ML20151Z121
| ML20151Z121 | |
| Person / Time | |
|---|---|
| Issue date: | 12/31/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151Z118 | List: |
| References | |
| NUDOCS 8602140028 | |
| Download: ML20151Z121 (234) | |
Text
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ENCLOSURE t
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM ~
FIRST QUARTER FY-86 UPDATE i
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! 0FFICE OF NUCLEAR REACTOR REGULATION
! DECEMBER 1985.
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i 8602140029 B60129 PDR DRQ NRRC PDR i
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. 1 TABLE OF CONTENTS (a) Generic Issue Management Control System (1) System Description (2) System Abbreviations (b) Summary of Generic Issues Schedule Slippage (c) Table 1 - Generic Safety Issues Scheduled for Resolution, New Generic Issues and Issues Resolved (d) Table 2 - Number of Generic Safety Issues Resolved and Scheduled for Resolution First Quarter FY-86 (e) Table 3 -
Generic Safety Issues Resolved by Fiscal Year (f) Table 4 -
Generic Safety Issues Scheduled For Resolution by Q
V' Fiscal Year (g) Table 4A - NRR Generic Safety Issues Scheduled for Resolution (h) Table 4B - NRR-TMI Generic Safety Issues Scheduled for Resolution (i) Table 4C - Non-NRR TMI and Generic Safety Issues Scheduled for Resolution (j) Table 40 - Human Factors Program Plan Generic Safety Issues Scheduled for Resolution (k) Table 5 -
Number of Generic Issues Prioritized in FY-83, FY-84, FY-85 and 1st Quarter FY-86 (1) Table 6 -
Generic Issues Prioritized as of First Quarter FY-86 (m) Table 7 -
Generic Issues to be Prioritized (n) Table 8 -
Generi: Issues to be Reprioritized (o) Table 9 -
Summary of the Prioritization of all New Generic Issues, Task Action Plan Items, and TMI Action Plan Items (p) Work Scope & Schedules for each Approved Generic Issue 1 J I
T GENERIC ISSUE MANAGEMENT CONTROL SYSTEM The Generic Issues Management Control System (GIMCS) provides appropriate information necessary to manage safety related and environmental generic issues through technical resolution and completion. For the purpose of this management control system technically resolved is defined as the point where the staff's technical resolution has been issued. Generally, speaking, this occurs when the technical resolution has been incorporated into one or more of the following:
(a Comission policy statement / orders b NRC Regulations
(( Standard Review Plan Regulatory Guide t( Generic Letter GIMCS is part of an integraded system of reports and procedures that would manage generic safety issues, TMI-related issues, and proposed new generic issues through the stages of prioritization, technical resolution, development .
of new criteria, review and approval, public comments, and incorporation into the Standard Review Plan (SRP), as appropriate. NUREG-0933 provides an evaluation for a recommended priority listing based on the potential safety significance and cost of implementation for each issue; NRR Office Letter Number 40 provided procedures and criteria for adding new generic issues to the system; and GIMCS provides proposed scheduling for resolving and completing O. issues on the prioritized listing. GIMCS will provide information to manage and control issues that are ranked High-priority generic issues, Medium-priority generic issues, issues for which possible resolution has been identified for evaluation, issues for which a technical resolution is available (as documented by memorandum, analysis, NUREG, etc.), and issues designated by the Director of NRR as issues for which resources have been made available for resolution and completion. Issues ranked as either " Low" or " Dropped" are not allocated resources. therefore, there is no resolution to be tracked by GIMCS.
Some new generic issues prioritized and processed in accordance with NRR Office Letter No. 40 may not have resources allocated for resolution and completion.
These issues will be listed in GIMCS as inactive issues. These will generally be Medium priority issues that have no safety deficiency demanding high-priority attention, but there is a potential for safety improvements or reduction in uncertainty of analysis that may be substantial and worthwhile. Efforts for resolution of these issues will be planned, over the next several years, but on a basis that will not interfere with the resolution of High-priority generic issue work or other high priority work. Thus,some(Medium) generic issues will be inactive until such time as resources become available to resolve the various issues. As resource allocations are directed at issue resolution, they will become active. The detailed schedule for resolving and completing the generic issue will be developed and monitored by the management control system.
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O Management and control indicators used in GIMCS are defined as follows:
- 1. Item No. -
Generic Issue Number.
- 2. Issue Type - Safety, Environmental or pegulatory Impact High, Note 1 or Note 2 (From NUREG-0933),
Medium.
- 3. -Action Level - Degree of management attention need to process generic issues in accordance with established schedules L1 - No management action is necessary L2 - Division Director action is necessary
- L3 - Director NRR action is necessary
- 4. Office /Div/Br - 1st listed has lead responsibility for re-solving issue, others listed have input to
, resolution.
- 5. Task Manager - Name of assigned individual responsible for schedule updating.
- 6. Tac Number - Each issue should be assigned a TAC f.
- 7. Title - Generic Issue Title.
- 8. Work Authorization - Who or what authorized work to be done on generic issue.
- 9. Contract Title - ProvideContractTitle(ifcontractissued).
- 10. Contractor Name/ Identify Contractor Name and FIN Number (as FIN No. - appropriate). If contract is not yet issued, indicate whether the contract is ircluded in ..
the FIN plan.
- 11. Work Scope - Describes briefly the work necessary to tech-nically resolve and complete the generic issue.
- 12. Affected Documents - Identifies documents that the technical resolution will be incorporated into to identify new criteria. -
- 13. Status - Describes current status of work.
! 14. Problem / Resolution - Identifies potential problem areas and describes l what actions are necessary to resolve them.
j 15. Technical Resolution - Identifies detailed schedule of milestone i dates that are required for completing the issue through the issuance of the SRP revision j or other change that documents requirements.
f Milestones - Selected significant milestones. The " original"
- schedule remains unchanged. Changes in schedule are listed under "rurrent". Actual completion j are listed under " Actual".
N GENERIC ISSUE MANAGEMENT CONTROL SYSTEM AB8REVIATIONS H - High -
N1 - Note 1 N2 - Note 2 i M - Medium i D - Drop
, R - Resolved NR - Nearly Resolved (Note 1 and Note 2s) j LI - Licensing Issue (Non-safety) j RI - Regulatory Impact Issue
] S() - Subsumed in another Issue (issue #)
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Action Level - Degree of management attention needed to process generic issues in accondance with established schedules I L1 - No management action is necessary
! L2 - Division Director action is necessary L3 - Director NRR action is necessary j L4 - Director EDO action is necessary LS - Commission action is necessary NRR-OP - Operating Plan
] tab - TMI Task Action Plan
- TBD - Schedule To Be Developed
, HFPP - Human Factors Program Plan j -ACA - Awaiting Commission Approval fo. Further Action -
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- Additional Milestones are Required to ~omplete Resolution of Generic Issue i
- New Generic Issues Approved This Quarter l - New Generic Issues Approved in previous f-84 Quarter
- - New Generic Issues Approved in FY-83 (from April 1,1983 through September 30,-1983) .
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j g GIMCS FIRST QUARTE'R FY-86 i,
SUMMARY
0F GENERIC ISSUES SCHEDULE SLIPPAGE i GENERIC ISSUES FOR WHICH SCHEDULE HAS SLIPPED I
Refer'to individual GIMCS sheets.
6 GENERIC ISSUES THAT HAVE A POTENTIAL FOR SCHEDULE SLIPPAGE
- Refer to individual GIMCS sheets.
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- TA8LE 1 i
Generic Safety Issues Scheduled For Resolution, New Generic Issues and Issue Resolved l FY-83 FY-84 FY-85 '
l ISSUE GIs New GIs GIs New GIs GIs New GIs
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TYPE Start + Issues - Resolved = End Start + Issues - Resolved = End Start + Issues - Resolved = End i i l USI 16 0 2 14 14 0 2 12 12 0 0 12 1 -
! HFPP 0 0 0 0 0 0 0 0 0 34 0 34 HIGH 24 2 0 26 26 1 1 26 22* 7 6 23 MEDIUM 31 2 0 33 33 4 3 34 28* 1 10 19 NEARLY 20 3 4 19 19 5 9 15 15 7 7 15
- RESOLVED 1
TOTAL 91 7 6 92 92 10 15 87 77 49 23 103 l Cummulative Totals
! FY-86 (1st Qtr.) FY-82 through FY-86 (1st Quarter) j ISSUE GIs New GIs ISSUE GIs New GIs
- TYPE Start + Issues - Resolved = End TYPE Start + Issues = Totals - Resolved = Totals
] USI 12 0 1 11 USI 16 0 16 5 11 I
i HFPP 34 0 0 34 HFPP 0 34 34 0 34
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i HIGH 23 0 0 23 HIGH 20* 10 30 7 23 NEDIUN 19 0 0 19 MEDIUM
- 25* 7 32 13 19 i
l NEARLY 15 0 1 14 NEARLY 20 15 35 21 14
! RESOLVED RESOLVED I TOTALS 103 0 2 101 TOTALS 81 66 147 46 101
, *(See Table 2 Note) 1
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TABLE 2 NUMBER OF GENERIC SAFETY ISSUES RESOLVED AND SCHEDULED FOR RESOLUTION First Quarter FY-86 Issues Scheduled Issues Resolved For Resolution FY-86 Quarters ISSUE Cumulative TYPE FY-83 FY-84 FY-85 1st 2nd 3rd' 4th Total FY-87 FY-88 TBD Total USI 2 2 0 1 4 1 1 7 4 0 1 16 HFPP 0 0 0 0 1 1 0 2 4 0 28 34 HIGH 0 1 6 0 4 1 3 8 ) 9 1 32*
MEDIUM 0 3 10 0 1 1 1 3 5 6 3 30*
NEARLY 4 9 7 1 2 1 1 5 3 1 6 35 RESOLVED (NR)
Total 6 15 23 2 12 5 6 , 25 23 16 39 147 Number of New Generic Issues Approved this Quarter, approved in previous FY Quarter and approved in previous years is shown on Table 1 and 5.
- 0ne medium generic issue, four high priority, and five medium priority TMI issues have been superseded by nine high priority subtask issues in HF-01 (refer to table 48 for TMI issue' ~ perseded an<~ '3 for HF-01 subtask issues).
cL As of First Quarter FY-86
O C O TABLE 3 GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Type of Date Approved Date Number Title Priority Resolution for Resolution Resolved GENERIC SAFETY ISSUES RESOLVED FY-83 A-11 Reactor Vessel Materials USI GL 82-26 01/79 10/82 Toughness A-16 Steam Effects on BWR Core Spray NR MPA-012 NRR-OP FY83 03/29/83 Distribution A-39 Determination of Safety USI SRP Revision 01/79 10/82 Relief Valve (SRV) Pool Dynamic Loads and Temperature .
Limits for BWR Containment B-53 Load Break Switch NR SRP Revision NRR-OP FY83 07/28/83 II.E.5.1 (B&W) Design Evaluation NR No NRR-OP FY83 03/21/83 Requirement IV.C.1 ExteM Lessons Learned From NR No NRR-OP FY83 04/15/83 TMI to Other NRC Programs Requirement 4_
GENERIC SAFETY ISSUES RESOLVED FY-84 12 BWR Jec Pump Integrity Medium No NRR-OP FY83 09/25/84 Requirement '
20 Effects c. Electromagnetic NR NUREG/ NRR-OP FY83 11/15/83 Pulse c.i Nuclear Plant Systems CR-3069 40 Safety Concerns Associated NR MPA-865 07/18/83 12/27/83 With Breaks in the BWR Scram System As of First Quarter FY-86
O O O Table 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED SY FISCAL YEAR Issue Type of Date Approved Date Number Title Priority Resolution for Resolution Resolved 45 Inoperability of Instruments NR SRP Revision 09/08/83 03/23/84 Due to Extreme Cold Weather.
50 Reactor Vessel Level NR MPA-F26 07/28/83 09/06/84 Instrumentation in BWRs 69 Make-Up Nozzle Cracking in NR MPA- 12/06/83 09/27/84 B&W Plants A-1 Water Hanmer USI SRP Revision 01/79 03/15/84 A-12 Steam Generator and Reactor USI SRP Revision 01/79 10/83 Coolant Pump Supports B-10 Behavior of BWR Mark III High SRP Revision NRR-OP FY83 09/10/84 Containments B-26 Structural Integrity of Medium No NRR-OP FY83 09/27/84 Containment Penetrations Requirement B-60 Loose Parts Monitoring NR GL NRR-OP FY83 09/25/84 Systems (LPMS)
I.A.1.4 Long-Ters Upgrading of NR New Rule NRR-OP FY83 01/01/84 Operating Personnel II.A.1 Siting Policy Reformulation Medium No NRR-OP FY83 09/20/84 ,
Requirement II.E.5.2 (B&W) Reactor Transient NR NUREG-0667 NRR-OP FY83 09/28/84 Response Task Force III.D.2.5 Offsite Dose Calculation Manual NR NUREG/ NRR-OP FY83 01/17/84 CR-3332 As of First Quarter FY-86 I
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c O O Table 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Type of Date Approved Date C Number Title Priority Resciution for Resolution Resolved GENERIC SAFETY ISSUES RESOLVED FY-85 22 Inadvertent Boron Dilution NR GL 85-05 11/05/82 10/15/84 Events A-41 Long Tern Seismic Program Medium No NRR-OP FY83 10/10/84 Requirement B-19 Thermal-Hydraulic Stability NR GL 01/03/85 05/21/85 B-54 Ice Condenser Containments Medium NUREG/ NRR-OP FY83 10/22/84 CR-4001 8-58 Passive Mechanical Failures Medium No NRR-OP FY83 07/09/85 Requirement C-11 Assessment of Failure and Medium No NRR-OP FY83 07/09/85 Reliability of Pumps and Requirement Valves I.A.2.2 Training and Qualifications High Policy NRR-OP FY83 06/24/85 of Operating Personnel Statement No Requirement I.A.2.6(4) Operator Workshops Medium No NRR-OP FY83 09/25/85 ,
Requirement .
I.A.2.7 Accreditation of Training Medium Policy NRR-OP FY83 06/24/85
- Institutions Statement No l Requirement As of First Quarter FY-86 l - - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _
Table 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Type of Date Approved Date Number Title Priority Resolution for Resolution Resolved I.A.3.4 Licensing of Additional Medium Policy MRR-OP FY83 02/12/85 Operations Personnel Statement No Requirement I.G.2 Scope of Test Program Medium No NRR-OP FY83 10/05/84 Requirement II.B.6 Risk Reduction For Operating High No NRR-OP FY83 09/25/85 Reactoss at Sites With High Requirement Populatica Densities II.B.8 Rulemaking Proceedings on - - - -
Degraded Cora Accidents (a) Hydrogen Rule High Rule NRR-OP FY83 07/19/85 (b) Severe Accidents High Policy NRR-OP FY83 08/12/85 Statement II.C.1 Interin Reliability Evaluation High No NRR-OP FY83 07/09/85 Program Requirement II.C.2 Continuation of Intrim High No NRR-OP FY83 09/25/85 Reliability Evaluation Program Requirement II.E.2.2 Research on Small Break LOCAs Medium No NRR-OP FY83 07/25/85 and Anomalous Transients Requirement ,
III.A.I.3(2) Maintain Supplies of NR Policy NRR-OP FY83 08/15/85 Thyroid-Blocking Agent Statement For Public I
! III.A.3.4 Nuclear Data Link Medium No NRR-OP FY83 06/26/85 j Requirement As of First Quarter FY-86 i
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Table 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Type of Date Approved Date Number Title Priority Resolution for Resolution Resolved III.D.2.3(1) Develop Procedures to NR ESRP NRR-OP FY83 08/28/85 Discriminate Between Sites / Revision Plants 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 III.D.2.3(4) Prepare a Summary Assessment NR ESRP NRR-OP FY83 08/28/85 Revision IV.E.5 Assess Currently Operating High No NRR-OP FY83 09/25/85 Plants Requirement GENERIC SAFETY ISSUES RESOLVED 1st Quarter FY-86 14 PWR Pipe Cracks NR No NRR-OP FY83 10/04/85 Requirements A-43 Containment Energy USI SRP 01/79 10/85 i Sump Performance Revision l
I As of First Quarter FY-86 l
Table 4 Generic Safety Issues Scheduled For Resolution by Fiscal Year Scheduled For Resolution 2nd Qtr. FY-86 m+
3 I.A.3.3 I . F.1 66 I.A.4.2(1) III.D.3.1 8-55 Scheduled For Resolution FY-86 (Next two Quarters) 23 79 121 HFPP-4.2 36 86 A-30 HFPP-4.4 65 II. F. 5 >
Scheduled For Resolution FY-87 29 101 C-8 I.8.1.1(6) 61 103 HFPP-3.1 I.B.I.1(7) 70 B-6 HFPP-3.2 II.B.5(3) 75 8-56 HFPP-3.3 II.E.4.3 93 HFPP-6.3 II.J.4.1 Scheduled For Resolution FY-88 and FY-89 51 94 B-5 II.B.5(2) k_,/
68 99 B-61 II.C.4 s 77 105 I.D.5(3) II.E.6.1 82 A-29 II.B.5(1) II.H.2 Scheduled For Resolution To Be Determined 48 119 HFPP-2.1 HFPP-4.5 49 B-64 HFPP-2.2 HFPP-5.1 67 I.D.3 HFPP-2.3 HFPP-5.2 83 HFPP-1.1 HFPP-3.4 HFPP-5.3 84 HFPP-1.2 HFPP-3.5 HFPP-5.4 87 HFPP-1.3 HFPP-4.1 HFPP-6.1 91 HFPP-1.4 HFPP-4.3 HFPP-6.2 MSPP-I.1 MSPP-I.3 MSPP-I.5 MSPP-I.8 MSPP-1,2 MSPP-I.4 MSPP-I.6 MSPP-I.9 MSPP-I.7 MSPP-Phase II~
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O O O Table 4A NRR GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION Lead Date Resolution Current Issue Division / Approved for Date as of Resolution humber Title Branch Priority Resolution June FY-85 Date 14 PWR Pipe Cracks DE/MTEB NR NRR-OP 09/85 Complete 23 Reactor Coolant Pump Seal Failures DST /GIB H NRR-OP 07/86 07/86 29 Bolting Degradation or Failures in DE/MTEB H Nf!R-OP. 05/86 01/87 Nuclear Power Plants 36 Less of Service Water (Calvert DSI/ASB NR 02/15/84 05/86 06/86 Ciiffs Unit 1)
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48 LCO for Class IE Vital Instrument DSI/ICSB NR 10/25/83 02/87 TBD Buses in Operating Reactors 49 Interlocks and LCOs for Class IE DSI/PSB M 07/31/84 09/88 TBD Tie Breakers 51 Proposed Requirements for Improving DSI/ASB M 06/03/83 05/88 05/88 Reliability of Open Cycle Service Water Systems 61 SRV Discharge Line Break Inside The DSI/CSB M 11/30/83 03/87 06/87 Wetwell Airspace of BWR Mark I &
Mark II Containments 65 Component Cooling Water System DST /GIB H 07/28/83 07/86 07/86 Failur.
66 Steam Generator Requirements DL/0RAB NR 11/16/83 11/85 02/86 67 Steam Generator Staff Actions DE/MTEB M TBD TBD TBD 68 Loss of AFWS Due to AFW Steam HELB DSI/ASB H 04/24/84 10/87 10/87 As of First Quarter FY-86
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O O Table 4A (continued)
Lead Date Resolution Current
- Issue '~
Division / -
Approved for Date as of Resolution Number Title Branch Priority Resolution June FY-85 Date 70 PORV and Block Valve Reliability DSI/RSB M 05/14/84 02/87 08/87
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77 Flooding of Safety Equipment DSI/ASB H 09/08/83 08/86 10/87 Compartments by Back-Flow Through Floor Drains 79 Unanalyzed Reactor Vessel Thermal DE/ME8 M 07/25/83 09/86 09/86 Stress During Natural Convection i Cooldown 1
82 Beyond Design Bases Accidents in DSI/AEB M 12/07/83 09/87 11/87 l
Spent Fuel Pools 83 Control Room Habitability (CRil) DSI/MTEB NR 08/83 TBD TBD 84 CE PORVs DSI/RSB NR 02/27/85 TBD TBD 86 Long Range Plan for Dealing With DE/MTE8 NR 10/01/84 04/86 07/86
. Stress Corrosion Cracking in BWR i Piping i
j 87 Failure of HPCI Steam Line Without DSI/RSB H 09/26/85 TBD TBD j
Isolation i 91 Main Crankshaft Failure In DL/TF NR 07/08/85 None TBD Transamerica DeLaval 93 Steam Binding of Auxiliary DSI/ASB H 10/19/84 06/87 09/87 -
Feedwater Pumps Additional Low-Temperature-94 DSI/RS8 H 07/23/85 None 11/87 Overpressure Protection For Light Water Reactors
, 99 RCS/RHR Suction Line Interlocks DSI/RSB H 08/13/85 None 10/87 on PWRs As of First Quarter FY-86
O O O Table 4A (continued)
Lead Date Resolution Current Issue Division / Approved for Date as of Resolution Number Title Branch Priority Resolution June FY-85 Date 101 BWR Water Level Redundancy DSI/RSB H 05/06/85 09/86 02/87 103 Design For Probable Maximum DE/HGE8 NR 09/04/85 TBD 12/86 Precipitation 105 Interfacing System LOCA at BWRs DSI/RSB H 06/11/85 TBD 04/88 A-3, 4 Steam Generator Tube Integrity DL/0RAB USI 01/79 12/85 02/86 and 5 A-17 Systems Interaction DST /GIB USI 01/79 08/86 08/86 I A-29 Nuclear Power Plant Design for the DSI/ASB M NRR-OP 05/87 04/88 l
Reduction of Vulnerability to l Industrial Sabotage
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] A-30 Adequacy of Safety Related DC Power DSI/PSB H NRR-OP 01/86 05/86
- Supplies
- A-40 Seismic Design Criteria DE/SGEB USI 01/79 06/86 TBD A-43 Containment Emergency Sump DST /GIB USI 01/79 09/85 Complete Performance A-44 Station Blackout DST /GIB USI 01/79 04/86 03/87 A-45 Shutdown Decay Heat Removal DST /GIB USI 02/81 03/87 03/87 ,
Requirements * '
A-46 Seismic Qualification of Equipment DST /GIB USI 02/81 12/85 04/86 in Operating Plants A-47 Safety Implications of Control DST /GIB USI 02/81 12/86 12/86 Systems As of First Quarter FY-86 I
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V Table 4A (continued)
Lead Date Resolution Current Issue Division / Approved for Date as of Resolution Number Title Branch Priority Resolution June FY-85 Date A-48 Hydrogen Control Measures and DST /GIB USI 02/81 10/86 09/87 Effects of Hydrogen Burns on Safety
- Equipment A-49 Pressurized Thermal Shock DST /GIB USI 12/81 11/85 03/86 B-5 Ductility of Two Way Slabs and DE/SGEB M NRR-OP 09/87 03/88 Shells and Buckling Behavior of Steel Containments B-6 Lesis, Load Combinations, Stress DE/MFA H NRR-OP 09/87 01/87 Limits 8-17 Criteria For Safety Related DHFS/PSRB M 03/22/82 Being resolved by HF-01 Operator Actions Issue HFPP-4.3 B-55 Improve Reliability of Target Rock DE/MEB M NRR-OP 12/85 12/85 Safety Relief Valves B-56 Diesel Reliability DSI/PSB H NRR-OP 05/86 01/87 B-61 Allowable ECCS Equipment Outage DST /RRAB M NRR-OP 09/87 05/88 Periods B-64 Decommissioning of Nuclear Reactors DE/CMEB NR NRR-OP 06/87 TBD C-8 Main Steam Line Isolation Valve DSI/ASB H NRR-OP. 12/86 03/87 Leakage Control Systems
- l As of First Quarter FY-86
l Table 4B NRR TMI GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION
! Lead' Date Resolution Current
! Issue Division / Approved for Date as of Resolution Number Title Branch Priority Resolution June FY-85 Date j I.A.'2.6 Long-Tern Upgrading of Training DHFS/LQB H Being resolved by HF-01, issue HFPP-1.2 (1) and Quali.fications - Revise Regulatory Guide 1.8 1.A.4.2 Research on Training Simulators DHFS/0LB H NRR-OP 08/85 03/B6 (1)
- I.A.4.2 Review Simulators for Conformance DHFS/0LB H Being resolved by HF"'" issue HFPP-3.3
- (4)
I . B.1.1 Organization and Management of - - - - -
Long Tern Improvements
! I . B .1.1 Prepare Draft Criteria DHFS/LQB M Being resolved by HF-01, issues HFPP-6.1 (1) and 6.3 I . B.1.1 Prepare Commission Paper DHFS/LQB M Being resolved by HF-01, issues HFPP-6.1 (2) and 6.3 t
j I . B.1.1 Issue Requirements for the DHFS/LQB M Being resolved by HF-01, issues HFPP-6.1 (3) Upgrading Management and and 6.3 Technical Resources I . B. I.1 Review Responses to Determine DHFS/LQB M Being resolved by HF-01, issues HFPP-6.1 (4) Acceptability and 6.3 ,
I . C. 9 Long-Term Program Plan for Upgrad- DHFS/PSRB M Being resolved by HF-01, issues HFPP-4.2 ing of Procedures and 4.4 and HF-02 1
As of First Quarter FY-86
O Table 4B (continued) i Lead Date Resolution Current Issue Division / Approved for Date as of Resolution Number Title Branch Priority Resolution June FY-85 Date I.D.4 Control Room Design Standard DHFS/HFEB H Being resolved by HF-01, issue HFPP-5.3 1.D.5(5) Disturbance Analysis Systems DHFS/HFEB H Being resolved by HF-01, issue HFPP-5.4 '
II.E.4.3 (Containment) Integrity Check DSI/CSB H NRR-OP 04/87 10/86 II.E.6.1 Test Adequacy Study DE/MEB M NRR-OP 05/88 05/88 III.D.3.1 Radiation Protection Plans DSI/RAB H NRR-0P 09/85 12/85 1
As of First Quarter FY-86
I Table 4C
[ NON-NRR TMI AND GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION 4
Lead Date Resolution Current ;
i Issue Division / Approved for Date as of Number Resolution j
! Title Branch Priority Resolution June FY-85 -Date 1 l l
{ 3 Set Point Drift in RES/EEICB NR NRR-OP 12/85 07/86 i Instrumentation
! 75 Generic Implications of ATWS IE/QAVT/QA8 NR 10/19/83 02/86 07/87 !
! Events at the Salen Nuclear '
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! 119 Piping Review Committee RES/DRA0 NR 09/10/85 T80 TBD Recommendations ,
121 Hydrogen Control for Large Dry RES/DRA0/RAMR8 H 09/26/85 T80 09/86 .
I j Containment
- I.A.3.3 Requirement for Operation RES/DRA0/HFSB H NRR-OP 09/85 03/86 Fitness I . B .1.1 Prepare Revisions to Regulatory IE/QAVT/QA8 M NRR-OP 02/86 07/87 *
(6) Guides 1.33 and 1.8 ,
I . B. I.1 Issue Regulatory Guides 1.33 and IE/QAVT/QA8 M NRR-OP 02/86 07/87 j (7) 1. 8 -
i
) I.D.3 Safety System Status Monitoring 'RES/DET/EEIC8 M NRR-OP 12/87 TBD l I.D.5 On-Line Reactor Surveillance RES/DET/EEIC8 NR NRR-OP 09/88 09/88 i
{ (3) Systems i I . F.1 Expand QA List IE/QAVT/QA8 H- NRR-OP 08/85 ACA !
II.B.5 Behavior of Severely Damaged RES/DAE/FSRB H NRR-OP 12/87 12/87 (1) Fuel t i
II.B.5 Behavior of Core Melt RES/DAE/FSR8 H NRR-OP 12/87 12/87 (2) I As of First Quarter FY-86
O v Table 4C (continued)
NON-NRR TMI AND GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION Lead Date Resolution Current Issue Division / Approved for Date as of Resolution Number Title B. ;.ich Priority Resolution June FY-85 Date II.B.5 Effect of Hydrogen Burning and RES/DAE/CSRB M NRR-OP 07/87 07/87 (3) Explosions on Containment Structure II.C.4 Reliability Engineering RES/DRA0/RRB H NRR-OP 12/87 12/87 II.F.5 Classification of Instrumenta- RES/DET/EEIC8 M NRR-OP 01/86 05/86 tion, Control, and Electrical Equipment II.H.2 Obtain. Technical Data on the RES/DAE/FSR8 H NRR-OP 12/86 12/87 Conditions Inside the THI-2 Containment Structure II.J.4.1 Revise Deficiency Report IE/DEPER/EA8 NR NRR-OP 07/86 11/86 Requirements As of First Quarte FY-86
)
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, Table 40 HUMAN FACTORS GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION Lead Date Resolution Current Issue Division / Approved for Date as of Resolution Ni:mber Title Branch Priority Resolution June FY-85 Date
. HF-01 HUMAN FACTORS PROGRAM PLAN (HFPP)
HFPP Subtask Numbers j 1.1 Policy Statement on Engineering DHFS/LQB H 10/01/84 TBD TBD j Expertise on Shift and Evaluate j Effectiveness of Policy Statement 1 1.2 Revise and Evaluate Changes to DHFS/LQB H 10/01/84 08/85 TBD 1
Regulatory Guide 1.8 1.3 Develop a Means to Evaluate DHFS/LQB H 10/01/84 TBD TBD Acceptability of NPP Personnel Qualifications Program 1.4 Review and Evaluate Industry DHFS/LQB H 10/01/84 T8D TBD i Programs 2.1 Evaluate Industry Training DHFS/LQ8 H 10/01/84 TBD TBD 2.2 Evaluate INPO Accreditation DHFS/LQ8 H 10/01/84 TBD TBD Program 2.3 Revise Standard Review Plan DHFS/LQ8 H 10/01/84 TBD TBD Section 13.2.3 3.1 Develop Job Knowledge Catalogue DHFS/0LB H 10/01/84 TBD 10/86 3.2 Develop Licensing Examinations DHFS/0LB H 10/01/84 TBD 10/86 Handbook 3.3 Develop Criteria for NPP DHFS/0LB H 10/01/84 02/87 03/87 Simulators As of First Quarter FY-86
\ T
)
i 4
Table 40 (Continued)
Lead Date Resolution Current
- Issue Division / Approved for Date as of Resolution l
Number Title Branch Priority Resolution June FY-85 Date i
! HFPP Subtask Numbers (Continued)
- 3.4 Training Requirements Package DHFS/0LB H 10/01/84 TBD TBD l (Revise 10 CFR 55 and RGs 1.149 and 1.8) 3.5 Develop Computerized Exam System DHFS/0LB H 10/01/84 TBD 120 4.1 Inspection Module for upgrading DHFS/PSRB - H 10/01/84 TBD TBD procedures
- 4.2 E0P Effectiveness Evaluation DHFS/PSRB H 10/01/84 02/86 06/86 4.3 Criteria for Safety-Related DHFS/PSRB H 10/01/84 TBD TBD Operator Actions (GI #B-17) l 4.4 Guidelines For Upgrading Other DHFS/PSRB H 10/01/84 12/85 01/86 Procedures 4.5 Applications of Artificial DHFS/PSRB H 10/01/84 TBD TBD Intelligence 5.1 Local Control Stations DHFS/0LB H 10/01/84 TBD TBD 5.2 Annunciators DHFS/0LB H 10/01/84 TBD TBD 5.3 Evaluate Operational Aid Systems DHFS/0LB H' 10/01/84 TBD TBD 5.4 Computers and Computers Displays DHFS/0LB H 10/01/84 TBD TBD 6.1 Development of Regulatory Position DHFS/LQB H 10/01/84 04/86+ 04/86+
on Management and Organization
O Table 40 (Continued)
Lead Date Resolution Current Issue Division / Approved for Date as of Resolution Number Title Branch Priority Resolution June FY-85 Date HFPP Subtask Numbers (Continued) 6.3 Revise Standard Review Plan DHFS/LQB H 1001/84 11/86 11/86 Section 13.1 HF-02 MAINTENANCE AND SURVEILLANCE PROGRAM PLAN (MSPP)
MSPP Subtask Numbers (Phase I)
I .1 Survey Current Maintenance DHFS/PSR8 H 03/06/85 TBD TBD Practices I.2 Maintenance Performance Indicators DHFS/PSRB H 03/06/85 TBD TBD I.3 Honitor Industry Activities DHFS/PSRB H 03/06/85 TBD TBD I.4 Participate In Standards Groups DHFS/PSRB H 03/06/85 TBD TBD I.5 Maintenance and Surveillance DHFS/PSRB H 03/06/85 TBD TBD Program Integration I.6 Analysis of Japanese /U.S. NPP DHFS/PSR8 H 03/06/85 TBD TBD Maintenance Programs I.7 Maintenance Personnel DNFS/PSRB H 03/06/85 TBD TBD Qualifications I.8 Human Factors In In-Service DHFS/PSRB H 03/06/85 TBD TBD ,
Inspections I.9 Human Error in Events Involving DHFS/PSRB H 03/06/85 TBD TBD Wrong Unit Wrong Train (GI #101)
MSPP Subtask Numbers (Phase II) 11.0 Phase II Tasks To Be Determined DHFS/PSRB H 03/06/85 TBD TBD After Resolution of Phase I As of First Quarter FY-86
O O O TABLE 5 NUMBER OF GENERIC ISSUES PRIORITIZED IN FY-83, FY-84, FY-85 and 1st QTR. FY-86 FY-86 1st Quarter Cumulative Issue Type FY-83 FY-84 FY-85 1st 2nd 3rd 4th Total Total l Issues Identified 56 19 54 2 - - - -
131 1
To Be Prioritized
, Issues Identified 19 2 0 0 - - - -
21 j To Be Reprioritized Total 75 21 54 2 - - - -
152
) New Issues (Entered into GIMCS)
High 2 1 7 0 - - - -
10 Medium 2 4 1 0 - - - -
7 Nearly Resolved 3 5 6 0 - - - -
14 Human Factor 0 0 34 0 - - - -
34 Issues i
Subtotal 7 10 48 O - - - -
65 l Resolved *** 4 0 1 2 - - - -
7 Low 1 4 0 0 - - - -
5 Drop 1 4 4 1 - - - -
10 i
Regulatory Impact /LI O 0 3 1 - - - -
4 Subsumed 8 2 3 0 - - - -
13 Total Issues 21 20 59 4 - - - -
104 Prioritized Remaining Issues 54 1 -5 -2 - - - -
48 To Be Prioritized
- or Reprioritized As of First Quarter FY-86 i
^ m TABLE 6 GENERIC ISSUES PRIORITIZED AS OF FIRST QUARTER FY-86 Action Item / Identification Date Current Issue No. Title Date Priorit' zed Priority Prioritized in 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) l Loss of Integrated Control System Power
- 39. Potential for Unacceptable Interaction Between 09/82 07/82 S(25)
- the CRD System and Non-Essential Control Air System
- 41. BWR Scram Discharge Volume Systems 09/82 07/83 R
- 42. Combination Primary / Secondary System LOCA 09/82 04/83 S(18)
- 45. Inoperability of Instrumentation Due to Extreme 09/82 09/83 NR Cold Weather
- 46. Loss of 125 Volt DC Bus 09/82 02/83 S(76)
- 47. Loss of Off-Site Power 09/82 04/83 R
- 50. Reactor Vessel Level Instrumentation in BWRs 09/82 07/83 NR 4
- 51. Proposed Requirements for Improving the j 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. Abnormal Transient Operating Guidelines as 09/82 02/83 S(A-45/I.D.1)
Applied to a Steam Generator Overfill Event
- 58. Inadvertent Containment Flooding 09/82 08/83 DROP
- 64. Identification of Protection System Instrument 10/82 02/83 R Sensing Lines ,
- 65. Probability of Core-Melt Due to Component Cool- 02/83 07/83 HIGH 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 0-1 Advisability of a Seismic Scram 09/82 06/83 LOW IV.E.2 Plan for Early Resolution of Safety Issues 09/82 06/83 R As of First Quarter FY-86
N
) N J
TABLE 6 (CONT.)
GENERIC ISSUES PRIORITIZED AS OF FIRST QUARTER FY-86 Action Item / Identification Date Current Issue No. Title Date Prioritized Priority Prioritized in FY-84
- 34. RCS Leak 09/82 02/84 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 S(43)
- 48. LCO for Class IE Vital Instrument Buses in 09/82 10/83 NR Operating Reactors
- 49. Interlocks and LOCs for Redundant Class IE 09/82 07/84 MFDIUM 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 ATWS Events at the Sales 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 8-65 Iodine Spiking 09/82 06/84 DROP As of First Quarter FY-86
N J
l TABLE 6 (CONT.)
