHFB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: RESOLUTION DATE- 09/90 WORK AUTHORIZATION: MEMO TO H. THOMPSON FROM H. DENTON DATED 10/1/84
" HUMAN FACTORS PROGRAM PLAN
- t FIN CONTRACTOR CONTRACT TITLE 39bh bbl LbbLbbbhRbLbhkkkbbb I
l WOR K SC0PE hHE FhRShbbk[bF hHbhbhK kb b bE hRkkbE kHERkbK Tb V LbE/kkPkb kNklYbhb hhl bhhbhkkbb bNkLhbhK b i
PUBLIC HEALTH AND SAFETY RESULTING FROM HUMAN ERROR AT LOCAL % RESOLVE THE LOCAL CONTROL STATIONS ISSUE. THE OBJECTIVE OF CONTROL STATIONS WITHIN A NUCLEAR POWER PLANT AND THE COST THIS WORK IS TO DEVELOP A REGULATORY GUIDE ON LOCAL CONTROL OF POTENTIAL MODIFICATIONS. THE METHOD TO TO DETERMINE RISK (/) STATIONS AND REVIEW GUIDELINES THE FOR EVALUATION OF LOCAL IS THROUGH THE USE OF PROBABILISTIC RISK ANALYSIS (PRA). CONTROL STATIONS.
FOR PLANNING PURPOSES. WE ASSUME THE RESULTS OF THE l
(
ST A 1 US l BY LETTER DATED DECEMBER 29 1987 THE SOW WAS AUTHORIZED BNL TO BEGIN PROGRAM.
l i
FORWARDED TO BNL. BY LETTER DATED MARCH 25 1988 NRC
(
AFFECTED DOCUMENTS PROBLEM / RESOLUTION I. A REGULATORY GUIDE ON LOCAL CONTROL STATIONS. NEW TASK IDENTIFIED WHICH MAY DELAY COMPLETION.
- 2. REVIEW GUIDELINE FOR THE EVALUATION OF LOCAL CONTROL THE PROCESSING OF THE CONTRACTOR TOOK LONGER THAN STATIONS (MODIFICATION OF STANDARD REVIEW PLANI. EXPECTED. RHFB IS INVESTIGATING MEANS OF PREVENTING j OR REDUCING ANY SLIPPAGE.
I ORIGINAL CURRENT ACTUAL l MILESTONES- DATE DATE DATE bEbibV[bk/kkPbhShbbYbF [bbklbbbhkbl Chh88 bhh8h l
STATIONS i
[ AS OF FY88 OUARTER 2
RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 148 ISSUE NUMBER: HF 5.1 TITLE: LOCAL CONTR01 *TATIONS ORIGINAL CURRENT ACTUAL M ILE S T0N E 'a DATE DATE DATE COMPLETE VALUE/ IMPACT STUDY 07/88 07/88 --
NRC C0t:PLETE REVIEW OF STUD, RESULTS 09/88 09/88 --
ISSUE S0W FOR DEVELOPMENT 6F REVIEW 11/88 11/88 --
GUIDELINES AND DRAFT REG, GUIDE COMPLETE DEVELOPMENT OF REVIEW GUIDELINES AND 09/89 09/98 --
DRAFT MODIFICATION TO SRP AND DRAFT REGULATORY GUIDES REVIEW OF DRAFT REG. GUIDE AND DRAFT 11/89 11/89 --
MODIFICATION TO SRP BY DIVISION DIRECTOR REVIEM OF DRAFTS BY OFFICE DIRECTOR 12/89 12/89 --
REVIEW 0F DRAFTS BY OTHER OFFICES 12/89 12/89 --
REVIEW OF CRAFTS BY ACRS 01/90 01/90 --
REVIEW OF DRAFTS BY CRGR (29) 02/90 02/90 --
FINAL REG. GUIDE AND MODIFICATION TO SRP 04/90 04/90 --
REVIEW OF FINALS BY DIVISION DIRECTOR 05/90 05/90 --
REVIEW OF FINALS BY OFFICE DIRECTOR 06/90 06/90 --
REVIEW OF FINALS BY OTHER OFFICES 06/90 06/90 --
REVIEW OF FINALS BY ACRS 07/90 07/90 --
REVIEW OF FINALS BY CRGR (53) 08/90 08/90 --
ISSUE SRP MODIFICATION AND REG. GUIDE 09/90 09/90 --
AS OF FY88 OUARTER 2 O O O
e Q sy RUN DATE: 05/II/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: I49 ISSUE NUMBER: HF S.2 TITLE: REV. CRIT _ FOR HUMAN FACTORS ASPECTS OF ADV CONTROLS AND INSTRUMENT.
IDENTIFICATION DATE: OP/83C PRIORITIZATION DATE: 10/84C TYPE: GSI PRIORITY: H TASK MANAGER: L. PELTRACCHI 0FFICE/ DIVISION / BRANCH: RES /DRPS/RHF8 ACTION LEVEL: ACTIVE STATUS-TAC NUMBERS: RESOLUTION DATE- 05/91 WORK AUTHORIZATION: MEMO TO H. THOMPSON FROM H. DENTON DATED 10/I/84, "HUMAN FACTORS PROGRAM PLAN" FIN CONTRACTOR CONTRACT TITLE A3967 BNL ANNUNCIATORS WORK SC0PE
__-----------_-_-----_------------_-__---------------------------------------_------_---------------.---------~~_-----
THIS ISSUE COMBINES THE ISSUES FROM THE HUMAN FACTORS RESULTS FROM A PRA WILL ESTABLISH THE MAGNITUDE OF THE RISK PROGRAM PLAN OF SECTION I.S.2 INVOLVED AND THE POTENTIAL REDUCTION IN RISK EXPECTED. A (A) COMPUTER AND COMPUTER DISPLAYS VALUE/ IMPACT ANALYSIS WILL ESTIMATE THE COST OF POTENTIAL (8) EVALUATION OF OPERATOR AID SYSTEMS MODIFICATIONS TO ANNUNCIATORS AND SERVE TO DETERMINE IF THE.
(C) ANNUNCIATORS NRC NEEDS TO DEVELOP NEW REGULATIONS TO RESOLVE H'JMAN (D) SAFETY STATUS INDICATION AND APPLICATIONS OF AUTO- FACTORS CONCERNS ON ANNUNCIATORS.
MATION AND ARTIFICIAL INTELLIGENCE. WE ASSUME THE RESULTS OF THE VALUE/ IMPACT ANALYSIS A MANAGEMENT REVIEW OF THESE ISSUES RESULTED IN A WILL REQUIRE ADDITIONAL WORK TO RESOLVE THE ANNUNCIATOR DECISION TO RETAIN OPILY THE ANNUNCIATOR ISSUE AS A GENERIC ISSUE. THE OBJECTIVE OF THIS ADDED WORK WILL BE TO EVALUATE ISSUE. THIS DECISION ALSO CONCLUDED THAT THE REMAINING ALARM REDUCTION TECHNIQUES. IN EVALUATING ALARM RfDUCTION ISSUES BE REASSIGNED AS RESEARCH ISSUES. A RESEARCH TECHNIOUES. WE PLAN TO USE THE RESEARCH RESULTS ON ADVANCED PROJECT ENTITLED "REVIEW CRITERIA FOR HUMAN FACTORS ASPECTS ALARM SYSTEMS CONDUCTED AT THE HALDEN PROJECT. THE RESULTS OF ADVANCED CONTROL AND INSTRUMENTAION." FIN 80852, FROM THIS EFFORT WILL DEVELOP GUIDELINES ON COMPUTER-BASED ADDRESSES THESE ISSUES. ANNUNCIATOR SYSTEMS. THESE GUIDELINES WILL SERVE AS THE THE GOAL OF THIS WORK IS TO DETERMINE THE RISK TO BASIS FOR A MODIFICATION TO THE STANDARD REVIEW PLAN AND FOR 4 PUBLIC HEALTH AND SAFETY RESULTING FROM HUMAN FRROR IN THE A NUREG ON ANNUNCIATORS.
USE OF INFORMATION FROM CONTROL BOARD ANNUNCIATORS. THE i
1 STA TUS
~~----------------------------~~--------------------
A S0W FOR THE VALUE/ IMPACT STUDY EXISTS. BY LETTER PROJECT AND BUDGET PROPOSAL FOR NRC WORK (NRC FORM 189)
DATED DECEMBER 29 1987 THE S0W WAS FORWARDED TO BNL. RECEIVED MARCH 7, 1988.
1 4
AS OF FY88 QUARTER 2
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9 0 1 9 RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 151 ISSUE NUMBER: HF 5.2 TITLE: REV. CRIT. FOR HUMAN FACTORS ASPECTS OF ADV CONTROLS ~AND INSTRUMENT.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE REVIEW OF FINALS BY ACRS 01/91 03/91 --
REVIEW OF FINALS BY CRGR 153) 02/91 04/91 --
ISSUE SRP MODTFICATION AND NUREG 03/91 05/91 --
e 4
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l l
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- .~. .. . _ _. _ . -
l RUN DATE: 05/11/88
.t l GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGF: 153 ISSUE NUMBER: HF 8 TITLE- MAINTENANCE AND SURVEILLANCE PROGRAM I AFFECTED DOCUMENTS PROBLEM / RESOLUTION
- NONE NONE i
f ORIGINAL CURRENT ACTUAL j M ILEST0NES DATE DATE DATE PREPARE AND ISSUE PROGRAM PLAN 04/85 --
04/85 (SECY-85-129)
. CONDUCT SITE SURVEY OF EIGHT PLANTS 01/86 --
01/86 l DEVELOP MAINTENANCE DATA BASE 01/86 --
01/86 t
- DEVELOP. ADMINISTER AND ANALYZE RESIDENT 03/86 --
03/86 j MAINTENANCE QUESTIONNAIRE I SUBMIT MSPP PHASE I REPORT TO THE EDO 05/86 --
05/86 t PREPARE REPORT ON MAINTENANCE TRENDS 09/86 --
09/86 l AND PATTERNS j PREPARE COMMISSION PAPER ON PHASE I 09/86 --
10/86
- RESULTS AND PHASE II PLANS DEVELOP POLICY STATEMENT ON MAINTENANCE 10/87 12/87 f
ISSUE POLICY STATEMENT 01/88 05/88 --
a l *
) '
i s
I
}
AS OF FY88 QUARTER 2 i
l RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 154 ISSUE NUMBER. I.A.4.2(4) TITLE. REVIEW SIMULATORS FOR CONFORMANCE TO CRITERIA IDENTIFICATION 3 ATE: 05/80C PRIORITIZATION DATE- 11/83C TYPE GSI PRIORITY: H TASK MANAGER: J. WACHTEL OFFICE / DIVISION / BRANCH- NRR /DLPQ/LOLB ACTION LEVEL: ASTIVE STATUS.
