ML20059F960

Generic Issue Mgt Control Sys Fourth Quarter FY93 Update

ML20059F960
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Issue date:	10/31/1993
From:	NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
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REF-GTECI-MI, REF-GTECI-SC, TASK-***, TASK-OR NUDOCS 9311050194
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Text

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l ENCLOSURE i

h GENERIC ISSUE MANAGEMENT CONTROL SYSTEM f

FOURTH QUARTER FY-93 UPDATE OFFICE OF NUCLEAR REGULATORY RESEARCH OCTOBER 1993 O

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TABLE OF CONTENTS (a)

Generic Issue Management Control System (1)

Description (2)

Abbreviatirens (b)

Table 1 -

Generic Safety Issues Scheduled for Resolution, Issues Resolved, and Issues Integrated (c)

Table 1 A - Summary of Generic Safety Issues Scheduled for Resolution, Issues Resolved, and Issues Integrated (d)

Table 2 -

Number of Generic Safety Issues Resolved and Scheduled for Resolution (Through 4th Quarter FY-93)

(e)

Table 3 -

Generic Safety Issues Resolved by Fiscal Year (f)

Table 4 -

Generic Safety Issues Scheduled for Resolution (by Fiscal Year)

(g)

Table 4A - Generic Safety Issues Scheduled for Resolution (by Priority) h (h)

Table 5 -

Number of Generic Issues Prioritized from FY-83

\\m/

through the 4th Quarter of FY-93 (1)

Table 6 -

Generic Issues Prioritized as of 4th Quarter FY-93 (j)

Table 7 -

Generic Issues to be Prioritized (k)

Table 8 -

Generic Issues to be Reprioritized (1)

Table 9 -

Regulatory Impact Issues Scheduled for Resolution I

(m)

Table 10 - Licensing Issues Scheduled for Resolution (n)

Work Scope & Schedules for each Approved Generic Issue t

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GENERIC ISSVE MANAGEMENT CONTROL SYSTEM DESCRIPTION The Generic Issue Management Control System (GIMCS) provides appropriate information necessary to manage the resolution of safety-related as well as non-safety-related generic issues. For the purpose of this management control system, resolved is defined as the point where the staff's final resolution product is issued and a memorandum sumarizing the resolution is issued to the EDO. For safety-related issues, this generally occurs when the resolution has been incorporated into one or more of the following documents:

(a)

Comission Order (e)

Regulatory Guide (b)

NRC Policy Statement (f)

Generic Letter (c)

Rule (g)

Bulletin (d)

Standard Review Plan (SRP:

(h)

Information Notice GIMCS is part of an integrated system of reports and procedures that is designed to manage generic safety issues through the stages of prioritization and resolution (development of new criteria, management review and approval, i

public comments, and incorporation into the regulations, as appropriate). The priority evaluation for each issue listed in this report is contained in NUREG-0933, "A Prioritization of Generic Safety Issues." The procedure and criteria for adding new generic issues to the system are outlined in RES O

Office Letter No. 1.

(Prior to the NRC reorganization of April 12, 1987, NRR Office Letter No. 40 was used for identifying new issues.) Guidance for resolving issues is provided in RES Office Letter No. 3.

GIMCS provides the proposed schedules for managing and controlling the resolution of: (1) issues that are ranked HIGH-priority; (2) issues that are ranked MEDIUM-priority; (3) issues for which possible resolutions have been identified for evaluation; (4) issues for which technical resolutions are available (as documented by memorandum, analysis, NUREG, etc.); and (5) other issues designated to receive resources for resolution.

Issues ranked as either LOW or DROP are not allocated resources for resolution and, therefore, are not tracked in GIMCS.

Some prioritized generic issues may not have resources allocated for resolu-tion; these issues are listed in GIMCS as inactive issues. Generally, these will be MEDIUM-priority issues that have no safety deficiency demanding high-priority M tention, but have potential for safety improvements or reduction in uncertainty of analysis that may be substantial and worthwhile. Efforts for the resolution of these issues will be planned over the next several years, but on a basis that will not interfere with work on the resolution of HIGH-priority generic issues or other high-priority work. Thus, some (MEDIUM-priority) generic issues may be inactive until such time as resources become available to resolve them. The detailed schedule for resolving generic issues is monitored by GIMCS.

i

iv LEGEND ANPRM Advance Notics of Proposed Rulemaking-BNL Brookhaven National Laboratory BTP Branch Technical Position =

DTR Draft Technical Resolution EPRI Electric Power Research Institute FIN Financial Identification Number FRN Federal Register Notice FTR Final Technical Resolution GL Generic letter GSI Generic Safety Issue H

High-priority GSI IEB Inspection & Enforcement Bulletin TN Information Notice INEL Idaho Nuclear Engineering Laboratory LI Licensing Issue N

MEDIUM-priority GSI NR Nearly-Resolved GSI ORNL Oak Ridge National Laboratory PNL Pacific Northwest Laboratories PRA Probabilistic Risk Assessment RAI Request for Additional Information RG Regulatory Guide RI Regulatory Impact S

Subsumed in Another Issue (No.)

50W Statement of Work SRP Standard Review Plan STS Standard Technical Specification T/A Technical Assistance TAP Task Action Plan TBD To be Determined TI Temporary Instruction TS Technical Specification USI Unresolved Safety Issue 9

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t DATA ELEMENTS Management and control indicators used in GIMCS are defined as follows:

1.

Issue No.

- Generic Issue Number 2.

Title

- Generic Issue Title 3.

Identification Date

- Date the issue was identified 4.

Prioritization Date

- The date that the prioritization evaluation.

was approved by the RES Director 5.

IX2g

- Generic Safety (GSI) Licensing (LI), or Regulatory Impact (RI) 6.

Priority

- High (H) or Medium (M) 7.

Task Manaaer Name of assigned individual responsible for resolution 8.

Office / Division / Branch - The Office, Division, and Branch of the Task Manager who has lead responsibility for resolving the issue.

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9.

Action level Active Technical assistance funds

(

appropriated for resolution and/or Task Manager actively pursuing resolution Inactive -

No technical assistance funds appropriated for resolution, Task Manager assigned to more important work, or no Task Manager assigned Resolved -

All necessary work has been completed and no additional resources will expended 10.

Status

- Coded summary as follows:

NR - (Nearly-Resolved);

3A - (Resolved with requirements);

38 - (Resolved with 82 requirements);

5 - (Licensing or Regulatory Impact issue that has been assigned resources for completion) 11.

TAC Number

- Task Action Control (TAC) number assigned to the issue b

vi 12.

Resolution Date.

- Scheduled resolution date for the issue 13.

Work Authorization

- Who or what authorized work to be done on the issue 14.

flh

- Financial identification number assigned to contract (if any) for technical assistance i

15.

Contractor

- Contractor name 1

1 16.

Contract Title

- Contract Title (if contract issue) 17.

Work Secoe

- describes briefly the work necessary to technically resolve and complete the generic issue 18.

Status

- Describes current status of work j

19.

Affected Documents

- Identifies documents into which the technical resolution will be incorporated i

20.

Problem / Resolution

- Identifies problem areas and describes what actions are necessary to resolve them l

21.

Milestones Selected significant milestones:

(a) the " original" scheduled dates reflect the original Task Action Plan plus additional milestone dates added during i

task resolution; (b) changes in the original scheduled dates are listed under " Current";

(c) actual completion dates are listed under " Actual" 4

0

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TABLE 1 GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION.

ISSUES RESOLVED AND ISSUES INTEGRATED FY-83 THROUGH FY-93 (4TH 00ARTER)

FY-83 FY-84 FY-85 ISSUE Gis New Gls Gls New GIs Gis New Gls TYPE Start +

Issues - Resolved - End Start +

Issues - Resolved - End Start +

Issues - Resolved - End USI 16 0

2 14 14 0

2 12 12 0

0 12 HIGH 24 2

0 26 26 1

1 26 22*

41 6

57 NEDIUM 31 2

0 33 33 4

3 34 28*

1 10 19 NR

'20 3

4 19 19 5

9 15 15 11 7

19 TOTAL:

91 7

6 92 92 10 15 87 77 53 23 107 FY-86 FY-87 ISSUE Gis New Gis ISSUE Gls New Gis Gis TYPE Start +

Issues - Resolved - End TYPE Start + Issues

- Resolved - Integrated End USI 12 0

1 11 USI 11 0

2 0

9 HIGH 57 (16)*

3 38 HIGH 38 4

3 7

32 HEDIUM 19 7

2 24 MEDIUM 24 1

4 5

16 NR 19 (3)*

3 13 NR 13 0

1 1

11 TOTAL:

101 (12)*

9 86 TOTAL:

86 5

10 13 68

• Extensive revisions to Human Factors issues resulted in priority changes.