GENERIC ISSUES PRIORITIZED AS OF FIRST QUARTER FY-86 i
~
Action Item / Identification Date Current Issue No. Title Date Prioritized Priority Prioritized in FY-85
- 37. Steam Generator Overfill and Combined Primary 09/82 05/85 S(USI-A47) and Secondary Blowdown
- 54. Valve Operator-Related Events Occurring 09/82 06/85 S(II.E.6.1)
During 1978, 1979, and 1980 1
- 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[S(TSIP)]
Shutdown
. 67. Steam Generator Staff Actions 06/83 03/85 MEDIUM i
- 81. Potential Safety Problems Associated With Locked 11/83 10/84 DROP Doors and Barriers in Nuclear Power Plants
- 83. Control Room Habitability 11/83 NR
- 85. Reliability of Vacuum Breakers Connected 11/83 07/85 DROP to Steam Discharge Lines Inside BWR Containments
- 86. NRC Pipe Cracking Review Group Study 12/83 10/84 NR I
- 87. Failure of HPCI Steam Line Without Isolation 01/84 09/85 HIGH
- 91. Transamerica Delaval Emergency Diesel 03/84 07/85 NR i Generator Main Crankshaft Failure
! 93. Steam Binding of Auxiliary Feedwater Pumps 07/84 10/84 HIGH
- 94. Additional Low-Temperature-Overpressure 08/84 07/85 HIGH Protection For Light Water Reactors
- 98. CRD Accumulator Check Valve Leakage 09/84 02/85 DROP
- 99. RCS/RHR Suction Line Interlocks on PWRs 09/84 08/85 HIGH 101. 8WR Water Level Redundancy 09/84 05/85 HIGH ,
102. Human Error in Events Involving Wrong Unit or 09/84 02/85 S(HF-02)
Wrong Train 103. Design For Probable Maximum Precipitation 10/84 09/85 NR 105. Interfacing System LOCA at BWRs 10/84 06/85 HIGH 108. BWR Suppression Pool Temperature Limits 12/84 02/85 RI(LOW) 119. Piping Review Committee Recommendations 07/85 09/85 RI(NR) 121. ' Hydrogen Control For Large Dry Containments 08/85 09/85 HIGH As of First Quarter FY-86
O O O TABLE 6 (CONT.)
GENERIC ISSUES PRIORITIZED AS OF FIRST QUARTER FY-86 Action Item / Identification Date Current Issue No. Title Date Prioritized Priority Prioritized in FY-85 B-19 Thermal-Hydraulic Stability 02/83 01/85 NR B-50 Post Operating Basis Earthquake Inspection 02/83 04/85 RI (LOW)
B-59 N-1 Loop Operation in BWRs and PWRs 02/83 06/85 R HF-01 Human Factor Program Plan (HFPP twenty four 08/83 10/84 HIGH subtask elements)
HF-02 Maintenance and Surveillance Program Plan 04/84 03/85 HIGH (MSPP ten subtasks elements).
Prioritized in FY-86
- 30. Potential Generator Missiles - Generator Rotor 09/82 10/85 DROP Retaining Rings
- 97. PWR Reactor Cavity Uncontrolled Exposure 09/84 10/85 R 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 As of First Quarter FY-86
O O O TABLE 7 GENERIC ISSUES TO BE PRIORITIZED Action Item / Identification Current
- Issue No. Title Date Schedule
- 38. Potential Recirculation System Failure as a Consequence of 09/82 12/85 Injection of Containment Paint Flakes or Other Fine Debris
- 57. Effects of Fire Protection System Actuation on Safety-Related 09/82 11/85 Equipment
- 62. Reactor Systems Bolting Applications 10/82 12/85
- 63. Use of Equipment Not Classified as Essential to Safety in 10/82 01/86 BWR 1ransient Analysis
- 71. Failure of Resin Demineralizer Systems and Their Effects on 06/83 11/85 Nuclear Power Plant Safety
- 72. Control Rod Drive Guide Tube Support Pin Failures 06/83 11/85
- 73. Detached Thermal Sleeves 06/83 11/85
- 74. Reactor Coolant Activity Limics for Operating Reactors 06/83 11/85
- 76. Instrumentation and Control Power Interactions 06/83 11/85
- 78. Monitoring of Fatigue Transient Limits for Reactor Coolant 06/83 11/85 System
- 88. Earthquake and Emergency Planning 01/84 12/85
- 89. Stiff Pipe Clamps 02/84 12/85
- 95. Loss of Effective Volume for Containment Recirculation 08/84 12/85 Spray
- 96. RHR Suction Valve Testing 04/84 11/85 100. OTSG Level 09/84 11/85 104. Reduction of Boron. Dilution Requirements 10/84 12/85 106. Piping and Use of Highly Combustible Gases in Vital Areas 10/84 11/85 107. Generic Implications of Main Transformer Failures 11/84 11/85 109. Reactor Vessel Closure Failure 12/84 11/85 '
110. Equipment Protection Devices on Engineered Safety Features 12/84 12/85 As of First Quarter FY-86
O .
av TABLE 7 (CONT.)
GENERIC ISSUES TO BE PRIORITIZED Action Item / Identification Current
- Issue No. Title Date Schedule 113. Dynamic Qualification Testing of Large Bore Hydraulic Snubbers 03/85 12/85 114. Seismic-Induced Relay Chatter 03/85 12/85 115. Reliability of Westinghouse Solid State Protection System 04/85 01/86 116. Accident Management 04/85 02/86 117. Allowable Outages Times For Diverse Simultaneous Equipment Outages 05/85 02/86 118. Tendon Anchorage Failure 07/85 03/86 120. On-Line Testability of Protection Systems 08/85 04/86 122. Davis-Besse Loss of All Feedwater Event 08/85 10/85 123. Deficiencies in the Regulations Governing DBA and Single Failure 11/85 Criterion Suggested by the Davis-Besse Incident of June 9,1985 124. Auxiliary Feedwater System Reliability 12/85
- Prioritization schedule for generic issues are being reevaluated based on the reorganization of NRR and available resources.
l l
As of First quarter FY-86 l
( .
l O O O TABLE 8 GENERIC ISSUES TO BE REPRIORITIZED l Action Item / Previous Identification Current
- i Issue No. Title . Priority Date Schedule
- 2. Failure of Protective Services on Essential Equipment M 05/83 03/86
- 21. Vibration Qualification of Equipment S (A-46) 03/83 03/86 l 24. Automatic Emergency Core Cooling System Switch to NR 03/83 03/86 i Recirculation A-19 Digital Computer Protection System LI '02/83 12/85 B-22 LWR Fuel LI 02/83 12/85 B-29 Effectiveness of Ultimate Heat Sinks LI 02/83 11/85 B-31 Das Failure Model RI 02/83 12/85
. B-32 Ice Effects on Safety Related Water Supplies LI 02/83 12/85 .
B-55 Ig roved Reliability of Target Rock Safety Relief Valves M 02/84 12/85 C-4 ftatistical Methods for ECCs Analysis RI 02/83 12/85 C-5 Decay Heat Update RI 02/83 12/85 C-6 LOCA Heat Sources RI 02/83 12/85 C-9 RHR Heat Exchanger Tube Failures D 07/84 12/85 C-14 Storm Surge Modes for Coastal Sites RI 02/83 12/85 0-2 Emergency Core Cooling System Capability for Future Plants S (A-45) 06/83 11/85 III.D.1.1(2) Review Information on Provisions for Leak Detection I 12/82 10/85 111.0.1.1(3) Develop Proposed System Acceptance I 12/82 10/85
- Prioritization schedule for generic issues are being reevaluated based on the reorganization of NRR and available resources. .
As of First. Quarter FY-86
. )
~
a TABLE 9 StWetARY OF THE PRIORITIZATION OF ALL TMI ACTION PLAN ITEMS, TASK ACTION PLAN ITEMS. NEW GENERIC ISSUES. AND HUMAN FACTORS ISSUES tegend NOTES: 1 - Possible Resolution Identified for Evaluation 2 - Resolution Available 3 - Resolution Resulted in either the Establishment ,
of New Requirements or No New Requirements 4 - Issues to be Prioritized in the Future 5 - Issue that is not a Generic Safety Issue but should be Assigned Resources for Completion HIGH - High Safety Priority MEDIUM - Medium Safety Priority LOW - Low Safety Priority DROP - Issue Dropped as a Generic Issue USI - Unresolved Safety Issue I - TMI Action Plan Item with Implementation .
of Resolution Mandated by MUREG-0737 As of First Quarter FY-86 1
P
. h es
- j Revision 4 TA8tE III (Continued)
COVERED RESOLVED STAGES ACTION ITEM / ISSUE GROUP IN OTHER NOTE NOTE NOTE NOTE NOTE.
I ISSUES 1 2 3 USI MIGH MEDILM LOW DROP '4 5 I?TAL
- 1. TNI ACTION PLAN ITEMS (352)
- (a) Safety (1) Generic Safety 94 55 1 1 106 0 9 . 4 12 7 2 -
291 (b) Non-Safety ,
(1) Licensing -
0 0 4 51 - - - -
0 0 6 61
- 2. TASK ACTION PLAN ITEMS (142)
(a) Safety (1) USI - -
0 1 14 12 - - - - - -
27 (ii) Generic Safety -
18 '0 1 28 -
4 4 3 9 10 - 77 j
(111) Regulatory Impact -
0 0 0 2 - - -
1 0 0 1 4 l
I (b) Non-Safety l (1) Licensing -
0 0 0 1 - - - -
7 0 11 19 (ii) Environmental -
1 0 0 6 - - - -
6 0 2 15 j 3. NEW GENERIC ISSUES (148)
(a) Safety (i) Generic Safety -
32 5 4 15 0 12 7 5 15 39 -
134 (11) Regulatory Impact -
0 0 0 1 -- - -
1 0 0 8 10 (b) Non-Safety 0 0 0 0 - - - -
0 0 4 4 (1) Licensing -
4, HUMAN FACTORS ISSUES l *
(a) Safety
- 0 0 0 0 0 33 0 0 0 0 -
33 (i) Generic Safety 94 106 6 11 224 12 58 15 22 44 51 32 675 TOTAL:
l .
I I
E ,
l l
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM v ;
Issue Issue Action Task Number- Type Q_ vel Office /Div/Br Manager Tac No 3 Safety / Active-L1- RES/DET/EEICB Al Hintze 52400 NR Title ---------------- Set Point Drift in Instrumentation.
Work Authorization --- NRR FY-84 Operating Plan, (Appendix G).
Contract Title ------- None Contractor'Name/
FIN No. ------------ None Work Scope ----------- Provide technical assistance, as required, to RES for the revision and issuance of Regulatory Guide 1.105, Revision 2.
Affected Documents --- Revise Reg. Guide 1.105, Rev. 2 (a revision to a SRP to incor-porate Reg. Guide is not anticipated).
Status -------------- The technical resolution is identified and documented in the revision to Reg. Guide 1.105.
[D Problem / Resolution -- After CRGR review, differing staff opinions could not be d resolved. RES will request NRR help in establishing bases for RG position.
Technical Resolution -
Milestones Original Current Accual Technical input necessary to - -
11/12/82 revise Reg. Guide 1.105 was transmitted to RES.
RES to submit CRGR package for 10/83 -
08/05/83 review.
CRGR review completed and 11/83 -
10/20/83 returned to RES with comments.
ACRS review completed - -
11/19/83 RES incorporated CRGR comment - -
12/12/83 and returned for approval.
CRGR review 03/84 -
01/11/84 O
As of First Quarter FY-86
-Generic Issue #3 Milestones Original Current Actual CRGR meeting - -
03/12/85 Issue Memorandum to NRR to 08/84 04/85 05/06/85 establish basis for R.G. Position.
NRR response to Position -
07/85 06/27/85 memorandum ACRS review complete 10/84 10/85 10/85 Reg. Guide issued. 05/84 01/86 -
Issue transfer memo to NRR/ICSB -
01/86 -
ICSB Staff assessment of **
02/86 -
Reg. Guide impact on SRPs, issue close-out memo or expand schbdule O
l l
=
- 0ne month after issuance of revised Regulatory Guide 1.105, ICSB will ; lose cut issue or provide schedule for the required SRP revision.
O As of First Quarter FY-86 l
1
l
, GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No 14 Safety / Complete NRR/DE/MTEB K. Wichman 11860 NR Title ---------------- 'PWR Pipe Cracks (Feedlines of Westinghouse and CE Plants)
Work Authorization --- NRR FY-84 Operating Plan, (Appendix G).
Contract Title ------- None Contractor Name/
FIN No. ------------ None Work Scope ----------- 1. Determine the current status of PWR's regarding this~ issue:
(a) Nature of mitigating measures taken (if any).
(b) Results of inservice inspections subsequent to short-term fixes.
(c) , Plans for further. actions (if any) (possibly meet with Ow4er's Group).
- 2. As necessary, draft new SRP Section regarding augmented inservice inspections of the PWR feed-water piping in the vicinity of the~ steam generator nozzles.
- 3. Issue the SRP Section for comment.
- 4. Resolve comments and issue final SRP Section.
- 5. Establish fut:r?e inspection schedules depending on mitigating actions taken, inspection results, and specific system geometry.
Affected Documents --- Issue SRP Section.
Status --------------- NUREG-0691 was published in September 1980. An implementation plan has not been developed and may not be needed because of recent modifications to, and improved inspections of feedwater piping systems.
Therefore, the DE staff is working with DL to deter- ,_
mine the current status of PWRs regarding this matter.
We will then evaluate the need for an implementation program. That could require an SRP revision (Work Scope item 2-5).
O As of First Quarter FY-86 1
-. --_.- -. ,1 - ..._ . ... . - . - - . . . - . _ . . - . . - - -- . _ - . . - . _ - _ _ - - - . - - - _ .
Generic Issue #14 The MTEB staff has not yet been successful in accomplishing item 1 of the Work Scope. This has resulted in several months delay. MTEB had explored with OL, alternative means to obtain the current status of inspection frequencies and results and any significant operating procedures or other remedial changes made at operating W and CE facilities.
These potential means varied from informal information gathering via TIA's to the Regional Offices to formal inquires via a generic letter. Some of the Regions declined to acccm-modate our requests and alternatively, going formal (50:54f) requires OM8 clearance and CRGR review, which was deemed dif-ficult to justify in view of the relative safety significance of this issue. Nevertheless, it was recently decided by DL, IE and DE management to formally request this information via 50.54f letters and to ascertain the current structural integ-rity of feedwater piping via an IE Bulletin issued simultane-ously with the letters. This process is dependent on the results of the Regulatory Analysis being performed by LLNL.
The Regulatory Analysis should be available in mid-CY 1985.
Problem / Resolution --- The preliminary results of the regulatory analysis received from LLNL in May 1985 indicate that this issue may have little safety significance. It is anticipated that this issue can be closed out on this basis and the milestone schedule below reflects this approach.
Tcchnical Resolution -
Milestones Original Current Actual Staff review of NUREG-0691 and 06/01/83* -
06/01/83 other existing information.
Receive Regulatory Analysis -
'05/85 05/85 l from LLNL and returned for rework Final regulatory analysis -
09/85 09/85 received from LLNL.
Closeout memorandum issued -
09/85 10/04/85*
reflecting low safety significance
- Memorandum from J. Knight for H. Denton dated October 4,1985 closed out Generic Issue 14. This issue is complete.
O As of First Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM J
Issue Issue Action Task Number Type Level Office /Div/Br Manager i
_ Tac No 23 Safety / Active-L1 NRR/DE/MEB J. Jackson 49716 High Title ---------------- Reactor Coolant Pump Seal Failures.
Work Authorization --- NRR FY-84 Operating Plan,~(Appendix G).
Contract Title ------- 1) Reactor Coolant Pump Seal Integrity
- 2) Assessment of Effect of Mechanical and Maintenance-Induced Reactor Coolant Pump Seal Failures on Risk
- 3) Evaluation of the Adequacy of Current RCP. Seal Instrumen-tation and Operator Responses to Possible RCP Failures
- 4) Reactor Coolant Pump Shaft Seal Behavior During Station Blackout
- 5) Leak Rate Analysis of Westinghouse Reactor Coolant Pump Contractor Name/
FIN No. ------------ 1) Brookhaven National Laboratory / FIN No. A-3751
- 2) Brookhaven National Laboratory / FIN No. A-3771
- 3) Brookhaven National Laboratory / FIN No. A-3806
- 5) Energy Technology Engineering Center / FIN No. B-3049
\ Work Scope ----------- The task action plan for this issue has been revised to incorporate work task necessary to complete Generic Issue 65. Review PWR reactor coolant pump seal failures caused by mechanical failures and loss of seal cooling to ascertain if increased NRC requirements are necessary to minimize seal failures. Evaluate the effects of system design, materials, operation, testing, and maintenance on seal failure mechanisms. Review the reliability of seal cooling systems and identify methods to minimize the effects of loss of seal cooling. Perform a risk assessment of seal failure from maintenance and mechanical effects.
This program will determine what steps the NRC should take, if any, to reduce reactor coolant pump (RCP) seal failure ,
to an acceptable level commensurate with the potential safety consequences of seal failure. The program consists of the following major tasks.
- a. Task 1 - Determine actual seal failure mechanisms. _
l b. Task 2 - Evaluate RCP seal cooling for all modes of l operation for which seal cooling is required using the l
reliability of typical RCP seal cooling system designs.
As of First Quarter FY-86 l
l
.....-. --.--._~._..-:. -. . _ . - - .- - - - _ . - -.-
Generic Issue #23
- c. Task 3 - Review mechanical and maintenance-induced failure mechanisms.
l The Task Action Plan is currently being reviewed to assure l that ACRS comments (August 14, 1984 Itr. J. Ebersole to l W. Dircks) regarding conversion of Generic Issue 23 to an l Unresolved Safety Issue (USI) are being incorporated. I Affected Documents --- Issue NUREG- (To be Determined)
Review and Issue Standard Review Plan (SRP) ;
Section 9.2.2 (To Be Determined) ;
Revise and Issue SRP Section 9.3.4 (To Be Determined)
Issue New Regulatory Guide and SRP Section (To Be Determined)
Status --------------- Work is currently in progress on Tasks 1, 2, and 3 as follows: RSB has provided imput to Task 1 (Assemble background information on seal failures). This work includes subtasks to: (1) perform an LER search, (2) review industry experience, and (3) perform a BWR screening review. BNL has completed additional work on this task under FIN # A-3771 which will be published as NUREG/CR-4400 by 12/85.
EQB is currently working on Task 2 (subtask 2.1). EQB's task is to evaluate the effects of loss of. seal cooling.
RES is providing input through contracts with AECL and ETEC. The AECL contract work has been completed and NUREG/
CR-4077, " Reactor Ccolant Pump Shaft Seal Behavior During Station Blackout" has been issued. The ETEC contract work has been completed and NUREG/CR-4294, " Leak Rate Analysis of the Westinghouse Reactor Coolant Pump" has been issued.
Additional concerns regarding seals which were discovered through research at AECL are to be investigated through a follow-on contract at AECL. Completion date is not yet available.
EQB, under technical assistance contract (FIN # A-3751) with BNL is working on Task 2 (subtask 2.2). The purpose of this subtask is to evaluate the reliability of cooling water systems. Subtask 2.2 has been completed and BNL draft report is under staff review.
EQB, under technical assistance con'ract (FIN # A-3771) with BNL is working on Task 3 (subtask 3.1). The purpose -
of this subtask is to evaluate the effect of mechanical and maintenance induced RCP seal failures or risk.
Subtask 3.1 has been completed and NUREG/CR-4400 will be issued by 12/85.
O As of First Quarter FY-86
Generic Issue #23
[ '
\
EQB, under technical assistance contract (FIN # A-3806) with BNL is working on Task 2 (subtask 2.3) and Task 3 (subtask 3.2). The purpose of these subtasks are to evaluate the adequacy of current RCP seal and seal cooling system instrumentation to detect RCP seal degradation and failures; to evaluate the adequacy of current automatic actions and manual operator responses to prevent RCP seal LOCAs or other unacceptable events and to propose possible instrumentation changes, automatic actions or manual operator responses which could improve the current RCP seal safety procedures. Subtasks 2.3 and 3.2 should be completed by 1/31/86.
Problem / Resolution --- The staff is still waiting for Westinghouse to make the results of the French RCP seal test available and to respond to the staff concerns regarding their submittal WCAP-10541 on RCP seal performance during station blackout.
Additional concerns regarding all types of RCP seals were raised as-a result cf the AECL test program. RES is extending their test program at AECL to further investi-gate these concerns. A revised schedule will be developed for this issue. The revised milestones will incorporate the results of the French test and the AECL work to the
['s
\_
extent possible at this time.
Milestones Original Current Actual GI Action Plan issued For 04/83 -
03/31/83 Comment Action Plan Approved by 10/83 -
10/26/83 Director, OSI.
Transferred Resolution - -
06/15/84 Responsibility from OSI to OE Transferred resolution - -
05/13/85 responsibility from DE to DST /GIB Complete documentation of back- 05/85 10/17/84 ground past seal failures, including LER search, review of IT industry experience, and review of BWR screening (Task 1).
1 As of First Quarter FY-86
l l
l Generic Issue #23 1 Milestones Original Current Actual j Complete evaluation of RCP 12/84 12/85* -
seal cooling, including determining effect of loss of cooling, evaluating reli-ability of cooling systems, and reviewing RCP seal cooling instrumentation (Task 2)
Issued request for proposal - -
11/02/83 to BNL for component cooling water PRA.
Complete evaluation of mechani- 01/85 09/85 09/85 cal and maintenance induced failure mechanisms (Task 3).
Complete feasibility study to 03/85 10/85* -
identify most effective fix.
Technical resciution complete. 07/85 10/85* -
Division Director approval of 08/85 10/85* -
CRGR package. Sent for Division Director comments.
Comments incorporated. CRGR 09/85 10/85* -
package sent to Director NRR.
Director, NRR review complete. 10/85* - -
Package sent to CRGR.
CRGR review complete. 11/85* - -
ACRS review complete. 11/85* - -
E00 approval. 12/85* - -
Federal Register Notice issued 12/85* - -
for public comment.
OM8 Clearance. 04/86* - -
Incorporation of comments 04/86* - -
Z
~
Package sent to Director, NRR.
Director, NRR review complete. 05/86* - -
CRGR review complete. 06/86* - -
As of First quarter FY-86
Generth Issue #23 Milestones Original Current Actual EDO approval. 06/86* - -
FR Notice of issuance of SRP 07/86* - -
Change.
~
(Note: Tasks 1, 2 and 3 are not sequential as they will be worked on simultaneously.)
1
- Schedule will be reevaluated and adjusted based on results received from the-French Reactor RCP seal Testing.
As of First Quarter FY-86
O d GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type level Office /Div/Br Manager Tac No 29 Safety / Active-L1 NRR/DE/MTEB C. D. Sellers 52454 High Title ---------------- Bolting Degradation or Failures in Nuclear Power Plants Work Authorization --- NRR FY-84 Operating Plan (Appendix G).
Contract Title ------- Bolting Applications Requirements
- Contractor Name/
FIN No. ------------ Brookhaven National Laboratory /A-3359 and A-3782 Work Scope ----------- 1. Development of the technical bases for bolting application requirements by MTEB t.hrough its contractor at BNL.
- 2. Review licensees' responses to IEB No. 82-02, " Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary of PWR Plants."
- 3. Draft staff recommendation for proposed criteria /
guidelines to be incorporated into SRP (NUREG-0800).
b 4. Develop a proposed ir.plementation plan for management consideration.
Affected Documents --- SRP section revision.
Status --------------- IEB No. 82-02 was issued in March, 1982. 'A technical assistance contact was made to BNL to develop the technical bases for a staff proposed new criteria / guideline. Work has been ongoing since the Spring of 1982. The draft contractor report was completed by July 15, 1983 but subcontracted work to Standard Pressed Steel will not be completed until December 14, 1983.
IEB No. 82-00 information has not been compiled. However, the completion of the compilation is not required for the preparation of a staff bolting position given that some infor-mation has been obtained from license submittals. In May 1984 BNL let a subcontract with ACH Technology to assist in preparing a draft staff position. ' Background information has been provided to the contractor for use in preparation of the __
staff position paper. A draft Standard Review Plan for ,
" Reactor Coolant Pressure Boundary Bolting" has been prepared.
V As of First Quarter FY-86
Generic Issue #29 Problem / Resolution --- There was a problem of PNL not being able to meet the schedule for providing an acceptable draft Value/ Impact statement.
This has resulted in a 5 month delay in the completion date of this GI. In addition the task manager has been assigned to a number of high priority quick turnaround material failure issues which has resulted in additional schedule slippage.
Tcchnical Resolution -
Milestones Original Current Actual Issued contract to BNL. - -
03/15/83 Draft NUREG/CR report received 07/83 -
07/15/83 from contractor.
Staff review of draft h0 REG /CR 07/83 03/84 03/06/84 report.
Draft Staff Position (Revise SRP -
07/84 08/10/84 Section).
Value Impact Statement prepared. 08/83 04/85 05/85 Final CRGR package prepared for 09/83 03/86 -
Division review.
Final CRGR package forwarded 10/83 04/86 -
for NRR divisions review.
NRR Director Review completed. 12/83 05/86 -
Review Package to CRGR. 01/84 06/86 -
1 CRGR review completed. 02/84 07/86 -
EDO approval. 03/84 07/86 -
l Federal Register Notice of 03/84 08/86 -
Issuance of Proposed SRP Raised for Public Comment.
Division review of public 07/84 11/86 -
comments completed. ._
i NRR Director review completed. 08/84 12/86 -
l CRGR review completed. 08/84 12/86 -
0 l As of First Quarter FY-86
~
l l
Generic Issue #29 '
1
- l 1 i
.i .
Milestores Original Current Actual l i l
- EDO approval. 08/84 12/86 -
i Federal Register Notice of 09/84 01/87 -
Issuance of SRP.
l$
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i, 1
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As of First Quarter FY-86 t
i+=---rom,9-e-e,,em.-gg-g.g,- g m m,wmy,w,,.g-ym,-.-, -- w-wiwrw w .----see +m iw w w = = w=rv n=*---w==N=+~M-+ ~~-****==---==- -
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GENERIC ISSUE MANAGEMENT CONTROL SYSTEM )
Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No
~
36 Safety / Active-L1 NRR/DSI/ASB N. Wagner 54482 NR Title ---------------- Loss of Service Water (Calvert Cliffs Unit 1).
Work Authorization --- Memorandum to R. J. Mattson from H. R. Denton dated February 15, 1984.
NRR FY-84 Operating Plan (Appendix G).
Contract Title ------- None Contractor Name/
FIN No. ------------ None Work Scope ----------- Revise SRP Section 9.2.1, 9.2.2 to incorporate concerns of interaction between safety and nonsafety-related portions of SW and CW systems which result in inoperability of safety-related portions, including possibility of entrance of air resulting in air binding of pumps.
Affected Documents --- SRP Secti)ns 9.2.1, 9.2.2.
Status -------------- ASB wi".1 begin preparing a SRP revision package in the third quarter of FY1985. The SRP revision package was submitted to DST for their review and approval on 8/12/85.
Problem / Resolution -- None Technical Resolution - See below Milestones Original Current Actual ASB completes SRP Revision 09/84 06/85 08/85 Package.
DSI Division Director Approval. 10/84 08/85 08/12/85 SPE8 Review and Package sent to 10/84 09/85 09/20/85 CRESS for Final Typing.
SRP Revision Package Returned - -
10/03/85 ,_
(Revision Tape Missing) to DST. - - -
SRP Revision Package to_DD for -
03/86 -
Review and Approval.
Final SRP Revision Package 11/84 04/85 -
for Office Director Approval.
(O)
O l
i As of First Quarter FY-86
I If
!/
Generic Issue #36 Milestones Original Current Actual Notify CRGR of Intent to 02/85 05/86 -
Publish.
FR Notice Issues and SRP Change 03/85 06/86* -
Issue for Use.
CMemoranduri for T. Speis from R. Bernero dated September 13, 1984 revised the schedule for resolution of Generic Issue #36.
O O
As of First Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
\
~
Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No 48 Safety / Active-L1 NRR/DSI/PSB 0. Chopra 55223 NR Title ---------------- LCO for Class IE 120V AC Vital Instrument Buses in Operating Reactors.
Work Authorization --- Memorandum to D. G. Eisenhut from H. R. Denton dated October 15, 1983.
Memorandum to R. J. Mattson from T. S. Speis dated March 1, 1984, " Transfer of Lead Responsibility for Generic Issue No. 48 from DL to DSI."
NRR FY-84 Operating Plan, (Appendix G).
Contract Title ------- PWR 120V AC Vital Instrument Buses and Inverter Technical Specifications Contractor Name/
FIN No. ------------ Lawrence Livermore National Laboratory /UCID 19469 Work Scope ----------- Review LLNL Technical Evaluation Report containing the
( technical finding to the above issue. Determine if there is any need for additional work to be performed by the staff or staff contractor. Prepare package containing the resolution of the issue for CRGR review. After CRGR approval issue generic letter requesting all licensees to propose technical specifications limiting the time the 120V AC vital buses may be energized from a source other than its Class 1E DC bus and associated inverter.
Affected Documents --- Plant Technical Specifications Status --------------- RRAB.has completed its review of the LLNL report and deter-mined additional work is required to complete this study.
RRAB has requested plant specific information to perform a new analysis on this issue.
Problem / Resolution --- RRAB concluded' original analysis was inadequate. New analysis from RRAB will not be available during FY1985 and will require additional detailed plant specific information. Based on the above, the schedule for GI 48 was slipped.
Technical Resolution -
Milestones Original Current Actual Generic Issue 48 assigned to - -
10/15/83 DL by Director, NRR L
As of First Quarter FY-86
'j .
l Q )
Generic Issue #48 Milestones Original Current Actual l Generic issue lead responsibility - -
03/01/84 transfer-from DL to DSI Request to RRAB for technical 10/84 -
05/01/84 assistance to review PRA done by LLNL Complete review of LLNL report 02/85 -
10/15/84 by the RRAB RRAB requested for plant specific - -
04/11/85 information to complete new study Collect information from selected -
10/85* -
licensees on 120V AC vital instrument busses Information received from -
10/85* -
licensees
, ICSB evaluation of the licer.see -
11/85* -
information Complete revised technical 03/85 03/86* -
resolution of the issue by RRAB Technical resolution identified. 04/85 04/86* -
Prepare review package for CRGR Division Director approval of 06/85 05/86* -
CRGR package. Package to other division directors for
~
comments.
Other division comments 07/85 06/86* -
incorporated. Package sent to Director, NRR.
Director, NRR review complete. 08/85 07/86* -
Package sent to CRGR.
CRGR review complete. 09/85 09/86* -
~
EDO approval. 10/85 10/86* -
OM8 clearance. 01/86 12/86* -
O As of First Quarter FY Generic Issue #48 1
Milestones Original Current Actual Issue close-out memorandum 02/86 01/87* -
(generic letter to all operating plants)
Technical resolution complete 02/86 02/87* -
- Resolution of this issue is contingent upon receipt of plant specific information.
The means by which the information is to be obtained has not yet been determined.
A new schedule will be provided after this determination has been made and the schedule reevaluated.
i l
f k
4 C
s As of First Quarter FY-86 i
w ,,-n ,-- , - - - :--,---.,----.m.---,------e,--- , - - , - - - ,~ -,evc'w- ,r-e -w w w~, .,-wv w v'-mr , ~-~----+-*~-w*w-=.- ~'~'#'- - - '~' ~ ' ^ ' ' ' ' ^ ~ ~ ' ~ * ' " ' ' ' ' ' ' ' ' ' ' ' ' - ' ' *
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Q/
Issue Issue Action Task Number Type _ Level Office /Div/Br Manager Tac No 49 Safety / Inactive-L1 NRR/DSI/PSB P. Gill TBP Medium Title ---------------- Interlocks and LCOs for Class IE Tie Breakers.
Work Authorization --- Memorandum to Daniel Muller from Harold Denton, dated July 31, 1984.
Contract Title ------- To be determined.
Contractor Name/
FIN No. ------------ To be determined.
Work Scee ----------- Prepare generic letter to all licensees requesting electrical interconnection design information. Prepare contract proposal for evaluation and assimilation of electrical'interconntetion design information. Prepare contract proposal for determining benefit / detriment of electrical interconnection. Evaluate staff contractors finding to determine if additional work needs to be performed by staff or staff contractor. Prepare package containing resolution findings for CRGR review. Issue g generic letter, as necessary, requesting all licensees to implement technical resolution.
Technical resolution will include
- 1. Prepare a generic information request for' transmittal to all operating plants to identify extent and design of electrical interconnections between Class 1E buses at operating plants. Solicit a contract proposal for evaluation and assimilation of this design information.
- 2. Determine benefit / detriment in permitting electrical interconnections between Class IE buses by performing a comparative PRA. Prepare and solicit a contract proposal for resolution.
- 3. Identify cost / benefit for each technical resolution (hardware, procedures, etc. ). Prepare a listing of all technical resolutions and solicit a contract pro-posal to obtain cost / benefit for each resolution identified. ,-
Affected Documents --- None k
As of First Quarter FY-86
i Generic Issue #49
,.- Status --------------- Inactive during FY 84 and FY 85. Work will not begin until FY 1986.
Problem / Resolution --- None Technical Resolution -
Milestones Original Current Actual Generic information request 11/65* .- -
to DL for comment Request CRGR review and comment 12/85* - -
CRGR review complete 01/86* - -
Generic information request 02/86* - -
to DL Generic letter to all OR's from 03/86* - -
DL Request RRAB comments on 04/86 - -
centract proposal RPAB comments received 05/86 - -
Contract proposal solicited 06/86 - -
Contract proposal evaluated 09/86 - -
and accepted Generic information received 09/86 - -
from OR Draft report from contractor 01/87 - -
Request RRAB comments on draft 02/87 - -
NUREG/CR report Comments received from RRAB 04/87 - -
Staff review of draft NUREG/CR 06/87 - -
reports -
.T Technical resolution complete 08/87 - -
CRGR package to NRR Division 12/87 - -
Directors for r view e
As of First Quarter FY-86
Generic Issue #49
~
Milestones Original Current. Actual CRGR Package to NRR Director 02/88 - -
Review Package to CRGR 03/88 - -
CRGR review complete 04/88 - -
E00 approval complete 05/88 - -
OMB clearance 08/88 - -
Issue generic letter as 09/88 - -
necessary to all operating plants
- Resolution of this issue is contingent upon receipt of plant specific information from licensees. Request for this information has not been sent to licensees as of yet. A new schedule will be provided after the overall schedule has been reevaluated.
l 1:
1 As of First Quarter FY-86 i
, ..~ _ -- . ...-.._._ _-
O GENERIC ISSUE MANAGEMENT CONTROL SYSTEM V
Issue Issue Action Task Numoe. Type Level Office /Div/Br Manager Tac No 51 Safety / Active-L1 NRR/DSI/ASB N. Wagner 53338 Medium Title ---------------- Proposed Requirements for Improving Reliability of Open Cycle
-Service Water Systems Work Authorization --- Memorandum to R. J. Mattson from H. R. Denton dated June 3, 1983.
NRR FY-84 Operating Plan, (Appendix G).
Centract Title ------- Determination of Methods for Surveillance and Control of Fouling of Open Cycle Water Systems.
Contractor Name/
FIN No. ------------
Battelle-Pacific Northwest Laboratories (PNL)/8-2977.
Wori Scope ----------- The detailed work scope is provided in Task Action Plan for resclution of Generic Issue No. 51 (Memorandum from R. Mattson to T. Speis, et al, dated 01/11/84). In summary, the scope of this task will be to evaluate the adequacy of surveillance
/O and control methods and to propose the use of those methods
() which will assure the continued reliability of open cycle service water systems against various forms of fouling.
Affected Documents --- To Be Determined Status --------------- Task action plan was revised and issued on 10/3/84. The statement of work (50W) was revised on 5/9/85 to incorporate RES project task V into NRRs technical assistance project.
The TAP was revised to be consistent with the 50W and to assure that it incorporated milestones necessary to process CRGR SRP packages through issuance and use. The first tasks associated with this issue are tied to research project 82463 performed by RES. The first four tasks are essentially complete. Based upon the results of this research which deals with biofouling,
, DSI will adapt, where possible, methods for surveillance and control of biofouling to fouling by mud, silt and corrosion products.
A modified PNL proposal dated October 1985 was received incor-porating the following new task. The contractor will deter-mine the applicability of biofouling surveillance and control
! methods contained in NRC furnished materials to open cycle water systems in nuclear power plants. Preparation of the final contractor report is scheduled for April 30, 1987.
n Coordination of this project with RES is documented in a
/ Memorandum from R. Mattson to F. Arsenault, dated 01/23/84.
As of First Quarter FY-86
V(
Generic Issue #51 Problem /Re.olution --- Due to budget contraints, RES was not be able to provide all of the technical assistance originally planned. In particular, they could not fund Task V of their FIN B2463; Task V called for preparation of a final report consolidating the results of the previous four tasks. NRR has established a technical assistance contract that will use the results of Tasks I-IV of RES FIN 82463 to develop methods for surveillance and control of fouling by mud, silt and corrosion products.
Technical Resolution -
Milestones Original Current Actual Task action plan Approved by 01/84 -
01/11/84 Director, DSI.