TAC NUMBERS: M42454 RESOLUTION DATE 06/88 WORK AUTHORIZATION: TMI ACTION PLAN. NUREG-0660 FIN CONTRACTOR CONTRACT TITLE b53$h MkbRbbbbh bEVkLbPhkhh bk NRb ShMbl TkbbkkbkLkhY kVkt PRbbRkM WOR K SC0PE THIS ITEM IS ADDRESSED BY ACTIVITES CURRENTLY UNDERWAY IN OPERATOR LICENSE EXAMINATIONS. AND RESULTS EXPECTED RESPONSE TO SECTION 306 PL 97-425 AND BY FIN D-1317. F ROM A T/A CONTRACT TITLED DEVELOPMENT SPECIFICALLY, PROPOSED CHANGES TO 10 CFR PART 55 OF AN NRC SIMULATION FACILITY EVALUATION PROGRAM,-
RECOMMENDED CHANGES TO REGULATORY GUIDE 1 149. ADDRESS THIS ISSUE NUCLEAR POWER PLANT SIMULATOR FACILITIES FOR USE IN STA TUS CONTRACT BEGAN 9/16/85. STEERING COMMITTEE HAS HELD FOUR NUREG-1258 ISSUED IN DRAFT FORM ON 3/25/87. FOUR SETS OF MEETINGS. SIMULATION FACILITY EVALUATION PLAN HAS BEEN COMMENTS WERE RECEIVED AND REVIEWED. COMMENTS WERE PILOT-TESTED AT THE NORTH ANNA SIMULATOR. 10 CFR PART 55 INCORPORATED AS APPROPRIATE. AND THE NUREG WAS ISSUED 12/87.
AND REG GUIDE 1.149 WERE PRESENTED TO THE ACRS HUMAN FINAL MEMO TO EDO APPROVED BY DLPO DIRECTOR ON 3/11/88-FACTORS SUBCOMMITTEE (11/851 FULL ACRS COMMITTEE (12/85). AWAITING APROVAL FROM NRR ASSOCIATE DIRECTOR FOR INSPECTION CRGR (2/86). AND TO THE COMMISSION (4/861 COMMISSION VOTED AND TECH ASSISTANCE.
IN 2/87 AND RULE PUBLISHED (52 FR 94531 ON 3/25/87.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION NUREG-IO21 NUREG-1258 NONE ORIGINAL CURRENT ACTUAL MI LEST0NES DATE DATE DATE 10 CFR 55 AND RG 1 149- 03/85 --
03/85 END OF PUBLIC COMMENT PERIOD AS OF FY88 OUARTER 2 O O O
- -s
)
i
, RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 155 i
ISSUE NUMBER: I.A.4.2(4) TITLE: REVIEW SIMULATORS FOR CONFORMANCE TO CRITERI.\
l 1
ORIGINAL CURRENT ACTUAL ll MILEST0NES DATE DATE DATE D-1317 RFP ISSUED 03/85 --
03/85 CONTRACT AWARDED (D-1317) 08/85 --
09/85
' DIVISION REVIEW OF 10 CFR 55 10/85 --
10/85 ACRS REVIEW 12/85 --
12/85 I
, OFFICE REVIEW OF 10 CFR 55 12/85 --
12/87 CRGR REVIEW OF 10 CFR 55 12/85 --
02/86 l COMMISSION VOTE ON 10 CFR 55 CHANGE 01/87 --
02/87 i EVALUATE PLAN FOR ANS 3.5 12/86 --
01/87 l SIMULATORS (D-1317)
PUBLISH NUREG OF PROPOSED PLAN FOR 03/87 --
03/87 EVALUATION OF ANS 3.5 SIMULATORS j (D-1317)
EVALUATE COMMENTS ON PROPOSED PLAN 08/87 --
08/87 4~
4 PUBLISH FINAL PLAN FOR EVALUATION OF ANS 3.5 09/87 --
12/87 j SIMULATORS ISSUE CLOSE00T MEMO TO EDO 06/87 06/88 --
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l RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SVSTEM PACE: 156 ISSUE NUMBER: I.D.3 TITLE- SAFETY SYSTEM STATUS MONITORING IDENTIFICATION DATE: 05/80C PRIORITIZATION DATE 11/83C TYPE. GOI PRIORITY N TASK MANAGER: S. AGGARWAL OFFICE / DIVISION / BRANCH RES /DE /MEB ACTION LEVEL: ACTIVE STATUS TAC NUMBERS: RESOLUTION DATE C2/89 WORK AUTHORIZATION: TMI ACTION PLAN. NUREG-0660 FIN CONTRACTOR CONTRACT TITLE B2360 PNL VERIFICATION, SYSTEM STATUS. AUTOMATIC VS MANUAL WOR K SCOP E PNL HAS REVIEWED THE EFFECTIVENESS OF SYSTEMS AND NECESSLARY AND FURTHER THAT THIS NEW REVISION SHOULD BE PROCEDURES RELATED TO SAFETY SYSTEM STATUS MONITORING APPLIED TO ALL PLANTS. BASED ON THE PNL AND HAS RECOMMENDED A REGULATORY POSITION ON THIS ISSUE RE COMME NDAT IONS , DHFS TRANSF ERRED RESPONSIBILITY PNL F INDINGS INDICATE THAT A REVISION OF RG 1 47 IS FOR THIS ISSUE TO RES (REVISE R G. 1.47)
S T A TUS ALL TECHNICAL REPORTS ON THIS ISSUE ARE COMPLETE. WILL BE VOLUNTARY THE PROJECT FINAL REPORT INCLUDES GUIDELINES FOR A DRAFT OF THE PROPOSED REVISION I TO R.G 1 47 WAS IMPROVING SYSTEM STATUS MONITORINS AS WELL AS THE DISTRIBUTED IN JULY. 87 FOR STAFF REVIEW. A MEETING WAS FINAL RECCMMENDATION OF PNL ON A REGULATORY POSITION HE LD ON SEPTEMBER 23. 1987 TO RESOLVE NRR (HUMAN FACTOPS THEIR RECOMMENDATION IS TO REVISE R G. 1.47 AND APPLY ASSESSMENT BRANCH l PERTAINING TO PROPOSED REVISION 1 IT TO ALL PLANTS. STAFF PROPOSES TO APPLY NEW STAfr CONSENSUS IS HOWEVER NOT REACHED.
REQUIREMENTS FOR FUTURE PLANTS ONLY. COMPLIANCE BY OL*S AFFECTED DOCUMENTS PROBLEM / RESOLUTION REVkhkbh hb R b k kh hHk EbhNkbIL RkhbLbhkbh bF kH h hhhh h L hk THE DEVELOPMENT OF AN NRC POSITION REGARDING THE NEED TO PEVISE R G 1 47 AS OF FY88 OUAPTER 2 O O O
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06/82 INDUSTRY PRACTICES SUBMIT PRELIMINARY RECOMMENDATION FOR 09/82 --
09/82 REGULATORY POSITION SUBMIT TECH REPORT ON EFFECTIVENESS OF 11/82 --
11/82 EXISTING SYSTEMS SUBMIT REPORT ON EFFECTIVENESS OF 12/82 --
12/82
- j. VERIFICATION PROCEDURES l* SUBMIT DRAFT ACCEPTANCE CRITERIA 04/83 --
04/83 SUBMIT DRAFT GUIDELINES FOR
- INTERIM- 07/83 --
07/83 l IMPROVEMENT SUBMIT PROGRAM PLAN FOR DEVELOPING 09/83 --
11/83 "FULL IMPLEMENTATION" GUIDELINES SUBMIT FINAL RECOMMENDATIONS FOR 09/83 --
02/84 REGULATORY POSITION COMPLETE DRAFT MEMO TRANSFERRING ISSUE 06/84 --
06/84 TO RES TRANSFEP MEMO APPROVED BY DD'S 07/84 --
10/84 TRANSFER MEMO TD RES APPROVED 08/84 --
10/84 BY NRR DIRECTOR RES PROVIDED MILESTONE NECESSARY TO' 09/84 --
04/85 COMPLETE ISSUE AND OUTLINED PROBLEMS WITH ISSUING REG GUIDE REVISION ISSUED MEMO FOR PROVIDING MILESTONES 11/85 --
11/85 PREPARE TASK CONTROL FORM (TCF) 10/85 --
03/86 OBTAIN TCF APPROVAL 10/85 --
05/86 AS OF FY88 QUARTER 2 g ___
RUC] DATE : 05/11/88 CENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 158 ISSUE NUMBER ID3 TITLE- SAFETY SYSTEM STATUS MONITORING ORIGINAL CURRENT ACTUAL M I LES T ON ES DATE DATE DATE RES PROVIDES NEW MILESTONE DATES 05/86 --
01/87 NECESSARY TO RESOLVE ISSUE INITIAL DRAFT COMPLETE (INFO COPY 10/85 --
07/87 TO CRGR/ACRS)
DIVISION REVIEW COMPLETE 10/85 04/88 --
DEVELOP REGULATORY ANALYSIS 03/86 04/88 --
OFFICE CONCURRENCE OF CRGR PACKAGE 02/88 04/88 --
CRGR. EDO. ACRS. REVIEW / APPROVAL (29) 07/86 05/88 --
RESOLUTION OF COMMENTS 09/86 05/88 --
PRINTING & DISTRIBUTION AUTHORIZED 09/86 06/88 --
PRINTED & ISSUED FOR COMMENT 10/86 07/88 --
COMMENT PERIOD 01/87 09/88 --
RESOLUTION OF COMMENTS 02/87 10/88 --
DIVISION OF ELD REVIEW COMPLETE 04/87 10/tB --
CRGP REVIEW COMPLETE [53) 07/87 12/88 --
ACRS REVIEW COMPLETE 07/87 01/89 --
RESOLUTION OF COMMENTS 09/87 01/8S --
0FFICE CONCURRENCE DBTAINED 10/87 02/89 --
PRINTED AND ISSUED 12/87 02/85 --
AS OF FY88 OUARTER 2 9 9 9
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, GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 159 1
ISSUE NUMBER: I.D.4 TITLE: CONTROL ROOM DESIGN STANDARD IDENTIFICATION DATE: 05/80C PRIORITIZATION DATE- 11/83C TYPE: GSI PRIORITY: M TASK MANAGER: D. SERIG OFFICE / DIVISION / BRANCH- RES /DRPS/RHFB ACTION LEVEL: INACTIVE STATUS: 38 TAC NUMBERS: RESOLUTION DATE. 03/88C WORK AUTHORIZATION: TMI ACTION PLAN. NUREG-0660 FIN CONTRACTOR CONTRACT TITLE NONE NONE NONE W0RK SC0PE DEVELOP REGULATORY GUIDE ON HUMAN FACTORS ENGINEERING CONTROL ROOM AND REMOTE SHUTDOWN PANELS.