T1-1 As of 4th Quarter FY-93

TABLE I (Continued)

GENERIC SAFETY ISSUES SCHEDULED FOR RESQLUTIQL ISSUES RESOLVED AND ISSUES INTEGRATED FY-83 THROUGH FY-93 (4TH OUARTER)

FY-88 FY-89 ISSUE Gls New Gis Gis ISSUE Gis New Gls Gls TYPE Start + Issues - Resolved - Integrated - End TYPE Start + issues - Resolved - Integrated - End USI 9

0 5

0 4

USI 4

0 4

0 0

HIGH 32 1

6 3

24 HIGH 24 1

9 0

16 MEDIUM 16 2

2 3

13 MEDIUM 13 1

3 1

10 NR 11 1

3 0

9 NR 9

0 2

0 7

TOTAL:

68 4

16 6

50 TOTAL:

50 2

18 1

33 FY-90 FY-91 ISSUE GIs New Gls Gis ISSUE GIs New GIs Gis TYPE Start + Issues - Resolved - Integrated - End TYPE Start +

lssues - Resolved - Inte9 rated - End HIGH 16 0

2 0

14 HIGH 14 2

2 0

14 MEDIUM 10 1

2 0

9 MEDIUM 9

3 1

0 11 NR 7

0 3

0 4

NR 4

1 1

0 4

TOTAL:

33 1

7 0

27 TOTAL:

27 6

4 0

29 FY-92 ISSUE GIs New GIs GIs TYPE Sta.: t + Issues - Resolved - Integrated - End HIGH 14 0

4 0

10 MEDIUM 11 1

2 0

10 NR 4

2 1

0 5

TOTAL:

29 3

7 0

25 TI-2 As of 4th Quarter FY-93 O

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TABLE 1 (Continued)

GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION.

ISSUES RESOLVED AND ISSUES INTEGRATED FY-83 THROUGH FY-93 (4TH OVARTER)

FY-93 ISSUE Gis New GIs GIs TYPE Start + lssues

- Resolved - Integrated -

End HIGH 10 0

7 0

3 NEDIUM 10 0

3 0

7 NR 5

2 0

0 7

TOTAL:

25 2

10 0

17 4

l TI-3 As of 4th Quarter FY-93

Table lA

SUMMARY

OF GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION.

ISSUES RESOLVED. AND ISSUES INTEGRATED Cumulative Total _s FY-83 Throuah FY-93 (4TH Ouarter)

ISSUE Gis New Gis GIs TYPE Start + Issues - Sub-Total - Resolved -

Integrated" - Remainder USI 16 0

16 16 0

0 HIGH 24 32*

56 43 10 3

MEDIUM 31 17 48 32 9

7 NR 20 22*

42 34 1

7 TOTAL:

91 71 162 125 20 17

• Extensive revisions to Human Factors issues resulted in priority changes in FY-85 and FY-86.

" GIs Intearated FY-81:

Issues 48, 49, and A-30 into Issue 128 Total (13)

Issue 65 into Issue 23 Issues 60; 122.1.a; 122.1.b; 122.1.c; and 125.II.I.b into Issue 124 Issues I.B.I.l(6) and I.B.I.l(7) into Issue 75 Issue B-6 into Issue 119.1 Issue 67.7 into 135-FY-88:

Issue 77 into A-17 Total (6)

Issues 1.D.5(5), II.B.5(1), II.B.5(2), II.B.5(3), and II.F.5 were integrated into the Research Activities Program and were reclassified as Licensing Issues.

FY-89:

Total (1)

Issue 131 was integrated into the External Events IPE Program.

TI-4 As of 4th Quarter FY-93 O

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O TABLE 2 NUMBER OF GENERIC SAFETY ISSUES RESOLVED AND SCHEDULED FOR RESOLUTION (Throuch 41H Ouarter FY-93)

RESOLVED ISSUE PRIORITY FY-83 FY-84 FY-85 FY-86 FY-87 FY-88 FY-89 FY-90 FY-91 FY-92 FY-93 TOTAL USl 2

2 0

1 2

5 4

0 0

0 0

16 HIGH 0

1 6

3 3

6 9

2 2

4 7

43 HEDIUM 0

3 10 2

4 2

3 2

1 2

4 33 NR 4

9 7

3 1

3 2

3 1

1 0

34 Total:

6 15 23 9

10 16 18 7

4 7

11 126 SCHEDULED FOR RESOLUTION ISSUE PRIORITY FY-94 FY-95 FY-96 FY-97 TBD Total HIGH 0

1 1

0 1

3 MEDIUM 4

1 0

0 2

'7 NR 5

0 0

0 2

7 Total:

9 2

1 0

5 17 T2-1

' As of 4th Quarter FY-93

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O TABLE 3 GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved f1-E.2 A-Il Reactor Vessel Naterials USI GL 82-26 01/79 10/82 Toughness A-16 Steam Effects on BWR Core Spray NR MPA D-12 NRR-0P FY83 03/29/83 Distribution A-39 Determination of Safety USI SRP Revision 01/79 10/82 Relief Valve (SRV) Pool Dynamic Loads and Temperature Limits for BWR Containment B-53 Load Break Switch NR SRP Revision NRR-0P FY83 07/28/83 II.E.5.1 (B&W) Design Evaluation NR No. Req.

NRR-OP FY83 03/21/83 IV.C.1 Extend lessons Learned From NR No. Req.

NRR-OP FY83 04/15/83 TMI to Other NRC Programs E.1:E.1 12 BWR Jet Pump Integrity Medium No. Req.

NRR-OP FY83 09/25/84 20 Effects of Electromagnetic NR HUREG/

NRR-0P FY83 11/15/83 Pulse on Nuclear Plant Systems CR-3069 40 Safety Concerns Associated NR MPA B-65 0'/18/83 12/27/83 With Breaks in the BWR Scram System 45 Inoperability of Instruments NR SRP Revision 09/08/83 03/23/84 Due to Extreme Cold Weather T3-1 As of 4th Quarter FY-93

TABLE 3 (Continued 1 EENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-84 (Cont'd) 50 Reactor Vessel Level NR MPA F-26 07/28/83 09/06/84 Instrumentation in BWRs 69 Make-Up Nozzle Cracking in NR MPA B-43 12/06/83 09/27/84 B&W Plants A-1 Water Hammer USI SRP Revision 01/79 03/15/84 A-12 Steam Generator and Reactor USI SRP Revision 01/79 10/83 Coolant Pump Supports 8-10 Behavior of BWR Mark III High SRP Revision NRR-0P FY83 09/10/84 Containments B-26 Structural Integrity of Medium No Req.

NRR-0P FY83 09/27/84 Containment Penetrations B-60 Loose Parts Monitoring NR GL NRR-0P FY83 09/25/84 Systems (LPMS) 1.A.I.4 Long-Term Upgrading of NR New Rule NRR-OP FY83 01/01/84 Operating Personnel II.A.1 Siting Policy Reformulation Medium No Req.

NRR-0P FY83 09/20/84 II.E.5.2 (B&W) Reactor Transient NR NUREG-0667 NRR-0P FY83 09/28/84 l

Response Task force III.D.2.5 Offsite Dose Calculation Manual NR NUREG/

NRR-OP FY83 01/17/84 l

CR-3332 l

T3-2 As of 4th Quarter FY-93 i

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v TABLE 3 (Continued)

GENERIC SAFE 1Y ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved f.hEl 22 Inadvertent Boron Dilution NR GL 85-05 11/05/82 10/15/84 Events A-41 Long Term Seismic Program Medium No Req.

NRR-0P FY83 10/10/84 B-19 Thermal-Hydraulic Stability NR GL 01/03/85 05/21/85 B-54 Ice Condenser Containments Medium NUREG/

NRR-OP FY83 10/22/84 CR-4001 8-58 Passive Mechanical Failures Medium No Req.

NRR-0P FY83 07/09/85 C-11 Assessment of Failure and Medium No Req.

NRR-OP FY83 07/09/85 Reliability of Pumps and Valves I.A.2.2 Training and Qualifications High Policy NRR-0P FY83 06/24/85 of Operating Personnel Statement (No Req.)

I.A.2.6(4)

Operator Workshops Medium No Req.

NRR-0P FY83 09/25/85 1.A.2.7 Accreditation of Training Medium Policy NRR-0P FY83 06/24/85 Institutions Statement (No Req.)

I.A.3.4 Licensing of Additional Medium Policy NRR-0P FY83 02/12/85 Operations Personnel Statement (No Req.)

I.G.2 Scope of Test Program Medium No Req.

NRR-OP FY83 10/05/84 T3-3 As of 4th Quarter FY-93

TABLE 3 (Continued)

GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-85 (Cont'd)

II.B.6 Risk Reduction For Operating High No Req.

NRR-0P FY83 09/25/85 Reactors at Sites With High Population Densities II.B.8 Rulemaking Proceedings on High Degraded Core Accidents (a) Hydrogen Rule Rule /

NRR-OP FY83 07/19/85 (b) Severe Accidents Policy NRR-OP FY83 08/12/85 Statement II.C.1 Interim Reliability Evaluation High No Req.

NRR-OP FY83 07/09/85 Program II.C.2 Continuation of Interim High No Req.

NRR-OP FY83 09/25/85 Reliability Evaluation Program II.E.2.2 Research on Small-Break LOCAs Medium No Req.

HRR-OP FY83 07/25/85 and Anomalous Transients III.A.I.3(2)

Maintain Supplies of Thyroid-NR Policy NRR-0P FY83 08/15/85 Blocking Agent for Public Statement III.A.3.4 Nuclear Data Link Medium No Req.

NRR-0P FY83 06/26/85 III.D.2.3(1)

Develop Procedures to Dis-NR ESRP NRR-OP FY83 08/28/85 criminate Between Sites / Plants Revision 111.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

'i T3-4 As of 4th Quarter FY-93 G

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GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-85 (Cont'd)

Ill.D.2.3(4)

Prepare 4 Sumary Assessment NR ESRP NRR-OP FY83 08/28/85 Revision IV.E.5 Assess Currently Operating High No Req.