Revised work plan approved and - -
10/03/84 issued Proposals solicited .07/84 -
10/31/84 PNLs response to request For - -
12/21/84 Proposal and 50W
~
Revised 50W to incorporate - -
05/09/85 RES Task V Proposal Evaluated and 02/85 10/85 08/85*
Accepted Contract Schedule 03/85 11/85 10/85 Draft NUREG/CR report from 07/86 03/87 -
contract consultant Staff review of draft NUREG/CR 08/86 03/87 -
rcport Staff review of final NUREG/CR 09/86 04/87 -
report Value Impact Statement prepared 10/87 06/87 -
Final-report prepared by 11/87 07/87 -
Division .
Final report. forwarded to DST 11/87 08/87 -
for processing NRR Director Review completed 12/87 09/87 -
aSubcontractor may revise proposal to incorporate additional work required by Task V of Research Project B-2463.
As of First Quarter FY-86
4 l Generic Issue #51 1
- Milestones Original Current Actual I
4 Peview Package to CRGR 12/87 10/87 -
, CRGR review completed 01/88 11/87 -
EDO approval 02/88 12/87 -
~ Federal Register Notice of 05/88 01/88 -
Issuance of SRP for Public Comment OMB Clearance, if applicable 06/88 01/88 -
i Division review of public 07/88 02/88 -
comments completed i NRR Director review 07/88 03/88 -
j completed
, CRGR review completed 08/88 04/88 -
- EDO Approval 09/88 04/88 -
i Federal Register Notice 09/88 05/88 -
l of Issuance of SRP 4-4 i
l 1
1 1
l As of First Quarter FY-86 I
. GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No 61 Safety / Active-L1 NRR/DSI/CSB F. Eltawila 55224 Medium Title ---------------- SRV Discharge Line Break Inside the Wetwell Airspace of BWR Mark I and Mark II Containments Work Authorization --- Memorandum to R. J. Mattson from H. R. Denton dated November 30, 1983.
NRR FY-84 Operating Plan (Appendix G)
Cetract Title ------- Steam Bypass in Mark I and II Containments Due to Postulated SRV Discharge Failure Contractor Name/
FIN No. ------------ BNL/A3793 Work Scope ----------- BNL's report, NUREG-31940, discusses the consequences of the above problem. The findings in NUREG-31940 involve a con-siderable amount of uncertainty. Additional study is needed to more accurately quantify the consequences associated with
, such accidents. This activity will develop the need for
(- additional work by the staff, staff contractor or applicants /
licensees of plants with Mk I & II containments. The results of this work will determine the next action to be taken to resolve issue.
Affected Documents --- BNL-NUREG-31940.
Status --------------- Revised proposal for .il tech assistance was accepted by DSI, letter dated 12/19/84. Comp 1r. tion of the contractors feasi-bility study to identify the most effective fix to reduce con-tainment failure due to SRV line break in air-space region of the suppression pool will not be completed until April 1986.
Milestone dates for resolution will slip 3 months.
j Problem / Resolution --- None i
! Technical Resolution -
Milestones Original Current Actual l
Issue assigned to DSI. 11/83 -
11/03/83 i Task Action Plan approved by 01/84 -
01/11/84 Director, DSI.
i Complete review of BNL-NUREG- 03/85 -
12/14/84 31940 I
As of First Quarter FY-86
Generic Issue #61 Milestones Original Current Actual Complete feasibility study to 10/85 04/86 ' -
identify the most effective fix to reduce containment failure due to SRV line break in air -
space region of the suppressien -
pool.
Technical resolution identified. 01/86 04/86 -
Prepare CRGR package or close-out documentation.
Division Director approval of 02/86 05/86 -
CRGR package. Package sent to DST, DL and others for comment.
DST, DL and other Division 03/86 06/86 -
Directors' comments incorporated.
Package sent to Director, NRR.
Director, NRR review complete. 05/86 08/86 -
package sent to CRGR.
CRGR review. 06/86 09/86 -
ACRS review. 07/86 10/86 -
EDO approval. 08/86 11/86 -
FR Notice of draft NUREG for 08/86 11/86 -
public comment.
OMB Clearance, if needed. 10/06 01/87 -
Incoporate pub 1fc comments. 11/86 02/97 -
Final issuance of NUREG. 03/87 06/87 -
Issue Generic Letter to all 03/87 06/87 -
operating BWR plants with Mark I and Mark II containments. ,
O As of First Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue' Issue Action Task Number Type Level Office /Div/Br Manager Tac No 65 Safety /- Scheduled NRR/DE/MEB J. Jackson 49716 High with GI 23 Title ---------------- Component Cooling Water System Failures Work Authorization --- Memorandum to R. J. Mattson from H. R. Denton dated September 8, 1983.
NRR FY-84 Operating Plan (Appendix G).
Contract Title ------- Reactor Coolant Pump Seal Integrity Contractor Name/
FIN No. ------------ Brookhaven National Laboratory / FIN No. A-3751 Work Scope ----------- The consequences of loss of component cooling water relative
' to reactor coolant pump (RCP) seal degradation, will be determined. The reliability of existing and proposed seal cooling systems will be assessed to determine if additional ifcensing requirements are required. This work comprises Task 2 of Generic Issue .?3, " Reactor Coolant Pump Seal
) Failures." In addition DST will coordinate work efforts with
/ the following Branches:
NRR/DSl(ICSB)(RSB) (ASB)
NRR/ DST (RRAB)
- NRR/DHF(HFEB)(PSRB)
Interruption of seal cooling may lead to RCP seal failure and subsequent loss of primary coolant to containment, i.e., a small LOCA. Where the component cooling water system is also used for cooling reactor coolant system makeup pumps, makeup capability could be lost coincident with the seal leakage and core melt could result.
The program will determine what steps the NRC should take, if any, to ensure increased reliability of the component cooling water system relative to its RCP seal cooling function. Test data will be reviewed to determine the time to failure of seals without seal cooling and the leak rate resulting from this type of failure. A probabilistic risk assessment will be performed to identify the major contributors to component cooling water .
system unreliability and the contribution to core melt proba- -
bility due to loss of RCP seal cooling systems. A review will E be performed of instrumentation available to the operator as 4
As of First Quarter FY-86 i
Generic Issue #65 well as automatic or manual actions which can be taken to minimize interruptions of RCP seal cooling or prevent unacceptable consequences from loss of seal cooling.
Affected Documents --- Issue NUREG- (To Be Determined)
Revise and Issue Standard Review Plan (SRP) Section 9.2.2 (To Be Determined)
Revise and Issue SRP Section 9.3.4 (To Be Determined)
Issue New Regulatory Guide and SRP Section (To Be Determined)
Status --------------- A revised Task Action Plan has been developed for Generic Issue 23 which includes work for Genaric Issue 65. A probabilistic risk assessmenc of component cooling water system reliability is being performed by BNL under a technical assistance contract (FIN No. A-3751).
Problem / Resolution --- None.
Tcchnical Resolution - Refer also to Generic Issue No. 23.
Milestones Original Current Actual Task Action Plan for Generic Issue -- --
10/26/83 23, " Reactor Coolant Pump Seal failure" was revised to incorporate GI-65 tasks and was issued.
Issued Request for Proposal to BNL -- --
11/02/83-for component cooling water PRA.
For milestone necessary to Resolve and complete this issue refer to Millstone for Generic Issue No. 23, Task 2 O
As of First Quarter FY-86
I
- a. .
l GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
! Issue Issue Action Task Number h Level Office /Div/Br Manager Tac No 1
66 Safety / Active-L1 NRR/DL/ ORA 8 E. Murphy T8P i NR 4
Title ---------------- Steam Generator Requirements (Integrated Program for Resolution of USIs A-3, A-4 and A-5 Regarding Steam Ger.erator Tube
! Integrity).
I
- Work Authorization --- Memorandum to D. G. Eisenhut from H. R. Denton dated
- November 16, 1983 NRR FY-84 Operating Plan (Appendix G).
. Contract' Title ------- None i Contractor Name/
! FIN No. ------------ None Work Scope ----------- Technically resolved Unresolved Safety ~ Issues A-3, A-4, and
( A-5 Regarding Steam Generator Tube Integrity.
I Affected Documents --- Issue NUREG-0844, "NRC Integrated Program for the Resolution of Unresolved Safety Issue A-3, A-4, and A-5 Regarding Steam j Generator Tube Integrity."
Status --------------- Draft.NUREG-0844 documents the Staff's proposed resolution of USIs A-3, 4, and 5 and was issued for pubife comment on April 22, l, 1985. With final publication of NUREG-0844, the USIs will
! . be considered technically resolved.
j As part of the technical resolution of USIs A-3, 4, and 5, the i staff issued a Generic Letter 85-02, dated April 17, 1985, to
, inform PWR licensees and applicants of staff recommendations i
stemming from its proposed resolution of the USIs and to request
- information regarding their programs to ensure SG tube integrity i.
and the mitigability of SGTRs.
! Problem / Resolution --- Milestones for completion of this issue were slipped by one month in order to incorporate Commission comments / directions into NUREG-0844 and the generic letter.
l Technical Resolution -
l Milestones Original Current Actual i ACRS review complete - -
10/18/83 i CRGR review complete - -
10/29/83 i
As of First Quarter FY-86
[
l
--,v~ ,~,~a,-,,.---e.,n-.n.-,- ,w..,-n..,, , , . , , . w- ._,w, .. , -e--, ,w ,,w,m- ~~www.-,,---v,,-----wev-
Generic Issue #66 Milestones Original Current Actual Commission Paper on Proposed USI - -
01/11/84 resolution (SECY 84-13)
Revised Commission Paper on -
07/84 09/07/84 proposed USI resolution (SECY 84-13A)
Commission Meeting 02/84 11/84 09/10/84 (a) Issue SECY 84-138 - -
11/05/84 (c) Issue SECY 85-62 - -
02/22/85 Issue generic letter 03/84 04/85 04/17/85 (85-02)
Issue FR Notice for public 03/84 04/85 04/22/85 comment on NUREG-0844 (For Comment)
Division incorporation of public 07/84 12/85 -
comments, Director, NRR review complete. 08/84 12/85 -
EDO review complete. 08/84 01/86 -
Issue FR Notice for Formal 09/84 02/86 -
determination by staff of USI resolution NUREG-0844 Issue report to Commission -
02/86* -
regarding responses to generic letter and clost-out memorandum O
As of First Quarter FY-86
- m. . _______. _ _ __ . . _ . _
i i
1 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac'No 1
67 Safety / Active-L1 NRR/DE/MTEB H. F Conrad 59303
, Subtask Medium i 67.7 .
1
~
Title ---------------- Steam Generator Staff Actions - Eddy Current Tests i Work Authorization --- Memorandum To J. Knight From H. Denton dated j March 28, 1985 Contract Title ------- ASME Code Provisions For Eddy Current Testing p Contractor Name/
j FIN No. ------------ Oak Ridge National Laboratory /A-9476 l Work Scope ----------- Review current ASME Code requirements with respect
- to licensing needs for eddy current inservice inspection of steam generator tubes. Provide a critique of current
- 1) code requirements. Formulate recommendations for in-l proving code provisions for eddy current testing.
=
Perform confirmatory testing as required to substantiate j technical validity of existing or proposed code pro-i visions. Attend and participate in pertinent Code subcommittee and subgroup meetings of both Sections V l and XI. In the event that the Code is unable to
[ incorporate those improved eddy current testing pro-j visions deemed necessary, provide recommendations for a Draft Regulatory Guide.
Affected Documents --- To.Be Provided Later l Status --------------- Proposal received from ORNL on September 16, 1985.
Problem / Resolution --- Issuance of contract to ORNL suspended pending discussions 2 with RES on the incorporation of this program into ongoing l PNL/RES program on steam generators. Delays in this generic
! issue have resulted because of RES stated needs for additional -
funding, possibly from NRR, to accelerate work to meet a
! schedule acceptable to NRR.
t Technical Resolution -
] '
l ' Milestones Original Current Actual Generic Issue Assigned - -
03/28/85 .
Preliminary discussions of - -
04/10/85 work plan with ORNL i ORNL provides preliminary - -
06/28/85 outline'of work plan As of First Quarter FY-86 i
i_.__.__.__.____._._..____._.__._____ _ _ _ _ . _ _ ~ . - .
Generic Issue #67.7 Milestones Original Current Actual R: quest for proposal submitted 09/85 -
08/20/85 t2 ORNL C:ntract Incorporated in 09/85 -
09/85 FIN Plan Pr:posal Evaluated 09/85 -
09/85 and Accepted Issue Contract 10/85* - -
to ORNL ORNL Issues Report 04/86* - -
on Recommendations fcr Improved Code Pr: visions and Action Plan ORNL Issues Report 06/87* - -
R: commending ASME Code Endorsement and/or r: commendations for R:gulatory Guide Endorsement with Exceptions Issue close-out memorandum 12/87* - -
from Director NRR recommending Ccd] Endorsement or Endorsement with Exceptions CResolution of this issue is contingent upon issuance of technical assistant contract, if not to ORNL then to PNL/RES. A new schedule will be provided after TA contract is issued and the effect an> overall schedule has been reevaluated.
e
O GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No 68 Safety / Active-L1 NRR/DSI/ASB J. Ridgely 55225 High Title ---------------- Loss of AFWS Due to AFW Steam HELB Work Authorization --- Memorandum to R. J. Mattson from H. R. Denton dated April 24, 1984 Contract Title ------- Not Yet Determined Contractor Name/
FIN No. ------------ Not Yet Determined Work Scope ----------- Not Yet Defined Affected Documents --- Standard Review Plan Status --------------- Work on the technical resolution of this issue has not been initiated. The staff is currently reevaluating the prioriti-zation of this issue.
Problem / Resolution --- Not Yet Defined Technical Resolution - Not Yet Defined Milestones Original Current Actual Prepare Draft Task Action Plan 12/84 -
12/84 Incorporate Coments 03/85 11/85 04/85 Issued reprioritization memo for coments - -
05/85 OSI coments received - -
05/11/85 Incorporated coments OSI coments - -
06/85 Issue closecut memo based on low reprioritization _
results 09/85 06/86* -
- Final close-out memorandum has not been issued by DSI. If reevaluation of schedule shows that close-out is not feasible by June 1986, then the remaining milestone dates will be revised to reflect a new resolution date.
As of First Quarter FY-86
GENERIC ISSUE #68 Milestones Original Current Actual Issue TAP - Approval by Director, DSI 05/85 12/85 -
Technical Resolution 01/86 - -
Draft NUREG/CR 03/86 - -
Staff review of draft NUREG/CR report 06/86 - -
Value Impact Statement prepared (coordinated with SPE8 and RRAB as applicable) 08/86 - -
Final report prepared by Division (include SPEB preliminary comments and SRP revision) 10/86 - -
Final report forwarded to DST for processing 11/86 - -
CRGR Package to NRR Director for Review 11/86 - -
OMB Clearance obtained con-currently if applicable 12/86 - -
Review Package to CRGR 01/87 - -
CRGR review and ED0 approval completed 02/87 - -
Federal Register Notice of Issuance of SRP for Public Comment 03/87 - -
Division review of public comments completed 06/87 - -
Comments incorporated and transmitted to DST for processing 06/87 - -
Final CRGR package to NRR Director for review 07/87 - -
Review Package to CRGR 08/87 -
CRGR review and ED0 approval completed 09/87 -
As of First Quarter FY-86
,: ?
i
!' GENERIC ISSUE #68 t !
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! Milestones Original Current Actual i
j' i- Federal Register Notice of ,
Issuance of SRP' 10/87. - -
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GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
(\s)
Issue Issue -Action Task Number Type Level Office /Div/Br Manager Tac No 70 Safety / Active-L1 NRR/DSI/RSB C. Liang 55226 Medium Title ---------------- PORV and Block Valve Reliability Work Authorization --- Memorandum to R. Mattson from H. R. Denton dated May 14, 1984.
Contract Title ------- Estimation of Risk Reduction from Improved PORV (GI-70)
Contractor Name/
FIN No. ------------ BNL/A3807 Work Scope ----------- Identify fundamental safety requirements of the PORVs and block valves. PRAs will be used to determine core melt frequencies and risk contributed by malfunction of PORV and block valves associated with various accidents and plant-protection features including SGTR events, LTOP, PORV-LOCA, RCS vents and BTP RSB 5-1. Based on the results from the PRA work, maximum risk reduction will be evaluated which will q consequently identify the maximum amount of money that could (V 4 be spent on PORV/ block valve improvements. Potential improve-ments with the maximum amount of money that could be spent will be identified in the aieas of design, equipment qualifica-tions, QA and QC, maintenance programs, technical specifica-tions, and testing requirements.
Affected Documents --- Develop new requirements for PORVs, incorporate into SRP or regulatory guide Status --------------- Task action plan was issued on April 30, 1985. A report to the Commission on the status of staff work on Generic Issue 70 is in concurrence and should be issued in December 1985. There is a six month schedule delay to complete the resolution of this issue due to the time required to obtain data from the disassembled PORV from TMI-2. The expected resolution date of this issue is now 8/87 rather than 2/87.
Problem / Resolution --- None Technical Resolution -
Milestones Original Current Actual {
Draft Action Plan to Director, -
12/84 ,
12/84 DSI
\_ '
As of First Quarter FY-86
Generic Issue #70 Milestones Original Current Actual Draft Action Plan approved by -
01/85 02/85 Director, DSI and forwarded to other Division Directors for comment Incorporate comments to Action -
03/85 03/28/85 Plan Final Action Plan approved by 06/84 03/856 04/30/85 Director, DSI and forwarded to DST Assemble background information 09/85 06/86 -
PORVs and block valves Determine fundamental safety 12/85 06/86 -
requirements of PORVs and block valves Identify the potential improve- 11/85 07/86 -
ment on PORV/ block valves Report to the Commission on 07/85 12/85 -
status of the staff work on GI 70 Estimation of risk reduction 01/86 04/86 -
from improved PORV/ block valve reliability Identify the recommended 04/86 08/86 -
improvements based on value/ impact assessment and other safety considerations CRGR review package completed 03/86 09/86 -
Division Director approval of 04/86 10/86 -
CRGR package. Package to other division directors for comments.
Other division comments 04/86 10/86 -
incorporated.
CRGR Package to NRR Director 05/86 11/86 -
for Review O
As of First Quarter FY-86
l Generic Issue #70
/' '
Milestones Original Current Actual OMB Clearance obtained con- 06/86 12/86 -
currently if applicable Review Package to CRGR 06/86 12/86 -
, CRGR review and EDO approval 07/86 01/87 -
completed Federal Register Notice of 08/86 02/87 -
1 -Issuance of SRP for Public Comment Division review of public 09/86 03/87 -
comments completed l Comments incorporated and 10/86 04/87 -
transmitted to DST for l processing Final CRGR package to NRR 11/86 05/87 -
Director for review Review Package to CRGR 12/86 G5/87 -
CRGR review and EDO approval 01/87 07/87 -
completed Federal Register Notice of 02/87 08/87 -
Issuance of SRP l
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As of First Quarter FY-86 i
i
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
'd Issue Issue Action Task Number e_
Typ_e Level Office /Div/Br Manager Tac No 75 Safety / Active-L1 IE/0QAVT/QA8 M. Malloy None Subtask 1 NR Title ---------------- Generic Implications of ATWS Events at the Salem Nuclear Plants - Quality Assurance Work Authorization --- Memorandum from H. Denton to R. C. DeYoung, " Schedule for Resolving and Completing Generic Issue No. 75," dated October 19, 1983.
NRR FY-84 Operating Plan, (Appendix G).
Contract Title ------- N/A Contractor Name/
FIN No. ------------ N/A Work Scope ----------- Revise Reg. Guide 1.33 " Quality Assurance Program Require-ments (Operations)" to contain more detailed guidance for operational QA programs. The staff will consider backfitting this Reg. Guide revision. The work scope of the TMI Task item I.8.1.1(6) and I.B.1.1(7) has been subsumed
\h by this generic issue subtask.
Affected Documents --- ANS-3.2 (1982)
Status --------------- During the past quarter, the staff finalized the draft guide (except in the area of records retention, as described below),
incorporated ELD's 7/85 comments on the guide, and prepared a package for review by the Ofrector, IE requesting a policy decision on obtaining additional public comments. Due to the accumulation of significant operating events since ANS-3.2 was published, the Director, IE decided in 10/85 that, to the maximum extent possible, the lessons learned from that operating experience, as well as inspections, be included in the revised guide. In doing so, the revised guide would be-come a "best practices" guideline for'all new appifcants which current licensees could chose to adopt. Further, the Director decided to issue the guide for a 60-day regior;al and other NRC program office review and then for public comment in order to gather the operating and inspection experience input. The _
staff is preparing an NRC review package, which includes a -
draft regulatory analysis, that will be issued in early 1986.
The staff has determined that the records retention guidelines need to be more specific. Consequently, it is preparing and
. coordinating a specific listing of operational phase records O
O As of First Quarter FY-86
a v
Gene'rfc Issue #75 to be maintained which will be added to the guide no later than its issuance for public comments. Pending issuance of the final guide licensee requests for the QA Branch licensing staff will review FSAR Chapter 17 revisions committing to ANS-3.2-1982 on a case-by-case basis.
Problem / Resolution --- See Status above.
T:chnical Resolution -
Milestones Original Current Actual Issued memcrandum to W. Dircks, -
07/84 07/26/84 EDO subsuming Task Action Plan Item I.8.1.1 subtasks 6 and 7 Issued draft R.G. 1.33 for - -
02/85 division comments Prepare package for CRGR Review 09/84 03/85 Deleted (include backfit issue study plan)
CRGR Review completed 10/84 05/85 Deleted ACRS Review completed 11/84 07/85 Deleted Public comments on 3rd proposed 01/85 08/85 Deleted Rev. 3 Re-issue draft R.G. 1.33 for 01/86 - -
division comments Prepare package for CRGR Review 04/86 - -
CRGR Review completed 06/86 - -
ACRS Review completed 07/86 - - -
End of 60-day public comment 09/86 - -
period Resolve comments and prepare 09/85 01/87 -
Regulatory Analysis Package for CRGR Review CRGR Review comple'.ed 10/85 03/87 -
ACRS Review completed 12/85 04/87 -
E00 Approval 01/86 05/87 -
c As of First Quarter FY-86
i-i.
l ' Generic Issue #75 ,
i ii Milestones Original Current Actual r
}' . Issue Federal Register 02/86 07/87 - i Notice on issuance and -
] availability of Rev. 3 to j Regulatory Guide 1.33 i
Issue Close-out meno to 02/86 07/87 -
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i GENERIC ISSUE MANAGEMENT CONTROL SYSTEM y L.J Issue Issue Action Task Number Type _, Level Office /Div/Br Manager Tac No 77 Safety / Active-L1 NRR/DSI/ASB A. Singh 52397 High ,
Title ---------------- Flooding of Safety Equipment Compartments by Back-Flow Through Floor Drains Work Authorization --- Memorandum to R. J. Mattson from H. R. Denton dated September 8, 1983.
NRR FY-84 Operating Plan, (Appendix G).
Contract Title ------- None Contractor Name/
FIN No. ------------ None Work Scope ----------- This generic issue will evaluate operating plants licensed prior to issuance of the Standard Review Plan (SRP) for com-pliance with SRP Sections 9.3.3, " Equipment and Floor Orainage Systems" and 10.4.5, " Circulating Water System" regarding flooding protection in connection with backflow through drains.
( The work will consist of a re-review of the previous flooding information and evaluations for nine (9) representative plants. The cause of the flooding will not be evaluated, but this issue will account for flooding resulting from both internal and external sources. The need to backfit further protective measures against flooding of safety-related equipment compartments due to backflow through drainage systems will then be determined and the appropriate backfit package prepared.
Affected Documents --- Since the present Standard Review Plan criteria in this area is considered to be adequate, no documents will be affected.
Status --------------- Information to conduct a re-review of previous flooding infor-mation and evaluations for nine selected representative plants is not currently available due to the reluctance of some of the selected utilities to provide the required information.
Problem / Resolution --- Information to conduct a re-review of previous flooding infor-mation and evaluations for about ten selected representative plants was requested to be provided on a voluntary basis. -
Only four or five of the selected plants indicated that they ,
would provide the requested information on a voluntary basis.
This information should be available by January or February of 1986. The remaining selected plants indicated that they would not voluntarily provide the requested information. Considera-tion is now being given to issuing a confirmatory order to As of First Quarter FY-86
.k
/
Generic Issue #77 these plants to obtain the required information. The addi-tional effort required to obtain the requested information will result in approximately a 15 month delay in the resolu-tion of this issue.
Using FSAR drawings, floor and equipment drainage system draw-ings and previous reviews of flooding of safety equipment com-partments at operating plants, determine the adequacy of the previous reviews for nine (9) plants. Where necessary, elicit from the licensee additional information regarding the measures taken to prevent flooding of safety-related equipment compartments due to backflow through the drainage systems.
Technical Resolution - Since the present SRP is indicated as being acceptable this issue involves a determination that actual features in plants are adequate to assure protection against flooding of safety-related compartments through the floor and equipment drains.
OL assistance may be required to assist in acquiring existing information and gathering information from licensees.
Estimate - 0.02 PSY in FY-85 h
Task No. Title /Millestones Starting / Completion Date 1 Select nine (9) plants to be included Start - October 1984 in the review effort. Complete - November 1984 2 Review information and previous evaluations Start - November 1984 for nine (9) plants in order to assess Complete - March 1985 the adequacy of existing protection provided against backflow through drains.
3 Determine the need for and efficacy of Start - May 1985 various corrective measures that can be Complete - August 1985 taken to detect, prevent and limit the consequences of backflow through the drainage systems.
4 Prepare CRGR package for backfit of any Start - August 1985 proposed modifications. Complete - August 1986 Milestones Original Current Actual Issue assigned to DSI. 09/83 -
09/08/83 [
Task Action Plan Approved by 01/84 -
01/10/84 Director, DS!*
Incorporate Division Comments -
09/84 09/09/84 As of First Quarter FY-86
Generic Issue #77 f Milestones Original Current Actual Revise and Reissue Approval -
10/84 10/31/84 Work Plan Task 1-Plant Selection. 10/84 -
11/84 Task 2-Information review. 12/84 12/86 -
Task 3-Assessment of backfit. 05/85 01/87 -
Task 4-Regulatory requirements 08/85 02/87 -
development.
l Value Impact Statement prepared. 08/85 02/87 -
Final report prepared, CRGR 11/85 03/87 - -
package approved by Director 05I. Sent to DST, DL and others for comment.
Comments from other Division 01/86 04/87 -
Directors incorporated. Package g
sent to Ofrector, NRR.
Package sent to CRGR. 02/86 05/87 -
CRGR review. 03/86 06/87 -
EDO approval. FR Notice issued 03/86 06/87 -
for public comment. .
Public comments incorporated. 05/86 08/87 -
OMB Clearance, if needed.
Final CRGR package to Ofrector, 06/86 09/87 -
NRR.
Review package to CRGR. 07/86 10/87 -
CRGR review. EDO approval. 08/86 10/87 -
Regulatory requirements issued.
\
As of First Quarter FY-86
1
( GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
\
Issue Issue Action Task Number Type Level Office /Div/8r Manager Tac No 79 Safety / Active-1 NRR/DE/MEB M. Hartzman 52140 Medium NRR/DS/RS8 Title ---------------- Unanalyzed Reactor Vessel Thermal Stress During Natural Convection Cooldown - PWR Work Authorization --- Memorandum to R. H. Vollmer from H. R. Denton dated July 25, 1983.
NRR FY-84 Operating Plan, (Appendix G).
Contract Title ------- Unanalyzed Reactor Vessel Thermal Stress Contractor Name/
FIN No. ------------ BNL/ Fin. No. A3822-5 Work Scope ----------- 1. PWR NSSS will provide thermal-hydraulic, heat conduction an>1 ASME III stress analysis of the reactor vessel.
- 2. RSB will verify acceptability of thermal analyses.
. 3. MEB will verify acceptability of stress analyses, evaluate results, and determine resolution of the issue.
d Affected Documents --- Potential SRP change and/or NUREG reports.
Status --------------- Contractor has been obtained to perform review.
Problem / Resolution --- The task manager for this generic issue has been a full time dedicated reviewer for special ifcensing projects and due to his unavailability the task will be performed under a technical assistance contract.
Technical Resolution -
Milestones Original Current Actual Meeting with B&W to clarify 11/83 -
03/84 issue.
Receipt of initial B&W analyses. 08/84 12/84 12/84 Prepare request for proposal for -
06/85 06/85 technical assistance contract Initiate contract and commence -
09/85 09/85 review As of First Quarter FY-86
Generic Issue #79 Milestones Original Current Actual Completion of audit calculations -
05/86 -
Preliminary technical evaluation -
07/86 -
for staff review Final technical evaluation -
08/86 -
completed Close-out memorandum issued * -
09/85 -
CNote: It is anticipated that vendor analysis will demonstrate acceptability of current designs. The milestone schedule is based on this assumption. No changes in regulatory requirements will be needed providing this assumption proves valid. However, if new regulatory requirements are needed the Schedule will have to be expanded by 12 months.
~
9 i
O As of First Quarter FY-86
}
tj 1
J GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type. Level Office /0iv/Br Manager Tac No 82 Safety / Active-L1 NRR/OSI/AE8 M. Wohl 53347 Medium Title ---------------- Beyond Design Bases Accidents in Spent Fuel Pools Work Authorization --- Memorandum to R. J. Mattson from H. R. Denton dated December 7, 1983 NRR FY-84 Operating Plan, (Appendix G).
Contract Title ------- Study of Beyond Design Basis Accidents in Spent Fuel Pools (Generic Issue 82)
Contractor Name/
FIN No. ------------ BNL/A3786 Work Scope ----------- Work Scope approved in Task Action Plan. See Memorandum from R. Mattson to T. Spets, dated February 2,1984.
RES has verified the possibility of igniting zircaloy cladding
, in the event relatively fresh spent fuel is uncovered due to
) pool failure. The circumstances of ignition and propagation, V and the consequences and likelihood of severe spent fuel pool accident will be assessed. Should the risk from such an acci-dent be judged unacceptable on a cost / benefit basis, then preventative and mitigative measures must be devised and considered.
EG&G, through INEL & RES, will perform hand calculations to assess temperature history of uncovered fuel, and the oxida-tion rate of zircaloy cladding to be expected. ASTP0 will provide an estimate of fission product release, predicated upon the earlier computations.
If assessments indicate that risk levels provide the bases for fixes with positive cost / benefits, corrective actions are to be pursued. The range of fixes which appear technically feasible include delaying storage of fresh assemblies, or the placement of fresh assembifes only near older ones. An SER will be prepared describing safety issues and cost / benefits analysis associated with alternative fixes. If fixes are warranted, a regulatory requirements package will be prepared ,
for CRGR review and issuance.
Affected Documents --- Possible outcomes could include:
Revise and issue Regulatory Guide 1.25 and SRP Section 15.7.4.
Resolution may require STS changes affecting cool-down times
(
As of First Quarter FY-86
Generic Issue #82 prior to fuel storage and/or limitations on the location of fresh assemblies.
Status --------------- Task Action plan approved via memorandum from R. Mattson to T. Speis, dated 02/02/84. A tentative agreement was reached with RES to initiate work on this generic issue.
Milestones for this generic issue were revised in May 1984, based upon the results of preliminary work by RES. RES contractor's assessment was received 05/21/84. DSI has issued a contract for PRA study of fuel pool accidents and possible confirmatory experiments and analytical study of oxidation propagation. A preliminary assessment of the likelihood and consequences of loss of pool integrity for the most vulnerable design indicates that an expanded work scope for risk study should be developed.
Problem / Resolution --- Delays encountered due to need for (1) broad-scale struc-tural analysis, (2) consideration of refueling cavity water seal failure (re: Haddam Neck) type events.
A preliminary expanded work scope has been developed and a request for a revised proposal reflecting the expanded work scope will be issued to BNL in January 1986. Due to the recent NRR reorganization, the degree of expanded work to be performed at Brookhaven on this issue may be reevaluated.
Tcchnical Resolution -
Milestones Original Current Actual Generic Issue 82 assigned to 12/83 -
12/07/83 OSI.
Tentative agreement reached with 01/84 -
01/23/84 RES to include under existing contractual effort, a task to determine whether Zircaloy igni-tion and source term release are possible in the event of a spent fuel pool failure.
Task Action Plan approved by 02/84 -
02/02/84 Director, DSI.
~
Receive RES Contractors' 04/84 -
05/21/84 '
assessment.
RES Contractors' assessment 05/84 -
05/05/84 sent to DL, DST, DE and DSI:
CPB and OSI:ASB for review and comment.
As of First Quarter FY-86
b Generic Issue #82 3
Milestones Original Current Actual Complete PID for inclusion of 04/84* 06/84 06/84 technical assistance support for GI 82 in FY-85 budget.
Issue RFP 08/84 -
08/27/84 Issue tech assistance contract 09/84** -
11/84 Complete Tasks 1 & 2a of tech -
04/85 05/85 assistance contract and receive contractor preliminary assess-ment of likelihood and conse-quences of loss of pool integrity for the most vulnerable design.
Prepare preliminary expanded 07/85 09/85 11/85 work scope for risk study.
Evaluate contract 08/85 09/85 11/85 results. Determine whether probabilities O
and phenomena warrant risk study. If not, prepare negative safety evaluation report. If so, prepare final PIDS for risk study.
Issue RFP for Structural 10/85 01/86 -
Evaluation and Risk Study of Spent Fuel Pools with High Seismic Vulnerability.
Risk Assessment of Reactor Cavity Seal Failure.
Issue RFP for risk 10/85 - -
study.
Evaluate risk contract 09/86 12/86 -
results. If negative, prepare SER. If positive, ,,
evaluate alternative regu- -
latory requirements and prepare
and prepare SER.
O .
As of First Quarter FY-86
1 Generic Issue #82 Milestones Original Current Actual Prepare generic letter to 09/87 11/87 -
licensees for consideration of CRGR. If necessary con-sider alternative closure possibilities C8y Memorandum for T. Speis from R. Mattson dated April 20, 1984 Cr8y Memorandum for T. Speis from R. Mattson dated June 5, 1984.
O O
As of First Quarter FY-86
y e
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
}
Issue Issue Action Task Number h Level Office /Div/Br Manager Tac No 83 Safety / Active-L1 NRR/DSI/ MET 8 J. Hayes 42235 NR Title ---------------- Control Room Habitability (CRH).
Work Authorization --- Dircks letter to Denton, 8/15/83.
Contract Title ------- In-Plant Reviews on Control Room Habitability.
Contractor Name/
FIN No. ------------ Argonne National Laboratory /A2325 and A2328 Work Scope ----------- Assess adequacy of habitability criteria, NRR review, plant systems and components, and testing procedures relative to control room habitability, including those areas of ACRS concern. A report will be prepared summarizing results and providing recommendations.
Affected Docun.ents --- 10 CFR 50, Appendix A, GDC 2, 3, 4, 5, 19, 60; SRP 6.4, 9.4.1
- 12. 3, 6. 5.1, 2. 3, 2. 2.1-2. 2. 3, 18, 9. 5.1; RGs 1. 78, 1. 95, 1.29, 1.52, 1.101, 1.140; NyREG-0737, Item !!!.D.3.4, !!.8.2, O 10 CFR 50: 50.48, Appendix R to 10 CFR 50; NUREG-0700; NUREG-0737, Supplement 1.
Status --------------- A program of survey visits to a total of 12 plants was initiated in September 1985. Visits to three operating plants have been completed. Preliminary vists to 2 additional plants have been made. Survey visits will be conducted at each of these plants. Seven additional plants will be surveyed during FY 86. NUREG-1129 and its supplement will be published during the first quarter of FY 86.
Problem / Resolution --- The original TAP for GI 83 contained a number of subtasks for implementation of the recommendations in the June 1984 Control Room Habitability Report. Work on implementation of these recommendations has been halted due to management concerns over 1) lack of resources to perform independent verification of acceptability of appilcants' submittals and the degree of safety gain to be achieved 2) reluctance to devote resources to updating SRPs and pertinent reg guides in the absence of new plant orders, and 3) reluctance to implement recommendations that might be interpreted as backfitting. ,
1 The implementation of the recommendations in the June 1984 4 report is being reevaluated in light of the above concerns.
A revised TAP will be prepared af ter the reevaluation is complett.
As of First Quarter FY-86
Gene'rfc Issue #83 Technical Resolution -
Milestones Original Current Actual Workshop on CRH 11/83 -
11/30/83 Award of Contract 02/84 -
01/26/84 Visit to Initial Plant 03/84 -
05/02/84 Report on CRH criteria to Director, NRR - -
06/01/84 Completion of contractor - -
08/23/84 visits to operating and NTOL plants Statement of Work written 11/84 -
10/29/84 for generic studies Request for proposal sent 12/84 -
11/15/84 to potential contractor (s)
Receipt of proposal (s) 02/85 -
03/04/85 Initiate program to visit -
09/85 09/85 12 additional Operating ,
Plants Reevaluate implementations -
01/86 -
of recommendations in EDO report Revise TAP based on reevalua- -
02/86 -
tion and provide milestones necessary to resolve issues O
As of first Quarter FY 86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number h Level Office /Div/8r Manager Tac No 84 Safety / Active-L1 NRR/DSI/RS8 V. Leung T8P NR Title ---------------- CE PORVs Work Authorization --- Memorandum to R. M. Bernero from H. R. Denton dated February 27, 1985.