STANDARDS AND PRACTICES FOR USE ON NEW (CP APPLICATION)
STATUS THIS ISSUE WA' EANSFERRED FROM NRR TO RES WITH THE SECTION 18.1 WHICH ADDRESSES CONTROL ROOM DESIGN AND 4/87 NRC REORGANI' . 14/10/87 MEMO FROM W. RUSSELL TO T REFERENCES NUREG-0700 AS APPROPRIATE GUIDANCE FOR CONTROL SPEIS). NO WORK EN COMPLETED ON THE ISSUE PRIOR TO ROOM DESIGN.
TRANSFER. SUBSEye TS REVIEW INDICATED THAT ALL THIS ISSUE HAS BEEN RESOLVED BY INDUSTRY COMPLIANCE
- OPERATING AND NT4 TS ARE CONDUCTING DETAILED CONTROL WITH TMI ITEM I.D.1 10 CFR 50.34(G). AND THE REVISION OF ROOM DESIGN REVI RESPONSE TO TMI ITEM I.D.I. SRP 18.1 TO INCLUDE REFERENCE TO NUREG-0700. THIS ISSUE WAS NUREG-0700 AND "FABLE SUBSTITUTES ARE BEING USED AS CLOSED BY A MARCH 28 1988 MEMORANDUM FROM E. BECKJORD TO CONTROL ROOM DE' <" STANDARDS FOR THIS EFFORT. APPLICATIONS V. STELLO. DESIGNS WILL BE ADDRESSED BY THE HUMAN FACTORS FOR FUTURE LIGHs W.;fER REACTORS SHALL INCLUDE. PER 10 CFR RESEARCH PROGRAM PLAN WHICH IS CURRENTLY UNDER DEVELOPMENT.
50.34(G), AN EVALUATION OF THE FACILITY AGAINST THE SRP 1
i i AFFECTED DOCUMENTS PROBLEM / RESOLUTION
~~.------------------------------- ------------------------------------------------------------
NONE NONE k
i ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATF DATE CLOSE OUT ISSUE 09/91 --
03/88 AS OF FY88 QUARTER 2
l CUN DATE 05/11/8f GENERIC ISSUE MANAGEMENT CO : TROL SYSTEM PACE: 160 ISSUE NUMBER: I.D.5(3) TITLE ON-LINE REACTOR SURVEILLANCE SYSTEMS IDENTIFICATION DATE: 05/80C PRIORITIZATION DATE 11/83C TYPE: GSI PRIORITY.
TASK MANAGER. W. FARMER OFFICE / DIVISION /SPANCH PES /DE /MEB ACTION LEVEL: ACTIVE STATUS NR TAC NUMBERS. NONE RESOLUTION DATE 12/88 WORK AUTHORIZATION- TMI ACTION PLAN. P4UR E G- 0 6 6 0 FIN CONTRACTOR CONTRACT TITLE bbh2h bhbL bbb bbbbb bb NE hEEbhbhbbkbEbhbkEMEVILbkkkhbb W0R K SC0P E THk b83EChkVk bF THkk REPbRh kS kb PEPFbRM PEbE RbH bN t E bbkbE bbhvEkLLkNCEbYShEMAhDTOPERFbhM TO DETERMINE THE FEASIBILITY OF DETECTING AND DIAGNOSING DE MO?.S TR AT IONS OF SUCH A SYSTEM IN AN NRC-LICENSED NUCLEAR POWER PLANT OPERATING ANOMALIES USING A CONTINUOUS CCMMEPCIAL BWR PLANT.
$TA T US A DEMONSTRATION OF SYSTEM FEASIBILITY AT AN BEF0DE THE FALL OF 1988. IT IS BELIEVED THAT SUFFICIENT OPE R AT ING PWR HAS BEEN COMPLETED THE SURVE I L L ANCE DATA IS AVAILABLE FROM THE ON-LINE REACTOR SURVEILLANCE INSTRUMENT SYSTEM HAS BEEN INSTALLED AT PEACH BOTTOM UNIT TESTS AT THE SEQUOYAH UNIT 2 IN 1983/84 ALONG WITH THE 2 A ND IS TO BE USED TO DEMONST RATE SYSTM F E ASIBILIT Y AT A SINGLE LOOP MEASUPEMENTS AT THE BROWNS FERRY BWP TO DEVELOP BWR (PEACH BOTTOM 15 MONTHS OUTAGES AND EQUIPMENT AND AN ACCEPTABLE EVALUATION OF THE ON-LINE REACTOR SURVEILLANCE DEGRADATION HAVE DELAYED PLANT MEASUREMENTS 18 MONTHS.) SYSTEM PEACH BOTTOM UNIT 2 IS NOW NOT EXPECTED TO PESTART AFFECTED DOCUMENTS PROBLEM / RESOLUTION NONE A PIL WILL BE PREPAPED SUMMAPIZING THE CONCLUSIJNS AND RECOMrdENDATIONS FPCM THE RESEARCH ON THIS ACTION ITEM ORIGINAL CURRENT ACTUAL M I LEST 0NES DATE DATE DATE INSTALL SYSTEM AT A PWR -- --
09/80 AS OF FV88 OUARTER 2 O O O
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ISSUE NUMBER: I.D.5(3) TITLE: ON-LINE REACTOR SURVEILLANCE SYSTEMS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE
( COMPLETE PWR DATA ACQUISITION 06/84 --
01/84 INSTALL' SYSTEM AT A BWR 04/84 --
06/85 ISSUE RIL TO NRR WITH CONCLUSIONS AND 09/88 09/88 --
RECOMMENDATIONS .
t ISSUE CLOSEOUT AND REMOVAL OF SYSTEM FROM 12/88 12/88 --
PEACH BOTTOM ;
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RUN DATE: 05/II/88 GENERIC ISSUE MANAGEME NT CON 700L SYSTEM PAGE: I62 ISSUE NUMBER: I.D.S(S) TITLE. DISTURBANCE ANALYSIS SYSTEMS IDENTIFICATION DATE: 05/80C PRIORITIZATION DATE II/83C TYPE- LI PRIORITY TASK MANAGER-. L. BELTRACCHI 0FFICE/ DIVISION / BRANCH RES /DRPS/RHFB ACTION LEVEL: ACTIVE STATUS: 5 TAC NUMBERS: RESOLUTION DATE 06/89 WORK AUTHORIZATION: TMI ACTION PLAN, NUREG-0660 FIN CONTRACTOR CONTRACT TITLE bO352 bkbl KEV bRkhhbR hbMkh hkbhbRb kbPEbhb bF kbVIbbEb bbkhRbLb k khbTRbM W0R K SC0PE THOSE FACETS OF THE DISTURBANCE ANALYSIS SYSTEM (DAS) DIF FICUL TIE S IN GENERATING AND VERIFYING THE ACCURACY OF DEALING WITH UPSET DIAGNOSIS AND REMEDIAL ACTION AhE THE LOGIC MODELS MUST BE OVERCOME BEFORE APPLYING A BASED ON DETAILED LOGIC MODELS THAT TRACE THE TIME- DAS TO A COMMERCIAL REACTOR ON A TOTAL PLAN! BASIS DE PE NDE N T CONSEQUENCES OF COMPONENT F AILURES. THE STA TU S BY M"40RANDUM DATED DECEMBER I2, 1987 IFOR THEMIS P EXISTS IN THIS AREA. A CURRENTLY FUNDED RESEARCH PROJECT.
SPEIS. FROM BRIAN W. SHERON.
SUBJECT:
RECOMMENDED FIN 0852. REVIEW CRITERIA FOR HUMAN FACTORS ASPECTS OF CONVERSION OF GENERIC ISSUES TO RESEARCH ISSUESI SPEIS ADVANCED CONTROLS AND INSTRUMENTATION. WILL EVALUATE AGXEES WITH THE DIVISION OF REACTOR AND PLANT SYSTEMS DISTURBANCE ANALYSIS SYSTEMS ALONG WITH OTHER ADVANCED RECOMMENDATION THAT THIS ISSUE BE *ECLASSIFIED AS A RESEARCH TECHNOLOGIES. SUCH AS COMPUTER-BASED OPERATOR AIDS AND ISSUE THE REASON GIVEN FOR THE f OMME NDA T I ON IS THE NEED ARTIFICIAL I NT E L L IGE NCE . THIS ISSUE WILL CONTINUE TO BE FOR SPECIFIC RESEARCH TO DETERMIy r A SAFETY PROBLEM TRACKED AS A LICENSING ISSUE TO FOLLOW THE RESEARCH WORK AFFECTED DOCUMENTS PROBLEH/ RESOLUTION ORIGINAL CURRENT ACTUAL M ILESTONES DATE DATE DATE NUREG/CR ON RESULTS OF SURVEY ON HG;4AN 06/89 06/89 --
FACTORS ASPECTS OF ADVANCED CONTROLS /
INSTRUMENTATION AS OF FY88 QUARTER 2 e
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TAC NUMBERS: RESOLUTION DATE: _ _ _ _ _ _
WORK AUTHORIZATION: TMI ACTION PLAN. NUREG-0660 FIN CONTRACTOR CONTRACT TITLE W0R K SC0PE DEVELOP GUIDANCE FOR LICENSEES TO EXPAND THEIN QA LIST TO COVER EQUIPMENT IMPORTANT TO SAFETY.
STA TUS kHkShFFHkskkbkkPkkkkhkhkkhkEhhEhbF kHkbkkbkh hMPbRhkkh hb hkFkkh kkL hhk kkbbkkEb bhkbh5 kkh HkVk OF THIS ISSUE AND THE QUALITY RELATED ACTIVITIES WHICH HAVE ALREADY BEEN TAKEN. THE NEXT STEP IS TO MAKE A MORE CAREFUL ALREADY TAKEN PLACE IN THE SUBSEQUENT EIGHT YEARS AND HAS REVIEW AND PROPOSE A PLAN OF ACTION TO RESOLVE THIS ISSUE.