NRR-OP FY83 09/25/85 Plants 5.1.$,E.

3 Setpoint Drift in NR Reg Guide NRR-0P FY83 05/19/86 Instrumentation Rev.

(No Req.)

14 PWR Pipe Cracks NR No Req.

NRR-OP FY83 10/04/85 36 Loss of Service Water NR SRP Revision 02/15/84 05/13/86 (No Req.)

61 SRV Discharge Line Break Medium No Req.

11/30/83 08/08/86 Inside the Wetwell Airspace of BWR Mark I and Mark 11 Containments A-43 Containment Emergency USI SRP Revision 01/79 10/85 Sump Perfomance (Req.)

I.C.9 Long-Tem Plan for Upgrading Medium No Req.

NRR-0P FY83 06/07/85 of Procedures III.D.3.1 Radiation Protection Plans High No Req.

NRR-OP FY83 05/19/86 HF1.2 Engineering Expertise on High No Req.

10/01/84 10/28/85 Shift NFl.3 Guidance on Limits and High No Req.

10/01/84 06/26/86 Conditions of Shift Work T3-5 As of 4th Quarter FY-93

TABLE 3 (Continued)

GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-87 91 Main Crankshaft Failures in NR HUREG-1216 07/85 09/87 Transamerica Delaval Diesel (No Req.)

Generators A-46 Seismic Qualification of USl GL 87-02 02/81 02/87 Equipment in Operating Plants (Req.)

A-49 Pressurized Thermal Shock USI Rule / Reg.

12/81 02/87 Guide 1.154 (Req.)

1.A.2.6(1) long-Term Upgrading of High Reg. Guide 10/82 05/87 Training and Qualifications -

1.8 (Req.)

Revise Reg. Guide 1.8 1.A.3.3 Requirement for Operator High No Req.

12/82 01/87 Fitness 1.A.4.2(1)

Research on Training High Reg. Guide 10/84 05/87 Simulators 1.149, Rev. 1 (Req.)

1.B.1.1 Oroanization and Manaaement Lono-Tern Imorovements I.B.I.l(l)

Prepare Draft Criteria Medium No Req.

12/82 01/87 I.B.I.l(2)

Prepare Comission Paper Medium No Req.

12/82 01/87 I.B.I.1(3)

Issue Requirements for the Medium No Req.

12/82 01/87 Upgrading of Management and Technical Resources I.8.1.l(4)

Review Responses.to Determine Medium No Req.

12/82 01/87 Acceptability T3-6 As of 4th Quarter FY-93 9

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TABLE 3 (Continued)

GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved U-EE 86 Long Range Plan for Dealing NR NUREG-0313, 10/84 01/88 with Stress Corrcsion Cracking Rev. 2, i

in BWR Piptog GL 88-01 (Req.)

93 Steam Binding of Aux 111ary High GL 88-03 10/84 02/88 Feedwater Pumps (No Req.)

1.D.4 Control Room Design Standard Medium No Req.

NRR-0P.FY83 03/88 II.E.4.3 (Containment) Integrity Check High NUREG-1273 NRR-OP FY83 03/88 (No. Req.)

B-5 Ductility of Two-Way Medium No Req.

NRR-0P FY83 04/88 Slabs and Shells and Buckling Behavior of Steel Containments HF8 Maintenance and Surveillance High Policy 03/85 05/88 Program Statement (No Req.)

1.A.4.2(4)

Review Simulators for High Rule NRR-OP FY83 05/88 Conformance (Req.)

A-44 Station Blackout USI Rule / Reg.

01/79 06/88 Guide 1.155

.(Req.)

43 Reliability of Air SystesT High GL 88-14 12/87 09/88 (Req.)-

. T3-7 As of 4th Quarter.FY,

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TABLE 3 (Continued)

GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-88 (Cont'd) 66 Steam Generator Requirements NR NUREG-0844 11/83 09/88 (No Req.)

102 Human Error in Events involving NR HUREG-1192 02/85 09/88 Wrong Unit or Wrong Train (No Req.)

125.11.7 Reevaluate Provision to High HUREG-1332 09/86 09/88 Automatically Isolate feedwater (No Req.)

from Steam Generator During a Line Break A-3,4,5 Steam Generator Tube Integrity USI NUREG-0844 01/79 09/88 (No Req.)

A-45 Shutdown Decay Heat Removal USI NUREG-1289 02/81 09/88 Requirements (No Req.)

fT-E2, 51 Proposed Requirements for Medium GL 89-13 06/83 08/89 Improving Reliability of Open (Req.)

Cycle Service Water Systems 82 Beyond Design Bases Accidents Medium NUREG-1353 12/07/83 04/89 in Spent Fuel Pools (No Req.)

99 RCS/RHR Suction Line Interlocks High GL 88-17 08/85 11/88 on PWRs (Req.)

101 BWR Water Level Redundancy High GL 89-11 05/06/85 06/89 (Req.)

T3-8 As of 4th Quarter FY-93 O

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O BBLE 3 (Cp_RLIDutil GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-89 (Cont'd) 115 Enhancement of the Reliability High NUREG-1341 07/07/86 04/89 of Westinghouse Solid State (No Req.)

Protection System 122.2 Initiating feed-and-Bleed High No Req.

01/86 04/89 124 Auxiliary Feedwater System NR 2 Plant-02/86 01/89 Reliability Specific Backfits (Req.)

125.1.3 SPDS Availability NR GL 89-06 05/06/88 04/89 (No. Req.)

134 Rule on Degree and Experience High Policy 01/86 08/89 Requirements for Senior Statement Operators (No Req.)

A-17 Systems Interaction USI NUREG-1174 01/79 08/89 (No Req.)

A-40 Seismic Design Criteria USI SRP Revisions 01/79 09/89 (Req.)

A-47 Safety Implications of Control USI GL 89-19 02/81 08/89 Systems (Req.)

A-48 Hydrogen Control Measures and USI Rules (Req.)

02/81 04/89 Effects of Hydrogen Burns on Safety Equipment HFl.1 Shift Staffing High Reg. Guide 10/01/84 05/89 1.114, Rev. 2 (Req.)

T3-9 As of 4th Quarter FY-93

TABLE 3 (Continued)

EENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date

(( umber Title Priority Product for Resolution Resolved FY-89 (Cont'd)

HF4.1 Inspection Procedure for High IN 86-64 10/01/84 10/88 Upgraded Emergency Operating (No Req.)

Procedures I.F.1 Expand QA list High No Req.

NRR-0P FY83 01/89 II.C.4 Reliability Engineering High No Req.

NRR-0P FY83 10 o8 f

II.E.6.1 Test Adequacy Study Medium GL 89-10 NRR-OP FY83 06/89 (Req.)

fl22 70 PORV and Block Valve Medium GL 90-06 05/14/84 06/90 Reliability 75 Generic Implications of NR Reg.

10/19/83 05/90 ATWS Events at the Salem Nuclear Power Plant 84 CE PORVs NR SECY-90-232 02/27/85 06/90 (No Req.)

94 Additional low-Temperature High GL 90-06 07/23/85 06/90 Overpressure Protection for (Req.)

LWRs 103 Design for Probable NR GL 89-22 09/04/85 11/89 Maximum Precipitation (Req.)

T3-10 s of 4th Quarter FY-93 a

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TABLE _3 (Continued)

GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved FY-90 (Cont'd)

A-29 Nuclear Power Plant Medium No Req.

NRR-OP FY83 10/89 Design for the Reduction of Vulnerability to Industrial Sabotage C-8 Main Steam line High No Req.

NRR-OP FY83 03/90 Isolation Valve leakage Control Systems f.ld.1 128 Electrical Power High GL 91-06, 11/28/86 09/91 Reliability GL 91-11 (Req.)

130 Essential Service Water High GL 91-13 03/10/87 09/91 System Failures at (Req.)

Multiplant Sites 135 Steam Generator Medium No Req.

05/27/86 03/91 and Steam Line Overfill

!!.J.4.1 Revise Deficiency NR Rule NRR-OP FYB3 07/91 Report Requirements (Req.)

T3-ll As of 4th Quarter FY-93

JABLE 3 (Continued'.

GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved f.1-21 29 Bolting Degradation or High No Req.

NRR-OP FY-83 10/91 Failure in Nuclear Power Plants 73 Detached Thermal Sleeves NR NUREG/

08/20/91 09/92 CR-6010 No. Req.

79 Unanalyzed Reactor Medium GL 92-02 NRR-OP FY-84 05/92 Vessel Thermal Stress No. Req.

During Natural Convection Cooldown 87 Failure of HPCI Steam High No Req.

09/26/85 12/91 Line Without Isolation 113 Dynamic Qualification High No Req.

07/02/87 08/92 Testing of Large Bore Hydraulic Snubbers 121 Hydrogen Control for High No Req.

09/26/85 03/92 Large, Dry PWR Containments 151 Reliability of ATWS Medium No Req.

08/27/91 09/92 Recirculation Pump Trip in BWRs T3-12 As of 4th Quarter FY-93 O

O O

O O

O JABLE 3 (Continued)

GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Resolution Date Approved Date Number Title Priority Product for Resolution Resolved i

FY-93 105 Interfacing Systems LOCA High No Req.