Contract Title ------- N/A Contractor Name/
FIN No. ------------ N/A Work Scope ----------- To be provided.
Affected Documents --- To be provided.
Status --------------- Awaiting final resolution of USI A-45 with respect to PORV requirements.
Problem / Resolution --- To be provided. .
\ Technical Resolution - To be provided.
Milestones Orlainal Current Actual Schedule to be developed following the completion of USI A-45 work.
As of First Quarter FY 86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number h Level Office /Div/Br Manager Tac No 86 Safety / Active-L1 NRR/DE/MTE8 W. S. Hazelton M07419 NR Title ---------------- Long Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping Work Authorization --- Memorandum to R. H. Vollmer from H. R. Denton dated October 3, 1984 Contract Title ------- None .
Contractor Name/
FIN No. ------------ None Work Scope ----------- Long Range Plan for dealing with pipe cracking is contained in N SECY-84-301; July, 1984 (1) Issue NUREG-1061, Vol. I for comment (2) Issue NUREG-0313 Rev. 2 (3) Issue generic letter incorporating NUREG-0313. Rev. 2 (4) Pursue ASME Code changes Af fected Documents --- NUREG-0313, Rev. 1 Status --------------- Staff is finalizing NUREG-0313 Rev. 2 for issuance; substantial rewrite will be needed as there is a separate technical document and the public comments on this technical document (NUREG-1061 Vol.1) must be factored into the revision. NUREG-1061 Vol. I was prepared by the task group on pipe cracks of the piping review committee.
Problem / Resolution - - The reason for the schedule s11ppage has been due primarily to the difficulty the'ASME Code Committee was having in resolving controversies involving the low toughness of certain type weldments originally raised by Prof. Paris in his letters to Commissioner Roberts and the staff. The staff's proposed acceptance criteria were based upon ASME Section XI Paragraph
!W8 3640, which was not endorsed by NRC because of this issue of weld low toughness. The staff worked closely with the Code Committee and a resolution was achieved during the Code meeting
, that took place in June 1985.
Technical Resolution - Resolution available as described in work scope. .
O As of First Quarter FY-86
Generic Issue #86 Milestones Original Current Actual SECY 84-301, NUREG 1061 07/84 -
07/30/84 to Commission Publish NUREG-1061, Vol. I 09/84 -
09/20/84 End of Comment Period 11/84 -
11/7/84 Complete preparation of Draft 01/85 07/85 09/85 NUREG-0313, Rev. 2 Proposed Generic Letter 09/85 12/85 -
and staff position in Draf t NUREG-0313, Rev. 2, circulated for NRR Div. Dir. review Proposed Generic Letter 10/85 01/86 -
and staff position in Draft NUREG-0313, Rev. 2, reviewed and endorsed by CRGR.
Draft NUREG-0313, Rev. 2, and 11/85 02/86 -
Generic Letter issued for public comment.
Draft NUREG-0313, Rev. 2, 02/86 04/86 -
revised to reflect public comments.
Commission Paper on staff 03/86 05/86 -
implementation plan and staff position (NUREG-0313, Rev. 2) reviewed and endorsed by CRGR.
Commission Paper on staff 04/86 06/86 -
implementation plan and staff position (NUREG-0313, Rev. 2) submitted for approval.
Issue Generic Letter and 05/85 07/86 -
close-out memorandum O
As of first Quarter FY-86
[ GENERIC ISSUE MANAGEMENT CONTROL SYSTEM c Issue Issue Action Task Number Tyge Level Office /Div/Br Manager Tac No 91 Safety / Active-L1 NRR/DL/TF TBP TBP NR Title ---------------- Main Crankshaft Failure in Transamerica DeLaval Work Authorization --- Memorandum To R. Bernero From H. Denton dated July 8, 1985 Contract Title ------- To Be Determined Contractor Name/
FIN No. ------------ To Be Determined -
Work Scope ----------- To Be Provided Later Affected Documents --- To 8e Provided Later Status --------------- To Be Provided Later Problem / Resolution --- To 8e Provided Later Technical Resolution -
Milestones Milestones necessary to resolve this issue are being developed.
As of First Quarter FY-86
[ GENERIC ISSUE MANAGEMENT CONTROL SYSTEM V
Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No 93 Safety / Active-L1 NRR/OSI/AS8 T. Chandrasekaran 56291 High Title ---------------- Steam Binding of Auxiliary Feedwater Pumps Work Authorization --- Memorandum to R. M. Bernero from H. R. Denton dated October 19, 1984 Contract Title ------- None Contractor Name/
FIN No. ------------ None Work Scope ----------- Generic preventive maintenance measures that may have to be implemented at all PWRs to reduce the potential for back-leakage of steam and hot water to the Auxiliary feedwater (AFW) system from the steam conversion system via isolation valves in the AFW system will be developed. It is expected that these measures will reduce the likelihood of steam binding of the AFW pump (s) and possible common mode failure (o
V) of the AFW system by ensuring that the valves perform their intended function. In addition the following will be determined: (1) The proper frequency of leaktesting for the appropriate isolation valves in the AFW system as part of the operability requirements for the AFW system. (2) The optimum method of performing survelliance of the AFW system temperature. (3) The necessary corrective actions to be taken (suggestions from industry groups, if censees and NRC staff will be solicited in this regard). (4) The hardware modiff-cations that may be required to implement leaktesting of the AFW system isolation valves, surveillance of the AFW system temperature and the performance of necessary corrective operator actions. (5) The acceptable interim measures to be adopted until the modifications are implemented, if hardware modifications are needed and if backfit is necessary for implementing the recommended preventive measures.
Affected Documents --- Standard Technical Specifications (STS) change for NSSS vendors. Standard Review Plan Section 10.4.9 acceptance criteria relating to the AFW system is considered to be adequate so it may not need any revision in this regard.
~
Status --------------- Some staff and industry effort relating to the potential ~
problem of steam binding of the AFW pumps has already been completed. Previous work on this problem is detailed in the work plan.
/O.
( )
\ /
As of First Quarter FY-86
Gene'ric Issue #93 Status (continued)----- Comments on the draft TAP have been received and these will be utilized in developing the guidelines for resolution of this issue. Based on their informal survey of the resident inspector's findings on actions completed at the various operating PWRs in response to IE temporary instruction 2515/67 dealing with the above issue, IE has issued Bulletin 85-01 dated October 29, 1985. The Bulletin requires all PWR CP holders and the licensees for 28 operating PWRs (identified in Attachment 1 of the Bulletin) to complete short term cor-rective actions described below within the time period stipu-lated in the Bulletin. IE has concluded that the actions already completed and/or design features present at the re-maining operating PWR facilities (30) do not pose a serious safety problem requiring short term corrective actions as identified in the Bulletin. The Bulletin requires the addresses to develop procedures for 1) a simple means of monitoring the AFW system temperature regularly such as touch-ing the applicable pipe during each shift to ensure that the fluid temperature at the AFW pump discharge is maintained at about ambient temperature, and 2) recognizing steam binding and restoring the system to OPERABLE status should steam bind-ing occur. It further requires the addressees to keep the identified procedural controls in effect u. 'I they are super-ceded by action (s) implemented as a result of the resolution of the issue.
Problem / Resolution --- Evaluation of plant specific information for adequacy of procedures will not be completed until April 1986. Milestone dates for technical resolution have slipped 3 months.
Technical Resolution -
Starting /
Task No. Title / Milestones Completion Date 1 Development of Guidelines - Solicit recommendations December 1985/
from interested interagency staff such as resident February 1986 inspectors, ORAS staff, Engineering and Plant Sys-tems staff in the Divisions of PWR licensing, etc.
for resolving the identified concerns in this regard.
Develop guidelines based on the above recommenda-tions, summary of reported backleakage events into the AFW system, findings and recommendations given in the AE00 study, and recommendations given in the -
INPO SOER, and recommendations and corrective 1 actions identified in the IE Bulletin 85-01.
2 Evaluation of Pla;1t-Specific Responses - Using the April 86/
guidelines developed in Task No. 1, evaluate plant June 86 specific information obtained from IE Temporary As of First Quarter FY-86
Generic Issue #93 Starting /
Task No. Title / Milestones Completion Date Instruction 2515/67 and IE Bulletin 85-01, concern-ing actions taken by individual ifcensees relating to preventive maintenance measures, surveillance programs for monitoring the AFW system fluid conditions, and performance of corrective operator actions when needed.
3 Development of Plant-Specific Requirements - Based July 86/
on the plant specific review identified in Task September 86 No. 2, develop additional and/or alternative generic or plant specific modifications, proce-dures, and revisions'to plant TS as necessary.
Additionally, develop interim measures as t
necessary to be adopted for the applicable plants until the proposed backfits are completed.
4 Prepare Regulatory Requirements Package - September 86/
January 87 1
Milestones Oriainal Current Actual Issue assigned to OSI 10/84 -
10/19/84 Prepare Draft Task Action Plan 12/84 -
12/84 (TAP)
Draft TAP approved by DSI 12/84 -
01/22/85 Director Incorporate comments by various 02/85 06/85 06/85 Divisions Revise and reissue approved TAP 07/85 -
06/25/85 Task 1 - Development of guidelines 10/85 01/86 -
for resolving the identified con-corns relating to this generic issue Task 2 - Evaluation of plant 01/86 04/86 -
specific information for adequacy of procedures and actions dealing with this concern using the guide-lines developed in Task No. 1
^
G l
2 As of first Quarter FY-86
Generic Issue #93 Milestones Original Current Actual Tcsk 3 - Generic or plant specific 04/86 07/86 -
preventive maintenance measures, surveillance requirements and c~rrective actions including cost-Cffective backfits and TS revisions when needed determined based on cvaluation of plant specific information referred to in Task No. 2.
Tcsk 4 - Regulatory Requirements 02/86 - -
Development Value Impact Statement prepared 05/86 08/86 -
Final report prepared, CRGR 07/86 10/86 -
package approved by Director, OSI. Sent to DST, OL and others for comment Comments from other Division 09/86 12/86 -
Directors incorporated. Package sent to Director, NRR Package sent to CRGR 10/86 01/87 -
CRGR review and E00 approval 11/86 02/87 -
completed Federal Register Notice of 12/86 03/87 -
issuance of regulatory require-ments for PWRs in this regard for public comments Public comments incorporated. 02/87 05/87 -
OMB clearance, if needed Final CRGR package to Director, 03/87 06/87 -
NRR Review package to CRGR 04/87 07/87 -
CRGR review and E00 approval 05/87 08/87 -
completed.
Issue regulatory requirements 06/87 09/87 -
for PWRs (generic letter if required).
As of First Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
-Issue Issue Action Task Number DEe Level Office /Div/Br Manager Tac No 94 Safety / Active-L1 NRR/DSI/RS8 E. Lantz 59465 High Title ---------------- Additional Low-Temperature-Overpressure Protection For Light Water Reactors Work Authorization --- Memorandum To R. Bernero From H. Denton dated July 23, 1985 Contract Title ------- None*
Contractor Name/
FIN No. ------------ None*
Work Scope ----------- Operating experience shows that the changes needed to reduce the probability of low temperature overpressurizations in reactor coolant systems (RCS) are:
(1) Technical Specifications that will reduce the probability of either train of a low temperature overpressure protec-tion system (LTOPS) from being inoperable when the RCS is in a " Water Solid" condition.
'(2) Changes to allow spring-loaded, pressure-relief valves in the residual heat removal systems (RNRS) to prevent low temperature overpressurizations.
The Scope of this task is to:
(1) Develop model Technical Specifications for item 1.
(2) Develop specific ways item 2 could be realized and evaluate the change in public risk associated with each.
(3) Put the results of this work in a generic letter to affected ifcensees.
Affected Documents --- Branch Technical Position RS8 5-2 Status --------------- Milestones will be rescheduled following transfer of review responsibility to DSRO.
Problem / Resolution --- Contractors risk assessment analysis (PRAs) for generic issue #99 will not be completed until April 1987. These PRA .
results are to be used to resolve this issue. Milestone -
dates for resolution have slipped 13 months.
Technical Resolution -
- The results of the risk assessment contract, which is to be issued for Generic Issue #99, will also be used for this generic issue.
As of First Quarter FY-86
Generic Issue #94 Milestones Original Current Actual Generic Issue #94 assigned - -
7/23/85 to RS8/DSI/NRR Draft of Task Action Plan 11/85* 04/36 -
Completed Task Action Plan approved 12/85* 05/86 -
by DSI Task Action Plan to Of rector 01/86* 06/86 -
of DE, DL, HFS, and AE00 Final Task Action Plan approved 02/86* 07/86 -
by Director, OSI and forwarded to DST Model Technical Specifications 03/86 10/86 -
developed Received results of PRA analyses 03/86 04/87 -
for Generic Issue #99 Draft report completed 04/86 05/87 -
CRGR package prepared 05/86 06/87 -
CRGR package approved by 06/86 07/87 -
Director, OSI and sent to other Divisions for comment Package sent to CRGR 07/86 08/87 -
Issue close-out memorandum 10/86 11/87 -
from Director NRR to DL (Generic Letter to Licensees and changes to Branch Technical Positions RS8 5-2)
CR: vised TAP has not been completed. New milestone dates will be provided after overall schedule has been reevaluated.
O As of First Quarter FY-86 9
f GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No 99 Safety / Active-L1 NRR/DSI/RSB E. Lantz 59653 High Title ---------------- RCS/RHR Suction Line Interlocks on PWRs Work Authorization --- Memorandum To R. Bernero from H. Denton dated August 13, 1985 Contract Title ------- RHR System Operability and Interlocks Contractor Name/
FIN No. ------------ Not assigned Work Scope ----------- Operating experien:e shows that a change in the auto-closure feature on the valves that isolate the inlets of the Residual Heat Removal (RHR) System from the Reactor Coolant System (RCS) is needed to prevent losses of residual heat removal. The autoclosure feature on these valves was designed to provide the double, high- -
pressure boundary that is needed for the RCS to con-for to GDC 14 of Appendix A of 10 CFR 50.
The scope of this task is to find the best way to change the autoclosure feature to reduce the losses of (AD) residual heat removal without increasing the risk of failure of the RCS boundary.
PRAs will be performed for the following:
- 1. The present autoclosure interlock system.
- 2. The present autoclosure system with various modifi-cations to the administrative controls.
- 3. Renoval of the autoclosure interlocks.
- 4. Installation of RHR pump low-suction trip devices.
- 5. A rewiring of the contrcl switches so that press-ing a single switch closes both of the tw0 in-series motor-operated valves.
- 6. Vcrious combinations of the preceding items.
The effects of making these modifications will be compared. An optimum modification will be selected
- and a cost-benefit analysis performed.
Affected Documents --- None b
Status --------------- (See attached Milestones Dates)
Problem Resolution --- A contract will be negotiated to provide risk assess-ments (PRAs) for various alternatives to the present O autoclosure interlocks between the RHR and RCS systems.
k The results of these PRAs will be used to find the As of First Quarter FY-86
Generic Issue #99 best method for reducing RHR system failures without increasing the risk due to an intersystem loss-of-coolant accident. Initiation of work on this issue has been delayed due to the transfer of review responsibilities resulting from the NRR reorganization.
Milestone Dates Original Current Actual Generic Issue #99 assigned to RS8/DSI/NRR - -
08/13/85 Preliminary discussion of 02/86 04/86 -
work plan with BNL Draft work plan to Directors, 03/86 05/86 -
DSI, DE, DL, HFS, and AE00 Incorporate comments in work plan 04/86 06/86 -
Final work plan approved by 04/86 06/86 -
Director, DSI and forwarded to DST Issue contract to BNL 05/86 07/86 -
Final report from BNL 02/87 04/87 -
Final report prepared, CRGR package 04/87 06/87 .-
approved by Director, DSI, and sent to other divisions for comment Comments from other Division Directors 05/87 07/87 -
incorporated. Package sent to Director, NRR Pcckage sent to CRGR 06/87 08/87 -
Issue close-out memorandum from 08/87 10/87 -
Director NRR to DL (Generic letter to PWL licensees)
O As of First Quarter FY-86
[
\v) GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No 101 Safety / Active-L1 NRR/DSI/RSB K. Desai 57749 High Title ---------------- BWR Water Level Redundancy Work Authorization --- Memorandum to R. M. Bernero from H. R. Denton dated May 6, 1985.
Contract Title ------- BWR Water Level Redundancy Contractor Name/
FIN No. ------------ INEL/D-6020 Work Scope ----------- Perform a detailed survey of all BWR plants to determine types of water level instrumentation. Compile failure data of instru-
,_ ment piping leaks / break and instrument failures for all BWR plants from LERs. Perform simplified risk analyses postulating instrument piping leaks, single failure in instruments and feed water control system failure to determine which BWR plants would have problem with existing water level instrumentation. Make recommendations to resolve'this issue.
Affected Documents --- To Be Provided Later Status --------------- INEL proposal for technical assistance on this project was accepted on 11/29/85.
Problem / Resolution --- EG&G has not started work on Final report (including value impact analysis) as of yet. The contractors report will not be completed until August 1986. Milestone dates for technical resolution have slipped 5 months.
Technical Resolution -
Milestones Original Current Actual Generic Issue 101 assigned to - -
05/06/85 RSB/DSI/NRR Prelimin.ary Discussion of our - -
05/24/85 work plan with EG&G EG&G will provide preliminary cost estimate of work plan 06/85 -
06/11/85 [
Develop work plan and contract 06/85 -
07/26/85 proposal As of First Quarter FY-86
P Generic Issue #101 Milestones Original Current Actual Draft work plant to Director, 06/85 -
08/01/85 OSI Incorporate Comments to work 09/85 -
10/15/85 plan Final work plan approved by 09/85 -
10/15/85 Director, DSI and forwarded to DST Issue contract to EG&G 10/85 -
11/29/85 Final report from EG&G to NRR 03/86 08/86 -
including Value Impact Analysis Final report prepared, CRGR 05/86 10/86 -
package approved by Director, DSI. Sent to other Divisions for comment Comments from other Division 06/86 11/86 -
Directors incorporated. Package sent to Director, NRR Package sent to CRGR 07/86 12/86 -
Issue close-out memorandum from 09/86 02/87 -
Director, NRR to DL (Generic Letter to BWR Licensees)
As of First Quarter FY-86
[ \
[ GENERIC ISSUE MANAGEMENT CONTROL SYSTEM i l
Issue' Issue Action Task Number Type Level Office /Div/Br Manager Tac No 103 Safety / Active-L1 NRR/DE/EHEB Don Chery TBP NR Title ---------------- Design for Probable Maximum Precipitation Work Authorization --- Memorandum to J. P. Knight from H. R. Denton dated September 4, 1985 Contract Title ------- To Be Determined Contractor Name/
FIN No. ------------ To Be Determined Work Scope ----------- Revise Standard Review Plan (SRP) Sections 2.4.2 and 2.4.3 incorporating the most recent National Weather Service pro-cedures for determination of Probable Maximum Precipitation (PMP). Prepare regulatory analysis (value/ impact) for use of most recent PHP determination. Prepare a package for review by the Committee for the Review of Generic Requirements.
Develop recommendations regarding backfit application of the most recent PMP determinations. Obtain necessary review and approvals, then publish Revision 3 of SRP Sections 2.4.2 and (q 2.4.3.
Affected Documents --- Standard Review Plan Sections 2.4.2 and 2.4.3 Status --------------- Draft SRP revisions issue for division comments Problem / Resolution --- None Technical Resolution -
Milestones Original Current Actual Identification of Potential - -
05/08/84 Generic Requirement Concerning Design for PMP/ Memorandum V. Stello to H. R. Denton Prepare draft revisions of - -
07/85 SRP Sections 2.4.2 and 2.4.3 ,
CRGR package sent DST, DL, DSI, - -
07/12/85 and PPAS for Division Review 7
CRGR package reviewed by - -
08/22/85 Divisions DSI comments on CRGR package - -
09/13/85 v
As of First Quarter FY-86
Generic Issue #103 Milestones Original Current Actual Revised CRGR package based on - -
10/85 coments CRGR package reviewed and 11/85 04/86 -
approved by Director NRR CRGR review and approval 12/85 05/86 -
Milestones on Backfit Issue 12/85 05/86 -
to be provided Federal Register Notice of 01/86 06/86 -
Issuance of Rev. 3 SRP Section 2.4.2 and 2.4.3 for public coment.
CRGR package revised incorpo- 04/86 09/86 -
rating public coment Revised CRGR package reviewed 05/86 10/86 -
and approved by CRGR Federal Register Notice Issuing 07/86 12/86 -
SRP Rev. 3 Sections 2.4.2 and 2.4.3 l
l l
l 9
As of First Quarter FY-86
O U Issue Number Issue hpe GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Action Level Task Of fice/Div /Br Manager Tac No 105 Safety / Active-L1 NRR/DSI/RSB G. Thomas 57979 High Title ---------------- Interfacing System LOCA at BWRs Work Authorization --- Memorandum to R. Bernero From H. Denton dated June 11, 1985 Contract Title ------- Inteifacing Systems LOCA at BWRs Contractor Name/
FIN No. ------------ BNL/A3829 Work Scope ----------- Perform a detailed design review of all systems penetrating RCPB. Review low pressure /high pressure interface valves arrangement.and categorize different designs into groups. Perform an LER search to determine causes of interfacing systems LOCA. Find solutions to prevent inter-facing systems LOCA. Perform PRA to determine core melt frequencies and risk contributed by interfacing systems LOCA. Develop new licensing f\ criteria if necessary for the generic resolution.
Affected Documents --- To Be Provided Later Status --------------- BNL proposal for technical assistance on this project was accepted on December 2, 1985. '
Problem / Resolution --- The BNL contract will not produce all of the information necessary to define proper bases and justification for pro-posed resolution (corrective action or lack thereof).
Considerable addition effort will be required to produce an acceptable cost / benefit analysis from the information received from BNL. Also the milestone dates did not include sufficient time for ACRS review and the time needed to perform the additional work. The milestone dates for resolution have revised to reflect the additional time required.
Technical Resolution -
Milestones Original Current Actual Generic Issue 105 assigned to - -
06/11/85 RSB/DSI/NRR h i
Preliminary Discussion of cur - -
06/17/85 work plan with BNL As of First Quarter FY-86 d
Generic Issue #105 Milestones Original Current Actual BNLs preliminary cost estimate 09/85 -
08/85 cf work plan 0;velop work plan and contract 09/85 -
08/85 pr:posal Draft work plan to Directors, 09/85 -
08/21/85 DSI, DE, DL, NFS, and AEOD Incorporate Comments into 10/85 -
10/85 work plan Final work plan approved by 10/85 -
11/18/85 Director, DSI and forwarded to DST Issue contract to BNL 10/85 -
12/02/85 Final report from BNL to NRR 07/86 - -
including Value Impact Analysis Finn 1 report prepared, CRGR 12/86 05/87 -
p:ckage approved by Director, OSI. Sent to other Divisions fcr comment '
Comments from other Division 01/87 07/87 -
Dircctors incorporated. Package s:;nt to Director, NRR Package sent to CRGR 02/87 08/87 -
Issue close-out memorandum 07/87 04/88 -
from Director, NRR to DL (Generic Letter to BWR Licensee or SRP Changes ETC) 1 l
As of First Quarter FY-86 L.
X GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No 119 Regulatory Active-L1 RES/DRAD/MSEB R. Kenneally N/A Impact /hR Title ---------------- Piping Review Committee Recommendations Work Authorization --- Memorandum to R. Minogue from H. Denton dated September 10, 1985 Contract Title ------- To Be Determined Contractor Name/
FIN No. ------------ To Be Determined Work Scope ----------- To Be Provided Later Affected Documents --- To Be Provided Later Status --------------- To Be Provided Later Problem / Resolution --- To Be Provided Later Technical Resolution - ,
Milestones Original Current Actual Provide Milestones' dates for 03/85 - -
subtask issues necessary to resolve this issue.
As of First Quarter FY-86 1
(q GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number M Level Office /Div/Br Manager Tac No 121 Safety / Active-L1 RES/DRA0/RAMR M. R. Fleishman None High Title ---------------- Hydrogen Control for Large, Dry PWR Containments Work Authorization --- Memorandum to F. Gillespie from T. Speis dated September 26, 1985 Contract Title ------- None Contractor Name/
FIN No. ------------ None Work Scope ----------- Establish a technical position on the need for hydrogen control for LWRS with large, dry containments and make recommendations to the Commission regarding rulemaking.
Af fected Documents --- Possible new amendments to 10 CFR Part 50.44 Status --------------- At the Commission meeting on December 10, 1984 and in SECY-83-3578, the staff indicated that recommendations for rulemaking related to LWRs with large, dry containments f]'s
\
would be provided at the conclusion of ongoing research in mid-1986. Work has been proceeding'and staff meetings were held in November 1985 to review the progress. Current indi--
cations are that the various research tasks will be completed during the first half of calendar year 1986. It is expected that a recommendation can be made to the Commission during the mid-1986 time period.
Problem /Resciution ---
Technical Resolution -
Milestones Original Current Actual Research Complete 06/86 - -
Transmit Recommendations 08/86 - -
Issue Closeout Memorandum 09/86 - -
to NRR or Provide Milestone .c Necessary to Implement ;.
Recommendations p
As of First Quarter FY-86 l
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No A-29 Safety / Active-L1 NRR/DSI/ASB A. Singh 20465 Medium Title ---------------- Nuclear Power Plant Design for the Reduction of Vulnerability
'to Industrial Sabotage Work Authorization --- NRR FY84 Operating Plan, (Appendix G)
Contract Title ------- Evaluation of Methods for Reduction in Vulnerability to Sabotage Contractor Name/
FIN No. ------------ Pacific Northwe!,t Laboratory / FIN No. 82548 Brookhaven National Laboratory / FIN No. A-3767 i
Work Scope ----------- Generic Issue A-29 deals with the effectiveness of different nuclear power plant system designs to reduce the vulnerability to sabotage and tampering. Design changes to plant lay outs and systems, and damage-control ~ methods will be evaluated to determine the potential for reducing the vulnerability to p sabotage and tampering. The issue consists of two main tasks.
2 Task I will assess new plant designs to determine their
(- vulnerability to sabotage and tampering and assess the decrease in vulnerability which could be provided by alternatives identi-fied in previous research work. Task 2 includes all operating reactors and reactors under construction. The vulnerabilly of existing reactors will be characterized generically and possible alternatives for reduction of the vulnerability will be evaluated.
For both tasks, plant designs to both protect against and miti-gate the effects of sabotage and tampering will be considered.
The Auxiliary Systems Branch (ASB) will provide overall manage-ment of the program to resolve this generic issue. ASB will require the assistance of other NRR divisions (DL and DHFS) and other NRC offices (NMSS and RES). Additionally, ASB will utilize technical assistance contracts. The contractor will develop the methodology for quantifying the plant vulnerability to sabotage and tampering. The contractors will also develop the methodology for quantifying the relative reductions in vulnerability provided by various plant design changes or damage control measures.
Affected Documents --- Not Yet Determined
^
O As of First Quarter FY-86
's j
Generic Issue #A-29 Ststus --------------- Both BNL and PNL have obtained subcontractors and have started the methodology development. The anticipated completion dates are May 1985 for the methods and September 1985 for the final reports. PNL will analyze 25 design alternatives which have been forwarded to the lab. The BNL contract ended in September 1985. The PNL contract has been extended to December 1985.
Problem / Resolution --- AS8 resources for A-29 total 14 PSW for FY-85. Impacted OR actions and Casework will be completed on overtime, pending ongoing DSI management review of resources assigned to generic issues. By memo dated 2/11/85 a revised TAP was forwarded to cognizant NRR, NMSS and RES divisions that extended the comple-tion date for A-29 from FY1986 to FY1987. This extension is due to contractor delay and turnover in ASB staff. A memo providing more detailed justification for the schedule change and requesting Office Director approval is in preparation.
~Tcchnical Resolution - The approach for resolution of this issue is outlined below.
Details of the approach for resolution are contained in the Task Action Plan.
~
Milestones Original Current Actual TAP issues for comment - -
08/26/83 Final TAP Issued 01/84 -
01/14/84 C:ntractor Support
- a. Proposals Solicited 02/01/84 -
02/02/84
- b. Proposal Evaluated 03/84 -
08/27/84
- c. Contract Issued 04/84 -
08/27/84 Task 1 - Evaluate New Plant Designs 1.1 - Evaluate the vulnerability cf the standard plant designs to s:_b:tage and tampering
- a. Start Subtask 08/83 -
09/83
- b. Complete GESSAR II review 02/84 09/85 09/85
- c. Complete Westinghouse APWR 06/84 01/86 -
=
1.2 - Evaluate alternative designs (plcnt layouts and systems) for r;ducing the vulnerability to sib;tage and tamper rg 9
As of First Quarter FY-86
V Generic Issue #A-29 Milestones Original Current Actual
- a. ' Start 09/83 -
- b. Complete 09/83 06/84 10/85 12/85 1.3 - Review the foreign plant experiences and designs
- a. Start 01/84 -
09/84
- b. Complete 04/84 -
01/85
, 1.4 - Develop a decision rationale for ranking acceptance criteria
- a. Start 02/84 03/86 -
- b. Management review 04/84 07/86 -
- c. Complete 05/84 08/86 -
Task 2 - Evaluate Existing Plants 2.1 - Evaluate a sample of operating reactors to determine their vulner-ability to sabotage and tampering
- a. Start 04/84 11/85 11/85
- b. Complete 11/84 12/85 11/85 2.2 Evaluate alternative plant designs and damage control measures for reduc-ing the vulnerability to .
sabotage and tr.mpering
- a. Start' 09/84 11/85 11/85
- b. Complete 01/85 11/85 11/85 2.3-bevelopadecision rationale for ranking pro-posed changes
- a. Start 01/85 04/86 -
- b. Management review 03/85 05/86 -
- c. Complete 04/85 06/86 -
2.4 - Prepare a regulatory package h Value Impact Statement prepared 07/86 10/86 -
As of First Quarter FY-86
Generic Issue #A-29 Milestones Original Current Actual Final report prepared, CRGR 08/86 11/86 -
p:ckage approved by Director, DSI. Sent to DST, DL and cthers for comment Comments from other Division 09/86 01/87 -
Directors incorporated. Package s;nt to Director, NRR Package sent to CRGR and ACRS 10/86 03/87 -
completed Fcderal Register Notice of issuance 11/86 06/87 -
cf regulatory requirements for PWRs in this regard for public comments Public comments incorporated. OMB 01/87 09/87 -
clearance, if needed Final CRGR package to Director, NRR 03/87 12/87 -
R: view package to CRGR 04/87 01/88 -
CRGR review and EDO approval completed 05/87 02/88 -
Fcderal Register Notice of Issuance 07/87 04/88 -
cf regulatory requirements O
As of First Quarter FY-86
,,m
( ) GENERIC ISSUE MANAGEMENT CONTROL SYSTEM V
Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No A-30 Safety / Active-L1 NRR/DSI/PSB A. S. Gill 04587 High 20470 Title ---------------- Adequacy of Safety-Related DC Power Supplies Work Authorization --- NRR FY-84 Operating Plan (Appendix G)
Contract Title ------- None Contractor Name/
FIN No. ------------ None Work Scope ----------- The staff's initial study of the adequacy of DC power supplies was documented in NUREG-0305, " Technical Report on DC Power Supplies in Nuclear Power Plants," (July 1977). This study recommended the performance of a quantitative reliability assessment. This assessment was performed and documented in NUREG-0666, "A Probabilistic Safety Analysis of DC Power Supply Requirements for Nuclear Power Plants," (April 1981). With the aid of a technical assistance contract, the NUREG-0666 recom-A mendations are being converted into proposed requirements.
Affected Documents --- Issue information notice S ta t u s --------------- Implementation guidelines were developed and discussed with the ACRS on 03/82 and 09/82. A review meeting was held with the Director, NRR on 09/30/83 to go over the CRGR package.
As a result of this meeting, the Director, NRR requested that four additional issues be considered prior to transmitting the A-30 package to CRGR. It was anticipated that this new work would take approximately four months to complete. A revised' schedule was approved by the Director, DSI.
As a result of a meeting between INPO and the Director, DSI and the AD/ CPS on 12/14/83, NRC agreed to review current INPO efforts regarding DC power supply systems to determine the acceptability of this guidance to licensees in lieu of issuing separate A-30 requirements. NRC review resulted in determining that INPO guidance was not sufficient and that the A-30 CRGR package would go forward.
CRGR package sent to Director, NRR on 01/31/84. However, .
additional modifications were requested. Director, NRR ,
approval obtained on 03/08/84. As a result of this change, all follow-on milestones were changed by one month.
O As of First Quarter FY-86
Generic Issue #A-30 The CRGR met to review NRR recommendations on Generic Issue A-30 on 5/9/84. The CRGR requested that revisions be made to the cost / benefit section of the package. The cost / benefit revisions requested by CRGR involve performing a more detailed probabilistic risk assessment (PRA) instead of the single minimum DC power system of NUREG-0666 study. This additional work has been conducted by RRBR of RES, GIB of DST and PSB.
Because of key personnel turnover, RRBR was unable to complete this work as scheduled. Also, a peer review of the cost /
benefit analysis was added to ensure that it was consistent with NRC guidelines. The peer review of the revised draft cost / benefit package has been completed and comments sent to RRBR of RES on January 29, 1985. Because of key personnel turnover again, RR8R is unable to prepare the final cost /
benefit package as scheduled. The milestones for resolution of this generic issue will be revised when the final revised cost / benefit package is received from RES.
Problem / Resolution --- However, RRBR has not delivered the revised cost benefit pack-age as yet. RRBR has indicated a revised completion schedule of 12/31/85 for the Cost / Benefit package.
Tcchnical Resolution - NUREG-0666 presents the technical resolution of this generic issue.
Milestones Original Current Actual NRC Issue NUREG-0305. - '- 07/77 NRC Issue NUREG-0666. - -
04/81 Acceptance criteria and implemen- - -
02/83 tation guidelines prepared from NUREG-0666 recommendations are incorporated into SRP Section 8.3.
~
Technical resolution package for - -
02/28/83 CRGR review complete Division Director approval of 04/83 -
04/08/83 CRGR package. Package sent to DST & DL.
DST & DL comments incorporated. 05/83 07/83 08/12/83 __
Package sent to Director, NRR. ,
Package returned to incorporate - -
09/20/83 new tasks requested by Director, NRR.
O As of First Quarter FY-86
Generic Issue #A-30 h Milestones Original Current Actual Package sent to Director, NRR. -
01/84 01/31/84 Director NRR review complete. 06/83 02/84 03/08/84 Package sent to CRGR.
CRGR review complete. 07/83 04/84* 05/09/84 Transmitted memorandum to DST - -
09/07/84 and RES/RRA8 requesting con-currence on their input schedule. -
Memorandum to RES/RRAB requesting - -
04/27/85 completion date Second CRGR pkg cost / benefit -
12/85** -
revisions complete (RRBR)
NRR Divisions review complete -
02/86 -
Director NRR review complete -
03/86 -
~
Second package sent to CRGR -
04/86 -
Issue information notice to -
05/86 -
Ifcensees Second CRGR review complete - - -
ACRS review complete. 07/83 -
NA EDO approval. 09/83 -
NA
! FR Notice issued for public 09/83 -
NA l comment on proposed SRP Change.
OM8 Clearance, if applicable. 12/83 -
NA Division incorporation of public 12/83 -
NA comments.
Director, NRR review complete. 01/84 -
NA CRGR review complete. 02/84 -
NA '.
4
- *By Memorandum for T. Speis from R. Mattson dated April 24, 1984.
- Milestone Date and subsequent dates are based on receipt of the final value impact package for GI A-30 from RRBR/RES by end of the first quarter FY l U
As of First Quarter FY-86 L
Generic Issur #A-30 Milestones Original Current Actual EDO approval. 03/84 -
NA FR Notice of issuance of SRP 04/84 -
NA change.
O l
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4 O
As of First Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM v
Issue Issue Action Task Number Type _ Level Office /Div/Br Manager _ Tac No B-5 Safety / Active-L1 NRR/DE/SGEB S. B. Kim '07419 Medium Title ---------------- Buckling Behavior of Steel Containments Work Authorization --- NRR FY-84 Operating Plan, (Appendix G)
Contract Title ------- None Contractor Name/
FIN No. ------------ None Work Scope ----------- A containment structure is an asymmetrical shell due to large penetrations. The current staff position allows use of a symmetrical shell model for buckling strength evaluation. To compensate for the uncertainty in this symplifying assumption, the staff requires a reduction factor of 25% on buckling strength. However, there is no guidance given by the staff as to what constitutes proper reinforcing. There are widely varying methods used. A combined analytical experimental pro-gram is needed to address this problem.
O Affected Documents --- SRP 3ection revision.