CONCLUDED THAT, WITH THE EXCEPTION OF THE DEFINITION OF AFFECTED DOCUMENTS PROBLEM / RESOLUTION IMPORTANT TO SAFETY REULEMAKING. THE FIRST STEP IN THE RESOLUTION IS TO EXAMINE THE RECORD TO SEE WHAT WAS REQUIRED AT THE BEGINNING, HOW MUCH OF THAT HAS BEEN ACCOMPLISHED BY OTHER MEANS, AND WHAT RELEVANT DECISIONS HAVE ALREADY BEEN MADE_ THIS INFORMATION WILL BE USED TO DEVELOP A PLAN OF ACTION FOR RESOLVING THIS ISSUE.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE hhkk bkVkLbPFkkhhhbRK bhh8h --
bhh8h AS OF FY88 QUARTER 2
RUN DATE: 05/11/89 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 164 ISSUE NUM8ER I.F.1 TITLE EXPAND OA LIST ORIGINAL CURRENT ACTUAL MILE ST ON E S DATE DATE DATE REVIEW NRC INTERNAL COMMENTS 04/83 --
07/83 ON NUREG/CR-2631 (REWRITE SCOPE /189 IF NECESSARY) AND PUBLISH NUREG TASK 2- START METHOD DEVELOPMENT 10/83 --
10/83 DEVELOP (ISSUE CONTRACT TO SANDIA)
COMPLETION OF TASK 2 09/84 --
05/85 ISSUE SECY-85-119. PROPOSED RULE 04/85 --
04/85 ON IMPORTANCE TO SAFETY ISSUE COMMISSION DISAPPROVED SECY-85-119 -- --
12/85 ISSUE REVISED PAPER FOR PROPOSED 05/86 --
05/86 RULE ON IMPORTANCE TO SAFETY ISSUE CONr4:SSION APPROVES REVISED RULE 06/86 TBD --
COMPLETE STAFF PLAN EXTABLISHING NEEDED 12/86 10/88 --
ACTIONS REMAINING AND PLAN FOR ACCOMPLISHING THEM
\
AS OF F Y'J 8 OU.*.R T E R 2 O -
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RUN DATE: 05/II/88.
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 165 ISSUE NUMBER: II.B.5(1) TITLE: BEHAVIOR OF SEVERELY DAMAGED FUEL IDENTIFICAVION DATE: 05/80C PRIORITIZATION DATE: II/83C TYPE: LI PRIORITY:
9 TASK MANAGER: M. SILBERBERG OFFICE / DIVISION / BRANCH: RES /DRAA/AEB ACTICN LEVEL: ACTIVE STATUS: 5 TAC NUMBERS: RESOLUTION DATE- 06/94 WORK AUTHORIZATION: TMI ACTION PLAN. NUREG-0660 FIN CONTRACTOR CONTRACT TITLE NONE NONE NONE W0RK SC0PE
-......--.---.---.-------...-.--.---......--.....-...--.--..---.-------------...--------.~.--------...............------...--
ISSUES II.B.5(I) AND II.B.5(2) ARE BEING RESOLVED CONTAINMENT ANALYSIS, AND FISSION PRODUCT RELEASE AND TOGETHER. RESEARCH IS SEING PERFORMED ON PHENOMENA TRANSPORT AS DESCRIGED IN DETAIL IN SECY-86-369. THIS ASSOCIATED WITH CORE DEGRADATION, FUEL MELTING, AND PROGRAM INVOLVES BOTH IN-PILE AND OUT-OF-PILE TESTS WITH EX-VESSEL PHENOMENA. CONDUCT AN EXTENSIVE EXPERIMENTAL AND ACTUAL AND SIMULATED CORE AND REACTOR STRUCTURAL MATERIALS, ANALYTICAL PROGRAM ON THE BEHAVIOR OF DAMAGED FUEL. HYDROGEN AND THE DEVELOPMENT CODES TO MODEL TPE PHENOMENA EXPECTED IN GENERATION AND CONTROL, FUEL STRUCTURE INTERACTION, THE REACTOR.
, STATUS NUREG-0956 IDENTIFIED EIGHT AREAS OF UNCERTAINTY IN OUT IN MARCH 1987 TO OVER 900 NRC. INDUSTRY. UNIVERSITY, AND REGULATORY INFORMATION NEEDED TO RESOLVE THE SOURCE TERM FOREIGN ADDRESSES. THE COMMENT PERIOD ENDED ON 8/2I/87.
ISSUE. THE RESEARCH PROGRAM FOR FY 1987 AND OUT YEARS IS MEANWHILE. RISK ANALYSIS OF A SIXTH PLANT (LASALLE) IS BEING REORIENTED TO RESOLVE THOSE AREAS OF UNCERTAINTY. UNDERWAY AND EXTERNAL EVENTS ANALYSIS OF TWO OF THE FIRST SECY-86-369 PROVIDES THE INITIAL RESEARCH PLAN. AN FIVE PLANTS WILL BE DONE. YHE LASALLE STUDY WILL BE EVALUATION OF THE RESEARCH RESOLUTION OF THESE AREAS OF PUBLISHED SEPARATELY FROM NUREG-1150. THIS GENERIC ISSUE UNCERTAINTY HAS BEEN CONDUCTED BY BNL, AND WAS REPORTED IN WILL BE CLOSED OUT (IN A LETTER TO EDO) AND ITS RESOLUTION APRIL 1987 AS NUREG/CR-4883. THE STAFF HAS USED THIS WILL CONTINUE IN ACCORD WITH SECY-86-369 IN SUPPORT OF EVALUATION TO EXAMINE THE NEED TO MAKE FURTHER REORIENTATION SEVERE ACCIDENT POLICY STATEMENT IMPLEMENTATION AP'D THE OF THE RESEARCH PROGRAM TO ASSURE THE MOST COMPLETE ISSUE SEVERE ACCIDENT PLAN. IN ACCORDANCE WITH A MEMO FOR T.
RESOLUTION POSSIBLE, GIVEN AVAILABLE RESOURCES. THIS SPEIS FROM R. HOUSTON ON 11/4/87 THIS ISSUE WAS D:TERMINED REVISED PROGRAM HAS BEEN DOCUMENTED IN A COMMISSION PAFER . TG BE WITHIN THE REALM OF SEVERE ACCIDENT RESEARCH.
WHOSE ISSUANCE HAS BEEN DEFERRED-TO THE EDO. REACTOR RISK THEREFORE, IT WILL CONTINUE TO BE TRACKED AS A LICFNSING REFERENCE DOCUMENT, NUREG-1150. DRAFT FOR COMMENT WAS MAILED ISSUE TO FOLLOW TNE RESEARCH WORK.
AS OF FY88 OUARICR 2-J
CUN DATE: C5/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PACE: 166 ISSUE NUMBER:. II.B.5(1) TITLE BEHAVIOR OF SEVERELY DAMAGED FUEL AFFECTED DOCUMENTS PROBLEM / RESOLUTION (1) NUREG-0956 REASSESSMENT OF TECHNICAL BASES FOR NONE LWR ACCIDENT SGURCE TERM (JULY 1986)
(2) NUREG-1150 NEW RISK PROFILES FOR FIVE REFERENCE PLANTS l DRAFT FOR COMMENT FEBRUAPY 1981)
(3) SECY-86-369 "PLAN TO ADDRESS SOURCE TERM TECHNICAL UNCERTAINTY AREAS.-
ORIGINAL CURRENT ACTUAL MILEST 0N ES DATE DATE DATE INITIAL DRAFT CONTRACTOR SOURCE TERM REPORT 01/83 --
01/83 SOURCE TERM ESTIMATES FOR SELECTED PLANTS 08/83 --
01/84 AND ACCIDENT SEQUENCES THOROUGH PEER REVIEW OF THE ABOVE 12/83 --
02/85 SCIENTIFIC BASES FOR REASSESSMENT DRAFT REASSESSMCNT OF THE TECHNICAL 12/83 --
07/85 BASES FOR ESTIMATING SOURCE TERMS (NUREG-0956)
NRC SEVERE ACCIDENT POLICY 11/85 --
07/85 COMPLETE DTR 12/86 --
12/86 SEVERE ACCIDENT RISK REBASELINING 12/83 --
03/87 PROGRAM DRAFT REPORT lNUREG-1150)
FINAL REASSESSMENT OF THE TECHNICAL BASES FOR 07/86 04/88 --
ESTIMATING SOURCE TERMS (NUREG-0956)
FINAL RECS TO THE COMMISSION DN SEVER" 06/84 08/88 --
ACCIDENT CONT. PERFORMANCE RQMNTS F OR (MARKI)
OPERATING PLANTS & PLANTS UNDER CONSTRUCTION ISSUE CLOSEOUT MEMO TO EDO 06/88 06/94 --
AS OF FY88 QUARTER 2 O O O
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ISSUE NUMBER: II.B.5(2) TITLE: BEHAVIOR OF CORE-MELT IDENTIFICATION DATE: 05/80C PRIORITIZATION DATE: 11/83C TYPE: LI PRIORITY:
- TASK MANAGER
- M. SILBERBERG OFFICC/ DIVISION / BRANCH: RES /DRAA/PRAB ACTION LEVEL: ACTIVE STATUS: 5 TAC NUMBERS: RESOLUTION DATE: 06/94 !
WORK A"THORIZATION: TMI ACTION PLAN. NUREG-0660 FIN CONTRACTOR CONTRACT TITLE NONE NONE NONE I
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W0RK SC0PE i SEE SCHEDULE FOR RESOLVING ISSUE II.B.5(1) i i
STA T US 3
4 IN ACCORDANCE WITH A MEMO TO T. SPEIS FROM R. HOUSTON OF SEVERE ACCIDENT RESEARCH. THEREFORE. IT WILL CONTINUE TO
- ON 11/4/87, THIS ISSUE WAS DETERMINED TO BE WITHIN THE REALM BE TRACKED AS A LICENSING ISSUE TO FOLLOW ThE RESEARCH WORK.
i AFFECTED DOCUMENTS PROBLEM / RESOLUTION l, __..__.._-_...........___-.--__ ....___........--_------- __ -.____ ......-...-_... ____..___.. .___.. .______ .____.....