06/11/85 06/93 at LWRs 120 On-Line Testability Medium No Req.

11/23/90 03/93 of Protection Systems 142 Leakage Through Electrical Medium No Req.

06/20/90 03/93 1solators 143 Availability of Chilled Water High No Req.

03/29/91 09/93 Systems and Room Cooling 153 Loss of Essential Service High No Req.

03/29/91 06/93 Water in LWRs B-56 Diesel Reliability High Reg Guides:

HRR-OP FY83 06/93 1.9, F.ev. 3; 1.160 (Req.)

HF4.4 Guidelines for Upgrading Other High No Req.

10/01/84 07/93 Procedures HF5.1 Local Control Stations High No Req.

10/01/84 06/93 HF5.2 Review Criteria for Human High No Req.

10/01/84 06/93 Factors Aspects of Advanced Controls and Instrumentation 1.D.3 Safety System Status Monitoring Medium No Req.

NRR-0P FY83 09/93 T3-13 As of 4th Quarter. FY-93.

. ~.

- - ~. -

. ~.

O O

O TABLE 4 17 GSIs SCifEDULED FOR RESOLUTION fBY FISCAL YEAR)

PRIORITY FY-94 FY-95 FY-96 FY-97 FY-98 FY-99 180 TOTAL HIGH 15 23 II.H.2 3

MEDIUM 24 B-61 78 7

57 B-55 106 B-17 NR 83 166 7

145 168 155.1 B-64 1.D.5(3)

TOTAL:

9 2

1 0

0 0

5 17 T4-1 As of 4th Quarter FY-93

.2..

Table 4A GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION Date Resolution Current Issue lead Office /

Approved for Date at end Resolution Number Title Division / Branch Priority Resolution of FY-92 Date 15 Radiation Effects on Reactor RES/DSIR/EIB H

02/89 03/96 03/96 Vessel Supports 23 Reactor Coolant Pump Seal RES/DSIR/EIB H

NRR-OP FY83 07/94 12/94 Failures II.H.2 Obtain Technical Data on the RES/DSR/AE8 H

NRR-OP FY83 06/93 TBD Conditions Inside the 1HI-2 Containment Structure 24 Automatic Emerger.cy Core Cooling RES/DSIR/SAIB H

07/23/91 03/94 08/94 System Switch to Recirculation 57 Effects of Fire Protection RES/DSIR/SAIB H

06/08/88 08/93 12/93 System Actuation on Safety-Related Equipment 78 Honitoring of Fatigue Transient RES/DSIR/EIB H

07/10/92 TBD TBD Limits for Reactor Coolant System 106 Piping and Use of Highly RES/DSR/RBSB H

11/03/87 12/92 10/93 Combustible Gases in Vital Areas B-17 Criteria for Safety-Related RES/DSR/HFB M

03/22/82 04/93 09/94 Operator Actions B-55 Improve Reliability of Target RES/DSIR/ElB H

NRR-OP FY83 06/96 TBD Rock Safety Relief Valves B-61 Allowable ECCS Equipment Outage RES/DSR/PRAB H

NRR-0P 12/93 12/94 Periods 83 Control Room Habitability RES/DSIR/SAIB NR 08/83 05/93 12/93 T4-2 As of 4th Quarter FY-93 O

O O

O O

O Table 4A (Continued)

GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION 1

Date Resolution

-Current Issue lead Office /

Approved for Date at end Resolution Number Title Division / Branch Priority Resolution of FY-92 Date 145 Improve Surveillance and RES/DSIR/PRAB NR 02/11/92 10/93 01/94 Startup Testing Programs 155.1 Nore Realistic Source RES/DSIR/SAIB NR 02/26/92 03/93 01/94 Term Assumptions 166 Adequacy of Fatigue Life NRR NR 04/01/93 NA TBD of Metal Components 168 Environmental Qualification NRR NR 04/01/93 NA TBD of Electrical Equipment B-64 Decommissioning of Nuclear NMSS/LLWM/LLRB NR NRR-OP FY84 10/92 10/93 Reactors I.D.5(3) On-Line Reactor Surveillance RES/DE/EMEB NR NRR-OP FY83 01/93 10/93 Systems Total: 17 T4-3 As of 4th Quarter FY-93 p

i4

-4 e

w

- - * = -

v' s

r-m. w ee

-ere ae

- m

-o, y

a m

.ma s

v+ -mnm m

.se-*-

---m.=-e-w n

- l IABLE 5 NUMBER OF GENERIC ISSUES PRIORITIZED FROM FY-83 TilROUGil THE 4TH DVARTER OF FY-93 Issue Tvoe fl-El fl-01 Ey-B1 f1-El fl-2Z fl-fA f102 EY-22 fl-21 EY-22 fl-?l Inl.Al Issues Identified 56 19 54 45*

6 3

38 3

29 7

5 265 To Be Prioritized Issues identified 19 2

0 1

1 2

0 0

0 0

0 25 l

To Be Reprioritized Total:

75 21 54 46 7

5 38 3

29 7

5 290 New Issues (Entered into GIMCS)

High 2

1 41 6

4 1

1 0

2 0

0 SS Medium 2

4 1

1 1

2 0

1 3

2 0

17 Nearly-Resolved 3

5 6

1 0

1 0

0 1

2 2

21 Subtotal:

7 10 48 8

5 4

1 1

6 4

2 96 l

Resolved 4

0 1

0 0

1 1

1 0

2 1

11 i

Low 1

4 0

2 1

0 0

2 0

4 3

17 l

Drop 1

4 4

6 13 9

2 8

5 24 6

82 l

RI/LI O

O 4

6 0

2 33 1

1 3

0 50 l

Integrated 8

2 3

6 0

1 1

3 0

5 0

29 l

lotal issues 21 20 60 28 19 17 38 16 12 42 12 285 Prioritized:

Remaining Issues

+54

+1

-6

+18

-12

-12 0

-13

+17

-35

-7 5

To Be Prioritized or Reprioritized:

• Extensive revisions to Human Factors issues resulted in priority changes.

l T5-1 As of 4th Quarter FY-93 E

O O

O IMLLs GENERIC ISSUES PRIORITIZED AS OF 4TH OVARTER FY-93 Action Item /

Identification Date Current Issue No.

Title Date Prioritized Priority I.E.~.El 31 Natural Circulation Cooldown 09/82 07/83 S(I.C.1) 32 Flow Blockage in Essential Equipment Caused 09/82 05/83 S(51) by Corbicula 33 Correcting Atmospheric Dump Valve Opening Upon 09/82 08/82 S(A-47)

Loss of Integrated Control System Power 39 Potential for Unacceptable Interaction Between 09/82 07/82 S(25) the CRD System and Non-Essential Control Air System 40 Safety Concerns Associated with Pipe Breaks in 09/82 07/83 NR the BWR Scram System 41 BWR Scram Discharge Volume Systems 09/82 07/83 RESOLVED 42 Combination Primary /Secondarv t..cm LGCA 09/82 04/83 S(18) 45 Inoperability of Instru % ation Due to Extreme 09/82 09/83 NR Cold Weather 46 Loss of 125 Volt DC Bus 09/82 02/83

$(76) 47 Loss of Off-Site Power 09/82 04/83 RESOLVED 50 Reactor Vessel level Instrumentation in BWRs 09/82 07/83 NR 51 Proposed Requirements for Improving the 09/82 06/83 MEDIL41 Reliability of Open Cycle Service Water Systems 52 SSW Flow Blockage by Blue Mussels 09/82 05/83 S(51) 56 Abnormal Transient Operating Guidelines as 09/82 02/83 S(A-45/I.D.1)

Applied to a Steam Generator Overfill Event 58 Inadvertent Containment Flooding 09/82 08/83 DROP 64 Identification of Protection System Instrument 10/82 02/83 RESOLVED Sensing Lines 65 Probability of Core-Melt Due to Component 02/83 07/83 HIGH Cooling Water System Failures 77 Flooding of Safety Equipment Compartments by 06/83 09/83 HIGH Back-Flow Through Floor Drains 79 Unanalyzed Reactor Vessel Thermal Stress During 06/83 07/83 MEDIUM Natural Convection Cooldown D-1 Advisability of a Seismic Scram 09/82 06/83 LOW IV.E.2 Plan for Early Resolution of Safety Issues 09/82 06/83 RESOLVED T6-1 As of 4th Quarter FY-93

TABLE 6 (Continued)

GENERIC ISSUES PRIORITIZED AS OF 4TH 00ARTER FY-93 Action item /

Identification Date Current Issue No.