Status --------------- Results from a technical assistance contract and input from RES were used to prepare a draft staff position. The staff previously planned to develop an SRP revision based on this position. It is now recognized that this position is not sufficiently complete for general use in licensing. Develop-ment of a technical resolution for this generic issue will require s mo basic research to be conducted. Research agreed to redirect related restarch on buckling and this research will form the basis for revising the SRP.
Preblem/ Resolution --- Because of budget reductions, the Buckling Research Program has been essentially terminated. This has resulted in a 6-month delay in obtaining the results needed to prepare the proposed SRP revision.
Technical Resolution -
Milestones Original Current Actual {
Results received from RES -
04/86 -
Proposed SRP re.zision prepared. 06/85 07/86 -
Value/ Impact Statement prepared. 07/95 12/86 -
As of First Quarter FY-86
Generic Issue #B-5 Milestones Original Current Actual Final CRGR package forwarded to 09/85 01/87 -
DST for processing.
NRR Director Review completed. 10/85 04/87 -
Review Package to CRGR. 11/85 05/87 -
CRGR review completed. 12/85 06/87 -
EDO approval. 01/86 06/87 -
Federal Register Notice of 02/86 07/87 -
Issuance of Proposed SRP Raised for Public Comment.
OM8 Clearance, if applicable. 03/86 08/87 -
Division review of public 05/86 10/87 -
comments completed.
NRR Director review completed. 06/86 12/87 -
CRGR review completed. 07/86 01/88 -
EDO approval. 08/86 02/88 -
Federal Register Notice of 09/86 03/88 -
Issuance of SRP T
O As of First Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM b
Issue Issue Action Task Number Type Level Office /Div/8r Manager Tac No B-6 Safety / Active-L1 NRR/DE/MEB 5. Hou 20179 High Title ---------------- Loads, Load Combinatiors, Stress Limits Work Authorization --- NRR FY-84 Operating Plan (Appendix G)
Contract Title ------- None Contractor Name/
FIN No. ------------ None Work Scope ----------- This generic issue is complete except for decoupling the LOCA and SSE events. The decoupling involves developing a more rational approach to the design of components and supports to withstand a spectrum of events, and events in combination, the effects of low probability postulated events of varying proba-bilities, such as SSE plus LOCA, this plan will proceed with the necessary action to decouple the SSE-LOCA load combinations using probabilistic methods. One possible alternative approach is to reduce the postulated pipe break area using deterministic (g) fracture mechanics procedures.
V Affected Documents --- SRP 3.9.3.
Status --------------- An on-going research program for Westinghouse and CE plants has completed the investigation of'the probability of having a LOCA induced directly by seismic loads, and found it to be 7 X 10 12f year for the large LOCA and 4 X 10 12/ year for the small LOCA.
Probability to have LOCA induced indirectly by structure or sup-port failures under seismic loads was found to be 10 7/ year.
Research results and decoupling hypothesis were discussed in ACRS meetings on 03/29/83 and 06/09/83. At these meetings, the staff proposed a position which would decouple SSE and LOCA for all PWR primary loops based on the results of the research pro-gram. The ACRS letter of 06/14/83 concludes that the technical work supports decoupling for mechanical components, which in-clude instrumentation and controls, and their supports. Simi-lar research work for decoupling of LOCA and SSE for B&W and GE plants is proceeding and is expected to conclude in early 1986, Preliminary indications are that pipe rupture probabilities in GE reactor coolant loops are substantially greater than in any .4 of the PWR vendors. In addition, a separate CRGR package on a t limited application of the leak-before-break hypothesis for PWR main coolant loops in 16 Westinghouse owners group plants based on deterministic fracture mechanics analysis has been approved under Generic Letter 84-04 issued by DL.
O t
As of First Quarter FY-86
Generic Issue #8-6 Problem / Resolution --- Revisions of SRP 3.9.3 is being performed by RES in accordance with the " Plan to Implement the PRC Recommendations." This revision will only permit decoupling of SSE and LOCA for PWRs.
A recommendation regarding decoupling for BWRs will be made by RES at the conclusion of the research study on GE plants. If this recommendation indicates that decoupling on certain classes of BWRs should be permitted by the SRP, the milestone schedule will have to be revised.
RES has stated that the contractors regulatory analysis will not be provided until March 1986. Milestone dates for resolu-tion have slipped 3 months.
TCchnical Resolution - For decoupling of SSE & LOCA loads, the probability of a LOCA occurrence due to an earthquake was under review to provide the probabilistic technical basis for the revision of SRP 3.9.3.
In addition, a parallel effort has been proceeded to utilize the results of the on going leak-before-break studies to justify deterministically the reduction of the postulated pipe break area. The technical resolution has been identified.
The NRC Piping Review Committee evaluated all the research re-sults and provided recommendations on needed regulatory actions on licensing requirement changes as a part of an overall resolu-tion to nuclear piping design problems. At request of the Committee, ELD has confirmed that change to GDC 2 is not required.
Milestones- Original Current Actual Issued NUREG-0484 which contain - -
05/80 guideline or dynamic response combination methodology.
Revised SRP Section 3.9.3 to - -
07/81 incorporate criteria and guide-lines for load combination's and stress limits.
ACRS subcommittee on leak before - -
03/29/83 break and decoupling.
ACRS full Committee meeting 05/83 -
06/09/83 Piping Review Committee to -
02/85 02/85 provide recommendation for decoupling.
Confirmation from ELD that -
04/85 04/85 change to GDC 2 not required.
As of First Quarter FY-86
_ ._. . _ _ - - . - - . _ - . - = - - . .. , _ - . _ .
M t
Generic Issue #B-6
(
1 Milestones Original Current Actual Piping review committee final - -
5/85
- report containing recommenda-
, tions for decoupling, issued
- to EDO.
Completion of draft SRP 3.9.3 - -
09/85 revision Completion of regulatory -
03/86 -
analysis for SRP 3.9.3 revision
! CRGR review -
04/86 -
Publication of Federal Register -
05/86 -
Notice
! Public comment period closes -
07/86 -
1
- Evaluation of public comments -
09/86 -
completed i
CRGR review of revised -
11/86 -
regulatory package completed l
EDO approval -
12/86 -
Final Federal Register Notice -
01/87 -
j of Issuance of SRP revision i
1 l
k l
t 4
I I
4 As of First Quarter FY-86 1
...vn,-------n------.. _,_,n.,,_,,_,,-,,___ ,, _ . , _ , , , _ . . . , _ - . . . . . - _ _ , , _ - - - - - , - - - - - . - -
l
( ) GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Tyge, Level Office /Div/Dr Manager Tac No B-17 Safety / Active-L1 NRR/DHFT/HFIB 180 TBD Medium Criteria for Safety Related Operator Actions 3
Title ----------------
i Work Authorization --- NRR FY-84 Operating Plan (Appendix G) l Contract Title ------- To Be Determined Contractor Name/ '
, FIN No. ------------ To Be Determined Work Scope ----------- The work scope and milestones necessary to complete this are provided in HF-01 issue HFPP-4.3.
4.
Affected Documents --- To Be Provided Later i g Status --------------- To Be Provided Later 4
N Problem / Resolution --- To Be Provided Later Technical Resolution -
i Milestones Original Current Actual Milestone necessary to complete this issue are provided in HF-01 issue HFPP-4.3.
i i
i 3
I i
As of First Quarter FY-86 i
O GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No 8-55 Safety / Active-L1 NRR/DE/MEB F. Cherny 48771 Medium Title ---------------- Improve Reliability of Target Rock Safety-Relief Valves Work Authorization --- NRR FY-84 Operating Plan, (Appendix G)-
Contract Title ------- None Contractor Name/
FIN No. ------------ None -
Work Scope ----------- Review BWR utility approaches to increasing SRV reliability to obtain sufficient data base to support the conclusion that-this issue has been solved. The utility approaches may include:
(1) demonstrating sufficient reliability of 3-stage valves by strict conformance to NSSS vendor instructions; (2) demon-strating sufficient reliability of 2-stage valves after design and/or system modifications, and (3) using different valves and demonstrating their reliability.
g Affected Documents --- None Status --------------- A report was submitted by the Owners Group (OG) in June 1984 that was expected to resolve the issue. A subsequent Boston Edison report on experience at Pilgrim indicated that the recommendations of the OG report were not sufficient to resolve this issue. The OG has recognized the need to pursue this problem further and will be evaluating new materials which can eliminate excessive setpoint drift. They have assembled a material selection panel composed of experts in both materials technology and nuclear valve design. Selected materials will be tested in several plants during upcoming fuel cycles. The results of this effort will be evaluated by the OG over about a two year period.
Problem / Resolution --- The resolution of this issue is aimed at increasing the relia-bility of these valves to meet the current plant Technical Specifications. Selected materials will be tested in certain plants with the objective of eliminating excessive setpoint drift. The actions taken thus far by the OG and the OG pro-gram are responsive to the issue. We expect that this issue will be resolved with minimum staff effort needed only to moni- ;._
tor their program. We will work with the OG and provide them g with our evaluation of their program and indicate our intent to rely on their program to resolve the issue. A generic issue close-out memorandum will reflect this understanding. At the completion of the OG program, which is not. expected until 1987, As of First Quarter FY-86
Generic Issue #B-55 the staff will review the industry resolution. NRR will esta-blish a new generic issue only if the resolution is inadequate or if not implemented properly by the utilities involved.
Technical Resolution -
Milestones Original Current Actual Meeting with BWR Owners 12/83 -
Setpoint Drift Committee 11/83 BWR Owners Report submitted 07/84 -
06/84 Boston Edison Report submitted - -
08/84 Completion of HRR evaluation of 10/84 -
Owners Group and Boston Edison 10/84 reports Communication to OG re: NRC - -
03/85 comments / concerns.
OG presentation to the staff -
10/85 10/85 Staff receives Owners' program -
10/85 10/85 for eliminating set point drift Owners begin to install new -
01/86 -
pilot disks to test in plant for one fuel cycle Issue close-out memorandum -
12/85* -
CR: solution for this issue is being reevaluated based on controversial SRU test data recently reported (January 9, 1986) by Brunswick 2.
L.
O As of First Quarter FY-86
O
\ GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action
-Number Task Type, Level Office /Div/Br Manager Tac No B-56 Safety / Active-L1 NRR/DSI/PS8 0. Chopra .49942 High Title ---------------- Diesel Reliability Work Authorization --- NRR FY-83 Operating Plan (Appendix G).
Contract Title ------- Review of Licensees responses to proposed staff actions to improve and maintain diesel generator reliability Contractor Name/
FIN No. ------------
Brookhaven National Laboratory / FIN No. A-3817 Work Scope ----------- In September 1983, DSI and DST coordinated the technical approaches to the resolution of Generic Issue 8-56 (Diesel Generator Reliability) and USI A-44 (Station Blackout).
Actions under 8-56 will include sending a 50.54(f) letter to all operating reactor licensees. This letter contains the following three items:
1.- Presents the staff's approach for reducing the number of cold fast start surveillance tests.
- 2. Requests licensees submit current diesel generator reliability data.
- 3. Requests Ifcensees submit a description of their diesel generator reliability program, if any, and provides example performance technical specifications for diesel generator reliability.
Responses from all licensees have been evaluated. Due to lack of adequate responses from the licensees regarding item #1 above, the staff met with the industry representatives including licensees, DG manufacturers and NSAC to discuss diesel generator testing. Additionally extensive comments '
have been received from ACRS, EPRI and DG manufacturers regarding DG testing. PS8 will provide overall management of the program to resolve this generic issue. PS8 will utilize technical assistance contracts. The contractor will review and assess all comments on DG testing. The staff will use contractors comments relating to enhancement of diesel _.
generator reliability in the revisions to RG 1.108 and STS. -
Affected Documents --- Standard Technical Specifications RG 1.108 (as a long-term effort associated with the final resolution of USI A-44).
As of First Quarter FY-86
Generic Issue #B-56 Status ---------------
Major revision made to scope.and schedule in September 1983 as a result of new direction requested by CRGR.
CRGR review of Package for Generic Issue B-56 complete 5/8/84.
DSI has transmitted a memo to DL transmitting 50.54(f) letter and recommending issuance to licensees.
A generic letter 84-15 was sent out to all licensees on July 2, 1984.
MPA "D19" has been established to resolve item #1 of the generic letter. For item #3, of the generic issue, a technical assistanca contract with BNL has been established.
BNL will review and assess licensee responses to this item and industry comments regarding DG reliability. This effort will be completed by January 1986.
Pr:blem/ Resolution --- Responses from all of the licensees to generic letter 84-15 have been evaluated. Responses to item #1 of the generic letter were inadequate. This required adjustment of the B-56 schedule. The staff met with industry groups, diesel generator manufacturers to implement item and#1.some utilities to determine their reluctance MPA "D19" has been established to re-solve item #1. Additionally, PSB has established a technical assistance contract with BNL to review and assess licensee re-sponses to item #3 of the generic letter and industry comments.
PSB will use this information in the revisions to RG 1.108 and standard technical specifications. Schedule was expanded by 8 months to incorporate the CRGR review process for the technical resolution of this issue.
Tcchnical Resolution -
Milestones Original Current Actual Technical resolution identified. - -
02/03/83 Director, DSI approval of 02/83 -
02/03/83 CRGR package. Sent to DL and DST for comments.
DST and DL comments 04/83 -
03/28/83 incorporated. Package sent to Director, NRR. --
Director, NRR review complete. 05/83 07/83 07/01/83 Package sent to CRGR.
CRGR review complete. 06/83 07/83 07/27/83 O
As of First Quarter FY-86
l
. 1 Generic Issue #B-56 O !
1 Milestones Original Current Actual Scope of issue modified to - -
09/27/83 coordinate technical resolution of B-56 with USI A-44 Scope of issue modified to - -
11/14/83 consider number of cold fast start surveillance tests.
Letter issued to licensees - -
12/16/83 requesting voluntary inforination on actual fast start testing.
Coordinated GI 8-56 and 02/84 -
01/24/84 USI A-44 CRGR package sent to Director, NRR.
Director, NRR review complete. 04/84 -
03/06/84 Package sent to CRGR.
CRGR review complete. 05/84 -
05/08/84 Issue 50.54(f) generic letter 06/84 -
07/02/84 (84-15) to licensees request-ing information discussed under work scope above.
Close of 90 day comment 09/84 10/84 11/01/84 period.
Staff meets with industry -
05/85 05/85 groups, et al.
Issued technical assistance -
06/85 06/20/85 contract to BNL 1
l BNLs analysis of licensee -
01/86 -
! response to 50.54(f) letter l .and industry comments Publish BNL report- -
02/86 -
a Final technical resolution to -
08/86 -
- divisions for comment l
CRGR package to Director, NRR -
09/86 -
V As of First Quarter FY-86
Generic Issue #8-56 Milestones Original Current Actual CRGR review complete -
11/86 -
EDG reliability program implemented - 01/87 -
into final USI A-44 resolution O
i l
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O I
As of First Quarter FY-86 l
L
/~x GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
(
Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No 8-61 Safety / Active-L1 -NRR/ DST /RRA8 E. Chow 52715 Medium
- T i tl e ---------------- Allowable ECCS Equipment Outage Periods Work Authorization --- NRR FY-84 Operating Plan (Appendix G)
Contract Title ------- To Be Determined Contractor Name/
FIN No. ------------ To Be Determined Work Scope ----------- In general, plants will be classified such that in each class, similar ECCS outage unavailabilities will have similar impacts on risk. The effect of a given ECCS availability on risk will be determined, for each class of plant, as well as the impacts of any changes in allowable ECCS outage period. Consideration of' support system outages must be included. Details of the work scope are contained in the draft action plan.
Affected Documents --- Technical Specification changes are possible.
U Status --------------- Task I has been completed.
Problem / Resolution --- Because of the RES workload in support of TPIP, Task II will be completed by the end of June 1986.
Technical Resolution -
Milestones Original Current Actual Draft Task Action Plan 01/84 -
01/30/84 issued for DD approval Coordinate Technical Resolution 04/84 07/84 08/21/84 with RES complete.
Task Action Plan approved Oi,/84 08/84 07/25/84 by Division Director Task I-Methodology Review and 11/84 04/85 04/30/85 development completed Task II-Apply to a PWR or BWR 02/85 06/86 -
Apply Methodology to a 08/85 02/87 -
Selection of Plants As of First Quarter FY-86
Generic Issue #8-61 Milestones Original Current Actual Develop a Licensing Position Develop an Initial 03/86 03/87 -
Recommendation for Staff Comments Final Technical Resolution 04/86 04/87 -
Prepare CRGR Package 06/86 07/87 -
Review of CRGR Package 07/86 08/87 -
by Division Directors NRR Director Review 08/86 09/87 -
Complete Review Package to CRGR CRGR Review and EDO 09/86 10/87 -
Approval Completed Issuance of Federal 11/86 11/87 -
Register Notice for Public Comment Sixty Day Comment Period 01/87 01/88 -
Ends Division Review of Public 02/87 02/88 -
Comments Completed, and final CRGR package completed NRR Review of CRGR package 04/87 03/88 -
completed (Division Review and NRR Director Review)
CRGR Review and EDO Approval 05/87 04/88 -
Completed Issuance of Proposed Changes 07/87 05/88 -
to Technical Specifications R;sturces Needed to Complete Projects FY-84 FY-85 FY-86 TA$ $50K $50K $50K [
PSY .5 .5 .5 O
As of First Quarter FY-86
l v) GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No B-64 Safety / Active-L1 NRR/DE/CMEB F. Witt 04765 NR RES/DET/CMEB K. Steyer Title ---------------- Decommissioning of Reactors Work Authorization --- NRR FY-84 operating Plan, (Appendix G).
Contract Title ------- Decontamination and Decommissioning Review Contractor Name/
FIN No. ------------ PNL/B-2342 Work Scope ----------- Develop a general decommissioning policy, prepare the atten-dent changes in regulations, develop the detailed information needed for use in licensing decisions for decommissioning, and establish guidance for facilitation of decommissioning.
Affected Documents --- 1. 10 CFR Part 50 and 51 amendments,
- 2. Regulatory Guide 1.86 revision, o
(d) 3, New regulatory guides on financial assurance, termination surveys and format and content for nuclear reactor decommissioning plans,
- 4. New standard review plan for decommissioning review.
Status --------------- Draft rule changes and other package material is targeted'for completion in September.
Problem / Resolution --- The schedule was previously slipped to accommodate the anti-cipated date of RES input. Schedule still dependent on RES input (see note below).
Technical Resolution - Published rule cFanges on decommissioning, issue new regula-tory guides and revision to R.G. 1.86, issue new standard review plan on decommissioning.
Milestones Original Current Actual CRGR review completed on - -
08/08/84 decommissioning rule (Research)
EDO approval of decommissioning - - -
09/07/84 SECY-84-354 (Research) 0
(
As of First Quarter FY-86
Generic Issue #8-64 Milestones Original Current At.ual Commission Approval of -
12/84 12/84 SECY-84-354 (Research)
Issuance of draft rule -
02/85 02/11/85 change for public comment Format and Content for Decommis- 02/84* 06/85 06/85 sioning Plans (from Research)
Issue Decommissioning Rule Extended public comment period -
07/85 07/12/85 complete Revised draft rule incorporating 02/86 10/86 -
public comments ready for RES management review Revised draft rules incorporating 08/86 06/87 -
public comments reviewed and approved by CRGR Final rules noticed in the 01/87** 10/87 -
Federal Register Revised and Issue SRP Section Draft SRP issued for staff comment - -
06/25/85 Issue transfer memo to RES -
02/86 -
SRP revision package to Div. 06/84 09/86**" -
Director for review NRR Director Review completed 07/84 10/86 -
Review Package to CRGR 08/84 11,86 -
r0riginal milestone dates necessary to resolve this issue were based on the receipt cf input on format and content for Decommissicning Plan from RES.
CCMilestone dates for issuance of final decommissioning rule and a proposed new SRP Z
^
s:ction are being processed concurrently. Schedule slippage that occurs in issuing the final rule will be reflected in the SRP issuance schedule.
^^ Milestone dates necessary to issue Decommissioning SRP will be incorporated into the SRPCS when Final Rule is issued.
O As of First Quarter FY-86 i
M Generic Issue #B-64 !
]
q l I Milestones Original Current Actual CRGR review completed 09/84 11/86 -
EDO approval 09/84 11/86 -
i Federal Register Notice of 10/84 12/86 -
l Issuance of. proposed RG and SRP j for Public Comment >
j OMB Clearance, if applicable 01/85 12/86 -
1 Division review of public 01/85 03/87 -
! comments completed ,
i j.
NRR Director review completed 02/85 04/87 -
CRGR review completed 03/85 05/87 -
P EDO approval 03/85 05/87 -
l Federal Register Notice of 04/85 06/87 -
Issuance ~of SRP l \s.
! l i
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4 As of First Quarter FY-86
i l
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM (V)
Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No C-8 Safety / Active-L1 NRR/DSI/AS8 J. Ridgely 51476 High Title ---------------- Main Steam Line Leakage Control (BWR)
Work Authorization --- NRR FY-84 Operating Plan (Appendix G).
Contract Title ------- MSIV Leakage and LCS Failure Contractor Name/
FIN No. ------------ Pacific Northwest Laboratories / FIN No. B-2529 Work Scope ----------- Review MSIV leakage and LCS failures with respect to plant maintenance and operating practices and equipment design and orientation. Provide an assessment of the realistic offsite doses using the LCS versus the normal steam path under LOCA
' conditions. The evaluation of this issue will also include utilities' efforts to reduce MSIV leakage and LCS failures.
Realistic calculation of offsite dose consequences arising from MSIV leakage following severe accidents involving sub-
[a tantial core damage will be performed. Realistic source terms V) for such accidents are not expected to be used in the evalua-tion of the risk associated with MSIV leakage and various con-trol options as new research informat, ion is not expected to yield updated interim source terms until June 1986. Assess-ments of risk through existing MSIVLCS, and for cost / benefit analysis of alternative fixes, will use the interim source term information. Maintenance and Design Improvements -
industry ~ approach and other alternatives to maintenance will be considered for all BWR MSIV's. However, the results of TVA's efforts are not yet available for evaluation of alterna-tives. Alternative maintenance and design changes are to be considered. Coordination with industry - BWRs utilize MSIV and LCS designs made by different manufacturers. In addition, the BWR standard plant application (GESSAR II) contains an alternative to many contemporary BWR LCS designs, a positive vacuum system which would force MSIV leakage into the contain-ment. Because of the differences in design and component manufacturers, no single solution for all plants is likely.
Because of this diversity the staf.f will seek a working relationship with industry (i.e., the BWR owners group) to solicit suggestions on improved traintenance and/or design. 7 Other offices and Divisions invcived in resolving this issue include NRR/DE/MEB, NRR/ DST /SPEE , NRR/DSI/AEB, NRR/DE/SGEB, and NRR/DL/SSPB.
As of First Quarter FY-86
Generic Issue #C-8 Affected Documents --- Issue NUREG-(to be determined).
Revise and Issue Regulatory Guide 1.5 (To be determined)
Revise and Issue SRP Change to Section 6.7 and 15.6.4 (To be determined).
Revise and Process Plant Specific and STS Changes (To be determined).
S ta t u s --------------- On 02/23/84, the BWR Owner's Group (BWROG) Committee on MSIV Leakage Control made a presentation to the staff on their review and recommendations concerning leakage through the MSIVs. The principal purpose of the meeting was to discuss the efforts of the Committee concerning data collection, evaluation, assessment, recommendations, and the effects of the recommendations.
Peach Bottom 2 has recer.tly tested the MSIVs after one cycle of operation using the BWROG recommendations. Seven out of eight MSIVs had leakage less than 11.5 SCFH and the eighth valve had a leakage rate of 14 SCFH.
The BWROG Committee proposed a method for all BWRs to imple-ment their recommendations. The Owners Group made a formal submittal to the staff.
The final NUREG on this issue will be published in January 1956. The CRGR package will then be prepared and submitted for approval.
Pr:blem/ Resolution --- Permission to incorporate the Owners Group material into the NUREG has been requested. PNL has issued a draft TER for comments. The staff has approved the contractor's model for filling, deposition and release processes in BWR steam lines under leaking MSIV conditions. PNL is currently running the dose / release calculations. PNL has submitted a revised schedule which maintains the final completion date. PNL has been retained as a consultant from the issuance of the NUREG until final resolution by the Commission.
Tcchnical Resolution - The CRGP package due January 1986 will not be completed until April 1986. Milestone dates for resolution have slipped 3 months.
Milestones Original Current Actual Task Action Plan approved by 10/83 -
10/31/83 Director, OSI. .}.~
Complete Task 4 (Develop 03/84 04/18/84 minimum design "iteria for alternative equipment for LOCA mitigation).
As of First Quarter FY-86
Generic Issue #C-8 Milestones Original Current Actual Received Initial BWROG Submittal -
04/09/84 Revised Work Plan based on - -
Submittal 05/25/84 Revised Work Plan Approved by DD - -
06/01/84 Revised request for Technical - -
Assistance to D0 for approval 06/15/84 Revised TA request Approved -
08/84 by 00 07/03/84 Complete Task 1 (Literature 08/84 -
search) 08/15/84 Complete Task 2 (Review BWROG 09/84 07/85 06/14/85 recommendations)
Review PNL model for filling, -
07/85 08/09/85 deposition and release processes
[ fn BWR steam ifnes under leaking MSIV conditions.
(
Complete Task 3 (Effectiveness 10/84 10/85 11/85 of BWROG reconnendations) ,
Complete Task 6 (Perform PRA 11/84 10/85 11/85 study of dif.'erent alternatives).
Complete Task 5 (Perform 03/85 10/85 11/35 (1) baseline offsite dose cal-culations, (2) thermal hydraulic modeling, and (3) alternate off-site dose calculations to deter-mine the effects of a LOCA and to determine maximum leakage rate within Part 100 for most favorable method).
Complete Task 7 (Review of -
10/85 11/85 compartment contamination) w Complete NUREG/CR 12/85 02/86 -
- 0 raft NUREG issued. Staff comments have been provided to PNL. Awaiting camera copy of NUREG for publication.
O As of First Quarter FY 86
-e- - - - ,o
I i
Generic Issue #C-8 Milestones Original Current Actual CRGR package approved by 01/86 04/86 -
Director DSI. Sent to Division Directors for comment.
Comments incorporated. CRGR 02/86 05/86 -
package sent to Director, NRR.
Director, NRR review complete. 03/86 06/86 -
Package sent to CRGR.
CRGR review complete. 04/86 07/86 -
ACRS review complete. 04/86 07/86 -
EDO approval. 05/86 08/86 -
Federal Register Notice 05/86 08/86 -
issued for public comment.
OM8 Clearance 09/86 12/86 -
Incorporation of comments. 09/86 12/86 -
Package sent to Director, NRR.
Director, NRR review complete. 10/86 01/87 -
Package sent to CRGR.
CRGR review complete. 11/86 02/87 -
E00 approval. 12/86 03/87 -
Federal Register Notice issued. 12/86 03/87 -
E.:
O As of First Quarter FY-86
I O GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Tyge_ Level Office /Div/Br Manager Tac No I.A.2.6 Safety / Active-L1 NRR/DHFT/MT8 J. Persensky None Subtask 1 High Title ---------------- Revise Regulatory Guide 1.8
}
J Work Authorization --- TMI Task Action Plan se.
j Contract Title ------- None l Contractor Name/
FIN No. ------------ None Work Scope ----------- The work scope and milestones necessary to complete this issue are provided in HF-01 issues HFPP-1.2.
Affected Documents --- Same as above Status --------------- Same as above Problem / Resolution --- Same as above Technical Resolution -
Milestones Original Current Actual Milestones necessary to complete this issue are provided in HF-01 issue NFPP-1.2.
1 r
d I
f i
I
. 7 As of First Quarter FY-86 J
l t--,----w,,-.-n ..-----_.ym-,-.._,.v-.,----,,--------,-.+-i..-~~-~w-,-._ ---**,.-.-==,-.+---'-r=-v- +ew-r- e---+ - - - - - ' -
( GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number e
_Typ_e, Level Office /Div/Br Manager Tac No I.A.3.3 Safety / Active-L1 RES/0RA0/HFSB T. G. Ryan None High Title ---------------- Requirements for Operator Fitness Work Authorization --- TMI Task Action Plan Contract Title ------- None Contractor Name/
FIN No. ------------ None Work Scope ----------- A rule (amending 10 CFR 50.54) is being promulgated requiring licensees with an operating license for a nuclear power unit issued under 10 CFR 50.21(b) or 50.22 to establish and imple-ment written procedures designed to provide reasonable assurance that personnel with access to nuclear power plants are not under the influence of alcohol, other drugs or otherwise unfit for duty.
Affected Documents --- Issue policy statement.
V Status --------------- On October 24, 1984, the Commission notified the staff that it would not promulgate a rule on fitness for duty for a minimum of two years, but would issue a policy statement on the subject (M841017). A proposed policy statement was submitted to the Commission on January 17, 1985, as SECY C5-21. In a separate action, a notice withdrawing the final fitness for duty rule submitted to the Commission on April 12, 1985, as SECY 85-21A.
The proposed policy statement (SECY 85-21) was reaffirmed by the staff in SECY 85-128 submitted to the Commission on August 26, 1985. SECYs 85-21, 21A, and 218 are being reviewed by the Commission for concurrence and publication, as appropri-ate in the Federal Register on, or about, 1 February 1986.
Technical Resolution ---
Milstones for Fitness for Duty Rule:
Milestones Original Current Actual Issue Draft Rule for Public - -
08/82 _.
Comment .
Complete Division Review - -
03/83 Complete Office Concurrence 04/83 -
06/83 O
As of First Quarter FY-86
iT I)
Generic Issue #I.A.3.3 Milestones Original Current Actual o
Complete CRGR Review 05/83 -
07/29/83 Complete ACRS Review 05/83 -
08/05/83 Complete Commission Review 06/83
- 10/24/85 Issue Final Rule Federal 07/83 * -
Register Notice Issue Final Rule 07/83 * -
Policy statement, SECY 85-21 - -
01/17/85 submitted to Commission for approval Withdrawal Notice, SECY 85-21A - -
04/12/85 submitted to Commission for approval Reaffrimation of policy statement - -
08/26/85 SECY 85-218, submitted to the Commission Commission approved policy -
02/86 -
statement and withdrawal notice Issue Federal Register Notice -
07/86 -
t:ithdrawing fitness rule Publish Policy Statement -
02/86 -
Issue close-out memorandum -
03/86 -
to EDO CFinal Rule will not be issued based on Commission discussion. Milettone dates necessary to complete this issue are dependent upon issuance of ( Policy Staten,ent appr;ved by the Commission and withdrawal notice for fitness for duty .ute.
O As of First Quarter FY-86
[m\ GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number h Level Office /Div/Br Manaaer Tac No I.A.4.2 Safety / Active-L1 NRR/0HFT/0LB TBP None Subtask 1 High Title ---------------- Research on Training Simulators Work Authorization --- TMI Task Action Plan Contract Title ------- Simulator Experiments Contractor Name/
FIN No. ------------ Oak Ridge National Laboratory /8-0821 Work Scope ----------- This project will use experiments on nuclear power plant training simulators supported by field data collection to pro-vide a data base of operator performance to address issues associated with the operational safety of nuclear power plants. On the basis of the data obtained, conclusions re-garding these issues can be made along with recommendations for considerations as regulatory guidance.
Affected Documents --- To Be Provided Later
( Status --------------- First Experiment on BWR Plant completed and draft report received. PWR Experiment is now underway.
Problem / Resolution --- None Technical Resolution -
Milestones Oriainal Current Actual Develop FY83 Research Plan 05/83 -
06/83 Conduct FY83 Experiment 05/83 -
09/83 Develop FY84 Research Plan 02/84 04/84 04/84 Prepare Report 09/84 01/83 -
Conduct FY84 Experiments -
12/84 12/84 Prepare FY84 Letter Report -
01/86 -
Prepare FY84 Simulator -
01/86 -
Experiment Report Issue Close-out memorandum to EDO -
03/86 -
As of First Quarter FY-86 I
[
\
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number h Level Office /Div/Br Manager Tac No I.A.4.2 Safety / Active-L1 NRR/0HFT/0LB B. Boger 42454 Subtask 4 High Title ---------------- Review Simulators for Conforman:e to Criteria Work Authorization --- TMI Task Action Plan Contract Title ------- None Contractor Name/
FIN No. ------------ None Work Scope ----------- The work scope and milestones necessary to complete this issue are provided in HF-01 issue HFPP-3.3.
Affected Documents --- Same as above Status --------------- Same as above Problem / Resolution --- Same as above
, Technical Resolution -
Milestones Original Current Actual Milestones necessary to complete this issue are provided in HF-01 issue HFPP-3.3.
. W.
O v
As of first Quarter FY-86
() GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Tyge_ Level Office /Div/Br Manager Tac No I . 8.1.1 Safety / Active-L1 NRR/0HFT/HFIB TBP None (1 - 4) Medium Title ---------------- Organization and Management of Long Ters Improvements Work Authorization --- TMI Task Action Plan Contract Title ------- None Contractor Name/
FIN No. ------------ None Work Scope ----------- The work scope and milestones necessary to complete this issue are provided in HF-01 issues HFPP 6.1 and 6.3.
Affected Documents --- Same as above Status --------------- Same as above Problem / Resolution --- Same as above Technical Resolution -
Milestones Original Current Actual Milestones necessary to complete this issue are provided in HF-01 issues HFPP 6.1 and 6.3.
\ As of First Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number h Level Of fice/Div/Br Manager Tac No I . 8.1.1 Safety / Subsumed IE/0QAVT/QA8 M. Malloy None Subtasks Medium NRR/DHFS/LQB 6&7 Title ---------------- Prepare and Issue a Revision to Regulatory Guides 3.33 and 1.8 Work Authorization --- TMI Task Action Plan Contract Title ------- None Contractor Name/
FIN No. ------------ None Work Scope ----------- Regulatory Guide 1.33 - QAVT/QA8 will revise and issue a change to the guidelines contained in this Guide. GI #75 subsumed the issue, and information pertaining to the changes in the guide-lines is now included in G! #75, Subtask 1.
Regul6 tory Guide 1.8 - HFS8 will revise and issue a change to the guidelines contained in R.G. 1.8 concurrent with the work scope of HF-01 issues HFPP-1.2 and 3.4.
\ Affected Documents --- Regulatory Guides 1.33 and 1.8 Status --------------- Refer to GI #75 subtask 1 and HF-01 issues HFPP-1.2 and 3.4 for Status.
Problem / Resolution --- None Technical Resolution -
Milestones Oriainal Current Actual Regulatory Guide 1.8 Refer to HF-01 issues HFPP-1.2 - - -
and 3.4 schedule for issuing a revision to Reg. Guide 1.8.
Reaulatory Guide 1.33 Refer to GI #75(1) - - -
schedule for issuing a _
revision to Reg. Guide 1.33*
- By memorandum from R. DeYoung for W. Dircks dated July 26, 1984, milestones necessary to complete Task Item I 8.1.1 Subtasks 6 and 7, have been subsumed by milestones for O, Generic Issue No. 75 subtask 1.
As of First Quarter FY-86
( GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Tyge_ Level Office /Div/Br Manager Tac No I.C.9 Safety / Active-L1 NRR/0HFT/HFIB TBP 43505 Medium Title ---------------- Long-Term Program for Upgrading of Procedures Work Authorization --- TMI Task Action Plan ontract Title ------- P-1 Development of Guidelines for Upgrading Maintenance Procedures P-2 Development of Guidelines for Upgrading Operating Procedures Contractor Name/
FIN No. ------------ Battelle Pacific Northwest Laboratories (PNL)/8-2360 Work Scope ----------- The work scope and milestones necessary to complete this issue are provided in HF-01 issues HFPP-4.2 and 4.4 and HF-02.
Affected Documents --- Same as above
(
\,
Status --------------- Same as above Problem / Resolution --- Same as above Technical Resolution -
Milestones Original Current Actual Milestones necessary to complete this issue are provided in HF-01 issues HFPP-4.2 and 4.4 and HF-02.
s- -
As of First Quarter FY 86
( GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number h Level Office /Div/Br Manager Tac No I.D.3 Safety / Active-L1 RES/DET/EEIC8 8. Morris 41030 Medium Title ---------------- Safety System Status Monitoring Work Authorization --- TMI Task Action Plan Contract Title ------- Verification, System Status, Automatic vs Manual Contractor Name/
FIN No. ------------ Pacific Northwest Laboratories /8-2360 Work Scope ----------- PNL has reviewed the effectiveness of systtas and procedures related to safety system status monitoring and has recommended a regulatory position on this issue. PNL findings indicate that a revision of R.G.1.47 is necessary, and further, that this new revision should be applied to all plants. Based on the PNL recommendations OHFS has transfered responsibility for this issue to the Office of Research (revise R.G. 1.47).
Responsibility for issue transferred back to NRR.
(d Affected Documents ---
Status ---------------
Revision to R.G. 1.47.
All technical reports on this issue are complete. The project final report has been published as NUREG/CR-3621. This final report includes guidelines for improving system status moni-toring as well as the final recommendation of PNL on a regu-latory position. Their recommendation is to revise R.G. 1.47 and apply it to all plants. Supplemental work may be required of the contractor to support revision of R.G.1.47 by RES, e.g. ,
value/ impact analysis, resolution of public comment, and de-velopment of a draft revision to R.G. 1.47. PNL has submitted a proposed program for this supplemental work.