- SEE ISSUE II.B. Sill. *** NONE ***
4 4
ORIGINAL CURRENT ACTUAL l MILEST0NES DATE DATE DATE 1
j _____.____....... _..... _____.._._..__....._ ..---- ... ___ ---_ .
j SEE, ISSUE II.B.i-(I) --
i 3
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AS OF FY88 OUARTER 2 t
RUN DATE: 03/II/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: I68 ISSflE NUMBER: II.B.513) TITLE- EFFECT OF HYDROGEN COMBUSTION ON CONTAINMENT STRUCTURES IDENTIFICATION DATE- 05/80C PRIORITIZATION DATE II/83C TYPE- LI PRIORITY TASK MANAGER: P. WORTHINGTON OFFICE / DIVISION / BRANCH RES /DRAA/AEB ACTION LEVEL: ACTIVE STATUS. 5 TAC NUMBERS RESOLUTION DATE 09/91 WORK AUTHORIZATION: TMI ACTION PLAN. NUREG-0660 FIN CONTRACTOR CONTRACT TITLE AI246 SNL HYDROGEN BEHAVIOR PROGRAM AI2TO SNL HYDROGEN BURN SURVIVAL AIJ36 SNL HYDROGEN MIXING STUDIES A7247 LANL HYDROGEN MITIGATION AND PREVENTIVE SCHEMES B8208 SNL HYDROGEN COM8USTION AND CONTROL DEMO. EXPER.
WOR K SC0PE PPOVIDE THE NRC EXPERIMENTS AND ANALYTICAL ME THODS FOR DETONATIONS. FLAME ACCELERATION. THE TRAdSITION TO UNDERSTANDING OF THE THREAT POSED BY HYOROGEN BURNING DURING DETONATION IDDT). THE EFFECT OF BURNING ON EclIPMENT. AND POSTULATED LWR ACCIDENTS. THIS WORK INCLUDES AN THE EFFICIENCY OF H2 CONTROL SYSTEMS UNDERSTANDING OF DEFLAGRATIONS. GLOBAL AND LOCAL STA TUS PROGRAMS ARE UNDERWAY WITH STATE-OF-THE-ART PAPERS WITH REVISED SECY-86-369 IN SUPPORT OF SEVERE ACCIDENT EXPECTED FOR FLAME ACCELERATION AND DDT AND DETONATION IN POLICY STATEMENT IMPLEMENTATION AND THE SEVERE ACCIDENT F Y- 8 8 AND F Y- 8 9 . PERFORMING EXPERIMENTS AND ANALYSIS TO CLOSURE PLAN.
PROVIDE ANALYTICAL TOOLS TO PREDICT COM8USTION MODE (IE., IN ACCORDANCE WITH A MEMO FOR T. SPEIS FROM R. HOUSTON DEFLAGRATION. DIFFUSION FLAMES. FLAME ACCELER-ATION AND DDT ON II/4/87 THIS ISSUE WAS DETERMINED TO BE WITHIN THE REALM AND DETONATION) FOR VARIOUS TYPES OF PLANTS UNDER SEVERE OF SEVERE ACCIDENT RESEARCH. THEREFORE. IT WILL CONTINUE TO ACCIDENT CONDITIONS. THIS ISSUE WILL BE CLOSED OUT WITH A BE TRACKED AS A LICENSING ISSUE TO FOLLOW THE RESEARCH WORK.
LETTER TO EDO AND ITS RESOLUTION WILL CONTINUE IN ACCORD AFFECTED DDCUMENTS PROBLEM / RESOLUTION SEVERE ACCIDENT RESEARCH PLAN [NUREG-0900 REV I. 4/86) NONE AS OF FY88 OUARTER 2 O O O
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 169 ISSUE NUMBER: II.B.5(3) TITLE- EFFECT OF HYDRUGEN COMBUSTION ON CONTAINMENT STRUCTURES l
ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE REVkEhbhbRkhbbbLhPLkhhHYbRbbEN 10/hh --
bb/83 IGNITOR SYSTEM ANALYSIS OF SEQUOYAH PLANT 09/83 --
02/84 l ANALYSIS OF HYDROGEN AND STEAM RELEASES TO 02/82 --
02/84 CONTAINMENT DURING DEGRADED CORE COOLING ACCIDENIS -
HYDROGEN BURN EQUIPMENT SURVIVAL REPORT 09/83 --
I!/84 FOR ICE CONDENSER HYDROGEN COMBUSTION EXPERIMENTS IN 12/86 --
12/86 FITS FACILITY 4
REPORT ON POSSIBILITY OF LOCAL DETON. 01/84 --
01/87 UNCERTAINTY PAPER ON H2 COMBUSTION 05/87 --
05/87 MARCH-HECTR ANALYSIS OF SELECTED ACCIDENT 12/84 --
02/85 j IN AN ICE-CONDENSER CONTAINMENT l
HECTR VERSION 1.0 02/85 --
02/85 HECTR VERSION 1.5 04/86 --
04/86
! HYDROGEN-STEAM JET FLAME FACILITY 02/85 --
02/85 AND EXPERIMENTS
} REPORT ON DETONATION EXPERIMENTS SERIES I 09/87 --
06/87 1 NTS DATA ANALYSIS FOR CONTINUOUS 05/85 --
11/87 INJECTION TESTS l
EFFECT OF SPRAYS ON IGNITORS REPORT 09/83 05/88 --
09/86 05/88 EFFECTIVENESS OF NONPOWERED IGNITORS --
]
EFFECT OF H2 BURNS IN AEROSOLS SCOPING 10/83 05/88 --
4 STUDY REPORT 1
4 AS OF FY88 QUARTER 2 i
I i
RUN DATE: 05/11/88
- GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 170 ISSUE NUMBER: II.B.5(3) TITLE. EFFECT OF HYDROGEN COMBUSTION ON CONTAINMENT STRUCTURES ORIGINAL CURRENT ACTUAL MILEST0N ES DATE DATE DATE NTS H2 DEMONSTRATION TEST REPORT 03/84 05/88 --
NTS DATA ANALYSIS FOR PREMIVED TESTS 05/85 05/88 --
LARGE SCALE FLAME ACCELERATION TESTS 05/84 05/88 --
REPORT HECTR VERSION 2.0 09/87 09/88 --
REPORT ON DETONATION EXPERIMENTS 05/87 09/88 --
SERIES II RIL TO NRR AND ISSUE CLOSEOUT MEMO 07/87 09/91 --
TO EDO AS OF FY88 QUARTER 2 9 -- --
9 9
w J RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 171 ISSUE NUMBER: II.C.4 TITLE: RELIABILITY ENGINEERING IDENTIFICATION DATE: 05/80C PRIORITIZATION DATE- 11/83C TYPE: GSI PRIORITY: H TASK MANAGER: C. JOHNSON OFFICE / DIVISION / BRANCH: RES /DRPS/RHFB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS: RESOLUTION DATE' 09/88 WORK AUTHORIZATION: TMI ACTION PLAN. NUREG-0660 FIN CONTRACTOR CONTRACT TITLE A3282 BNL OPERATIONAL SAFETY RELIABILITY I WORK SCOPE EVAL _ THE EFFECT. OF RELIABILITY PROGRAM ELEMENTS (3) EVALUAIE RELIABILITY TECHNOLOGY FROM OTHER AND TECHNIQUES APPLICABLE TO MAINTAINING LWR SAFETY INDUSTIRES APPLICATION TO LWRS. (IN PROCESS)
DURING THE OPER LIFE OF THE PLANT. TASKS INCLUDE: (4) EVALUATE THE EFFECTIVENESS OF A RELIABILITY PROGRAM
[ (1) SURVEY GENERIC ISSUES AND PRECURSORS TO ASSESS THE THROUGH TRIAL APPLICATIONS. (IN PROCESS) l EFFECTIVENESS OF RELIABILITY TECHNOLOGY TO HELP (5l PUBLISH A TECHNICAL REPORT (NOREG/CR) THAT l RESOLVE CURRENT SAFETY ISSUES. (COMPLETE) INTEGRATES INTERIM FESULTS FROM THE ABOVE TASKS TO j (2) VISIT 5 PLANTS TO IDENTIFY RELIABILITY TECHNIOUES IDENTIFY THE ESSENTIAL ELEMENTS OF A RELIABILITY i THAT UTILITIES HAVE FOUND TO BE EFFECTIVE. AND PROGRAM. EVALUATE THEIR EFFECTIVENESS. AND IDENTIFY IDENTIFY THE ATTRIBUTES OF SUCCESSFUL RELIABILITY ATTRIBUTES OF SUCCESSFUL RELIABILITY PROGRAMS.
! PROGRAMS. (COMPLETE). (DRAFT ISSUED)
STA TUS THIS RESEARCH HAS: THESE RESULTS ARE DESCRIBED IN BNL*S DRAFT NUREG/
IDENTIFIED THE ESSENTIAL ELEMENTS OF A CLOSED-LOOP CR-4618 5/86. AFTER PRESENTING THE RESULTS TO NRC STAFF RELIABILITY PROGRAM APPLICABLE TO LWR OPERATIONAL IN 6/86 AND 7/86 BNL WORK ON THIS PROJECT STOPPED FOUND THAT USE OF RELIABILITY TECHNOLOGY WITHIN TEMPORARILY. PENDING NRC REVIEW OF THE RESULTS.
l THIS TYPE OF CLOSED-LOOP FRAMEWORK CAN HELP TO WE COMPLETED THIS INTERNAL REVIEW IN 2/87 AND l PREVENT PROBLEMS F ROM OCCicRRING. AUTHORIZED BNL TO RESTART THE RESEARCH IN 3/87.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION TO BE DETERMINED TASK MANAGER AVAILABILITY LIMITED BY OTHER WORK (RISK BASED PERFORMANCE INDICATORS). RESULTED IN 2-MONTH SLIP IN CONTRACTOR REPORT.