Title Date Prioritized Priority FY-84 34 RCS Leak 09/82 02/84 DROP 35 Degradation of Internal Appurtenances in LWRs 09/82 02/84 LOW 36 Loss of Service Water 09/82 02/84 NR 43 Contamination of instrument Air Lines 09/82 11/83 DROP 44 Failure of Saltwater Cooling System 09/82 10/83 S(43) 48 LCO for Class IE Vital Instrument Buses in 09/82 10/83 NR Operating Reactors 49 Interlocks and LCOs for Redundant Class IE 09/82 07/84 MEDIUM Tie Breakers 53 Consequences of a Postulated Flow Blockage 09/82 09/84 DROP Incident in a BWR 60 Lamellar Tearing of Reactor Systems Structural 10/82 11/83 S(A-12)

Supports 61 SRV Line Break Inside the BWR Wetwell Airspace 10/82 11/83 MEDIUM of Mark I and II Containments 66 Steam Generator Requirements 06/83 11/83 NR 68 Postulated loss of Auxiliary Feedwater System 06/83 04/84 HIGH 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 PORY and Block Valve Reliability 06/83 05/84 HEDIUM 75 Generic Implications of ATWS Events at the Salem 06/83 10/83 NR Nuclear Plant 80 Pipe Break Effects on Control Rod Drive Hydrau-06/83 01/84 LOW lic Lines in the Drywells of BWR Mark I and 11 Containments 82 Beyond Design Basis Accidents in Spent Fuel 08/83 12/83 MEDIUM Pools 90 Technical Specifications for Anticipatory Trips 02/84 08/84 LOW 92 Fuel Crumbling During LOCA 04/83 07/84 LOW B-65 lodine Spiking 09/82 06/84 DROP T6-2 As of 4th Quarter FY-93 O

O O

O O

O TABLE 6 (Continued)

GENERIC ISSUES PRIORITIZED AS OF 4TH OVARTER FY-93 Action item /

Identification Date Current Issue No.

Title Date Prioritized Prierity 37 Steam Generator Overfill and Combined Primary 09/82 05/85 S(A-47) and Secondary Blowdown 54 Valve Operator-Related Events Occurring 09/62 06/85 S(II.E.6.1)

During 1978,1979, a:

1980 55 Failure of Class IE 5 Jaty-Related Switchgear 09/82 03/85 DROP Circuit Breakers 59 Technical Specification Requirements for Plant 10/82 02/85 RI Shutdown 67 Steam Generator Staff Actions 06/83 03/85 NEDIUM 81 Potential Safety Problems Associated With Locked 11/83 10/84 DROP Doors and Barriers in Nuclear Power Plants 83 Control Room Habitability 11/83 06/84 NR 84 CE PORVs-11/83 02/85 NR 85 Reliability of Vacuum Breakers Connected 11/83 07/85 DROP to Steam Discharge Lines Inside BWR Containments 86' NRC Pipe Cracking Review Group Study 12/83 10/84 NR 87 Failure of HPCI Steam Line Without isolation 01/84 09/85 HIGH 91 Transamerica Delaval Emergency Diesel Generator 03/84 07/85 NR Main Crankshaft Failure 93 Steam Binding of Auxiliary Feedwater Pumps 07/84 10/84 HIGH 94 Additional Low Temperature Overpressure 08/84 07/85 HIGH Protection For Light Water Reactors 98 CRD Accumulator Check Valve Leakage 09/84 02/85 DROP 99 RCS/RHR Suction Line Interlocks on PWRs 09/84 08/85 HIGH 10m BWR Water Level Redundancy 09/84 05/85 HIGH 102 Human Error in Events Involving Wrong Unit or 09/84 02/85 S(HF-02)

Wrong Train 103 Design For Probable Maximum Precipitation 10/84 09/85 NR 105 Interfacing Systems LOCA at LWRs 10/84 06/85 HIGH 108 BWR Suppression Pool Temperature Limits 12/84 02/85 RI(LOW) 119 Piping Review Committee Recommendations 07/85 09/85 RI(HR) 121 Hydrogen Control For large Dry PWR 08/85 09/85 HIGH Containments i

T6-3 As of 4th Quarter FY-93

TABLE 6 (Continued)

GENERIC ISSUES PRIORITIZED AS OF 4TH OVARTER FY-93 Action item /

Identification Date Current Issue No.

Title Date Prioritized Priority FY-85 (Cont'd)

B-19 Thermal-Hydraulic Stability 02/83 01/85 NR B-50 Post Operating Basis Earthquake Inspection 02/83 04/85 RI(LOW)

B-59 N-1 Loop Operation in BWRs and PWRs 02/83 06/85 RESOLVED HF-01 Human Factor Program Plan (HFPP with 24 08/83 10/84 HIGH subtasks)

HF-02 Maintenance and Surveillance Program Plan 04/84 03/85 HIGH (MSPP with 10 subtasks)

FY-86 21 Vibration Qualification of Equipment 03/83 06/86 DROP 30 Potential Generator Missiles - Generator Rotor 09/82 10/85 DROP Retaining Rings 74 Reactor Coolant Activity Limits for Operating 06/83 05/86 DROP Reactors 97 PWR Reactor Cavity Uncontrolled Exposures 09/84 10/85 3(III.D.3.1) 111 Stress Corrosion Cracking of Pressure Boundary 01/85 11/85 LI Ferritic Steels in Selected Environments 112 Westinghouse RPS Surveillance Frequencies and 01/85 10/85 RI(R)

Out-of-Service Times 114 Seismic-Induced Relay Chatter 03/85 06/86 S(A-46) 115 Reliability of Westinghouse Solid State 04/85 07/86 HIGH Protection System 122.1.a Common Mode Failure of Isolation Valves in 08/85 01/86 HIGH Closed Position-122.1.b Recovery of Auxiliary Feedwater 08/85 01/86 MEDIUM 122.1.c Interruption of Auxiliary Feedwater Flow 08/85 01/86 HIGH 122.2 Initiating Feed-and-Bleed 08/85 01/86 HIGH 122.3 Physical Security System Constraints 08/85 01/86 LOW 124 Auxiliary Feedwater System Reliability 12/85 02/86 NR T6-4 As of 4th Quarter FY-93 O

O O

O O

O TABLE 6 (Continued)

GDi[EIC ISSUES PRIORITIZED AS OF 4TH OVARTER FY-93 Action item /

Identification Date Current issue No.

Title Date Prioritized Priority FY-86 (Cont'd) 125.I.2.a PORV Reliability - Test Program 11/85 06/86 S(70) 125.I.2.b PORY Reliability - Surveillance 11/85 06/86 5(70) 125.I.2.c Auto Block Valve Closure 11/85 06/86 DROP 125.I.2.d Equipment Qualification for Feed-and-Bleed 11/85 06/86 S(A-45)

Environment 125.11.3 Review Steam / Feed Line Break Mitigation 11/85 08/86 DROP Systems for Single Failure 125.11.4 OTSG Dryout and Reflood Effects 11/83 09/86 DROP 125.11.7 Reevaluate Provisions to Automatically 11/85 09/86 HIGH lsolate Feedwater from Steam Generator During Line Break 125.II.9 Enhance Feed-and-Bleed Capability 11/85 08/86 S(A-45) 125.11.14 Remote Operation of Equipment Which Must 11/85 08/86 LOW Now be Operated locally 133 Update Policy Statement on Nuclear Plant 07/86 07/86 LI Staff Working Hours 134 Rule on Degree and Experience Requirement 07/86 07/86 HIGH C-4 Statistical Methods for ECCS Analysis 02/83 06/86 RI(R)

C -5 Decay Heat Update 02/83 06/86 RI(R)

C-6 LOCA Heat Sources 02/83 06/86 RI(R)

E1::al.

113 Dynamic Qualification Testing of Large Bore 03/85 07/87 HIGH Hydraulic Snubbers 125.I.1 Availability of the STA 11/85 07/87 DROP 125.I.4 Plant-Specific Simulator 11/85 02/87 DROP 125.I.7.b Realistic Hands-On Training 11/85 03/87 DROP 125.I.8 Procedures and Staffing for Reporting to 11/85 06/87 DROP NRC Emergency Response Center T6-5 As of 4th Quarter FY-93

~

- ~. -

TABLE 6 (Continued) ftENERIC ISSUES PRIORITIZED AS OF 4TH OUARTER FY-93 Action Item /

Identification Date Current Issue No.

Title Date Prioritized Priority FY-87 (Cont'd) 125.II.l.a Two-Train AFW Reliability 11/85 10/86 UROP 125 II.l.b Review Existing AFW Systems for Single Failure 11/85 10/86 HIGH 125.II.l.c NUREG-0737 Reliability Improvements 11/85 10/86 DROP 125.II.l.d AFW Steam and Feedwater Rupture Control 11/85 10/86 OROP System /ICS Interactions in B&W Plants 125.11.2 Adequacy of Existing Maintenance Requirements 11/85 06/87 DROP for Safety-Related Systems 125.11.5 Thermal-Hydraulic Effects of loss and 11/85 06/87 DROP Restoration of Feedwater on Primary System Components 125.11.6 Reexamine PRA Estimates of Core Damage Risk 11/85 03/87 OROP from loss of All Feedwater 125.11.8 Reassess Criteria for Feed-and-Bleed Initiation 11/85 03/87 DROP 125.II.10 Hierarchy of Impromptu Operator Actions 11/85 02/87 OROP 125.II.12 Adequacy of Training Regarding PORV Operation 11/85 03/87 DROP 127 Testing and Maintenance of Manual Valves in 05/86 06/87 LOW Safety-Related Systems 128 Electrical Power Reliability 05/86 11/86 HIGH 130 Essential Service Water Pump Failures at 06/86 03/87 HIGH Multiplant Sites 135 Steam Generator and Steam Line Overfill 05/86 06/87 MEDIUM f1.EE 43*

Reliability of Air Systems 04/87 12/87 HIGH 55*

Failure of Class IE Safety-Related Switchgear 09/85 02/88 DROP Circuit Breakers to Close on Demand 57 Effects of Fire Protection System Actuation 09/82 06/88 MEDIUM on Safety-Related Equipment

• Previous priority evaluation published in NUREG-0933.