Problem / Resolution --- Response by RES to NRR dated April 17, 1985 identifies need to coordinate plan to revise R.G. 1.47 and fund work. The termi-nation of human factors research funding at the end of FY 1985 necessitates that this issue be reassigned to DHFS/NRR.
Technical Resolution - The technical resolution of this issue will be the development of an NRC position regarding the need to revise R.G.1.47 and to apply this revised version to all plants for compliance /
O As of First Quarter FY-86
Generic Issue #I.D.3 Milestones Original Current Actual Complete draft report of - -
06/04/82 current industry practices Submit prelininary recommendation - -
09/30/82 for regulatory position Submit tech report on effective- - -
11/30/82 ness of existing systems Submit tech report on effective- - -
12/15/82 ness of verification procedures Submit draft acceptance criteria - -
04/01/83 Submit draft guidelines for 07/01/83 -
07/83
- interim" improvement Submit program plan for 09/30/83 11/83 11/30/83 developing " full implementation" guidelines Submit final recommendations 09/30/83 02/84 02/15/84 for regulatory position Draft memo transferring issue - -
06/01/84 to RES complete Transfer memo approved by 00's 07/84 10/84 10/84 Transfer memo to Minogue approved 08/84 11/84 10/30/84 by NRR, Director RES provided milestone 09/84 04/85 04/17/85 necessary to complete issue and outlined problems with issuing Reg. Guide revision Issued memorandum for providing - -
11/25/85 cilestones RES provides new milestone -
02/86 -
dates necessary to resolve issue ,
Prepare Task Control Form (fCF) -
10/85* -
Obtain TCF Approval -
10/85* -
O As of First Quarter FV-86
Generic Issue #I.D.3 Y .
Milestones Original Current Actual Initial Draft Complete -
10/85* -
(Info Copy to CRGR/ACRS)
Division Review Complete -
10/85* -
Develop Regulatory Analysis -
03/86* -
Office Concurrence of CRGR -
04/86* -
Package CRGR, EDO, ACRS Review / Approval -
07/86* -
Resolutten of Comments -
09/86* -
Printing and Distribution -
09/86* -
Authorized Printed ,and Issued for Comment -
10/86* -
Comment Period -
01/87* -
Resolution of Comments -
02/87* -
Division of ELD review complete -
04/87* -
CRGE review complete -
07/87* -
ACRS review complete -
07/87* - -
Resolution of comments -
09/87* -
Office concurrence obtained -
10/87* -
Printed and Issued -
12/87* -
- A new revised schedule will be provided by RES.
'.~
As of First Quarter FY-86
'l GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type _ Level Office /Div/Br Manager Tac No I.D.4 Safety / Active-L1 NRR/0HFT/HFIS None None High Title ---------------- Control Room Design Standard Work Authorization --- TMI Task Action Plan Contract Title ------- None Contractor Name/
FIN No. ------------ None Work Scope ----------- The work scope and milestones necessary to complete this issue are provided in HF-01 issues HFPP-5.3.
Affected Documents --- Same as above Status --------------- On hold for the indefinite future. No NRR resources are budgeted in FY 86 or 87 for this high priority issue. OHFT/HFIS wfIl seek EDO concurrence with reclassifying this non-scheduled issue.
Problem / Resolution --- Same as above Technical Resolution -
Milestones Original Current Actual Milestones necessary to complete this issue are provided in HF-01 issue HFPP-5.3.
~_-
As of first Quarter FY-86
GENERIC !$5UE MANAGEMENT CONTROL SYSTEM v
Issue Issue Action Task Number h Level Office /Div/Br Manager fac No I . D. 5 Safety / Active-L1 RES/DET/EEIC8 J. Vora 96005 Subtask 3 NR Title ---------------- On-Line Reactor Surveillance Systems Work Authorization --- TMI Task Action Plan Form 173 No. 60-83-061 dated November 30, 1983 No. 60-83-182 dated March 17, 1983.
Contract Title ------- " Continuous On-Line Reactor Noise System Evaluations" Contractor Name/
FIN No. ------------ Oak Ridge National Laboratory / FIN No. 80828.
Work Scope ----------- The objective of this effort is to perform research to deter-mine the feasibility of detecting and diagnosing nuclear power plant operating anomalies using a continuous on-line noise surveillance system and to perform demonstrations of such a system in an NRC Ifcensed commercial PWR plant and an NRC Ifcensed commercial BWR plant.
Affected Documents --- Not Applicable.
Status --------------- Work is in progress. A demonstration of system feasibility at an operating PWR has been completed. The survet11ance instru-ment system has been installed at Peach Bottom Unit 2 and is to be used to demonstrate system feasibility at a BWR.
Problem / Resolution --- See Technical Resolution.
Technical Resolution - Determine the feasibility of the system to detect and diagnose LWR operating anomalies using continuous on-line surveillance.
Milestones Oriainal Current Actual Install System at a PWR - -
09/80 Coms.'ete PWR Data Acquisition 06/84 -
01/84 Insta11 System at a BWR 04/84 06/85 06/85 Complete 8WR Data Acquisition 04/87 12/87 -
!ssue transfer memo to NRR with - 04/88 data, recommendations and implementation As of First Quarter FY 06
Generic Issue I.D.5 Subtask 3
.g.
Milestones Original Current Actual NRR assessment of available -
09/88 -
data, issue close-out memorandum or expand schedule O
l i
O 1 As of First Quarter FY-86 i
,, GENERIC !$5UE MANAGEMENT CONTROL SYSTEM
'\ ,
Issue Issue Action Task Number ,Tyge. Level Office /Ofv/Br Manager Tac No
- !.0.5 (5) Safety / Active-L1 NRR/DHFT/HFIS None None '
High l
Title ---------------- Disturbance Analysis Systems
, Wo rk Authorization --- TMI Task Action Plan I Contract Title ------- None 1
Contractor Name/ '
FIN No. ------------ None Work Scope ----------- The work scope and milestones necessary to complete this issue are provided in HF-01 issue HFPP-5.4.
1 Affected Documents --- Same as above Status --------------- On hold for the indefinite future. No NRR resources are budgeted in FY 86 or 87 for this medium priority issue. l
- 0HFT/HFI8 will seek office concurrence with reclassifying this non-scheduled issue.
l Problem / Resolution --- Same as above .
I' Technical Resolution -
Milestones Original Current Actual Milestones necessary to complete this issue are provided in HF 01 issue HFPP-5.4.
1 I
i 1
As of First Quarter FY-86
,.,-e__
l
\
\.
'(O)
\J GENERIC ISSUE MANAG(MENT CONTROL SYSTEM l Issue Issue Action i s Task "
l Number Type, e Level Office /Div/Br Manaaer Tac No I . F.1 Safety / Active-L1 IE/DQAVT/QA8 W. Scott None High Title ---------------- Expand QA List I Work Authorizatirn --- TMI Task Action Plan Contract Title -------
None Contractor Name!
FIN No. ------------ None Work Scope ----------- Develop guidancs for ifcensees to expand their QA list to cover equipment important to safety.
Affected Documents --- None Status --------------- SECY-85-119. " Issuance of Proposed R'ule on Important to Safety" being considered by Commfuion.
Problem / Resolution - - No plans to expand QA list. Issue proposed rulemaking.
v Technical Resolution - '
j - y Milestones, Original current Actual Task 1: Develop Frame Work - -
02/83 Review NRC Internal Comments 04/83 -
07/83 on NUREG/CR-2631 (rewrite Scope /189 ff necessary) and publish NUREG Task 2: Start Method 10/83 -
10/83 Development (Issue contract to Sandia) .
Completion of Task 2 09/84 05/85 - 05/85 Issued SECY 85-119, proposed - -
04/05/85 rule on importance to safety <
issue Commission approves $ECY 85-119 -
ACA -
Issue close out memo to E00 -
ACA -
or provide additional mile-
. stones necessar; to complete
) issue based on Commission dis- ,
v' cussion.
As of First Quarter FY 86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number h Level Office /Div/Br Manager Tac No 11.8.5 Safety / Active-L1 RES/DAE/FSRB M. Silberberg None Sub- High RES/DAE/CSRB R. T. Curtis task 1&2 Title ---------------- Research on Phenomena Associated With Core Degradation and Fuel Melting Work Authorization --- TMI Task Action Plan LRRP, Budget Authorization Documentation Contract Title ------- Multiple contracts Contractor Name/
FIN No. ------------ SNL/INEL/BCL/PNL Work Scope ----------- Conduct an extensive experimental and analytical program on the behavior of damaged fuel, hydrogen generation and control, fuel structure interaction, containment analysis, and fission product release and transport as described in detail in NUREG-0900, the Nuclear Power Plant Severe Accident Research C
\
Plan (Sections 5.4 through 5.7 and 5.9). This program involves both in pile and out-of pile test with actual and simulated core and reactor structural materials and the development of codes to model the phenomena expected in the reactor.
Affected Documents --- NUREG-0900 Nuclear Power Plant Severe Accident Research Plan (Jan. 1983 with draft Supplement 8/84 and final 01/86 -
planned).
NUREG-1070 Severe Accident Policy Statement (July 1985).
NUREG-0956 Reassessment of Technical Bases for LWR Acci-dent Source Term (Draft for Comment July 1985).
NUREG-1150 New Risk Profiles for Five Reference Plant (Draft for Comment August 1986).
Status --------------- Severe fuel damage in pile research is in progress in ACRR and the Canadian NRU reactors and complete in P8F.
Core melt - ex-reactor core melt / structure interaction tests are underway at Sandia National Lab. and elsewhere.
Large scale hydrogen tests are underway at Sandia National r As of First Quarter FY-86
l l
. l Generic Issue #II.B.5 (1 and 2)
Lab. Large scale out-of pile tests on core / concrete interac-tions, direct containment heating and fission product transport in containment are continuing as is the development and assess-ment of computer codes such as SCDAP, HECTR, CORCON, MELPROG, TRAP-MELT, and CONTAIN. Milestone charts for this work and a more complete description of the work appears in NUREG-0900.
Integrated PRA analysis codes such as the Source Term Code Package (STCP) (complete 9/85) and MELCOR (1987) will be used for extensive uncertainty analysis through FY 1988-89.
Pr:blem/ Resolution --- A report (NUREG-1150) on severe accident risk rebase-lining is being prepared to assure that risk is being given appro-priate attention in the severe accident source term reassess-ment. This report is expected to be complete - Summer, 1986.
Tcchnical Resolution -
Milestones Original Current Actual Initial draft contractor - -
01/83 Source Term Report Annual Review of Severe Accident Spring 1983 10/84 -
Research Program Summary of data base for 08/83 10/83 12/83 validation of codes to preduct releases (draft)
Source term estimates for 08/83 10/83 01/84 selected plants and accident sequences Thorough peer review of the 12/83 02/85 02/85 above scientific bases for reassessment Severe Accident Risk Rebase- 12/83 06/86 -
lining program final report (NUREG-1150) l Draft Peassessment of the 12/83 07/85 07/85 Technict Bues for Estimating Source Terms (NUREG-0956) _..
As of First Quarter FY-86 O
J t
t Generic Issue #II.B.5 (1 and 2) 4 Milestones Original Current Actual l Final Reassessment of the -
04/86 -
Technical Bases for Estimating Source Terms (NUREG-0956)
NRC Severe Accident Policy -
11/85 07/85
! Final Recommendations to the Mid-1984 11/87 -
Commission on Severe Accident Requirements for Operating i Plans and Plants under
- Construction i Issue close-out memo to ED0 -
12/87 -
1 2
1 i
i i
'I As of First Quarter FY-86 i
. ~ . . _ - . .
(o)
'O GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No II.B.5 Safety / Active-L1 RES/DAE/CSRB P. R. Worthington None Sub Medium Task 3 Title ---------------- Effect of Hydrogen Combustion on Containment Structures Work Authorization --- TMI Task Action Plan Contract Title ------- Hydrogen Behavior Program, Hydrogen Burn Survival, Hydrogen Combustion and Control Demonstration Experiment, Hydrogen Mitigation and Preventive Schemes, Hydrogen Mixing Studies.
Contractor Name/ Sandia National Laboratory /LANL FIN No. ------------ (A-1246), (A-1270), (8-8208), (A-7247), and (A-1336).
Work Scope ----------- Provide the NRC with a better technical understanding of the threat posed by hydrogen burning during postulated lightwater reactor accidents. This work includes an understanding of p) deflagrations, global and local detonations, flame accelera-tion and the transition to detonation. The effect of burning (V on equipment and the efficiency of H2 control systems.
Affected Documents --- Severe Accident Research Plan (NUREG-0900, 0/84)
Status --------------- Programs are underway with major results expected in FY 1985 and the completion of the experimental program in FY 1986 and final analysis and close-out report written in early FY 1987.
Problem / Resolution --- None Technical Resolution - Performing experiments and analysis for various plant and containment types to assess various scenarios and the efficiency of H control systems.
2 Milestones Original Current Actual Analysis of Sequoyah Plant 09/83 02/84 02/84 Review of Grand Gulf Plant 10/83 -
03/83 [
Hydrogen Igniter System Hydrogen Burn Equipment Survival 09/83 09/84 11/84 Report for Ice Condenser
) Effect of Sprays on Ignitors 09/83 01/86 -
U Report As of First Quarter FY-86
Generic Issue II.B.5 (3)
Milestones Original Current Actual Effectiveness of Nonpowered -
03/86 -
Igniters Effect of H Burns in Aerosols 10/83 10/86 -
ScopingStu$yReport Report of Experiments on Local 01/84 07/86 -
D;tonation NTS Data Analysis for Premixed - -
05/85 Tssts NTS Data Analysis for Continuous - -
05/85 Injection Tests NTS H 2 Demonstration Test Report 03/84 06/86 -
Large Scale Flame Acceleration 05/84 12/86 -
Tests Report MARCH-HECTR Analysis of Selected 12/83 03/85 02/85 Accident in an Ice-Condenser C:ntainment Analysis of Hydrogen and Steam 02/82 -
02/84 Releases to Containment During D: graded Core Cooling Accidents l Light Water Reactor Hydrogen -
05/87 -
l Manual revision l
l R: search information Letter to -
07/87 -
NRR and issue close-out memo to ED0 HECTR Version 1.0 - -
02/85 l HECTR Version 2.0 -
12/86 -
Hydrogen-Steam Jet Flame - -
02/85 __
Facility and Experiments ;
l O
As of First Quarter FY-86
(O V) GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No II.C.4 Safety / Active-L1 RES/DRA0/RR8 C. E. Johnson None Medium Title ---------------- Reliability Engineering Work Authorization --- TMI Task Action plan Contract Title ------- Operational Safety Reliability Contractor Name/
FIN No. ------------ Argonne National Laboratory, A-2242 Brookhaven National Laboratory, A-3282 Work Scope ----------- Evaluate the effectiveness of reliability program elements and techniques applicable to maintaining LWR safety during the operating life of the plant. Tasks include:
(1) Refine the previous (ANL) evaluation of the effectiveness of reliability requirements to help resolve current safety issues (as exemplified by. generic issues).
'( (2) Through case studies, identify the attributes (i.e. , '
('
success criteria and reasonable applications) of successful reliability program applied to LWR safety.
.(3) Adapt reliability techniques used in other industries (for example, alert levels for trial application to LWRs.
(4) Evaluate the elements and attributes of reliability program
, through intial trial application to an example safety system
( at 1 plant.
i (5) Extend the trial use to cover several safety systems at 1 plant.
(6) Peer review of the results.
I l (7) Publish a evaluation of the effectiveness of the elements and attributes of a successful reliability program as a NUREG/CR and recommend regulator reforms that reliabilit) techniques could facilitate and that would encourage volun-l tary application of these reliability techniques. __
i :r
-Affected Documents --- To be determined based on the results of this project.
Status --------------- Case studies and initial trial application are in progress.
I f Technical Resolution -
a As of First Quarter FY-86 l
i .
l l
l l
l Generic Issue #II.C.4 1
Milestones Original Current Actual Discuss with INPO the needs to 06/83 -
11/83 d;velop agreement (See U.S.
Nuclear Regulatory Commission P3licy and Planning Guidance 1983, NUREG-0885, Issue 2, prges 11 and 12).
R; search generic reliability 12/83 03/84 04/84 methodology.
Survey / adaptation of reliability 06/84 -
02/85 t';chniques & identification of r211 ability program elements for ditailed evaluation.
8: gin trial use. 12/84 -
07/85 Complete case study of 5 plants -
b2/86 -
to identify reliability tech-niques that industry has found to be effective.
Centractor interim report- -
04/86 -
d; scribing what is a reliabil-ity program and identifying practical reliability techni-quis and reasonable applications.
Issue draft interim report for staff review and comments.
Publish incarim report as -
04/87 -
NUREG/CR ACRS Subcommittee review -
05/87 -
Publish final NUREG -
12/87 -
Issue close-out memo -
12/87 -
to E00 I
O As of First Quarter FY-86
r V}
[s GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No II.E.4.3 Safety / Active-L1 NRR/DSI/CSB Y. S. Huang 52409 High Title ---------------- Containment Design - Integrity Check Work Authorization --- NRR FY-84 Operating Plan (Appendix G).
Contract Title ------- 1. Reliability Analysis of Containment Isolation Systems
- 2. Feasibility Study of Alternative Containment Test Methods Contractor Name/
FIN No. ------------ 1. Pacific Northwest Laboratories / FIN No. B-2526
- 2. Sandia National Laboratory / FIN No. A-1802 Work Scope ----------- To determine whether a gross containment leak test should be required. In order to accomplish this task the following sub-tasks will be performed under T/A contract:
Task 1: Collect operating data and information; Task 2: Establish the expected frequency of undetected breach of containment integrity and the expected (VO) frequency of containment unavailability and their uncertainty bounds; and
~
Task 3: Evaluate the feasibility of alternative containment test methods for periodically verifying the contain-ment integrity.
Affected Documents --- Not Yet Determined Status --------------- On 06/20/63, contract with PNL was initiated for tasks 1 and 2 above. The results of the PNL study were published in NUREG/CR-4220.
The CSB review of the PNL report and associated data base confirms that the reliability of containment integrity with regard to gross leakage is still a valid concern. As a result, in December 1984, the CSB requested a proposal from SNL to evaluate the feasibility of alternative containment test methods.(Task 3 above). The SNL proposal was reviewed and accepted by the CSB in May 1985, and the contract with SNL .
was initiated immediately. g The SNL contract is scheduled to be completed in September 1986. The results of the SNL study will be used by the CSB O
V As of First Quarter FY-86
Generic Issue #II.E.4.3 staff to formulate the licensing bases for requiring alterna-tive or additional containment leakage rate test. Affected NRC docuraents will be identified and final technical resolution and milestones will be developed.
Problem / Resolution --- The milestones for technical resolution are based on the projected completion date for Task 3. This milestone will determine whether issue will be closed-out or whether additional milestones are needed to develop new regulatory requirements.
Tcchnical Resolution - The results of this study will be used to determine what kind of gross containment leak test shoeld be required and how it should be implemented. If necessary, a program will be initiated to develop revisions to the appropriate Regulatory Guides, Standard Review Plan Sections, and Standard Technical Specifications.
Milestones Original Current Actual R;; quest for Proposal for - -
01/12/83 Tasks 1&2 Issued.
Evaluation of Proposals 06/83 -
06/15/83 fer Tasks 1&2 Completed Issue Contract to Evaluate 07/83 -
06/24/83 Reliability of Containment Integrity (Tasks 1&2)
Riceive Contractor Draft Report 02/15/84 05/84* 05/18/84**
on Review of Containment Integrity (Task 1&2)
Based on Review of Part 1 of 04/15/84 07/84 08/08/84***
Contractor Draft Report, Issue o Memorandum closing out Issue, or Proposing the Need to Develop Additional Milestones for Resolu-tion of the Issue, including the Initiation of Task 3 of the Work Scope.
"R; vised schedule approved in Memorandum from R. Mattson to T. Speis, dated 02/24/84. [
- Part 1 of Draft Report (regarding Task 1) received; receipt of Part 2 of Draft Rep:rt (regarding Task 2) deferred to 9/84.
" Memorandum from R. Bernero to T. Speis, dated 08/08/84, Transmitting Finding that Further Technical Resolution of the Issue i's Warranted.
As of First Quarter FY-86
.J r 4 -
Generic Issue #II.E.4.3 v
Milestones Original Current Actual Request for Proposal for Task 3 11/84 -
12/84 Issued Issue Contract to Evaluate -
04/85 05/85 Feasibility of Alternative Containment Test Methods (Task 3)
Milestones for Completion of -
05/85 05/85 Task 3 will be Developed after Contract is Issued Receive contractors final -
09/86 -
report on the Feasibility -
Study for Alternative Containment Test Methods
' Evaluate report on Alternative -
10/86 -
' Containment Test Methods Feasi-bility. If Alternative Tests t Methods are not feasible issue !
) close-out memo to EDO. If fea- !
'v sible provide schedule for full scale testing /rulemaking
[
i
=
l l
[
l
! s I
l'
! As of First Quarter FY-86 I
t .
f)
(v) GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No II.E.6.1 Safety / Aci " L1 NRR/DE/MEB 0. Rothberg 42416 Medium Title ---------------- Test Adequacy Study Work Authorization --- NRR FY-84 Operating Plan (Appendix G)
Contract Title ------- In Situ Testing of Valves Contractor Name/
FIN No. ------------ Brookhaven National Lab / Fin A3821 Work Scope ----------- (1) Survey industry pratices and requirements for design, specification, qualification, and pre-operational and surveillance testing cf valves in safety-related systems.
(2) Comparison of the tests with performance requirements and specifications.
(3) Identify performance requirements that are not adequately verified by analysis or test.
V (4) Evaluate alternate means of verifying performance.
(5) Develop staff ~ positions for additional periodic valve capability tests.
Affected Documents --- Revise R.G. 1.106, 10 CFR 50.55(g) and Standard Technical Specifications.
Status --------------- A complete milestone schedule has been drafted and was issued in a work plan memorandum on July 30, 1984. A contract effort has been initiated to accomplish the. tasks outlined in the work scope.
Problem / Resolution --- The question is if current in situ valve testing methods will adequately assure that safety related valves will perform their intended safety function (open, close, stay open, stay I closed,.any combination) under design basis conditions.
AnattemptisbeingmadetoresohvethevariousprobIemsnow being identified with current valve in situ testing methods to determine if design basis results can be extrapolated from _
the current no-load tests.
l As of First Quarter FY-86
Generic Issue #II.E.6.1 Technical Resolution -
Milestones Original Current Actual Prepare Users Request for RES to 05/84 -
05/84 contract for in plant pilot programs.
Review RES supplied DOE Lab 05/84 -
05/84 proposals for pressure isolation valve leak tests and other testing. Provide recommendations to RES for revisions to test scope and selection of testing lab.
DE Project Manager prepares -
07/85 07/85 work scope for DOE Lab contract (re: study of adequacy of current valve inservice test-ing methods) and issues RFP.
DE contract initiated -
10/85 12/85 DE contractor completes review 05/85 12/86 -
of comments to be obtained from '
AE00, INPO, BWR Licensees, valve manufacturers, determine tentative recommendation for revision or cancellation of R.G. 1.lu6, ASME C:de, Standard Tech Specs to resolve Thermal Overload Protection 0;vice Concern (TOPDC).
Issuance of ETEC DOE Lab report 09/85 07/86 -
cn PIV and MOV testing (RES contract).
Issuance of Movats report re 09/85 - -
in situ signature tracing tests (AEOD contract).
Completion of review of Novats 11/85 - -
reports by NRR including receipt of comments from AE00. ((
Draft final staff positions and 02/86 04/87 -
proposed tech specs re addition /
modification to current valve in situ testing based on staff evaluation of input from DE, RES and AE00 contracts.
As of First Quarter FY-86
i Generic Issue #II.E.6.1
'N Milestones Original Current Actual Value/ Impact statement prepared -
04/87 -
NRR Division Directors Review -
06/87 -
completed NRR Director Review completed -
08/87 -
Review Package sent to CRGR -
08/87 - '
e CRGR Review Completed -
09/87 - I Issuance of proposed staff -
10/87 -
position and tech. specs l
t Public Comments resolved by -
01/88 -
staff NRR Director review completed -
03/88 -
Review Package sent to CRGR -
03/88 -
CRGR Review completed -
04/88 -
Final Register Notice issued -
05/88 -
Issue close out memo to EDO -
05/88 -
i i
l l
i 1
i; l
l t
As of First Quarter FY-86.
l
,~
(v) GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No II.F.5 Safety / -Active-L1 RES/DET/EEICB D. Basedekas 96005 Medium Title ---------------- Classification of Instrumentation, Control and Electrical Equipment Work Authorization --- TMI Task Action Plan Jan. 15, 1982 and Nov. 8, 1982, NRC Form 173, K. R. Go11er, DF0 Contract Title ------- Classification of Systems Important to Safety
- Contractor Name/
FIN No. ------------ Brookhaven National Laboratory FIN.# A-3249 Work Scope ----------- To develop a methodology for the classification of systems important to safety.
Affected Documents --- Draft Regulatory Guide for the classification of Instrumenta-tion, Control and Electrical Systems and Components (ICES /E)
Important to Safety.
[' ' Status --------------- Draft report by BNL has been submitted in September 1984 and is awaiting review and comment by NRR.
Problem / Resolution --- IEEE has not yet issued a standard on classification of systems important to safety. IEEE Std. P-827 has been abandoned in favor of a different approach involving the development of new standard taking into accou.nt applicable work done by other technical societies such as ASME and ANS. NRC is participat-ing in this effort as stipulated by Item II.F.5. The parallel NRC effort to develop a draft regulatory guide on classifica-tion of systems important to safety has been designated as priority C and has been taken off the list of active RES tasks.
Technical Resolution - The technical resolution of this Item may be achieved by the issuance by the IEEE of a suitable standard which may sub-sequently be endorsed in whole or in part by a regulatory guide, or alternatively by the issuance of a regulatory guide irrespectively of what or when IEEE might issue a standard in this area. At this time we are continuing our participation in the IEEE effort to develop a draft Standard P-1049 under IEE/NREC/SC-6.2, Working Group on System Classification.
t i t 4 G
As of First Quarter FY-86
Generic Issue #II.F.5 Milestones Original Current Actual Issue Reg. Guide for comment 10/83 On hold * -
Issue transfer memo to NRR for -
02/86 -
Issue close-out memo ta EDO -
05/86 -
Issue BM Report 12/84 Not Scheduled -
Issue IEEE Std. *1980 Not Scheduled -
"LGtt:r from H. Denton to R. Minogue, Dec. 31, 1983.
O l
As of First Quarter FY-86 i
L
,< x il V GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No II.H.2 Safety / Active-L1 RES/DAE/FSRB R. Foulds None High Title ----------------
Obtain Technical Data on the Conditions Inside the TMI-2 Containment Structure j Work Authorization --- TMI Task Action Plan .
LRRP, Budget Authorization Documentation i
Contract Title ------- None Contractor Name/ .
FIN No. ------------ None Work Scope ----------- NRC is cooperating with DOE and industry on development of plans and guidance for implementation of research and data gathering programs within the TMI-2 containment.
These programs concentrate on retrieving data which characterize the progression of the accident and the resulting radiological source term for this case. The O
programs address the examination of the reactor inter-nals (especially the reactor core and fuel), the primary system piping and vessel, the dose reduction effort during decontamination, and various mechanical, elec- l trical and instrumentation equipment. NRC primarily provides technical expertise in the program formulation and implementation, the programs are generally carried out with funds from DOE and others.
Affected Documents --- NUREG-0900 Severe Accident Research Plan (08/84).
Status --------------- Several dozen information reports have been issued by EG&G Idaho for DOE as a series of GEND reports numbered GEND-001, et. seg. (GEND indicated: General Public Utilities, Electric Power Research Institute, Nuclear Regulatory Commission, and Department of Energy - who are cooperating in a number of technical working groups to manage the planning.) Current efforts are concen-trating on final plans for TMI-2 core examination both on-site and of f-site. NRC will conduct a series of off-site examinations of selected core materials at a national laboratory. A planning basis for work to be ___
supported by NRC and separately by DOE has been developed ::. .
including a priority analysis. Implementation within NRC depends upon an agreement on scope and availability of samples from DOE.
V As of First Quarter FY-86
Generic Issue #II.H.2 Problem / Resolution --- Lack of full funding support for projected operations in the utility's recovery / cleanup program delay the avail-ability of data. An industry supported technical advisory group is assisting the utility in the engineering projects required, to speed the cleanup effort. Examination of detailed test description and information needs by 00E, EPRI, GPU, NRC, technical working group has delineated a priority based plan that can be implemented by NRC & DOE within anticipated funding limits. Performance of lower priority tasks depends on DOE success in seeking foreign and industrial support.
Technical Resolution -
Milestones Original Current Actual Revised Core examination plan 04/83 10/84 10/84 (DOE Responsibility)
Head Removal 07/83 08/84 07/84 Plenum Removal -
07/85 05/85 Revise core examination plan -
12/85 -
Core Sampling -
12/85 -
Defueling -
04/86 -
Final Fuel Analysis Report -
09/87 -
Issue close-out memo to EDO -
12/87 -
O As of First Quarter FY-86
p GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No II.J.4.1 Safety / Active-L1 IE/DEPER/EAB J. Zudans None NR Title ---------------- Revise Deficiency Reporting Requirements Work Authorization --- TMI Action Plan Contract Title ------- None Contractor Name/
FIN No. ------------ None Work Scope ----------- NRC will revise, as necessary, the reporting requirements of 10 CFR part 50.55(e) and 10 CFR Part 21 to assure that all reportable items are reported promptly and that the informa-tion submitted is complete. A major objective will be to eliminate duplicative evaluation and reporting and establish consistency with the NRC safety deficiency reporting require-ments. The reports received as a result of these rule changes will provide increased information on component failures that
% affect safety so that prompt and effective corrective action
) can be taken. The information will also be used as input to U an augmented role of the NRC's vendor end construction inspec-tion program.
IE/EAB has obtained office concurrences in the proposed revi-sion to 10 CFR Part 21 and 10 CFR Part 50.55(e), has submitted the proposed revision to the CRGR ar.d has submitted the package to the EDO for signature and transmittal to the Commission.
After E00 and Commission approval, the proposed 10 CFR Part 21 and 10 CFR Part 50.55(e) rules will be issued for public com-ment by a Federal Register Notice.
Affected Documents --- 10 CFR Part 21 and 10 CFR Part 50.55(e)
Status --------------- The proposed rule was transmitted for Office concurrence by Memorandum for all Office Directors from R. C. DeYoung,
" Proposed Rule Concurrence Request - 10 CFR Part 21 and 10 CFR Part 50.55(e)," " Reporting of Defects and Non-compliance" and " Reporting Defects in Design and Construction" respectively, dated November 30, 1984. Concurrences from all offices have been obtained. The proposed rule was submitted to CRGR on _
June 5, 1985. On July 8,1985, CRGR met and concluded that n the staff should make several changes agreed to by all parties and then should proceed with issuance for public comment.
The changes recommended by CRGR have been incorporated into the proposed rulemaking. Currently the staff has submitted
[ T the proposed rule to the EDO for signature and transmittal to y/ the Commission for approval to be issued for public comment.
As of First Quarter FY-86
Generic Issue #II.J.4.1 problem / Resolution--- Schedule revised to reflect delay caused by temporary reassignment of task manager to other high priority work.
7echnical Resolution -
Milestones Original Carrent Actual Office concurrence complete 04/83 03/85 06/85 Transmitted to CRGR for - -
06/05/85 r; view CRGR Review Complete 05/83 07/85 07/08/85 Pap;r to Commission 05/83 12/85 -
Issue Federal Register Notice 06/83 01/86 -
cf Proposed Rule changes for public comment Comments Received 08/83 03/86 -
Comments Incorporated 10/83 04/86 -
Office concurrence for -
06/86 -
Final Rule CRGR Review Complete -
07/86 -
Final Rule to Commission -
08/86 -
Issu2 Federal Register Notice -
09/8C -
for issuance of Final Rule Ruls is effective, issue -
11/86 -
c1 css-out memo to EDO 2
O As of First Quarter FY-86
(O V
J- GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action . Task Number Type Level Office /Div/Br Manager Tac No III.D.3.1 Safety / Active-L1 NRR/DSI/RA8 R. J. Serbu 42928 High Title ---------------- Radiation Protection Plans Work Authorization --- NRR FY-84 Operating Plan (Appendix G).
Contract Title ------- None Contractor Name/
FIN No. ------------ None Work Scope ----------- Finalize a " Letter of Agreement" which outlines the relation-ship between INPO and the NRC during the period when INPO will actively assist licensees in implementing ALARA-integrated radiation protection programs. Develop an auditing method whereby the NRC can assess INP0/ industry progress and success in achieving ALARA integrated radiation protection programs.
Affected Documents --- Directly Related Documents A
- 1. " Memorandum of Agreement Between INPO and the USNRC" (April 1, 1982), Appendix Number Three, " Coordination Plan for Radiological Protection Activities" (March 3,
, 1983).
- 2. NUREG-0761 (draf t March 1981) - revised into Regulatory Guide format as R.G.8.XX.
- 3. R.G. 8.XX - revise and hold for issue pending success of INP0/ Industry.
- 4. " Development of a Program to Evaluate Industry Efforts to Achieve Successful ALARA-Integrated Radiation Protec-tion programs," (R. J. Mattson, June 16, 1983). -
Action Plan / Assessment Method - developed to evaluate INP0/ industry progress and success in implementing ALARA integrated radiation protection programs.
- 5. " Evaluation of' Industry Efforts to Achieve Successful ALARA Integrated Radiation Protection Programs" (April 23, 1985, D. R. Muller to Division Directors) - criteria, ..
worksheets and examples for Regions to evaluate aspects n of industry radiation protection programs.
t As of First Quarter FY-86
l Generic Issue #III.D.3.1
- 6. " Request for the Regions to Assist in the Evaluation of Industry Success in Achieving ALARA-Integrated Radiation Protection Programs at Power Reactors" (H. L. Thompson to DRP Division Directors, May 8, 1985).
- 7. " Request for Research Assistance in Establishing a Radiological Data Base" (H. R. Denton to R. B. Minogue -
in concurrence).
- 8. " Evaluation of industry efforts to achieve successful ALARA Integrated Radiation Protection Programs - Summary Analysis of Selected Radiological Trends at Power Reactors" (D. R. Muller to DRSS Division Directors, November 19, 1985).
Status --------------- A " Coordination Plan for Radiological Protection Activities,"
effective March 3, 1983, has been prepared by NRC/INPO staffs and approved by the NRC EDO and the President, INPO as Appendix 3 to the NRC/INPO Memorandum of Agreement dated April 1, 1982. A Commission Information Paper discussing the Coordination Plan and related staff actions was provided to the Commission by the NRC staff. Following coordination between NRR, RES, IE, and the Regions, a program to evaluate INP0/ industry efforts under the Coordination Plan was promulgated (R. J. Mattson letter dated June 16, 1983,
" Development of a Program to Evaluate Industry Efforts to Achieve Successful ALARA - Integrated Radiation Protection '
Programs"). The staff completed a topical review of NRC and INPO radiation protection /ALARA guidance (letter Congel to Muller dated June 30, 1983), and established a schedule with IE and INPO in June 1983 to accompany INPO site visits beginning in September of 1983. NRR Staff members have accompanied INPO personnel, as observers, during their INP0 site evaluations during the period October 1983 through March 1985.
Regulatory Guide 8.XX (NUREG-0761) and Revision 4 of Regulatory Guide 8.8 have been held in abeyance, and the NRC staff has proposed delaying consideration of specific rulemaking regard-ing radiation protection plans until the upcoming major revi-sion of Part 20 is promulgated. The NRC staff has completed its evaluation of industry's radiation protection /ALARA efforts under its evaluation programs as planned. The staff evalua-tions have found the INP0/ industry effort successful, and the _
issue is considered to be resolved. The staff has recommended g withdre.ing R.G.8.XX as implementation guidance to an ALARA rule, bu;. will continue to pursue ALARA rulemaking as proposed in the current major revision to Part 20. R.G. 8.8 revision and update will be considered during a review in Ff-86.
O As of First Quarter FY-86
i .
- Generic Issue #III.D 3.1 l
Based on staff experience with the NRC/INPO Coordination Plan 1 and evaluation program, the staff recommends that the NRC 1
! research, format and analyze existing NRC information sources i
! to establish a radiological data base which will (1) provide i an NRC-originated source of radiological data, (2) broaden our j over-all trending and analysis capability in radiation protec-t tion, (3) support future cooperation with INP0 by supplementing our data sharing with INPO, and (4) provide further capability i;
) to validate the findings and conclusions of our industry j , evaluation program.
e i
The staff has compiled, trended, and evaluated radiological l data for 6 of 11 criteria, since that data is available from i
NRC sources, and INP0 data for these criteria and the remain- .
ing criteria cannot be released to the NRC for the public [
record. Data processing was completed by RA8 in September, ;
1985; a draft " Summary Analysis of Selected Radiological Trends At Power Reactors" was prepared and sent to IE, the Regions and
} RES by NRR in November 1985. A final version will be forwarded .
l to the EDO in December of 1985 by NRR indicating that the issue j has been resolved, and the staff plans to forward and informa-tion paper regarding the related ALARA rulemaking issue to the i .