l f AS OF FY88 OUARTER 2 l
l
l 1
i CUN DATE: 03/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE 172 ISSUE NUMBER: II C.4 TITLE- RELIABILITY ENGINEERING ORIGINAL CURRENT ACTUAL M I LEST ON ES DATE DATE DATE DISCUSS WITH INPO THE NEEDS TO DEV AGREEMENT 06/83 --
11/83 ISEE NRC POLICY & PLANNING GUID_ 1983 NUREG 0885 ISSUE 2 PGS, 11 & 12)
RESEARCH GENERIC RELIABILITY METHOD 12/83 --
04/J4 SURVEY / ADAPT. OF RELIABILITY TECHNIQUES & 06/84 --
02/85 IDENTIFICATION OF RELIABILITY PRCGRAM ELEMENTS FOR DETAILED EVALUATION BEGIN TRIAL USE 12/84 --
07/85 COMPLETE CASE STUDY OF 5 PLANTS TO IDENTIFY 02/86 --
03/86 RELIABILITY TECHNIQUES THAT INDUSTRY HAS FOUND TO BE EFFECTIVE DRAFT INTERIM TECH RPT IDENT. ELEMENTS OF 04/86 --
05/86 RELIAB. PROGRAM, EVAL EFFECTIVENESS &
TECHNIQUES & APPS. ISS DRAF T RPT FOR REVIEW STAFF MEMO TO EDO EVALUATING REGULATORY 06/86 --
02/87 NEEDS FOR RELIABILITY ASSURANCE AND OUTLINING PLAN FOR IMPLEMENTATION PUBLISH FINAL NUREG 12/87 06/88 --
ISSUE CLOSEOUT MEMO TO EDO 12/87 09/88 --
AS OF FY88 QUARTER 2 O O O
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J G - v RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 173 ISSUE NUMBER: II.E.4.3 TITLE: CONTAINMENT DESIGN-INTEGRITY CHECK IDENTIFICATION DATE: 05/80C PRIORITIZATION DATE- 11/83C TYPE: GSI PRIORITY: H TASK MANAGER: A. SERKIZ OFFICE / DIVISION / BRANCH: RES /DRPS/RPSI ACTION LEVEL: INACTIVE STATUS: 38 TAC NUMBERS: RESOLUTION DATE: 03/88C WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN (APPENDIX G)
FIN CONTRACTOR CONTRACT TITLE A1802 SNL FEASIBILITY STUDY OF ALTERNATIVE CONTAINMENT TEST MTHDS
'I W0RK SC0PE TO DETEkMINE WHETHER ALTERNATIVE OR ADDITIONAL METHODS CONTAIMENT LEAKAGE TESTS ARE NEEDED FOR VERIFICATION TASK 2- FEASIBILITY ASSESSMENT OF ALTERNATIVE LEAKAGE OF CONTAIMENT INTEGRITY, AND WHETHER IMPROVEMENTS DETECTION METHODS AND COSTS TO INSTALL IN PLANT ADMINISTRATIVE AND OPERATIONAL IMPLEMENTATION TASK 3: ATTAINMENT OF CONTAINMENT ISOLATION THROUGH OF PROCEDURES COULD BE MADE TO IMPROVE CONTAINMENT ADMINISTRATIVE AND PROCEDURAL CHANGES AVAILABILITY. TASK 4: PREPARATION OF A TECHNICAL FINDINGS REPORT TASK 1; SURVEY AND EVALUATION OF CONTAINMENT LEAKAGE ST A TUS THE RESULTS Of SNL*S LETTER REPORTS FOR TASKS 1, 2 AND CFR 100 ARE NOT EXCEEDED.
3 HAVE BEEN COMBINED WITH THE RISK ANALYSES ASSOCIATED WITH REVIEW AND CONCURRENCE ON NUREG-1273 "TECHNICAL CONTAINMENT LEAKAGE RATES WHICH ARE REPORTED IN FINDINGS AND REGULATORY ANALYSIS FOR GENERIC SAFETY ISSUE NUREG/CR-4330 TO DEVELOP A TECHNICAL FINDINGS AND REGULATORY II.E.4.3. CONTAINMENT INTEGRITY CHECK, HAVE BEEN COMPLETED.
ANALYSIS FOR THIS SAFETY ISSUE. THESE FINDINGS SUPPORT THESE FINDINGS SUPPORT CLOSURE OF GSI II.E.4.3. A MEMO FROM MAINTAINING THE CURRENTLY-EMPLOYED TYPE A. 8 AND C TESTS THE DIRECTOR /RES TO THE EDO WAS ISSUED ON 3/22/88, THIS j WITH SOME FOTENTIAL FOR RELAXATION OF ALLOWABLE LEAKAGE ISSUE IS RESOLVED.
- RATES PROVIDED RADIOACTIVITY DOSE LIMITS AS REQUIRED BY 10 AFFECTED DOCUMENTS PROBLEM / RESOLUTION 10 CFR PART 50 APPENDIX J NONE AS OF FY88 QUARTER 2 l
4
K U'1 DA T E - 05/11/88 GENERIC ISSUE MANAGEMENT C04 TROL SYSTEM PAGE: 174 ISSUE NUMBER' II.E 4.3 TITLE CONTAINMENT DESIGN-INTEGRITY CHECK ORIGINAL CURRENT ACTUAL M I LE S T 0N E S DATE DATE DATE hhShkhbN RkhhkhkVktbkhkhkkhkhkthhY bh b4/85 --
05/85 TEST METH005 INTERIM REPORT ON THE FEASIBILITY OF 03/S6 --
05/86 ALTERNATIVE CONTAINMENT LEAK TESTS TASK I DRAF T REPORT 03/87 --
12/86 TASK 2 DRAFT REPORT 06/87 --
12/86 TASK 3 DRAFT REPORT 05/87 --
12/86 DRAFT REGULATORY ANALYSIS 10/87 --
05/87 RECEIVE CONTRACTORS FINAL REPORT ON THE 09/86 --
12/86 FEASIBILITY STUDY FOR ALTE9 NATIVE CONTAINMENT TEST METHODS EVALUATE REPORT ON ALTERNATIVE CONT AINME NT 10/86 --
05/87 TEST METHODS FEASIBILITY DTR 12/87 --
03/88 CLOSEOUT PACKAGE TO RES DIRECTOR 01/87 --
03/88 RESOLUTION OF ISSUE 02/88 --
03/88 AS OF FY88 CUARTER 2 O O O
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 17S ISSUE NUMBER: II.E.6.1 TITLE. IN-SITU TESTING OF VALVES IDENTIFICATION DATE: 05/80C PRIORITIZATION DATE- II/E3C TYPE. GSI PRIORITY- M TASK MANAGER: 0. ROTHBERG OFFICE / DIVISION / BRANCH. RES /DE /EIB ACTION LEVEL; ACTIVE STATUS-.
1 TAC NUMBERS: RESOLUTION DATE- 10/89 WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN (APPENDIX G)
FIN CONTRACTOR CONTRACT TITLE A3821 BNL ADEOUACY OF CURRENT VALVE INSERVICE TEST METHODS W0RK SC0PE (1) SURVEY INDUSTRY PRACTICES AND REQUIREMENTS FOR (3) IDENTIFY PERFORMANCE REQUIREMENTS THAT ARE NOT DESICM, SPECIFICATION, QUALIFICATION. AND PRE- ADEQUATELY VERIFIED BY ANALYSIS OR TEST.
OPERA 110NAL AND SURVEILLANCE TESTING OF VALVES (4) EVALUATE ALTERNATE MEANS OF VERIFYING PERFORMANCE.
IN SAFETY-RELATED SYSTEMS. (5) DEVELOP STAFF POSITIONS FOR ADDITIONAL PERIODIC (2) COMPARE THE TESTS WITH PERFORMANCE REQUIREMENTS CAPABILITY TESTS.
AND SPECIFICATIONS.
STA TUS
_.-__-~-_....._...___-.____._.-_.__......____._______.----_-.-.------_-___-_._---.-_..._-._._.---.._----_-._.-.-__._.-_--_
- 1. CHECK VALVES 2. THERMAL OVERLOAD DEVICES THIS ITEM IS BEING RESOLVED BY INDUSTRY EFFORTS. A JOINT A DRAFT REPORT OF THE INVESTIGATION BY EIB 0F REG. GUIDE OWNERS GROUP TASK FORCE FOR CHECK VALVES WAS FORMED BASED ON 1.106 HAS BEEN PREPARED AND SUBMITTED TO INTERESTED PARTIES MEETINGS IN 1986 BETWEEN THE INDUSTRY AND NRC. THE TWO WITHIN NRC FOR TECHNICAL REVIEW. THE CONCLUSION OF THE I
MAJOR COMPONENTS OF THE INDUSTPY PROGRAM ARE SOER 86-03 FROM STUDY WAS THAT THE GUIDANCE CONTAINED IN REG. GUIDE I 106 INPO AND APPLICATIONS GUIDE. SOER 86-03 0F 10/15/86 IS TECHNICALLY CORRECT. HOWEVER, LICENSEES HAVE BEEN ENTITLED "CHECK VALVE FAILURES OR DEGRADATION.* HAS BEEN DESIGNING THERMAL OVERLOAD DEVICES POORLY, MOSTLY DUE TO IMPLEMENTED WITH MIXED RESULTS, ACCORDING TO NRR. .NRR LACK OF INDUSTRY GUIDANCE. ACCORDINGLY. IT WILL BE PROPOSED INSPECTORS HAVE SURVEYED TWO PLANTS AND HAVE THREE OTHERS TO ASK THAT INDUSTRY GROUPS SUCH AS NMAC/EPRI, ASME/0M.
SCHEDULED. A DRAFT OF THE APPLICATIONS GUIDE WAS SUBMITTED IEEE. OR INP0/NUMARC DEVELOP SUCH STANDARD GUIDANCE FOR USE TO NRC AND GIVEN APPROVAL ON 9/3/87. ACRS (SUBCOMMITTEE) 0F THERMAL JVERLOAD PROTECTION. TOL DRAFT IS COMPLETE AND WAS BRIEFED IN 3/88. AS OF NOW, NO FURTHER ACTION IS IS BEING PROCESSED FOR. ISSUANCE.
PLANNED FOR THIS ITEM UNDER II.E.6.1. ASSUMING THAT THE 3. MOTOR OPERATED VALVES IMPLEMENTATION OF THE INDUSTRY PROGRAM PROVES TO BE THE STAFF HAS CONTRACTED WITH BNL TO PREPARE A EFFECTIVE. THIS ITEM WILL BE CONSIDERED RESOLVED. COST-BENEFIT / REGULATORY ANALYSIS IN ORDER TO SUPPORT RES/EIB IS TO RECEIVE FINAL VERSION OF EPRI APPLICATIONS EXTENDING REQUIREMENTS TO VERIFY SWITCH SETTINGS AND VERIFY GUIDE FOR REVIEW. NRR IS ISSUING PERIODIC PROGRESS REPORTS OPERATING PARAME TERS FOR ALL SAFE TY-RELATED MOTOR-OPERATED TO THE COMMISSION DESCRIBING INDUSTRY IMPLEMENTATION VALVES. THIS WOULD BE AN EXiENSION OF IE BULLETIN 85-03 J
EFFORTS. REQUIREMENTS. A DRAFT OF THE BNL REG. ANALYSIS WAS RECEIVED AS OF FY88 OUARTER 2
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 177 ISSUE NUMBER: II.E.6.I TITLE. IN-SITU TESTING OF VALVES AFFECTED DOCUMENTS PROBLEM / RESOLUTION STANDARD GUIDANCE FOR THE APPLICATION OF THESE DEVICES TO SAFETY-RELATED VALVE OPERATORS.