T6-6 As of 4th Quarter FY-93 O

O O

O O

O TABLE 6 (Continued)

GENERIC ISSUES PRIORITIZED AS OF 4TH OVARTER FY-93 Action Item /

Identification Date Current Issue No.

Title Date Prioritized Priority FY-88 (Cont'd) 62 Reactor Systems Bolting Applications 10/82 08/88 S(29) 88 Earthquakes and Emergency Planning 01/84 10/87 RESOLVED 104 Reduction of Baron Dilution Requirements 10/84 08/88 DROP 106 Piping and Use of Highly Combustible Gases 10/84 11/87 MEDIUM in Vital Areas 125.I.3 SPDS Availability 11/85 05/88 NR 125.I.6 Valve Torque Limit and Bypass Switch Settings 11/85 12/87 DROP 125.I.7A Recover Failed Equipment 11/85 12/87 DROP 125.11.11 Recovery of Main Feedwater as Alternative to AFW 11/85 06/88 DROP 125.11.13 Operator Job Aids 11/85 03/88 DROP 126 Reliability of PWR Main Steam Safety Valves 03/86 03/88 LI 136 Storage and Use of Large Quantities of 09/86 03/88 LI Cryogenic Combustibles on Site C-14 Storm Surge Model for Coastal Sites 02/83 05/88 LI(DROP)

III.D.1.1(2) Review Information on Provisions for leak 12/82 09/88 DROP Detection III.D.I.l(3) Develop Proposed System Acceptance Criteria 12/82 09/88 DROP fl-El 15*

Radiation Effects on Reactor Vessel Supports 09/88 02/89 HIGH 125.I.5 Safety Systems Tested in All Conditions 11/85 11/88 DROP Required by Design Basis Analysis 131 Potential Seismic Interaction Involving the 07/86 07/89 S(IPE)

Moveable In-Core Flux Mapping System Used in Westinghouse P1 ants-139 Thinning of Carbon Steel Piping in LWRs 12/86 11/88 RESOLVED l

B-31 Dam Failure Model 02/83 02/89 LI(DROP) 0-2 ECCS Capability for Future Plants 06/83 10/88 DROP

. Previous priority evaluation published in NUREG-0933.

T6-7 As of 4th Quarter.FY-93

TABLE 6 (Continued)

GENERIC ISSUES PRIORITIZED AS OF 4TH 00ARTER FY-93 Action Item /

Identification Date Current issue No.

Title Date Prioritized Priority FY-90 63 Use of Equipment Not Classified as 10/82 02/90 DROP Essential to Safety in BWR Transient Analysis 71 Failure of Resin Demineralizer Systems and 06/83 02/90 LOW Their Effects on Nuclear Power Plant Safety 81*

Impact of Locked Doors and Barriers on 12/86 02/90 DROP Plant and Personnel Safety 95 Loss of Effective Volume for Containment 08/84 02/90 RESOLVED Recirculation Spray 96 RHR Suction Valve Testing 04/84 02/90 S(105) 107 Generic Implications of Main Transformer 11/84 02/90 LOW Failures 109 Reactor Vessel Closure Failure 12/84 02/90 DROP 116 Accident Management 04/85 09/90 5

117 Allowable Time for Diverse Simultaneous 05/85 02/90 DROP Equipment Outages 129 Valve Interlocxs to Prevent Vessel 05/86 02/90 DROP Drainage During Shutdown Cooling 137 Refueling Cavity Seal Failure 10/86 05/90 DROP I40 Fission Product Removal Systems 03/87 02/90 DROP 141 L8LOCA With Consequential SGTR 04/87 05/90 DROP 142 Leakage Through Electrical Isolators 06/87 06/90 MEDIUM B-29 Effectiveness of Ultimate Heat Sinks 02/83 08/90 LI(RESOLVED)

B-32 Ice Effects on Safety-Related Water Supplies 02/83 08/90 S(153) f.l.:;21 24 Automatic Emergency Core Coolin9 03/83 07/91 MEDIUM System Switch to Recirculation 38 Potential Recirculation System 09/82 08/91 DROP Failure as a Consequence of Ingestion of Containment Paint Flakes or Other Fine Debris T6-8 As of 4th Caarter FY-93 9

O O

O O

O TABLE 6 (Continued)

GENERIC ISSUES PRIORITIZED AS OF 4TH 00ARTER FY-93 Action item /

Identification Date Current Issue No.

Title Date Prioritized Priority 72 Control Rod Drive Guide Tube Support Pin 06/83 10/90 DROP Failures 73 Detached Thermal Sleeves 06/83 08/91 NR 100 Once-Through Steam Generator Level 09/84 09/91 DROP 120 On-line Testability of Protection Systems 08/85 11/90 MEDIUM 143 Availability of Chilled Water Systems and 10/87 03/91 HIGH Room Cooling 150 Overpressurization of Containment 04/89 08/91 DROP Penetrations 151 Reliability of Anticipated Transient 04/89 08/91 MEDIUM Without Scram Recirculation Pump Trip in BWRs 153 Loss of Essential Service Water in LWRs 05/90 03/91 HIGH A-19 Digital Computer Protection System 02/83 11/90 LI B-22 LWR Fuel 02/83 06/91 DROP f.1-E 2

Failure of Protective Devices on Essential 05/83 07/92 OROP Equipment 76 Instrumentation and Control Power 06/83 04/92 DROP Interactions 78 Monitoring of Fatigue Transient Limits for 06/83 07/92 MEDIUM Reactor Coolant System 81' Impact of Locked Doors and Barriers on 08/91 04/92 LOW Plant and Personnel Safety 89 Stiff Pipe Clamps 02/84 08/92 MEDIUM 110 Equipment Protection Devices on 12/84 06/92 DROP Engineered Safety Features 118 Tendon Anchorage Failure 07/85 01/92 RESOLVED

• Previous Priority Published in NUREG-0933 T6-9 As 4th Quarter FY-93

TABLE 6 (Continued)

GENERIC ISSUES PRIORITIZED AS OF 4TH OUARTER FY-93 Action Item /

Identification Date Current Issue No.

Title Date Prioritized Priority FY-92 (Cont) 123 Deficiencies in the Regulations 11/85 12/91 DROP Governing DBA and Single Failure Criterion Suggested by the Davis-Besse Incident of June 9,1985 132 RHR Pumps Inside Containment 07/86 03/92 DROP 138 Deinerting of BWRs With MARK I and II 10/86 10/91 LOW Containments During Power Operations Upon Discovery of Reactor Cooling System Leakage or a Train of a Safety System Inoperable 144 Scram Without a Turbine / Generator Trip 03/88 03/92 LOW 145 Improve Surveillance and Startup Testing 09/88 02/92 NR Programs 147 Fire-Induced Alternate Shutdown / Control Room 04/89 08/92 LI Panel Interactions 148 Smoke Control and Manual Fire-Fighting 04/89 08/92 Effectiveness 154 Adequacy of Emergency and Essential Lighting 09/90 01/92 LOW 155.1 Mere Realistic Source Term Assumptions 02/91 02/92 NR 155.2 Establish Licensing Requirements for 02/91 04/92 RI Non-Operating Facilities 155.4 Improve Criticality Calculations 02/91 08/92 DROP 155.5 More Realistic Severe Reactor Accident Scenario 02/91 06/92 DROP 155.6 Improve Decontamination Regulations 02/91 08/92 DROP 155.7 Improve Decomissioning Regulations 02/91 04/92 DROP 156.1.1 Settlement of Foundations and Buried Equipment 02/91 08/92 S(IPEEE) 156.1.2 Dam Integrity and Site Flooding 02/91 01/92 DROP 156.1.3 Site Hydrology and Ability to Withstand Floods 02/91 01/92 DROP 156.1.4 Industrial Hazards 02/91 03/92 DROP T6-10 As of 4th Quartt? FY-93 O

O O

O O

O TABLE 6_fcontinued)

GENERIC ISSUES PRIORITIZED AS OF 4TH OUARfER FY-93 Action item /

Identification Date Current Issue No.

Title Date Prioritized Priority FY-92 (Cont) 156.1.5 Tornado Missiles 02/91 01/92 DROP 156.1.6 Turbine Missiles 02/91 10/91 DROP 156.2.1 Severe Weather Effects on Structures 02/91 01/92 DROP 156.2.2 Design Codes, Criteria, and Load 02/91 07/92 DROP Combinations 156.2.3 Containment Design and Inspection 02/91 05/92 DROP 156.2.4 Seismic Design of Structures, Systems, 02/91 03/92 DROP and Components 156.3.1.1 Shutdown Systems 02/91 03/92 DROP 156.3.1.2 Electrical Instrumentaion and Control 02/91 03/92 DROP 156.3.2 Service and Cooling Water Systems 02/91 03/92 DROP 156.3.3 Ventilation Systems 02/91 09/92 DROP 156.3.4 Isolation of High and Low Pressure 02/91 12/91 DROP Systems 156.3.5 Automatic ECCS Switchover 02/91 11/91 S(24) 156.3.6.1 Emergency AC Power 02/91 02/92 S(B-56) 156.3.8 Shared Systems 02/91 06/92 DROP 156.4.1 RPS and ESFS Isolation 02/91 11/91 S(142) 156.4.2 Testing of the RPS and ESFS 02/91 03/92 S(120) 157 Containment Performance 10/91 02/92 RESOLVED EY-M 146 Support Flexibility of Equipment and Components 01/89 09/93 RESOLVED 149 Adequacy of Fire Barriers 04/89 10/92 LOW 152 Design Basis for Valves That Hight Be 03/90 01/93 LOW Subjected to Significant Blowdown loads 155.3 Improve Design Requirements for Nuclear 02/91 01/93 DROP Facilities 156.3.6.2 Emergency DC Power 02/91 03/93 LOW 159 Qualification of Safety-Related Pumps While 10/91 09/93 DROP Running on Minimum Flow T6-ll As of 4tF Quarter FY-93

TABLE 6 (Continued)

GENERIC ISSUES PRIORITIZED AS OF 4TH 00ARTER FY-93 Action Item /

Identification Date Current Issue No.