Commission during December, also. Final comments from the Regions and IE are being received and incorporated as of
{ December 2, 1985.
i Problem / Resolution --- The free flow of information from INP0 has been hampered by INP0's reluctance to provide proprietary information to the
' NRC (in summary or detail) which could then be requested under F0IA by intervenor groups, or compiled and analyzed by NRC i staff for regulatory purposes. "
The NRC staff had originally intended to validate and use INPO I
- data in conjunction with NRC-originated data, but it became i
necessary for NRC staff to generate all data for evaluation i criteria, in lieu of sharing the effort with INPO. This effort' j has resulted in extending the planned resolution of the issue until 12/85. The NRR/RA8 staff, in an expedited effort has
! developed the capability to compile and analyze NRC-originated data. Only six of the eleven (11) criteria could be compiled l from NRC sources; however, these were adequate for the evalua-tion program. This issue, particularly since it may have r l
generic implications for other Coordination Plans, has been I reviewed by upper level management (DSI, DHFS, EDO) and L.,
j discussed with INPO.
' ' tr. I i ;
Technical Resolution - Milestones are as follows: ;
j i
As of First Quarter FY-86
Generic Issue #III.O.3.1 Milestones Original Current Actual Draft Proposed Revised NRC/INPO - -
01/19/83 Coordination Plan distributed for review and comment by OIE, RES, and Director, OSI.
Draft Plan to INPO Staff for - -
01/26/83 rcview and comment.
Staff Recommendation to EDO to - -
02/25/83 transmit proposed Coordination Plan to INPO (Follow-up to INPO (Wilkinson) letter dated August 26, 1983).
C: ordination Plan signed and in - -
03/03/83 cffect.
Draft audir.able criteria for 04/83 -
04/15/83 ALARA/ radiation protection cvaluation nf INPO Program, includin,t ALARA checklists and cvaluation criteria, distribute to IE, RES, and Regions for comment.
Revise evaluation criteria based 06/83 -
06/15/83 cn comments.
Complete a topical / functional 06/83 - -
comparison of INPO objectives, criteria and guidelines against NRC criteria.
Establish ALARA checklist 07/83 -
06/15/83 parameter, SALP/ inspection findings, etc., tracking system.
Establish schedule of NRC 09/83 -
07/06/83 accompanied INPO Appraisals.
Draft criteria for determination 10/83 -
06/15/83 cf acceptability /unacceptability of INP0/ Industry success. :-
Establish milestone for criteria 10/83 -
06/15/83 approved process.
O As of First Quarter FY-86
,ss Generic Issue #III.D.3.1 Milestones Original Current Actual
- Finalize criteria for deter- 12/83 -
06/15/83 mination of acceptability /
unacceptability of INP0/ Industry success.
- Receive IIPO input -
04/85 04/01/85
- Initiate radiological data base -
09/85 -
- Evaluation of INP0/ industry 03/85 11/85 11/85 success completed.
Radiation Protection Plan RG 03/85 12/85 -
1 either issued or withdrawn j based on determination of success or failure of INP0/
industry program l Technical Resolution Complete. 03/85 12/85**** -
i (Issue close-out documentation memo to EDO.)
4 O *INPO data viewed by NRC staff, but not officially submitted to NRC by INPO.
- Proposed effort still under review in NRR (Document #7 above).
- ***NRC staff must identify, compile, and evaluate data and trends from solely NRC sources, duplicating INPO efforts. An additional 2 months are needed to incor-oorate this effort. Final documentation is planned for December of 1986.
- Resolution completed close-out memo to EDO in approval process.
$$ r,
\
As of First Quarter FY-86
CN GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type _ Level Office /Div/Br Manager Tac No HF-01 Safety / Active-L1 NRR/0HFT/MTB C. Goodman T8P Subtask High HFPP-1.1 Title ---------------- Issue Policy Statement on Engineering Expertise on Shift and ,
Evaluate Effectiveness of Policy Statement '
Work Authorization --- Memorandum to H. Thomoson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title ------- None Contractor Name/
FIN No. ------------ None Work Scope ----------- Staff Prepare Policy Statement Affected Documents --- None Status --------------- Final policy statement approved by Commission on September 12, 1985. Published in Federal Register ,
g October 28, 1985, 50 FR 43621.
Problem / Resolution ---
Technical Resolution -
Milestones Original Current Actual Schedule and milestone dates 09/85 11/85* -
will be developed based on approval of NUREG-0985, Revision 2
- Completed per memorandum, W. T. Russell to H. R. Denton dated November 21, 1985,
" Completion of Human Factors Program Plan Items (NUREG-0985, Rev. 1)."
As of First Quarter FY-86 l
9
[4 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number h Level Office /Div/Br Manager Tac No HF-01 Safety / Active-L1 NRR/0HFT/MTB C. Goodman M40408 Subtask High M40409
- 1. 2 M40404 Title ---------------- Revise and Issue a Revision to Regulatory Guide 1.8 Work Authorization --- Memorandum for H. Thompson from H. Denton dated October 10, 1984 Human Factors Program Plan (HFPP)
Contract Title ------- Task S2 - Shift Crew Qualifications Contractor Name/
FIN No. ------------ Pacific Northwest Laboratory / Fin No. B-2360 Work Scope ----------- This issue incorporates the work scope of Task Action Plan Item I.A.2.6(1). The qualifications of the operating shift crew has been the object of numerous staff papers including:
SECY-79-330-E-G, SECY-80-492, SECY-81-84 and 81-84A, SECY-82-162 and SECY-84-106, SECY-84-355 and SECY 85-50. In January, 1983, the Nuclear Waste Policy Act PL 97-425, Sec-r tion 306 was signed into law. That law directed the NRC to .
(
promulgate regulations or other appropriate guidance for the qualification of NPP personnel including the opeating shif t Crew.
Efforts related to the law and to close the issue of qualifi-cations include preparation of a policy statement on training and qualifications aad fitness for duty in response to $306, the industry will be responsible for (1) ensuring that per-sonnel have qualifications appropriate to the performance requirements of the jobs to which they are assigned, (2) prep-aration of a policy statement on engineering expertise on shift (3) revision of Reg. Guide 1.8 to endorse ANS 3.1-1981, and (4) completion of a contractor study on the issue of job-related educational qualifications based on the results of existing JTA data.
Affected Documents --- Reg. Guide 1.8 Policy Statement Eng. Exp. on Shift NUREG/CR-Engineering Expertise Status --------------- SECY-84-106 was submitted to the Commission in March 1984 and was rejected in November 1984. The Commission :. .
directed the staff to obtain NUMARC comments on the Final n Policy statement on Engineering expertise. The Commission f~h O
As of First Quarter FY-86
Generic Issue #HF-01 Subtask HFPP-1.2 approved a Final Policy Statement on September 12, 1985 It was published in the Federal Register on October 28, 1985, 50 FR 43621.
Problem / Resolution --- Regulatory Guide 1.8 may be delayed due to the extent of the revision following public comment.
Technical Resolution -
Milestonas Original Current Actual Recommendations of Peer Panel. - -
05/82 RES JTA Completion. 06/83 -
06/83 .
Draft Policy Statement on 06/83 -
07/83 Engineering Expertise on Shift Engineering Expertise on Shift 09/83 12/83 12/83 r port Proposed Rule to Commissioners 03/84 -
03/84 c:ncerning equirements for Senior Managers Final Policy Statement for 01/84 04/85 04/85 Engineering Expertise on shift C:ntractor report on job-related -
11/84 12/84 educational qualifications based cn JTA data bases Pr: posed revision to Regulatory -
02/85 01/85 Guide 1.8 published for public comment Issue revised R.G. 1.8 for use 06/84 05/85 -
Issue close-out memorandum - * -
- Revisirn to Regulatory Guide 1.8 is being reviewed and approved as part of the 10 CFR 55 rule change package (HFPP-3.3 and 3.4).
O As of First Quarter FY-86
( i' GENERIC ISSUE MANAGEMENT CONTROL SYSTEM 4 Issue Issue Action Task Numberi c Tyge, Level Office /Div/8r Manager Tac No HF-01 Safety / Active-L1 NRR/0HFT/MT8 J. Persensky TBP Subtask High HFPP-1.3 ,
Title ---------------- Develop a Means to Evaluate Acceptability of NPP Personnel Qualifications Program Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP) 1 l Contract Title ------- To Be Determined Contractor Name/
FIN No. ------------ To Be Determined j Work Scope ----------- Develop Review Guidance to be used by staff in post-accreditation reviews.
- Affected Documents --- Policy Statement on Training,6nd Qualifications (SECY 85-1)
^ L f^~ Status --------------- On hold until decision on role ~of accreditation is made.
(
Problem / Resolution --- To Be Provided Later Technical Resolution -
Milestones Original Current Actual Schedule and milestone dates 09/85 02/86 -
, will be developed based on
. approval of NUREG-0985, Revision 2 l
^
t 1
i
\
. As of first Quarter FY-86
. . -_ c -. -
^^
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number h Level Office /Div/Br Manager Tac No HF-01 Safety / Active-L1 NRR/DHFT/MTB J. Persensky T8P Subtask High HFPP-1.4 Title ---------------- Review and Evaluate Industry Qualification Programs I
Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title ------- None Contractor Name/
FIN No. ------------ Not applicable Work Scope ----------- Apply Review Guidance in post-accreditation reviews Affected Documents --- Policy Statement on Training and Qualifications (SECY 85-1)
Status --------------- On hold Problem / Resolution --- To Be Provided Later v
i Technical Resolution -
Milestones Original Current Actual Schedule a.1d milestone dates 09/85 02/86 -
will be developed based on +
approval of NUREG-0985, Revision 2 1
O As of First Quarter FY-86
6-() GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No HF-01 Safety / Active-L1 NRR/DHFT/MTB TBP T8P Subtask High HFPP-2.1 Title ---------------- Evaluate Industry Training Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title ------- None Contractor Name/
FIN No. ------------ Not applicable Work Scope ----------- Use new inspection modules and Training Review Guidance to inspect utility training products and in event-based reviews.
Affected Documents --- Policy Statement on Training and Qualifications (SECY 85-1)
. Status --------------- Inspection Modules 41400 and 41701 issued and Training Review criteria and procedures developed. Three post-accreditation reviews completed.
Problem / Resolution --- INPO objection to NRC performing post-atireditation i reviews.
Technical Resolution -
Milestones Original Current Actual Schedule and milestone dates 09/85 02/86 will be developed based on approval of NUREG-0985, Revision 2
(
k As of First Quarter FY-86
(O) GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No HF-01 Safety / Active-L1 NRR/0HFT/MTB J. Persensky TBP Subtask High HFPP-2.2 Title ---------------- Evaluate INPO Accreditation Program Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, .
1984, Human Factors Program Plan (HFPP) h F
Contract Title ------- None Contractor Name/ '
FIN No. ------------ Not Applicable Work Scope ----------- Monitor industry progress in echieving accreditation through observation of INPO team visits, performing post-accreditation reviews and monitoring indicators data.
Affected Documents --- Policy Statement on Training and Accreditation (SECY 85-1)
Status --------------- Three post-accreditation reviews completed, 20% of Team visits gO observed. All Accreditation Board review meetings ooserved.
Problem / Resolution --- INP0 objection to Post-Accreditation reviews.
1 Technical Resolution -
Milestones Original Current Actual Schedule and milestone dates 09/85 02/86 i will be developed based on I
approval of NUREG-0985, ,
Revision 2 l
A
\
J l
l As of First Quarter FY-86
i l
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task 3 Number Type Level Office /Div/Br Manager Tac No l HF-01 Safety / Active-L1 NRR/DHFT/MTB J. Persensky TBP Subtask High 1 HFPP-2.3 s.
Title ---------------- Revise Standard Review Plan Section 13.2.3 Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, '
1984, Human Factors Program Plan (HFPP) i Contract Title ------- To Be Determined ,
Contractor Name/
FIN No. ------------ To Be Determined Work Scope ----------- To Be Provided Later Affected Documents --- To Be Provided Later Status --------------- On hold until effect of Policy Statement on Training and Qualifications is determined. Issue to be closed-out.
's- Problem / Resolution --- To Be Provided Later Technical Resolution -
Milestones ' Original Current Actual Schedule and milestone dates- 09/85 02/86 -
will be developed based on approval of NUREG-0985, Revision 2 .
l l
i l
0 ~
As of First Quarter FY-86
] GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task
. Number Type Level Office /Div/Br Manager Tac No HF-01 Safety / Active-L1 NRR/0HFT/0LB B. Boger M40428 Subtask High HFPP-3.1 Title ---------------- Develop BWR Job-Knowledge Catalogue (NUREG-1123)
Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title ------- Developments of NRC Reactor Operator Licensing Examination Specifications Contractor Name/
FIN No. ------------ Professional Examination Service /0-1315 Work Scope ----------- Develop Job-Knowledge Catalogue using INP0 BWR JTA, GE Morris Training Center, and Subject Matter Expert panel review.
Affected Documents --- None Status --------------- Contract effective June 17, 1985
(,,) Problem / Resolution --- None Technical Resolution -
Milestones Original Curr'ent Actual Draft Catalogue for panel 01/86 03/86 -
review Final Draft for NRC review 03/86 06/86 -
Issue NUREG-1123 06/86 09/86 -
Issue Close-out Memorandum 07/86 10/86 -
l i
nv As of First Quarter FY-86
J CENERIC ISSUE MANAGEMENT CONTROL SYSTEM
/
Issue Issue Action Task Number Tyge_ Level Office /Div/Br Manager Tac No HF-01 Safety / Active-L1 NRR/DHFT/0LB B. Boger M40428
- Subtask High HFPP-3.2 Title ---------------- Develop Licensing Examination Handbook (NUREG-1121)
Work Authorization --- Memorandum to.H. Thompson from H. Denton dated October 10, l 1984, Human Factors Program Plan (HFPP)
Contract Title ------- Development of NRC Operator Licensing Examinations Specifications Contractor Name/
FIN No. ------------ Professional Examination Services /D1315 Work Scope ----------- Review Examiner Handbook developed under FIN B-2517, evaluate pilot test; make-recommendations for Examiner Standards (NUREG-1021) i Affected-Documents --- Examiner Standards (NUREG-1021)
Status'--------------- Contract effective June 17, 1985 Problem / Resolution --- None Technical Resolution - .
! Milestones Original Current Actual
- Pilot Test begun 10/85 -
09/85 i
Pilot Test complete 03/86 .
Contractor recommer.1ations 07/86 - -
i
( Final Pilot Test complete 09/86 - -
l Revise NUREG-1021 11/86 - -
I Issue Close-out Memorandum 12/86 - -
t l
As of First Quarter FY-86 t
[
\
g GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No HF-01 Safety / Active-L1 NRR/0HFT/0LB B. Boger 42454 Subtask High 49618 HFPP-3.3 40435 56190 Title ---------------- Develop Criteria for NPP Simulators Work Autnorization --- Memoranduia for H. Thompson from H. Denton dated October 10, 1984, " Human Factors Program Plan" (HFPP)
Contract Title ------- " Development of an NRC Simulation Facility Evaluation Program" Contractor Name/
FIN No. ------------ Microanalysis and Design /01317 Work Scope ----------- This item is addressed by activities -currently underway in response to Section 306 PL 97-425, and by FIN 0-1317. Speci-fically, proposed changes to 10 CFR Part 55, recommended changes to Regulatory Guide 1.149, " Nuclear Power Plant
- g Simulator Facilities for use in Operator License Examina-
[ tions," and results expected from a technical assistance con-
\
tract titled " Development of an NRC Simulation Facility Evalua-tion Program," address this issue.
Affected Documents ~--- None Status --------------- Contract began September 16, 1985. Steering Committee has held first meeting. Draft simulation facility evaluation methodology will be presented to Committee in January 1986.
10 CFR Part 55 and Reg., Guide 1.149 were presented to ACRS Human Factors Subcommittee (November 1985) and full ACRS Committee (December 1985). .
Problem / Resolution --- None Technical Resolution -
Milestones Original Current Actual For 10 CFR part 55 and RG 1.149:
End of Public Comment Period 03/85 -
03/85 :::;
Division Review 10/85 -
10/85 Office Review 12/85 - -
CRGR Review 12/85 02/86 -
D As of First Quarter FY-86
Generic Issue #HF-01 Subtask HFPP-3.3 Milestones Original Current Actual For D-1317:
RFP issued 03/85 -
03/85 Contract awarded 08/85 09/85 09/85 Eval. Plan for ANS-3.5 12/86 01/87 -
simulators Eval. Plan for Nsn-ANS-3.5 02/87 03/87 -
simulators 9
I i
i l
l l
l l .-
t O
As of First Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br- Manager Tac No HF-01 Safety / Active-L1 NRR/DHFT/0LB S. Shankman None Subtask High HFPP-3.4 Title ---------------- Examination Requirements (Revise 10 CFR 55, RGs 1.149 and 1.8)
Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10,
, 1984, Human Factors Program Plan (HFPP)
Contract Title ------- Development of Regulatory Guide and Regulatory Analysis Contractor Name/
FIN No. ------------ Analysis & Technology, NRC-03-83-10' Work Scope ----------- Provide Support for resolution of Public Comments and develop regulatory analysis.
Affected Documents --- None Status --------------- Complete
- 'N Problem / Resolution --- None Technical Resolution -
Milestones Original Current Actual Schedule and milestone dates 09/85 02/86 -
will be developed based on approval of NUREG-0985, Revision 2 l
[
l l
=
l O
As of First Quarter FY-86 i
I _. . -
9 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br ' Manager Tac No HF-01 Safety / Inactive-L1 NRR/DHFT/0LB TBP T8P Subtask High HFPP-3.5 Title ---------------- Develop Computerized Examination System Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, -
1984, Human Factors Program Plan (HFPP) ;(
Contract Title ------- To Be Determined Contractor Name/ E FIN No. ------------ To Be Determined
}
Work Scope ----------- To Be Provided Later
, Affected Documents --- To Be Provided Later Status --------------- Deferred. No funds in FY-1985 budget. ~
Problem / Resolution --- To Be Provided Later
Technical Resolution - -
i Milestones Original Current Actual Schedule and milestone dates 09/85 02/86 -
will be developed based on approval of NUREG-0985, Revision 2 z
As of First Quarter FY-86
l fa
( ) GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No i HF-01 Safety / Active-L1 NRR/0HFT/HFIB J. Bongarra TBP 1 Subtask High 1
, HFPP-4.1 Title ---------------- Inspection Modules for Upgraded Procedures 1
Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP) ;
i Contract Title ------- To Be Determined Contractor Name/
FIN No. ------------ To Be Determined l Work Scope ----------- To Be Provided Later
- Affected Documents --- To Be Provided Later I
Status --------------- To Be Provided Later g Problem / Resolution --- To Be Provided Later Technical Resolution -
Milestones Original -Current Actual Schedule and milestone dates 09/85 02/86 -
will be developed based on 1 approval of NUREG-0985, Revision 2 i
1 i
I i
(- ::
G As of First Quarter FY-86 l
l
[
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM v
Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No
.HF-01 Safety / Active-L1 NRR/DHFT/HFIB TBP 48436 Subtask High HFPP-4.2 Title ---------------- E0P Effectiveness Evaluation ;
Work Authorization --- Memorandum for H. Thompson from H. Denton dated October 10, -
1984, " Human Factors Program Plan" (HFPP) j Contract Title ------- Revise the Inspection Module and Develop Associated Training for Regional Audit of E0Ps Contractor.Name/
FIN No. ------------ Not applicable Work Scope ----------- Revise current I&E inspection modules to reflect changes required to audit upgraded E0Ps and E0P development programs.
Assist with training of I&E inspectors in the use of revised inspection modules.
Affected Documents --- NRC I&E inspection module. Possible revision to SRP Section (s
s 13.5.2.
Status --------------- Two E0P audit completed.
Problem / Resolution --- Delay in scheduling a third E0P audit may cause schedule to change. Alternate sites being considered for third audit.
1 Technical Resolution -
Milestones Original Current Actual Issue revised SRP Section 13.5.2 08/84 -
08/84 Complet'. draft inspection module revision and forward to IE for review 09/84 10/85 10/85 IE comments Incorporated into revised draft -
03/86 -
Assist I&E in _
conducting inspection training 01/85 04/86 -
Implement Inspection Module -
05/86 -
O,
\ ,
Issue close-out memorandum -
06/86 -
As of First Quarter FY-86
\\v
[V h GENERIC I'SSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager. Tac No HF-01 Safety / Active-L1 NRR/DHFT/HFIB TBP T8P .
Subtask High HFPP-4.3 Title ---------------- Criteria for Safety Related Operator Actions (8-17) i.
Work Authorization --- Memorandum for H. Thompson from H. Denton dated October 10, 1984, " Human Factors Program Plan" (HFPP)
Contract Title ------- To Be Determined Contractor Name/
FIN No. ------------ To Be Determined Work Scope ----------- To Be Provided Later Affected Documents --- To Be Provided Later
\~~ Status --------------- To Be Provided Later Problem / Resolution --- To Be Provided Later .
Technical Resolution -
Milestones Original Current Actual DHFS has Issued a memorandum 02/84 -
03/22/84 to RES transferring B-17 to their office.
RES issued memorandum trans- - -
04/17/85 ferring B-17 to NRR/DHFS/PSRB Incorporate B-17 into HFPP - -
06/07/85 Schedule and milestones dates -
02/85 -
will be developed based on :;
approval of NUREG-0985 Revision 2.
/
As of First Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM v
i Issue Issue Action Task Number Typ_e_ Level Office /Div/Br Manager Tac No HF-01 Safety / Active-L1 NRR/0HFT/HFIB TBP 55402 Subtask High HFPP-4.4 Title ---------------- Guidelines for Upgrading Other Procedures Work Authorization --- Memorandum for H. Thompson From H. Denton dated October 10, 1984, " Human Factors Program Plan" (HFPP)
Contract Title ------- Develop guidance and regulatory action for ops and AOPs Contractor Name/
FIN No. ------------ Battelle Pacific Northwest Laboratories (PNL)/8-2360, P-2 Work Scope ----------- Recommend improvements in nuclear power plant operating procedures and develop an implementation plan for upgrading operating procedures.
Affected Documents --- Not yet determined. Possible revision to SRP Section 13.5.2 C N Status --------------- Task 1 (Define Scope of Project and Refine Project Focus),
f i Task 2 (Review Existing Data Base) have been completed.
D) Task 3 (Define Current Industry Practices and Problems) and Task 4 (Select and Convene Project Peer Review Group) have been completed with the exception of reviewing sample plant procedures (task 3, subtask h)
Problem / Resolution --- None i
Technical Resolution - NRC will determine the amount of upgrade effort necessary for each type of procedure based on a contractor interim report and industry inputs with respect to costs and benefits.
Milestones Oriainal Current Actual Issued contract to PNL to develop - -
02/01/83 guidelines for upgrading operat-ing procedures.
Define scope of operating - -
01/31/84 procedures
- Submit a summary letter report - -
01/31/84 ._
i n
V As of First Quarter FY-86
1 l
Generic Issue #HF-01, Subtask HFPP-4.4 1
Milestones Original Current Actual Complete review of data on - -
07/01/84 nuc1 car power plant operating pr:cedures Submit summary letter report - -
08/15/84 Develop discussion items for - -
01/31/84 sit] visits and submit to NRC Inc rporate NRC comments and - -
02/15/85 submit final letter report Complete site visits 09/84 01/85 02/01/85 Complete preliminary assessment - -
01/15/85 of interface problems and submit summary letter report Complete analysis of procedures 09/84 07/85 -
in operating plants R:ceive comments from NRC on - -
02/28/84 P;;r Review Group Select and contact Peer - -
03/30/84 R view Group Crnv:ne first Peer Review Group 07/84 -
07/19/84 C nv:ne second Peer Review Group 10/84 01/85 12/04/84 Submit any recommendations for 09/84 08/85 09/85 urg:nt NRC action Submit draft report 09/84 08/85 09/85 R:ccive NRC and peer review group 01/85 09/85 10/85 comments Submit final report 02/85 10/85 11/85 Publish final report -
12/85 -
Issua close-out memorandum -
01/86 -
O As of First Quarter FY-86
I
( GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Tyge_ Level Office /Div/Br Manager Tac No HF-01 Safety / Active-L1 NRR/DHFT/HFIB W. Kennedy 59929 15A1 i Subtask High HFPP-4.5 Title ---------------- Applications of Automation Artificial Intelligence Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 20, 1984, Human Factors Program Plan (HFPP)
Contract Title ------- To Be Determined Contractor Name/
FIN No. ------------ To Be Determined Work Scope ----------- To Be Provided Later Affected Documents --- To Be Provided Later Status --------------- To Be Provided Later
- Problem / Resolution --- To Be Provided Later Technical Resolution -
Milestones Original Current . Actual Schedule and milestone dates 09/85 02/86 -
- will be developed based on approval of NUREG-0985, Revision 2 i
- n l
i As of First Quarter FY-86 I
(A v
) GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No HF-01 Safety / Active-L1 NRR/0HFT/HFIB R. W. Froelich M 40444 Subtask High HFPP-5.1 l
Title ---------------- Local Control Stations I Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, {
1984, Human Factors Program Plan (HFPP) '
Contract Title ------- To Be Determined Contractor Name/
FIN No. ------------ To Be Determined i Work Scope ----------- In process. Principal issue is the extent of actual hands-on local control station human factors design review. This review process would consist of on-site analyses and reviews of local control stations conducted in nuclear power plants '
of cooperating utilities.
O
('j An initial step in this process would be the confirmation of the local control station definition that was provided in August 1985.
Variables still needing resolution include the number of site visits, whether or not contractor personnel would be ,
needed, NSSS types to consider, plant designs, plant age, plant status, and the form and distribution of any reports prepared on an individual plant basis.
The possibility that plant reviews could be handled by industry groups (e.g., INPO) should be considered. Minimal participation of NRC/HFIB personnel would still be desirable.
A plan of work is needed that would be based on the premise that no site visits to review local control stations will be permiEod.
Affected Documents --- The principal one would be NUREG-0700. One primary output of the local control stations review process would be an addendum to NUREG-0700 that would provide guidelines for industry conduct of local control station design reviews.
Status --------------- Currently going through the ORNL LER data bank retrieval system in an attempt to develop a search program that would have a high probability of selecting LERs for further review that were based on local control station problems.
b O
As of First Quarter FY-86
Generic Issue #HF-01 Subtask HFPP-5.1 Problem / Resolution --- None Technical Resolution -
Milestones Original Current Actual Schedule and milestone dates 09/85 01/86 -
will be developed based on approval of NUREG-0985, Revision 2 O
l O
As of First Quarter FY-86
l
\ GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No HF-01 Safety / Active-L1 NRR/DHFT/HFIB D. Jones TBP Subtask High HFPP-5.2 Title ---------------- Annunciators f
Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, '
1984, Human Factors Program Plan (HFPP) l i
Centract Title ------- 1. Human Factors in Annunciator / Alarm Systems W
- 2. Computerized Man-Machine Communication -
Contractor Name/ 4 FIN No. ------------ 1. Sandia National Laboratories / FIN No. A1394
- 2. OECD Halden Project / FIN No. B7488 Work Scope ----------- 1. Recommend Annunciator / Alarm prioritization schemes.
Experimentally evaluate impact of alarm prioritization on operator performance.
- 2. Conduct experimental comparison of three computer-based alarm systems.
Status --------------- 1. Experimental evaluation of alarm prioritization is awaiting availability of ANO simulator.
Problem / Resolution --- Availability of ANO simulator to conduct experimental evalua-tion of alarm prioritization plan. Coordination with SNL underway.
Technical Resolution -
Milestones Original Current Actual Schedule and milestone dates 09/85 02/85 will be developed based on approval of NUREG-0985, Revision 2
(
x As of First Quarter FY-86
f%
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Typjt, Level Office /Div/8r Manager Tac No HF-01 Safety / Active-L1 NRR/0HFT/HFIB T8P T8P Subtask High HFPP-5.3 Title ---------------- Evaluate Operational Aid Systems Work Authorization --- Memorandum for H. Thompson from H. Denton dated October 10, 1984, " Human Factors Program Plan" (HFPP)
Contract Title ------- To 8e Provided Later Contractor Name/ Idaho National Engineering Laboratory /A-6308 FIN No. ------------ Brookhaven National Laboratory /A-3254 (Completed)
Work Scope ----------- Identification of display design criteria and guidelines for the display of computer generated data to verify the technical accuracy of NUREG-0700 and NUREG-0835 for the control and display elements in the control rooms.
Affected Documents --- NUREG-0700 and NUREG-0835 0
Status --------------- Research began in FY81 with reports being issued annually.
Human Factors Subcommittee 7.0, Power Committee IEEE, also is engaged in development of a human factors design standard. Decision to prepare a Rule, Guideline, or only technical reports has not been affirmed.
Problem / Resolution --- Contract terminated at end of FY-85 Technical Resolution -
Milestones Original Current Actual Begin criteria development 09/80 -
12/80 research First report, NUREG/CR-1994, 04/81 -
04/81 April 1981 Second report, NUREG/CR-2147, 09/81 -
08/81 September 1981 Third report, NUREG/CR-2828, 06/82 -
08/82 ..
August 1982 Fourth report, NUREG/CR-2776, 09/82 -
09/82 September 1982 As of First Quarter FY-86
Generic Issue #HF-01 Subtask HFPP-5.3 Milestones Oricinal Current Actual Fifth report, NUREG/CR-2916, 09/82 -
09/82 September 1982 Sixth report, NUREG/CR-2942, 10/82 -
10/82 October 1982 Sev: nth report, NUREG/CR-3103, 09/82 -
01/83 J:nu:ry 1983 Eighth report, NUREG/CR-3003, 09/83 -
04/83 April 1983 Ninth report, NUREG/CR-3557 -
12/83 12/83 December 1983 Tenth report, NUREG/CR-3461, - -
01/84 Janu:ry 1984 E1 v: nth report, NUREG/CR-3631 - -
02/84 February 1984 Issun report on control room 01/84 11/84 12/84 human engineering criteria Issue transfer memo to NRR/0HFS -
06/85 07/03/85 DHFS memorandum provided -
11/85 08/08/85 cil: stone necessary to complete issue l Work scope for issue I.D.4 will -
02/86 -
be integrated into HF-01 issue HFPP-5.3 O
As of First Quarter FY-86
y, GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No HF-01 Safety / Active-L1 NRR/0HFT/HFIB TBP TBP Subtask High HFPP-5.4 Yitle---------------- Computers and Computers Displays Work Authorization --- Memorandum for H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title ------- Display Design and Evaluation Contractor Name/
FIN No. ------------ Idaho National Engineering Laboratory /A-6308 A-6108 (Completed FY82)
Work Scope ----------- (1) Development of display design criteria for disturbance analysis system were started in FY81 and will be completed in FY84.
(2) Study adequacy of disturbance analysis methods was not started because of funding cuts.
Affected Documents --- NUREG/CR-2118 NUREG/CR-1994 V NUREG/CR-2147 NUREG/CR-2776 N'.;ltEG/CR-2711 NUREG/CR-2828 NUREG/CR-3103 NUREG/CR-2916 NUREG/CR-2942 Status --------------- Improved dispaly and diagnostics were installed in LOFT June 1982 and documents listed above have been produced to date. Additional research stopped because of lack of funds Problem / Resolution --- Contract terminates end of FY-85 Technical Resolution -
Milestones Oriainal Current Actual A-6308 Work Scope (2) - - -
Development of Display Design FY81 -
FY81 Criteria Started System Design Completed FY84 09/84 09/84
~
Issue transfer memo to NRR/DHFS -
06/85 07/03/85 DHFS memorandum provide -
11/85 08/08/85 -
Milestone necessary to complete issue '
Work scope for issue I.D.5 (5) -
02/86 -
q will be integrated into HF-01 issue HFPP-5.4 As of First Quarter FY-86
j GENERIC ISSUE MANAGEMENT CONTROL SYSTEM V
Issue Issue Action Task Number h Level Office /Div/8r Manager Tac No HF-01 Safety / Active-L1 NRR/DHFT/HFIB T8P 55587 Subtask High HFPP-6.1 Title ---------------- Development of Regulatory Position on Management and Organization Work Authorization --- Memorandum for H. Thompson from H. Denton dated October 10, 1984, " Human Factors Program Plan" (HFPP)
Contract Title ------- Human Factors Safety Technology Program, Project M-1 Contractor Name/
FIN No. ------------ Battelle PNL/ FIN No. 82360 (M1) i Work Scope ----------- This issue will be resolved by accomplishing the following objectives: (1) complete evaluation of existing management and organization assessment activities; such as INPO assistance visits, NRC Performance Assessment Team (PAT) Inspections and Systematic Assessment of Licensee Performance Program (SALP);
s (2) develop technical basis for an NRC regulatory position on g
v' management and organization at operating nuclear power plants; (3) make decision on need for a new regulatory position on management and organization; and (4) develop new regulatory position, if required.
Affected Documents --- NUREG-0800, 10 CFR, NUREG-0731 Status --------------- The contractor developed report on evaluation of INPO assistance visits to utility corporate and plant facilities has been completed. This information is currently being evaluated with information on PAT. SALP and other independent evaluators of management and organization at nuclear power plants. A staff recommendation on what the NRC positions should be concerning management and organization at operating nuclear power plants is scheduled for July 1985.
Problem / Resolution --- Close out issue from Human Factors Program plan, resolution complete due to NUMARC self-mitatives and Commission decision not to issue new requirements for two years.
Technical Resolution -
Milestones Original Current Actual Contractor Evaluation of INPO 09/83 02/84 02/84 Review Criteria in Management and Organization.
s As of First Quarter FY-86
I
(
Generic Issue #hF-01, Subtask HFPP-6.1
.g-Milestones Original Currant Actual Establish Technical Basis for a 09/83 07/84 07/84 Regulatory Position, Make Decision.
Prepare Staff Paper - Recommend- 09/84 * -
ing the NRC Position on M&O at NPPs.
Develop Regulatory Package, If 09/85 * -
Required.
Issue close-out memorandum to - -
EDO.
CClose-out issue based on issuance of commission policy statement.
O O
As of First Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number h Level Office /Div/Br Manager Tac No HF-01 Safety / Active-L1 NRR/DHFT/HFIB T8P T8P Subtask High HFPP-6.2 Title ---------------- Evaluation Criteria for SALP Reviews Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title ------- To Be Determined Contractor Name/
FIN No. ------------ To Be Determined Work Scope ----------- To Be Provided Later Affected Documents --- To Be Provided Later Status --------------- To Be Provided Later Problem / Resolution --- To Be Provided Later Technical Resolution -
Milestones Original Current Actual Schedule and milestone dates 09/85 02/86 -
will be developed based on approval of NUREG-0985, Revision 2 J
l As of First Quarter FY-86
~
)
4
,/~
j GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager Tac No HF-01 Safety / Active-L1 NRR/DHFT/NFIB TPP 40450 Subtask High HFPP-6.3 Title ---------------- Revise Standard Review Plan Section 13.1 Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, 1984, " Human Factors Program Plan" (HFPP)
Contract Title ------- Human Factors Safety Technology Program, Project M-1 Contractor Name/
FIN No. ------------ Battelle PNL/ FIN No. 82360 (M1)
Work Scope ----------- This issue will be resolved by accomplishing the following objectives: (1) develop guidelines which describe required minimums for acceptable management and organization at nuclear power plants; (2) prepare workbook to accompany guidelines; (3) publish the guidelines and workbook for use
, by NRR reviewers of operating license applications; (4) train
[ ,'>, technical reviewers *to effectively use workbook and improve x
v interview skills; and (5) revise and issue SRP revision.
Affected Documents --- NUREG-0800, NUREG-0731, SRP Section 13.1 Status --------------- A set of guidelines and an accompanying workbook have been developed and have completed interof fice and Division concur-rence. Final versions of the guidelines and workbook were published in June 1984. The guidelines and workbook will be incorporated into a revision to SRP Sections 13.1. Action on SRP is delayed pending NUMARC initiatives in accord with Commission guidance.
Problem / Resolution --- A decision to revise SRP is pending due to NUMARC initiatives which may eliminate the need for revision Technical Resolution -
Milestones Original Current Actual Develop Guidelines for OLs. 07/83 11/83 11/83 Develop Workbook for OLs. 09/83 11/83 11/83 p
( )
LJ As of First Quarter FY-86 J
Generic Issue #HF-01, Subtask HFPP-6.3
.g-Milestones Original Current Actual Revise and issue a revision to SRP Sections 13.1 Complete SRP and NUREGs -
01/85 02/85 draft changes Complete V/I Analysis -
06/85* -
Complete preparation of -
06/85* -
CRGR package Complete NRR review -
08/85* -
R: solve NRR comments and -
09/85* -
transmit for NRR Director's review Complete NRR Director's review -
11/85* -
Complete CRGR review -
01/86 -
Issue draft SRP for public -
02/86 -
comment Public comment period ends -
03/86 -
R: solve / incorporate public -
05/86 -
comments Complete NRR review -
07/86 -
Complete NRR Director review -
08/86 -
Complete CRGR review -
09/86 -
Issue revised SRP sections -
11/86 -
)f1:ston:s will be revised after overall schedule has been reevaluated.