PRESSURE ISOLATION VALVES. WHICH ARE TWO VALVES IN SERIES AT EACH INTERFACE SEPARATING THE HIGHER PRESSURE l RCS FROM ATTACHED LOWER PRESSURE SYSTEMS, MUST BE PERIODICALLY TESfED. SOME OLDER PLANTS DO NOT PERFORM SUCH TESTS ON ALL PIV'S. STUDIES ARE BEING PERFORMED TO JUSTIFY IMPOSING SUCH PERIODIC TESTING ON ALL PIV'S.
ORIGINAL CURRENT ACTUAL l i MILEST0N ES DATE DATE DATE INSERVICE TESTING OF CHECK VALVES -- -- --
(INPO) ISSUE SOER REGARDING 07/86 --
10/86 AUGMENTED TESTING OF CHECK VALVES I
(NRR/RES) REVIEW SOER TO SEE IF NRC 10/86 --
02/87 ,
CONCERNS ON IN-SITU TESTING OF "SIMPLE" CHECK 4
VALVES SATISFIED. ISSUE RPT &/OR LTR (NSSS OWNERS GROUP) ISSUE OWNERS OS/87 --
11/87 GROUP APPLICATION GUIDE FOR CHECK j VALVES (NRR/RES) REVIEW DWNERS GROUP APPL GUIDE TO 08/87 --
01/88
, SEE IF NRC CONCERNS ON IN-SITU TEST OF "SIMPLE" CHECK VALVES ARE SATIFIED
]
] (NRR/RES) REPORT (ACRS) 08/87 --
03/88 INSERVICE TESTING OF MOV*S -- -- --
tRES) ISSUE MOVATS REPORT REGARDING 09/85 --
01/86 USE OF SIGNATURE TRACING TECHNIQUES
- 10 EVAL. THE OPERABILITY OF MOV'S 1
l (NRR/RES) REVIEW MOVATS REPORT AND AEOD 11/85 --
08/86 j COMMENTS ON MOVATS REPORT t
AS OF FY88 QUARTER 2 I
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 178 ISSUE nut 48ER. II.E.6.1 TITLE IN-SITU TESTING OF VALVES ORIGINAL CURRENT ACTUAL M I LES T 0N E S DATE DATE DATE (NRR) REVIEW RESPCNSES TO IE BULLETIN 01/87 06/89 --
85-03 FPOM LICENSEES AND APPLICANTS (RES/EIBl PREPARE STAFF POSITION 02/86 --
10/87 ON ADDITIONAL AND/OR MODIFIED IN SITU TESTING OF MOV"S (RES/EIB) PREPARE VALUE/ IMPACT STMT & CnST/ 04/87 --
02/88 BENEFIT ANALYSIS FOP STAFF POSITION ON MOV IN-SILO TEST COMPLETE PROPOSED RESOLUTION PACKAGE 03/88 06/88 --
DIVISION DEPUTY DIRECTOR RES REVIEW COMPLETED 04/88 07/88 --
PACKAGE TO CRGR (29) 06/88 09/88 --
CRGR REVIEW COMPLETE 08/88 10/88 --
ISSUANCE OF FINAL RESOLUTION MEMO ON MOV'S 09/89 12/88 --
THERMAL OVERLOAD PROTECTION OF MOV'S -- -- --
lRES/EIB) STAFF COMPLETES REVIEW TO 05/85 --
10/87 DETERMINE REQUIRED MOD, IF ANY. TO REG GUIDE 1.106 REGARDING TOL PROTECTION (RES/EIB) STAFF PREPARES POSITION VALUE/ 02/86 --
10/87 IMPACT STMT. COST / BENEFIT ANAL., DRAFT RG MOD AND/OR GEN LTR PKG ON PESULTS RES DIRECTOR COMPLETE REVIEW OF TOL 08/87 04/88 --
PROTECTION PACKAGE & ISSUE NUPEG FOR PUBLIC COMMENT PUBLIC COMMENTS RECEIVED ON DRAFT NUREG 05/88 05/88 --
FINAL NUREG ISSUED WITH C0t1MENTS 07/98 07/88 --
PRESSURE ISOLATION VALVES -- -- --
AS OF FY88 OUARTER 2 O O O
- O RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONIROL SYSTEM PAGE; 179 ISSUE NUMBER: II.E.6.1 TITLE: IN-SITU TESTING OF VALVES ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE (RES/EIB) REVIEW RES PROPOSALS FOR PRLSSURE 05/84 --
05/84 ISOLATION VALVE LEAK TESTS & OTPERS. PROVIDE RECS TO RES FOR REVS TO TEST SCOPE & LAB SEL.
(RES) INITIATE CONTRACT FOR PIV 05/84 --
10/84 LEAK RATE TESTING (ETEC) ,
(RES/EIB) ISSUE INTERIM MEMO. TO VENDOR 07/86 --
07/86 DIVISIONS CALLING FOR PIV TESTING AT i MTOL*S IN ACC. WITH 10CFR 50.109 r
(RES/EIB) PREPARE GENERIC LETTER TO ALL 08/86 --
08/86 LICENSEES ASKING FOR PROOF OF VERIF. OF RCPB BY TESTING PIV'S (NRR) DIRECTOR, NRR FORWARD 50.54(F) 08/86 --
02/87 GENERIC LETTER FOR CRGR APPROVAL (CRGR) REVIEW AND APPROVE 50.54(F) 09/86 --
03/87 LETTER TO ALL LICENSEES REGARDING VERIFICATION SF PIV'S (NRR/DSRO) ISSUE 10 CFR 50.54(F) 09/86 --
03/87 LETTER ON PIV VERIFICATION (RES) REVIEW LIC RESP TO 10CFR 50.54(F) 01/87 --
10/87 ON PIV VERIF. DETERM)NE PROCS ARE ADEQUATE TO ASSURE INTEG OF RCTR COOLANT PRES BNDRY IRES) ISSUE ETEC/ DOE LABORATORY REPORTS 07/86 04/88 --
ON PIV TESTING.(1) CHECK VALVES; 32)
GATE VALVES (RES/EIB) COMPLETE GSI 105 "INTERSYSTEM .04/88 09/88 --
LOCA IN LWR'S" PACKAGE TO CRGR (RES/EIB) PREPARE POSITION FOR PIV BOUNDARY 06/88 --
02/88 VERIFICATION TESTING BASED ON RESULTS OF GSI 405 & ETEC TESTS AS OF FY88 QUARTER 2
l
! RUN DATE. 05/11/88 1
j GENERIC ISTUE PENAGEME NT CONTPOL SYSTEM PAGE 180 ,
i !
j ISSUE NUMBER- II E.6.1 TITLE- IN-SITU TESTING OF VALVES ORIGINAL CURRENT ACTUAL
! M ILEST 0N E S DATE DATE DATE
- j __._. ____.....__...___._____________._______
i DIVISION DEPUTY DIPECTOR PES REVIEW COMPLETED 05/88 10/88 --
CONCURRENCE BY OTHER OFFICES 07/88 01/89 --
i l PROPOSED RESOLUTION SENT TO CRGR BY PES /E IB 10/88 03/89 --
, i j CPGR CCMPLETES REVIEW OF PROPOSED PIV TESTING 10/88 06/89 --
FRN OF ISSUANCE OF FINAL PESOLUTION 04/89 10/89 --
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\s RUN DATE: 05/II/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 181 l ISSUE NUMBER: II,F.S TITLE- CLASSIFICATION OF INSTRUMENTATION CONTROL AND ELECTRICAL EQUIPMENT l IDENTIFICATION DATE: 05/80C PRIORITIZATION DATE- II/83C TYPE: LI PRIORITY:
i TASK MANAGER: TBD OFFICE / DIVISION / BRANCH- RES /DE /EIB ACTION LEVEL: INACTIVE STATUS: 5 l
l TAC NUMBERS: RESOLUTION DATE- _ _ _ _ _
WORK AUTHORIZATION: TMI ACTION PLAN. NUREG-0660 FIN CONTRACTOR CONTRACT TITLE A3249 BNL CLASSIFICATION OF SYSTEMS IMPORTANT TO SAFETY .
W0RK SC0PE TO DEVELOP A METHODOLOGY FOR THE CLASSIFICATION OF SYSTEMS IMPORTANT TO SAFETY.
5TA !US kkkkNkkhbhhkkkhkhkbkhhkhbIRhbhbtEbbkhkbkkkbhhk khE kkhHh b L Rkhhlb hh hh kHkh kkkk hkh hk kbHkkVkb SYSTEMS IMPORTANT TO SAFETY. IEEE STD. P-827 HAS BEEN BY THE ISSUANCE BY THE IEEE OF A SUITABLE STANDARD WHICH MAY ABANDONED IN FAVOR OF A DIFFERENT APPROACH INVOLVING THE SUBSEUENTLY BE ENDORSED IN WHOLE OR IN PART BY A REGULATORY DEVELOPMENT OF A NEW STANDARD TAKING INTO ACCOUNT APPLICABLE GUIDE. OR ALTERNATIVELY BY THE ISSUANCE OF A REGULATORY WORK DONE BY OTHER TECHNICAL SOCIETIES SUCH AS ASME AND ANS. GUIDE IRRESPECTIVE OF WHAT OR WHEN IEEE MIGHT ISSUE A NRC IS PARTICIPATING IN THIS EFFORT AS STIPULATED BY ITEM STANDARD IN THIS AREA. AT THIS TIME WE ARE CONTINUING OUR II.F.S_ THE PARALLEL NRC EFFORT TO DEVELOP A DRAFT PARTICIPATION IN THE IEEE EFFORT TO DEVELOP A DRAFT STANDARD REGULATORY GUIDE ON CLASSIFICATION OF SYSTEMS IMPORTANT TO P-1409 UNDER IEE/NREC/SC_6.2. WORKING GROUP ON SYSTEM SAFETY HAS BEEN DESIGNATED AS PRIORITY C AND HAS BEEN TAKEN CLASSIFICATION.