Title Date Prioritized Priority FY-93fCont.)

160 Spurious Actions of Instrumentation Upon 10/91 09/93 DROP Restoration of Power 161 Use of Non-Safety-Related Power Supplies in 10/91 03/93 DROP Safety-Related Circuits 162 Inadequate Technical Specifications for Shared 10/91 07/93 DROP Systems at Multiplant Sites When One Unit Is Shut Down 164 Neutron Fluence in Reactor Vessel 10/92 03/93 DROP 166 Adequacy of Fatigue Life of Metal Components 04/93 04/93 NR 168 Environmental Qualification of Electrical 04/93 04/93 NR Equipment T6-12

/

4th Quarter FY-93 O

O O

O O

O TABLE 7_

GENERIC ISSUES TO BE PRIORITIZED AS OF 4th OVARTER FY-93 Action item /

Identification Current issue No.

Title Date Schedule 156 SEP Issues 156.6.1 Pipe Break Effects on Systems and Components 02/91 12/93 158 Performance of Power-Operated Valves Under 10/91 11/93 Design Basis Conditions 163 Multiple Steam Generator Tube Leakage 06/92 12/93 165 Safety and Safety / Relief Valve Reliability 10/92 12/93 167 Combustible Gas Storage Facilities 06/93 180 TOTAL: 5 l

T7-1 As of 4th Quarter FY-93

O O

O TABLE 8 GENERIC ISSUES TO BE REPRIORITIZED AS OF 4TH OVARTER FY-93 Action item /

Previous identification Current Issue No.

Title Priority Date Schedule NONE 1

4 4

T8-1 As of.4th Quarter FY-93

O O

O TABLE 9 REGULATORY IMPACT ISSUES SCHEDULED FOR RESOLUTION Date Resolution Current Issue lead Office /

Approved for Date at end Resolution.

Number Title Division / Branch Priority Resolution of FY-92 Date NONE 5

T9-1 As of 4th Quarter FY-93

.-..- -..u.

O O

O TABLE 10 LICENSING ISSUES SCHEDULED FOR RESOLUTION Lead Office /

Issue Division /

Resolution Number Title Branch Date 67.5.1 Reassessment of Radiological Consequences RES/DSIR/RPSI 02/94 147 Fire-Induced Alternate Shutdown / Control Room RES/DSIR/SAI6 10/93 Panel Interactions 148 Smoke Control and Manual Fire-Fighting Effectiveness RES/DSIR/SAIB 11/93 I.D.5(5)

Disturbance Analysis Systems RES/DSR/HFB 11/93 TOTAL: 4 T10-1 As of 4th Quarter FY-93

.~

/

RUN DATE. 10/20/93 INDEX OF ISSUES GENERIC ISSUE MANAGEMENT CONTROL SYSTEM ISSUE NUMBER T ITLE PAGE 15 RADIATION EFFECTS ON REACTOR VESSEL SUPPORTS 1

23 REACTOR COOLANT PUMP SEAL FAILURES 5

24 AUTOMATIC EMERGENCY CORE COOLING SWITCHOVER TO RECIRCULATION 9

57 EFFECTS OF FIRE PROT. SYS. ACTUATION ON SAFETY-RELATED EQUIP.

12 67.5,1 REASSESSMENT OF SGTR DESIGN BASIS 15 78 MONITORING OF FATIGUE fRANSIENT LIMITS FOR REACTOR COOLANT 18 83 CONTROL ROOM HABITABILITY 20 105 INTERFACING SYSTEMS LOCA AT LWRS 23 106

. PIPING AND USE OF HIGHLY COMDUSTIBLE GASES IN VITAL AREAS 27 143 AVAILABILITY OF CHILLED WATER SYSTEM AND ROOM COOLING 31 145 ACTIONS TO REDUCE COMMON CAUSE FAILURES 33 147 FIRE-INDUCED ALTERNATE SHUTDOWN / CONTROL ROOM PANEL INTERAC110NS 35 148

- SMOKE CONTROL AND MANUAL FIRE-FIGHTING EFFECTIVENESS 37 153 LOSS OF ESSENTIAL SERVICE WATER SYSTEM IN LWRS 39 155.1 MORE REALISTIC SOURCE TERM ASSUMPTIONS-41 166 ADEQUACY OF FATIGUE LIFE OF METAL COMPONENTS 44 168 ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT 46 B-17 CRITERIA FOR SAFETY-RELATED UPERATOR ACTIONS 48 B-55 IMPROVE RELIABILITY OF TARGET ROCK SAFETY-RELIEF VALVES 50 B-56' DIESEL GENERATOR RELIABILITY 53 B-61 ALLOWABLE ECCS EQUIPMENT OUTAGE PERIODS 57 B-64 DECOMMISSIONING OF. REACTORS 60' l

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RUN DATE: 10/20/93 INDEX OF ISSUES GENERIC ISSUE MANAGEMENT CONTROL SYSTEM ISSUE NUMBER T IT LE PAGE HF 44 GUIDELINES FOR UPGRADING OTHER PROCEDURES 62 HF 5 1 LOCAL CONTROL STATIONS 64 HF 5.2 REV. CRIT. FOR HUMAN FACTORS ASPECTS 00 ADV 50NTROLS AND INSTRUMENT.

66 I.D.3 SAFETY SYSTEM STATUS MONITORING 68 I.D.5(3)

ON-LINE REACTOR SURVEILLANCE SYSTEMS TO I.D.5(5)

DISTURBANCE ANALYSIS SYSTEMS 72 II H.2 OBTAIN DATA DN CONDITIONS INSIDE TMI-2 CONTAINMENT 74 9

9 9

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U RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMEN) CONTROL SYSTEM PAGE:

1 ISSUE NUMBER: 15 TITLE: RADIATION EFFECTS ON REACTOR VESSEL SUPPORTS IDENTIFICATION DATE: 06/80 PRIORITIZATION DATE: 02/89 TYPE: GSI PRIORITY: H TASK MANAGER:

R.

JOHNSON OFFICE / DIVISION / BRANCH: RES /DSIR/EIB ACTION LEVEL: ACTIVE STATUS:.

TAC NUMBERS-RESOLUTION DATE: 03/96 WORK AUTHORIZATION: FEB.

8, 1989 MEMO FROM E.

BECKJORD TO R.W.

HOUSTON FIN CONTRACTOR CONTRACT TITLE A2256 ANL SHIPPINGPORT SHIELD TANK TESTING (MED A3841 BNL TROJAN SUPPORT STABILITY ANALYSIS (ES B]

00415 ORNL TROJAN SHIELD FLUX ATTENUATION (MEBJ (MEB) 85848 MEA MTR IRRADIATION OF STRUCTURAL STEELS B6021 LLNL CONSEQUENCE EVALUATION OF EMBRITTLED RPV SUPPORTS (SSEB) 86224 NIST TROJAN CAVITY DOSIMETRY MEASUREMENT (MED)

G1169 MPD NETWOR NUCLEAR MATERIALS DATA RETRIEVAL FROM THE MPD NETWORK (EIB)

L1098 ORNL HEAVY.SECTION STEEL IRRADIATION PROGRAM (MEB)

LI191 PAL ASSOCI RPV SUPPORTS TECHNICAL ASSISTANCE (EMTB)

L1296 INEL RADIATION EFFECTS ON REACTOR VESSEL SUPPORTS (EIB]

L1386 BNL

-IRRADIATION ANALYSES (EIB)

L2552 ORNL HFIR NEUTRON SPECTRUM MEASUREMENT (EIB)

W0RK SC0PE WORK SCOPE REVISION. (NOTED TO BE UNDERWAY IN LAST PRESSURE VESSEL STEEL SURVEILLANCE SPECIMENS QUARTERLY REPORT):

3.

DETERMINE THE APPLICABILITY OF THE FINDINGS TO 1.

QUANTITATIVELY EVALUATE THE HFIR NEUTRON FLUX OVER THE OPERATING REACTOR PRESSURE VESSEL SUPPORTS FULL ENERGY SPECTRUM 4.

RESOLVE GS!-15 WITH EITHER A GENERIC LETTER TO 2

REEVALUATE THE SIGNIFICANCE OF THE MEASURED AND LICENSEES REQUESTING REASSESSMENT OF RPV SUPPORTS OH A REPORTED CHANGES IN MECHANICAL PROPERTIES OF THE HFIR CLOSE0VT MEMORANDUM IF THE SAFETY ASPECTS CAN BE ANNULLED.