O As of First Quarter FY-86
[s O
b MSPP I-1:8LG DEC 13 jgg3 MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 1 Issue Issue Action Task TAC Number h Level Office /Dir./Br. Manager Number NF-02 Safety / L2 NRR/DHFT/MTB 8.L. Grenier 56465 High N.B. Le :
J.L. Koontz Subtask: MSPP:I.1 .
Title:
Survey of Current Maintenance Practices Work Authorization: MSPP/ Phase I approved for implementation by the EDO on January 11, 1985.
Contract
Title:
Survey of the Status of Maintenance in the U.S. Nuclear p Power Industry ,
Contractor Name/ FIN: PacificNorthwestLaboratory(PNL)/ FIN 82984 :
Work Scope: This project will include a review and analysis of inspection ;
reports for operating reactors and identification and review (
of additional information needs and sources (e.g., AE00 '
analyses, INP0 evaluations, PAT inspection reports), '
development of a classification scheme for identified problems, in order to identify the characteristics of current maintenance programs and practices in the U.S. nuclear power industry. The development, implementation, and the effectiveness of the proventive maintenance program at Salem will be evaluated as an example of a recent ifcensee response to a recairement for maintenance.
A maintenance review protocol will be developed for direct assessment of licensee maintenance performance using, e.g., a workbook, checklist, or other evaluatin tool for NRC use.
Input to development of this protocol will be the experience gained from surveys of current maintenance practices. The use of the protocol will be to detennine. licensee maintenance performance effectiveness and response to maintenance program improvements. .
The result of this project, then, will be to assimilate data for assessing the present status of maintenance in the nuclear industry and to develop a method to describe the performance of the maintenance programs at nuclear power plants. Several sites (e.g., one in each Region) will be selected for
. . , , . ,,._,--.,y -----w-~v.---w-y.m.w v-- f' "'N-'-- '
DEC 131985 evaluation by a team to determine the maintenance program effectiveness. The reviews will (1) provide baseline data as reference for the assessment of future developments due to implementation of new or revised maintenance practices, standards, etc., and (2) identify areas where improvements in maintenance progra :s are most needed to enhance safety of operation.
Affected Documents: Report to the EDO, April 1986 Status: The protocol (Task 4) has been completed. Only the Brunswick Site Survey remains to be completed in Task 5. The review of the Salem Preventive Maintenance Program site survey has been completed and only the trip report remains to be completed for Task 2. The ,
Questionnaire to the Resident Inspectors has been forwarded to them for completion and responses are expected by the end of December.
Plant Background Information and Plant Operations and Performance Data has been entered into the data base and an analysis plan has been developed. Results of analysis should be completed in January (Task 1).
Problem / Resolution: Plant Maintenance Program Descriptions were not collected by the contractor as originally intended. This information will now be gathered from limited sources, i.e. from documents legally binding on licensees / applicants and will be inputted in the Maintenance Data Base. This has delayed completion of Task 1. Generally, site survey trip reports have taken about twice as long to complete as originally planned. This, however, is not expected to have an overall impact on the contract.
Technical Resolutions:
Milestones Original Current Actual Develop Statement of Work 2/28/85 -
2/28/85 Issue Request for Proposal 3/1/85 -
3/1/85 Select Contractor 5/1/85 -
4/20/85 Initiation of Contract 5/15/85 -
5/15/85 Collect and categorize data and build maintenance data base structure 7/5/85 -
11/22/85 Prepare and submit question-naire to be administered to Regions a) draft 8/2/85 -
7/3/85 b) final 9/6/85 11/19/85 Send Questionnaire to RIs 9/15/85 11/22/85 Prepare Quest. Analysis Plan not scheduled 12/20/85 Compile questionnaire results 11/8/85 1/29/86
m DEC 131965 Milestones ' Original Current Actual Input data for each plant and submit data file (Background and Plant Operations and Perfor-mance Data only.) 7/12/85 11/27/85 Develop and submit maintenance review protocol for use on site surveys a) draft 7/19/85 7/19/85.
b) final 8/7/85 8/23/85 ,
~
Conduct on-site maintenance surveys:
1 - Kewaunee (pilot) site visit 7/26/85
- 8/2/85 a) draft trip report 8/2/85 9/12/85 b) final trip report not scheduled 10/25/85 11/22/85 2 - Millstone site visit 9/13/85 -
8/30/85
(* a Rough drafi. re; ort not scheduled 10/15/85 b NRC input & res:o se not scheduled 10/21/85 c Draft trip report 9/20/85 12/5/85
- d NRC comments not scheduled 12/18/85 e Final report 10/18/85 12/31/85 3 - Davis-Besse (additional) not scheduled 9/20/85 site visit a) draft trip report not scheduled 11/11/85 b) final trip report not scheduled 11/20/85 4 - Rancho Seco site visit 10/4/85 10/4/85 a) rough draft report not scheduled 10/21/85
~ b NRC input & response not scheduled 10/28/85 c Draft trip report 10/11/85. 11/27/85 d NRC comments not scheduled 12/13/85 e Final report 11/8/85 12/31/85 5 - ANO-2 site visit 10/25/85 11/8/85 a Rough draft report not scheduled 11/19/85 b NRC input & response not scheduled 11/22/85 ,
c Draft trip report 11/1/85 12/13/85 l d NRC coments not scheduled 12/20/85 .
e) Final report 11/29/85 1/4/86 6 - Turkey Pt-4 site visit 11/15/85 12/6/85 A a) Rough draft report 12/13/85
(
V) b) NRC coments c) Draft report d) NRC comments 12/19/85 11/22/85 1/10/86 1/3/86 e)-Final report 12/20/85 1/22/86
DEC 131985
. 4 Milestones Original Current Actual 7 - Brunswick site visit 12/6/85 1/17/86 a Rough draft report 1/24/86 b NRC input & response 1/30/86 c Draft report 12/13/85 2/13/86 d) NRC comments 2/20/86 e) Final report - 1/10/86 2/28/86 Gather, review data and assess lesson learned on Salem Preven-tion Maintenance Program 7/6/85 -
8/20/85 Conduct Salem site visit 9/6/85 11/1/85 a) Rough draft report not scheduled 11/27/85 b) NRC input & response not scheduled 12/4/85 c) Draft report 9/27/85 12/19/85 d)NRCcomments 1/3/86 e) Final report 11/8/85 1/15/85 Collect and input plant maintenance program descriptions into maintenance data base Prepare and submit analysis plan for plant operations and perfortnance data (Task 1) not scheduled 11/15/85 Receive NRC consnents on Task I analysis plan 12/13/85 Complete analysis for plant i
operations and performance l data and submit report a) draft b) final l
l Prepare Project Report l a outline not scheduled l b draft 12/27/85 3/18/86 i
c final 2/21/85 4/30/86 l Incorporate experience from site survey and update mainten-l ance review protocol l a) draft 12/30/85 3/11/86 l b) final 1/31/86 4/14/86 Incorporate results into l E00 report 4/1/86 l
DEC 13 565 N
MSPP I-2:BLG MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 2 i
Issue Issue Action Task TAC Number Tyge_ Level Office /Dir./Br. Manager Number -
HF-02 Safety / L2 ' NRR/DHFT/MTB B. L. Grenier 56467 High Subtask: MSPP:I.2 ,
Title:
Maintenance P'erformance Indicators Work Authorization: MSPP/ Phase I approved for implementation by the EDO on January 11, 1985: .
i Contract
Title:
- Statistical Analysis of Maintenance Performance Indicators (B2980)
-~1 - - Development of Maintenance Performance Indicators (B2983)
]
, Contractor Name/ FIN: Pacific Northwest Laboratory (PNL)/ FIN B2980 Pacific Northwest Laboratory (PNL)/ FIN 82983
- Work Scope
- Preliminary investigations of plant performance safety indicators have shown that multiple variables may be selected which in combination, indicate.the effectiveness of a nuclear utility's maintenance practices. The development of mainte-nance safety indicators will build upon preliminary analyses of variables to derive a set of indicators which may be used to describe industry maintenance performance, compare plant maintenance effectiveness, and assess maintenance trends and patterns. This task will provide further baseline data as reference for industry progress in maintenance program im-provement. Alternative data sources and methods will be evaluated for applicability to maintenance performance assess-ment.
Affected Documents: Report to the EDO, April 1986 I
4 v, --n-y. mm -,,-n------n.-- ,--nv --.--n, v-w - n--n-----v--- ---ee- +- ---n-- ----------e,---- - - - - ~ - - - - - . - . - w-- - - - -
DEC I 21985 0
Status: Additional sources of information for indicators have been identified and a collection plan approved. A list of 20 plant / maintenance measures have been developed and approved.
contractor is proceeding to compile data for these measures in what will become a preliminary " Indicators Data Base".
Problem / Resolution: None.
Technical Resolutions:
Milestones Original Current Actual Development of 50W (B2980) 11/11/84 -
11/11/84 ,
Issuance of Contract (B'2980) 12/10/84 -
12/10/84 and. Start of Work Appointment of NRC Task Force 1/9/85 -
1/9/85 NRC Task Force Recomendation 1/15/85 -
1/15/85 and Assessment of Industry Proposed Indicators Complete Task 1 - Evaluation 1/15/85 -
1/15/85 of 12 NUMARC Draft Maintenance Performance Indicators (B2980)
Complete Task 2 - Evaluation 1/16/85 -
1/16/85 of Indicators Prepared by the NRC Maintenance Indicators Task Force (B2980)
Provide NRC Comments to Industry 1/21/85 -
1/21/85 (NUMARC) l Approval of NUMARC Indicators 5/29/85 Issue Request for Proposal and 8/12/85 8/12/85 Start Work, 82986 Task 1 - Identification of. Data
! Sources and Collection Plan l
(a) Identify data sources 9/20/85 10/17/85 l (b) Develop potential 10/11/85 11/27/85 l data elements (c) Develop collection plan l (1) draft 11/1/85 11/15/85 l (2) final 12/1/85 12/3/85 l
l l
DEC 131985 Milestones (cont'd) Original Current Actual Task 2 - Develop Maintenance
~ Indicator Data Base (a) Collect and compile data '
for years '80 '84 12/6/85 (1)AugmentedLERdata, OSHA data, and thermal power 12/13/85 (2) FERC data and additional LER data 2/15/86 (b) Code and normalize data 12/27/85 *
(c) Submit computerized data files 1/10/86 Task 3 - Develop maintenance performance indicators and -
reliable indicator models (a) Analyze relationship between variables 2/14/86
- r (b) Analyze data trends 3/28/86 (c) Develop initial alternative model 6/20/86 (d) Prepare report (1 dra f t - 6/20/86 (2 final 7/25/86 Task 4 - Validate Models (a) Collect, sort and compile data for 1985 7/11/86 (b) Analyze data files 8/1/86 (c) Comparative analysis 8/22/86 (d) Prepare report 8/22/86 Task 5 - Prepare Final Report
! (a) draft 9/12/86 ~
(b) final 10/31/86 i
'O .
4
DEC 131985 fm
(
V) MSPP I-3:BLG MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 3 Issue Issue Action Task TAC Number Type Level Office /Dir./Br. Manager Number HF-02 Safety / L1 NRR/DHFT/MTB 3.L. Grenier 56469 High Subtask: MSPP:1.3 ,
Title:
Monitor Industry Activities Work Authorization: MSPP/ Phase I approved for implementation by the EDO on January 11. 1985.
Contract
Title:
Review and Integration of Information from Programs Related to the Maintenance and Surveillance Program Plan.
Contractor Name/ FIN: Support within Project 2. FIN 82984 Pacific Northwest Laboratory (PNL)
Q("T Work Scope: The Maintenance Section personnel will monitor industry progress and experience in developing strategies for improved maintenance. Coordination with INP0 will be necessary to monitor the effectiveness of the INPO plant evaluations, accreditation of training, and good practices in enhancing maintenance performance in the nuclear industry. Implementa-tion of EPRI guidelines and the results of industry initiatives will be monitored and their impact assessed. In addition, industry activities such as standards development and data reporting will provide input to the NRC development of perfor-mance measurement methods, guidelines, and criteria for maintenance and surveillance.
Affected Documents: Report to the EDO, April 1986 U
9 DEC 1319g5 0
Status: The Maintenance Section staff continuously stays abreast of on-going industry activities and are in receipt of literature for
'information and for cocinent and attend meetings when scheduled Problem / Resolution: None Technical Resolutions:
Milestones Original Current Actual Attend NUMARC/EDO Coordination 1/3/85 1/3/85 Meeting Regarding the MSPP Attend NUMARC-INP0 Coor.dination 2/26/85 2/26/85 Meeting in Atlanta Attend EPRI Seminar to Review 3/19-21/85 3/19-21/85 EPRI report on " Maintain-ability" Participate in EPRI Workshop on 4/16-17/85 4/16-17/85 Maintenance Safety Related Equipment Attend ANS Maintenance Panel 6/12/85 6/12/85 Meeting, Boston Attend VEPCO Presentation on 7/16/85 7/16/85 Team Approach to Maintenance Participate in EPRI Program 7/16/85 7/16/85 Review 1
i Meeting with NUMARC on Indicators 7/17/85 7/17/85 Review of IAEA Maintenance 8/5/85 8/5/85 Manual (Revision 2)
Attend meeting with NUMARC 10/16/85 10/16/85 and selected utilities to discuss Preventive Maintenance Program development and diagnostic tools Attend Worksop on Predictive .
Maintenance at General Physics 10/7/85 10/7/85 Note: Additional " milestones" to be added as they are identified Incorporate results in ED0 report 4/1/86
A DEC 131985 MSPP I-4:BLG MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 4 Issue Issue Action Task TAC Number Type Level Office /Dir./Br. Manager Number NF-02 Safety / L1 NRR/DHFT/MTB B.L. Grenier 40004~
High Subtask: MSPP:I.4 .
Title:
Participate in Standards Groups Work Authorization: MSPP/ Phase I approved for. implementation by the EDO on January 11, 1985.
Contract
Title:
None Contractor Name/ FIN: N/A Work Scope: Maintenance Section personnel participate in development of industry national standards for maintenance by IEEE, ASME, ANS and ANSI groups. Industry standards are perceived as a means of promoting maintenance program improvements without NRC i regulation. NRC endorsement of industry standards will be considered during the maintenance program.
Affected Documents: Report to the EDO,. April 1986 e .
a i 1
- {
o DE ~ 131995 0
Status: The Maintenance Section staff is assigned to various standards committees associated with maintenance and surveillance testing and will attend when scheduled.
Problem / Resolution: None Technical Resolutions >
Milestones Original Current Actual Participate in IEEE 3.3 Goal 10/16/84 10/16/84 Setting Meeting ,
Attend IEEE 3.3 Standar'ds Com- 12/10/84 12/10/84 mittee Meeting to Devise Guidelines for Maintenance
" Good Practices" Attend IEEE 3.3 Standards Com- 2/6-7/85 2/6-7/85 mittee Meeting to Devise Guidelines for Maintenance "
" Good Practices" Review and Provide Comments on 4/19/85 4/19/85 IEEE Standards Comraittee 3.2 Draft (#338) " Periodic Surveillance Testing of NPG Systems" Attend IEEE Standards Committee 4/30-5/1/85 4/20-5/1/85 Committee Meeting 3.3 to Devise Maintenance " Good Practices" Serve as Panel Member and Present 6/11/85 6/11/85 Paper to ANS Annual Meeting on
" Maintenance Program and Practices" Attend IEEE 3.3 Standards 8/6-7/85 8/6-7/85 Comittee Meeting to Devise Guidelines for Maintenance _
" Good Practices"
~
Attend ASQC Meeting in 9/5/85 9/5/85 Knoxville, TN O.
r i
/
DEC 131985 Attend ANSI /ASME NQA Sub-
-committee on Operations <
meeting (WG on Maintenance, Repairing and Inservice Inspec-tion) to discuss Standard NQA-2 9/11/85 9/11/85 Attend IEEE WG 3.3 Meeting re:
" Maintenance Management" 10/22-25/85 cancelled Attend IEEE WG 3.3 Meeting re:
" Maintenance Guidelines" 11/4-8/85 cancelled Attend IEEE WG 3.3 meeting re:
, " Good Maintenance Practices" 2/5/86 Attend IEEE WG 3.3 meeting re:
" Good Maintenance Practices" 5/86 O
I 1
J i
DEC .i n 1995 i
MSPP.I-5:BLG MAINTENANCE AND SURVEILLANCE PROGRAM PLAN ,
Phase I/ Task 5 Issue Issue Action Task TAC Number Type Level Office /Dir./Br. Manager Number HF-02 Safety / L1 NRR/DHFT/MTB B.L. Grenier 56471 High .
Subtask: MSPP:1.5 , ,
Title:
Maintenance and Surveillance Program Integration (NRC Related Programs)
Work Authorization: MSPP/ Phase I approved for implementation by the ED0 on January 11,.1985.
Contract
Title:
Review and Integration of Information fr w Programs Related to the Maintenance and Surveillance Program Plan.
g ,
Contractor Name/ FIN: Pacific Northwest Laboratory (PNL)/ FIN B2984 Work Scope: A number of diverse, multidisciplinary programs related to maintenance are expected to produce technical data and information that will support the goals and objectives of the Maintenance and Surveillance Program (MSPP). Some of these programs are listed in Table 3.1 of the MSPP and are described in Section 3 of the MSPP. While the scope of these programs encompasses objectives other than maintenance, it is.important that all maintenance-related data and information available from these programs be extracted, assessed and integrated into MSPP activities and ensuing regulatory strategy to form a compre-hensive technical basis for NRC decision-making regarding U.S. nuclear power plant maintenance policies.
With respect to the contractual support, task assignments will be placed on an "as required" basis. Generally, for each task placed under the contract, the contractor will review and assess interim and final reports, plans, products, or other information (e.g., attending industry meetings) from the standpoints of their relationship (including possible duplica-tion of effort) and possible use in MSPP activit.ies and proposed NRP actions.
Affected Documents: Report to the EDO, April 1986
~
DEC 131985 9l '
Stat's:
u Reports are being read, evaluated and sumarized in a manner that will allow integration in current project activities or integrated in the report to the EDO.
Problem / Resolution: The QA Program Plan has yet to be approved for implementation, the staff will continue to interface on a periodic basis with the QA staff to exchange information of mutual interest / concerns. Not much is happening with the EQ program and no improvement is expected in view of the NRR reorganization.
Technical Resolutions: ,
Milestones Original Current Actual Quality Assurance Program Plan (QAPP)
The Commission paper forwarding the QAPP was signed 2/25/85 and no action has been taken to date.
Follow-up status review. 9/20/85 9/2d/85 Attend ACRS meeting on QA Plan 12/13/85 12/13/85 Safety Implications of Control Systems :
(USIA-47)
Review of NUREG/CR-4326, " Effects 1/10/86 of Control System Failures on Transients and Accidents on Westinghouse 3-Loop PWRs (Aug. 85).
Review of NUREG/CR-4262, " Effects 1/24/86 of Control System Failures on Transients and Accidents on BWRs" (Sept. 85)
Review of NUREG/CR-4047, " Effects 2/7/86 of Control System Failures on Transients and Accidents on B&W PWRs" (Sept. 85)
Review of NUREG/CR-(Unassigned 2/21/86 No.) "Effe;;ts of Control System Failures on Transients and Accidents on CE PWRs"
DEC 'I 31985 Milestones (cont'd) Original Current Actual Technical Specifications Research Review of report " Surveillance 11/30/85 not received Test Intervals" .i i
Review of report " Application 1/31/86 Guide for Allowed Outage Times" i Technical Specifications Improve-ment Project (TSIP)
Review of TSIP . final report 11/15/85 11/30/85 Nuclear Plant Aging Research Review of NUREG/CR-4156: - Operating 7/11/85 7/11/85 Experience and Aging-Seismic Assessment of Electric Motors i Review of NUREG-CR-4234: Aging and 7/11/85 7/11/85 Service Wear of Electric Motor-5 Operated Valves Used in Engineered Safety-Feature Systems of Nuclear
- Power Plants - Part 1.
4 j Review of Draft Special Report: 8/21/85 8/21/85 Evaluation of the Motor-Operated Valves Analysis and Test System (MOVATS) to detect degradation,
, incorrect adjustment and other abnormalities in Motor-Operated Valves.
-Review of NUREG/CR-3543: Survey of 11/18/85 11/1/85 Operating Experience from LERs to Identify Aging Trend.
Review of NUREG/CR-4144: Importance 11/25/85 not received Ranking based on Aging Considera-
, tions of Components Included in Probabilistic Risk Assessments.
Review of NUREG/CR-4279: Draft 12/13/85 not received .
Report on Aging / Service Wear of Hydraulic and Mechanical Snubbers
\
w -w e-- em- . - . , _ - , , - , _ ,.,..w___
DEC 13 v3g5 0
Milestones (cont'd) Original Current Actual Review of NUREG/CR-4257: Inspec- 12/20/85 tion / Surveillance and Monitoring of Electrical Equipment inside Containment of Nuclear Power Plants - with application to Electrical Cable. -
Effectiveness of Industry ALARA Programs Review of RES report on 6/30/85 6/30/85 occupational dose reduction and ALARA (NUREG/CR-4254)
Comment on Commission paper on 11/8/85 not received cooperation with INPO to evaluate industry success in achieving ALARA - integrated radiation protection programs.
R; view of RES report on evaluation 12/13/85 not received of occupational dose reduction activities (RES)
Equipment Qualification - R.G. 1.89 Currently, a multi-office-(NRR/IE/ Regions) E.Q. inspection team is conducting a series of 10 inspections to review the licensee's implementation of the E.Q. requirements of 10 CFR 50.49 for establishing and maintaining the qualification of equipment.
The results of these inspections is to ensure equipment reliability towithstand the adverse environ-mental conditions during a design basis event. The Mainenance and Surveillance Section (MSS) is monitoring these activities.
The following inspection reports on the plants listed below will be reviewed for findings pertinent to the Maintenance and Surveillance Program:
1 DEC 131985 b(m Milestones (cont'd) Original Current Actual
- 1. Calvert Cliffs '3/15/85 3/15/85
- 2. Zion 4/15/85 4/12/85
- 3. Crystal River 5/15/85 5/17/85
- 4. Fort Calhoun 6/15/85 6/14/85
- 5. Rancho Seco 7/15/85 7/12/85
- 6. Point Beach . 8/15/85 ,
8/16/85
- 7. Brunswick 10/15/85 not received
- 8. Nine Mile Point 11/15/85 not received
- 9. San Onofre 12/15/85 not received
- 10. Sequoyah or Browns Ferry 1/15/85 not received Reliability Research ,
Review of NUREG/CR-2641 "The 10/25/85 11/15/85 In-Plant Reliability Data Base for Nuclear Power Plant Compo-nents: Data Collection and Methodology Report," July 1982 Review of NUREG/CR-2886 "The 11/8/85 11/15/85 r' In-Plant Reliability Data Base 5
for Nuclear Power Plant Com-ponents: Interim Report -
the Valve Component,"
December 1983.
Review of NUREG/CR-3154 "The 11/29/85 11/15/85 In-Plant Reliability Data Base for Nuclear Power Plant Com-ponents: Interim Report -
the Valve Component,"
December 1983.
Review of ORNL/TM-9066- 12/13//85 11/15/85 "In-Plant Reliability Data Base for Nuclear Plant Components: A Feasible Study on Human Error Information," March 1984 Review of NUREG/CR-3831 "The 12/27/85 In-Plant Reliability Data Base for Nuclear Plant .
Components: Interim Report - Diesel Generators, Batteries, Chargers and Inverters," January 1985
DEC 131985 Milestones (cont'd) Original Current Actual Review of NUREG/CR-3541 12/27/85
" Measures of the Risk Impact of Testing and Maintenance Activities" Review of RES report "Appli- 12/27/85 cability of Reliability Program to Help Resolve Generic Issues" Review of RES report " Case 1/15/86 Studies on Attributes of Successful Reliability Programs" Te.ining and Qualifications of Personnel Review of INP0 Accreditation Observation Reports (as available)
- 1) Vermont Yankee 1/15/86
- 2) Dresden 1/31/86 Review of Post-Accreditation Training Review Reports (as available) 1 Susquehanna 10/23/85 10/23/85 2 Dresden 11/21/85 11/21/85 Integration of NDE Reliability and Fracture Mechanics Program Review of semi-annual program 12/13/85 progress report
! Review of annual program progress 2/7/86 report l Interfacing Systems LOCA at i BWRs - Generic Issue No.105 l
Coments on Task Action Plan 9/12/85 9/12/85 Comments of 50W for contract 9/27/85 9/27/85 in support of GI 105 l Review of Interim Progress 1/17/86
! Report I
i DEC 131985 O !
- Milestones (cont'd) Original Current Actual Other NRC Programs (Miscellaneous)
Review of Turkey Pt. 1 & 2 IE HQ 10/29/85 10/21/85 inspection of AFWS Review of NUREG/CR-3715 Report on maintainability 10/15/85 9/17/85 e
b 1
?
h l
i l
s l
i 5
l I
~
l
- 7. DEC 131985
's MSPP I-6:8LG MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 6 Issue Issue Action Task TAC Number Type _ Level Office /Dir./Br. Manager Number
, HF-02 Safety / L1 NRR/DHFT/MTB 8.L. Grenier 56468 High J.P. Jankovich Subtask: MSPP:I.6 .
Title:
Analysis of Jap'anese/U.S. NPP Maintenance Programs Work Authorization: NRC/MITI International Agreement Contract
Title:
Analysis of Japanese-U.S. Nuclear Power Plant Maintenance Programs Contractor Name/ FIN: Pacific Northwest Laboratory (PNL)/ FIN 82550
/3
) Work Scope: The objective of of this project is to assess the degree to which differing Japanese and U.S. approaches to the regulation and practice of nuclear power plant (NPP) maintenance may explain the difference in reactor. trips / scrams and safety i
equipment availability between U.S. and Japanese plants. This project consists of three tasks: (1) comparing and contrast .
ing Japanese and.U.S. NPP preventive maintenance programs (2) assessing Japanese maintenance organizational and management practices, and (3) identification of the difference in Japanese
- - U.S. NPP operating experience and factors which may account for the differences.
Affected Documents: Report to the EDO, April 1986 I
_ _ _ _ _ . _ - - - - _ .- __ _ . . . ~ _ _ - _ _ _ _ _ .
DEC 1319es Status: This project is completc. The results will be integrated into the MSPP, Phase I report to the EDO.
Note: This project was started during development of the MSPP because of the opportunity to exchange information on the subject of maintenance with Japanese at the time.
Problem / Resolution: None Technical Resolutions:
Milestones' Original Current Actual Develop Statement of Work 2/1/84 2/1/84 Obtain HFRG Approval and Forward to Contractor to ,
Start Work .
Complete Task 1 - Assess 4/15/84 5/1/84 Differences in Operating Experience Complete Task 2 - Assess 4/15/85 5/31/85 Organization and Management Complete Task 3 - Compare / Con- 4/15/85 4/15/85 trast PM programs
- Appendix B 4/30/85 5/31/85 Prepare, report of U.S. 4/15/85 4/30/85 operating experience (additional task)
Printing NUREG/CR 3883 5/31/85 7/6/85 NUREG/CR 3883P 7/31/85 8/15/85 l
l Review report and incorporate 4/1/86 l results, as appropriate, in the ED0 report O
DEC 131985 U MSPP I-7:BLG MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 7 Issue Issue Action Task TAC Number h Level Office /Dir./Br. Manager Number HF-02 Safety / L2 NRR/DHFT/MTB B.L. Grenier 57267 High J.L. Koontz Subtask: MSPP:1.7 .
Title:
Maintenance P'ersonnel Qualifications Work Authorization: MSPP/ Phase I approved for implementation by the EDO on January 11, 1985. -
Contract
Title:
Determination of Job-Relevant Maintenance Personnel Qualifications.
[v Contractor Name/ FIN: To be detennined Work Scope: The purpose of this project is to identify from job and task analysis data, the knowledges, skills, and abilities required for the duties of electrical, mechanical, instrumentation and control, and supervisory maintenance personnel. The pertinent
~
education and vocational training backgrounds as well as any aptitudes which provide the appropriate knowledge, skills, and abilities will be determined. The goal is to determine the appropriate maintenance personnel qualifications for use in i developing standards and by which to assess current industry practice in ensuring the qualifications of maintenance person-nel.
The results will provide information about the present level of maintenance personnel skills and the necessary personnel qualifications, i.e., knowledges, skills, and abilities, for correct performance of maintenance tasks. The results of this project will also be used to determine format, content, and use of job performance aids as means of improving maintenance personnel performance.
Affected Documents: Report to the EDO, April 1986 .
-~
O .
,--r.- .,7-, . , - - - -- -, - - -
DEC .12 ses Status: The draft Statement of Work has been prepared; however no contractual support will be sought in Phase I. Staff will continue e
to monitor the INP0 Accreditation Program and industry standards group activities in this area to assess their initiatives.
Problem / Resolution: Given limited resources in view of ongoing industry efforts, no specific staff action is planned in Phase I.
NOTE: In the earlier version of the MSPP. this task was to have been supported (funded) by RES but was dropped by RES as a part of their discontinuance of support to the human factors areas.
Technical Resolutions:
Milestones Original Current Actual ,
Develop Draft Statement of Work 6/30/85 -
6/10/85 Incorporate Assessment of Industry Initiatives in EDO Report 4/1/86 9
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9
DEC 131985 MSPP l-8:Bl0 MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 8 Issue Issue Action Task TAC ,
Number h Level Office /Dir./Br. Manager Number ,
HF-02 Safety / L1 NRR/DHFT/MTB B.L. Grenier 57268 l High D. Persinko Subtask: MSPP:I.8 ,
Title:
Human Factors in In-Service Inspection Work Authorization: MSPP/ Phase I approved for implementation by the EDO on January 11, 1985.
Contract
Title:
Human Factors Aspects of Ultrasonic Testing / Inservice Inspection Tasks Contractor Name/ FIN: Pacific Northwest Laboratory (PNL)/ FIN B2983
%d Work Scope: NRC regulations (10 CFR 50.55a(g)) require that nuclear power plants have an effective ISI program in place. With respect to maintenance requirements, ISI programs may not provide sufficient data to support an effective preventive maintenance program which requires considerable data on equipment history and operation. Therefore, in order to obtain sufficient objective infonnation to determine the practicality of trade-offs between ISI requirements and predictive / preventive maintenance requirements, a feasibility study investigating ultrasonic testing (UT) techniques and associated human error potential will be performed. This project will be conducted in conjunction with the RES-sponsored program titled "Inte-i gration of NDE Reliability and Fracture Mechanics." Identi-l fication of probable sources of human factors problems contributing to ineffective UT/ISI processes and the need for and scope of subsequent studies will be determined during Phase I.
l Affected Documents: Report to the EDO, April 1986 l
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DEC 131985 Status: Analyses were completed in.0ctober and the draft report has been submitted for staff review and comment. The follow-on study has been O
, cancelled because the pipe crack materails used in the MRR were.
laboratory destroyed as part of the RES study and the MRR teams members were no longer available.
Problem / Resolution: None Technical Resolutions:
Milestones Original Current Actual DevelopStatementofhork 5/15/85 -
5/13/85 and Send Request for Proposal to Contractor Authorization and Start of 5/31/85 5/28/85
- Work by Contractor Task 1 - Collection 7/31/85 7/19/85 of Human Factors Data from Mini-Round-Robin (MRR)
Tasks Task 2 - Analysis of MRR 10/25/85 10/31/85 Data Task - Site Visit to the 11/25/85 cancelled EPRI NDE Training Center Task - Preparation for MRR 11/22/85 cancelled Workshop Task - Conduct MRR Workshop 12/20/85 cancelled Task - Analyze Workshop Data 1/10/86 cancelled Contract Modification 9/27/85 9/24/85 Task 3 - Prepare and Submit Final Report a draft 11/15/85 11/20/85 b final 2/14/86 Incorporate Result of Work 4/1/86 in ED0 Report 9
7 DEC 131985 V MSPP I-9:BLG MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phr.se I/ Task 9 Issue Issue Action Task TAC Number Type Level Office /Dir./Br. Manager Number HF-02 Safety / L1 NRR/DHFT/MTB B.L. Grenier 57269 High D. Persinko Subtask: MSPP:I.9 ,
Title:
Human Error in Events Involving Wrong Unit or Wrong Train (Generic Issue 102)
Work Authorization: MSPP/ Phase I approved for implementation by the EDO on January 11, 1985.
Contract
Title:
None Contractor Name/ FIN: N/A Work Scope: In January 1984, the Office of Analysis and Evaluation of Operational Date (AE00) issued a special study report describing a number of events that resulted from human error in removing equipment from service or restoring equipment following maintenance that involved the wrong unit or wrong train of equipment being rendered unavailable. Although the scope of the study was narrow, AE00 found that 19 out of 27 events identified resulted from human error during maintenance and surveillance testing. AEOD considered such events to be examples of events that could have high safety significance due to potential loss of safety system functions.
As part of the project, the Maintenance Section will identify existing practices that may lead to human errors involving wrong unit / wrong train and to recommend improvements that may be appropriate. The scope of this project will include review operating experience, conduct site visits, interview licensee personnel of a select number of plants to determine the extent and nature of loss of safety function resulting from errors involving the wrong unit / wrong train and will identify actions for resolution of the Generic Issue or for further inves-
~
tigation.
Affected Documents: Report to.the EDO, April 1986
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. DED 131985 Status: All scheduled trips have been completed. Work to complete trip reports and the final report is on schedule.
Problem / Resolution: Schedule may be altered if the MSS follow-on trip to Davis-Besse materializes, and AEOD support is not rendered.
Technical Resolutions:
Milestones Original Current f.ctual Identify Concern and Develop 4/17/85 4/17/85 Plan for Action for Resolution
. Develop Site Visit Protocol 5/1/85 5/1/85 Perform Site Surveys as Follows: ,
1.a. Site Visit to Dresden 5/9/85 5/9/85
- b. Prepare Trip Report 2.a. Site Visits to Surry and 6/20/85 6/20/85 North Anna
- b. Prepare Trip Report 9/20/85 9/23/85 3.a. Site Visits to Salem and 7/26/85 -
7/26/85 Peach Bottom
- b. Prepare Trip Report 10/31/85 12/20/85 4.a. Site Visits to Calvert 10/1/85 Cliffs cancelled
- b. Prepare Trip Report 10/18/85 5.a. Site Visits to Oconee and 10/25/85 10/25/85 McGuire
- b. Prepare Trip Report 12/20/85 6.a. Site Visits to D.C. Cook 11/15/85 11/15/85 and LaSalle
- b. Prepare Trip Report 1/17/85 12/20/85 7.a. Site Visits to Turkey Pt. 11/22/85 11/22/85 (and Browns Ferry)*
- b. Prepare Trip Report 1/31/86 12/20/85 Issue Draft Report for 11/15/85 1/31/86 Management Review Issue Final Report 1/15/86 2/28/86 Incorporate Results into 4/1/86 E00 Report
- Browns Ferry cancelled
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\1 DEC 131985 O
MSPP I-10:BLG MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 10 Issue Issue Action Task TAC Number h Level Office /Dir./Br. Manager Number HF-02 Safety / L1 NRR/DHFT/MTB 8.L. Grenier 57270 High J.P. Jankovich Subtask: MSPP:I.10 ,
Title:
Development of an NRC Model Maintenance Program Work Authorization: MSPP/ Phase I approved for implementation by the EDO on January 11, 1985.
Contract
Title:
None Contractor Name/ FIN: N/A Work Scope: The maintenance model to be developed will serve as a conceptual framework to allow a consnon interpretation for the role of maintenance between the NRC, the industry, and the standardization groups. The modelling approach will be similar to the instructional systems development used in training by being general for overall acceptance and by providing a common basis to make plant-specific programs comparable. The model will be used to develop the site survey protocol. The modelling approach will include (1) the MSPP definition of maintenance, i.e., preventive, corrective, surveillance, organization, support, etc.; (2) the alignment of safety goals with the goals of the maintenance program; (3) means to compare plant-specific programs with each other for the industry assessment in Phase I of the MSPP.
Affected Documents: Report to the EDO, April 1986 O
l DEC 131985 Status: The NRC Model Maintenance Program is considered to be an O
unofficial. "living" document at this time since its development and refinement will take place throughout Phase I. Therefore, work on this project is continuous and no major milestones have been established.
Problem / Resolution: None Technical Resolutions:
Milestones -
Original Current Actual Development of Concept ,
4/29/85 4/29/35 Development of Draft Model 6/30/85 7/11/85 Prepare Final Draft of.Model 10/25/85 10/2/86 Incorporate Model as Appendix 4/1/86 to EDO Report 9