OFF THE LIS' 0F ACTIVE RES TASKS.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION l
DRAFT REGULATORY GUIDE FOR THE CLASSIFICATION OF FOR THE PAST FIFTEEN YEARS IEEE/NPEC AND NRC STAFF HAVE INSTRUMENTATION. CONTROL AND ELECTRICAL SYSTEMS AND BEEN ATTEMPTING TO DEVELOP A STANDARD TO DEFINE REQUIREMENTS COMPONENTS (ICES /El IMPORTANT TO SAFETY. FOR EQUIPMENT AND SYSTEMS THAT ARE NOT SAFETY-RELATED. BUT ARE SUFFTCIENTLY IMPORTANT TO SAFETY TO WARRANT SPECIAL CONSIDERATION. .THESE EFFORTS HAVE NOT MEY WITH SUCCESS; NOR HAS BNL BEEN ABLE. IN THE OPINION OF E ME B . TO DEVELOP AN l
ACCE P TABLE ' STANDARD' OVER THE PAST SEVERAL YEARS UNDER CONTRACT TO NRC. IEEE/NPEC WORKING GROUP 6.2 IS CURRENTLY AS OF FY88 OUARTER 2 l
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEFENT CONTROL SYSTEM PAGE: 182 ISSUE NUFFEP- II.F 5 TITLE CLASSIFICATION Or INSTRUMENTATION CONTROL AND ELECTRICAL EQUIPMENT AFFECTED DOCUMENTS PROBLEM / RESOLUTION TRVING TO DEVELOP A STANDAPD. WE WILL PARTICIPATE IN THIS ACTIVITY BY APPOINTING AN NRC STAFF MEMBER TO THE WORKING GROUP i ORIGINAL CURRENT ACTUAL M ILEST 0N ES DATE DATE DATE
! ,UE TRANSFER MEMO TO NPR 02/86 --
12/85 ISSUE CLOSEOUT MEMU TO EDO 05/86 TBD --
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RUN DATE: 05/11/88 1
GENERIC ISSUE MANAGEME NT CONTROL SYSTEM PAGE: 153 ISSUE NUMBER: II.H.2 TITLE: OBTAIN DATA CN CONDITIONS INSIDE TMI-2 CONTAINMENT l IDENTIFICATION DATE: 05/80C PRIORITIZATION DATE- II/83C TYPE: GSI PRIORITY: H TASM MANAGER: R. VAN HOUTEN OFFICE / DIVISION / BRANCH. RES /DRAA/AEB ACTION LEVEL: ACTIVE STATUS:
TAC NUMBERS:
RESOLUTION DATE I2/89 WORK AUTHORIZATION: TMI ACTION PLAN. NUREG-0660 FIN CONTRACTOR CONTRACT TITLE D2072 MPR TMI-2 BOTTOM HEAD SAMPLING NONE NONE NONE W0RK SC0PE hRbHkbbbbPkkkhkbWkkbbbk b hbbb RY b EbhhbH VEbbkl hHkbbhkRkbbbhhbN bRkbbkkhbbkbbN hh bh AND DATA-GATHERING PROGRAMS WITHIN THE THI-2 CONTAINMENT. AND VARIOUS MECHANICAL. ELECTRICAL. AND INSTRUMENTATION THESE PROGRAMS CONCENTRATE ON RETRIEVING DATA WHICH EQUIPMENT. PRIOR TO CY88 NRC PRIMARILY PROVIDED TECHNICAL CHARACTERIZE THE PROGRESSION OF THE ACCIDENT AND THE EXPERTISE AND HOT-CELL EXAMINATION OF CORE MATERIALS. THE PESULTING RADIOLOGICAL SOURCE TERM. THE PROGRAMS ADDRESS PROGRAMS WERE GENERALLY CARRIED OUT WITH FUNDS FROM DOE AND T Hi EXAMINATION OF THE REACTOR INTERNALS (ESPECIALLY THE OTHERS. EARLY IN CY88, NRC INITIATED ITS OWN COOPERATIVE REACTOR CORE AND FUEL). THE PRIMARY SYSTEM PIPING AND PROGRAM TO EXAMINE THE DAMAGED BOTTOM HEAD.
STATUS PRkbhkkkbRhbbbhbkkhRkhkbbhhhk-2bbhkkXkhkhkhhhh kFhkR kHkkbbkbkkhHkbkkkhkhPRbbRkkhkbhkhbbThh5 BOTH ON-SITE AND OFF-SITE. A PLANNING BASIS FOR WORK MINUTES. DOE HAD NOT BUDGETED FOR THE ADDITIONAL RESEARCH SUPPORTED BY NRC AND SEPARATELY BY DOE INCLUDED A PRIORITY TO EXAMINE THE EFFECTS OF THIS MOLTEN MATERIAL ON THE VESSEL ANALYSIS. DEPENDING UPON AVAILABILITY OF SAMPLES FROM DOE. BOTTOM AND VESSEL COMPONENTS. THE CHARIMAN INDICATED THAT NRC IS CONDOCTING: A SERIES OF OFF-SITE EXAMINATIONS OF HE BELIEVED TilIS EXAMINATION TO BE VERY IMPORTANT. NRC SELECTED CORE MATERIALS AT A NATIONAL LABORATORY. ASMED DOE TO PERFORM THE EXAMINATION BUT DOE DECLINED _
RECENT CORE EXAMINATIONS INDICATE A LARGE FLOW OF NRC INITIATED A COOPERATIVE PROGRAM JANUARY 15 1988.
MOLTEN MATERIAL (HORE THAN 15 TONS) INTO THE LOWER PLENUM NEGOTIATIONS WITH PROSPECTIVE PROGRAM PARTNERS CONTINUE.
AFFECTED DOCUMENTS PROBLEM / RESOLUTION DEVELOPED AND DEMONSTATED PRIOR TO THE 10/15/89-12/1/89 AS OF FY88 QUARTER 2
RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE- 184 ISSUE NUMBER: II.H.2 TITLE. OBTAIN DATA ON CONDITIONS INSIDE THI-2 CONTAINMENT AFFECTED DOCUMENTS PROBLEM / RESOLUTION SAMPLING WINDOW ORIGINAL CURRENT ACTUAL M I LEST 0N E S DATE DAeE DATE REVISED CORE EXAMINATION PLAN IDOE 04/83 --
10/84 RESPONSIBILITY HEAD REMOVAL 07/83 --
07/84 PLENUM REMOVAL 07/85 --
05/85 BEGIN DEFUELING 10/85 --
12/85 REVISE CORE EXAMINATION PLAN 12/85 --
02/86 CORE DRILLING 07/86 --
03/87 COMPLETE DEFUE8 ING - 06/87 12/88 --
FINAL FUEL ANALYSIS REPORT 09/87 10/89 --
ISSUE CLOSEOUT MEMO TO EDO 12/87 I2/89 --
AS OF FY88 OUARTER 2 O O O
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RUN DATE: 05/11/88 8
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 185 ISSUE NUMBER: II.J.4.1 TITLE: REVISE DEFICIENCY REPORTING REQUIREMENTS IDENTIFICATION DATE: 05/80C PRIORITIZATION DATE: 11/83C TYPE: GSI PRIORITY:
TASK MANAGER: W. JONES OFFICE / DIVISION / BRANCH: AE00/SPDV/SPRO ACTION LEVEL: ACTIVE STATUS. NR TAC NUMBERS:
RESOLUTION DATE: 11/88 WORK AUTHORIZATION: TMI ACTION PLAN, N9 REG-0660 l
! FIN CONTRACTOR CONTRACT TITLE I
NONE --- ..-------.......-.......-------------.------. -------...----------
NONE NONE W0RK SC0PE NRC WILL REVISE THE REPORTING REQUIREM'NTS OF 10 CFR REPORTS RECEIVED AS A RESULT OF THESE RULE CHANGES WILL 50.55(El AND 10 CFR 21 TO ASSURE THAT ALL REPORTABLE ITEMS PROVIDE INCREASED INF ORMATION ON COMPONENT F AILURES THAT ARE REPORTED PROMPTLY AND THAT THE INFORMATION SU8MITTED IS AFFECT SAFETY SO THAT PROMPT AND EFFECTIVE CORRECTIVE ACTION COMPLETE. A MAJOR OBJECTIVE WILL BE TO ELIMINATE CAN BE TAKEN.
DUPLICATIVE EVALUATION AND REPORTING AND ESTABLISH THE INFORMATION wit.L ALSO BE USED AS INPUT TO CONSISTENT SAFETY DEFICIENCY REPORTING REQUIREMENTS. THE AN AUGMENTED ROLE OF THE NRC*S VENDOR AND CONSTRUCTION-INSPECTION PROGRAM.
STA TUS
--.---CRGR -----.........------.-----...------ ---....-.--..---- ...------ ..---........--.----------.......---...--...---.......
REVIEWED THE PROPOSED 10 CFR 21 AND 50.55tEl RULE AMELJMENTS ON 11/12/87 AND CRGR COMMENTS WERE PROVIDED IN A SUBMITTED TO THE CRGR STAFF ON 12/29/87 FOR REVIEW AND 12/17/8 7 MEMO. FORWARDING TO THE EDO. FORWARDED TO COMMISSION ON 3/9/88.
THE PROPOSED AMENDMENTS WERE REVISED TO ACCOMMODATE THE CRGR COMMENTS. THE AMENDMENTS WERE COMMISSION PROCEEDING.
VOTING COMPLETED ON 4/18/88. AWAITING SRM BEFORE AFFECTED DOCUMENTS
.......--......--....---------.----...----.-----....-------- PROBLEM / RESOLUTION 10 CFR 50.55tE), 10 CFR 21 ------.--....--...------------.--......---------.----..-..--
THE SCHEDULE HAS BEEN REVISED TO REFLECT DELAYS IN THE REVIEW AND CONCURRENCE PROCESS. THE SCHEDULE FOR FINAL PUBLICATION OF THE RULE IS NOT EXPECTED TO CHANGE.
ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE 0FFICE CONCURRENCE COMPLETE 04/83 --
06/85 AS OF FY88 OUARTER 2
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RUN DATE: 05/11/88 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE: 187 ISSUE nut 48ER : II.J.4.1 TITLE. REVIS[ DEFICIENCY REPORTING REOUIREMENTS ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE RESOLUTION OF PUBLIC COMMENTS COMPLETE 06/88 09/88 --
PACKAGE TO EDO '
EDO CONCURRENCE PACKAGE TO COffilSSION 01/88 10/88 --
FINAL RULE PUBLISHFD 09/88 11/88 --
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AS OF FY88 OUARTER 2
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