STA TUS 1,

ORNL COMPLETED THE WORK PLANNED UNDER FIN L2552. A 2.

INEL PREPARED A DRAFT REPORT ON GAMMA RADIATION WH{CH FINAL IDRAFT) LETTER REPORT WAS WRITTEN AND DISTRIBUTED MAY BE HELPFUL IN PROVIDING A MEASURE OF GAMMA DPA THE FOR COMMENT A PRELIMINARY TOPICAL REPORT, NUREG/CR-INEL P.I. WAS BRIEFFD ON THE ORNL FINDINGS AND THE 6117, WAS WRITTEN AND DISTRIBUTED FOR COMMENT.

COMMENTS EXPECTED PATH TO RESOLVE GSI-15.

FROM NRC REVIEWERS WERE TRANSMITTED TO THE ORNL P.I.

A 3.

THE TASK MANAGER HAS BEGUN PREPARATIONS TOWARD AN ISSUE NO. COST CONTRACT MODIF ICATION WAS EXECUTED TO ALLOW TIME RESOLUTION PACKAGE AND EXPECTS To MEET THE REMAINING TO ISSUE THE ABOVE REPORTS.

MILESTONES.

AS OF FY93 QUARTER 4

RUN DATE. 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE-2 ISSUE NUMBER.

15 TITLE. RADIATION EFFECTS ON REACTOR VESSEL SUPPOM!S AFFECTED DOCUMENTS PROBLEM / RESOLUTION 10 CFR 50 THE IDEA THAT THE UNEXPECTED IHIGH) SHIFT IN THE FRACTURE ST ANDARD REVIEW PLAN SECTIONS 3.9 AND 5. 4 MODE TRANSITION TEMPERATURE EXHIBITED BY THE HFIR ASME SECTION III SURVEILLANCE SPECIMENS WAS A RESULT OF GAMMA RADIATION DOES ASME SECTION XI NOT LEND ITSELF TG LXPERIMENTAL VERIF ICATION BECAUSE OF THE ASTM STANDARD E1035 TIME REQUIRED TO ACHIEVE CONDITIONS RE PRESE NT ATIVE OF THOSE IN HFIR.

THE PROPOSED RESOLUTION, THEREFORE. MAY HAVE TO REST ON THEORETICAL GROUNDS.

ORIGINAL CURRENT ACTUAL MI LE 5T 0NE5 DATE DATE DATE GSI 15 ASSIGNED TO RES/DSIR/EIB 02/89 DRAFT TAP TO DSIR DEPUTY DIRECTOR 05/89 05/89 DRAFT TAP APPROVED BY DSIR DIRECTOR AND 06/89 07/89 FORWARDED TO OTHER RES DIVISION DIRECTORS AND NRR FOR COMMENT INCORPORATE COMMENTS IN TAP 07/89 09/89 FINAL TAP APPROVED BY DSIR DIRECTOR 08/89 01/90 COMPLETE IRRADIATION DAMAGE CALC 07/90 07/90 COMPLETE SUBTASK 3.1 09/90 09/90 COMPLETE SHIPPINGPORT NST REVIEW 09/90 10/90 TAP REV. 1 TO DSIR DEPUTY DIRECTOR 03/91 02/91 COMPLETE COST / BENEFIT ANAL (INEL) 06/91 06/91 PROVIDE DRAFT SCREEN./ EVAL. ANAL. (INEL) 06/91 05/91 COMPLETE HFIR DOSIMETRY (ORNLi 04/92 04/92 COMPLETE 8/HE ANALYSIS (ORNL]

05/92 05/92 AS OF FY93 QUARTER 4 4

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RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

3 ISSUE NUMBER:

15 TITLE: RADIATION EFFECTS ON REACTOR VESSEL SUPPORTS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE PkbVkbbihkR Lb[bAlbbLkikbN[kbRNLh

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-+

08/93 PROPOSE SUPPORTS RADIATION MODEL-09/93 09/93 PROPOSE ISSUE RESOLUTION PATH 11/93 11/93 DRAFT PACKAGE TO DSIR DIRECTOR (REVIEW) 01/92 01/94 PROPOSED RESOLUTION PACKAGE TO OTHER OFFICES 02/92 02/94 PROPOSED RESOLUTION TO CRGR AND ACRS 07/93 05/94 PROPOSED RESOLUTION PACMAGE TO BE ISSUED FOR 08/92 08/94 PUBLIC COMMENT (INCLUDES DRAFT GL)

END PUBLIC COMMENT PERIOD 11/92 11/94 FINAL RESOLUTION PACKAGE INCLUDING 03/92 02/95 COMM INFO PAPER PREPARED BY EIB FINAL RESOLUTION PACKAGE TO DSIR DIRECTOR 03/93 03/95 (APPROVE) r FINAL RESOLUTION PACKAGE TO OTHER OFFICES FOR 05/93 07/95 REVIEW FINAL RESOLUTION PACKAGE TO CRGR AND ACRS 07/93 09/95 FINAL RESOLUTION PACKAGE TO NRR FOR ISSUANCE 10/93.

11/95 AS OF FY93 QUARTER 4 6

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RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

5 ISSUE NUMBER.

23 TITLE: REACTOR COOLANT PUMP SEAL FAILURES IDENTIFICATION DATE: 12/80C PRIORITIZATION DATE: 04/83C TYFC: GSI PRIORITY: H TASK MANAGER:

K.

SHAUKAT OFFICE / DIVISION / BRANCH: RES /DSIR/EIB ACTION t.EVEL: ACTIVE STATUS:

TAC NUMBERS:

RESOLUTION DATE: 12/94 WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN, (APPENDIX G)

FIN CONTRACIOR CONTRACT TITLE A3751 BNL REACTOR COOLANT PUMP (RCP) SEAL INTEGRITY A3771 BNL ASSESS EFFECT OF MECH. MAINT. RCP SEAL A3806 BNL EVAL. ADEQ. OF RCP SEAL INSTR. & RESP. TO RCP A6322 INEL RCP SHAFT SEAL BEHAVIOR DURING ST. BLACKOUT B2953 PNL REACTOR COOL. PUMP SEAL FAIL. VAL. IMP. ANALYSIS B3049

-ETEC LEAK RATE ANALYSIS OF WESTINGHOUSE RCP DITGO SCIENTECH REG. ANAL. FOR GI-23 RCP SEAL FAIIURES WDRK SC0PE khkkkPkbkkhkkkhbbEhkhkkVkhkbkbkhbbh bbbbLb kkKk kk h kbREbbbkkb[hkkLkkktbhkkhkh PORATE WORK NECESSARY TO COMPLETE GSI 65, REVIEW ACCEPTABLE LEVEL COMMENSURATE WITH THE POTENTIAL SAFETY PWR RCP SEAL FAILURES CAUSED BY MECHANICAL FAILURES CONSEQUENCES OF SEAL F AILURE.

THE PROGRAM CONSISTS OF AND LOSS OF SEAL COOLING TO ASCERTAIN IF INCREASED NRC THE FOLLDWING MAJOR TASKS:

REQUIREMENTS ARE NECESSARY TO MINIMIZE SEAL FAILURES.

TASK I - DETERMINE ACTUAL SEAL FAILURE MECHANISMS.

EVALUATE THE EFFECTS OF SYSTEM DESIGN, MATERIALS, TASK 2 - EVALUATE RCP SEAL COOLING FOR ALL MODES OF OPERA-OPERATION, TESTING, AND MAINTENANCE ON SEAL FAILURE TION FOR WHICH SEAL COOLING IS REQ'D USING THE MECHANISMS. REVIEW THE RELIAB, OF SEAL COOLING SYSTEMS RELIABILITY OF TYPICAL RCP SEAL COOLING SYSTEM AND IDENTIFY METHODS TO MINIMIZE THE EFFECTS OF LOSS OF DESIGNS.

SEAL COOLING.

PERFORM A RISK ASSESSMENT OF SEAL FAILURE TASK 3 - REVIEW HECHANICAL AND MAINTENANCE-INDUCED FROM MAINTENANCE AND MECHANICAL EFFECTS.

FAILURE MECHANISMS.

THIS PROGRAM WILL DETERMINE WHAT STEPS THE NRC TASK 4-FEASIBILITY STUDY TO IDENTIFY MOST EFFECTIVE FIX STATUS kkhkkbkbEkkbLkhkkkkbR kNkbRMkkkbhbNLhhhkhhbEb RkbbLkkbkkbbkbEbb$kbbtkhbkhEbRkkkkEbbtkkbR5khkLhhkb MAY 2, 1991. TO INFORM LICENSEES OF THE POTENTIAL IMPACT NUREG-1401.

THE STAFF DECIDED TO PROCEED WITH A RULEMAKING ON SB0 ANALYSES. A FEDERAL REGISTER NOTICE WAS PUBLISHED FOR OFF-NORMAL CONDITIONS, WHILE THE NORMAL CONDITIONS ARE APRIL 19, 1991, REQUESTING PUBLIC COMMENT ON DRAFT BEING ADDRESSED UY A PROPOSED GENERIC LETTER.

AS OF FY93 QUARTER 4

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RUN DATE: 10/20/93 GENERIC ISSUE MANAG(MENT CONTROL SYSTEM PAGE-6 ISSUE NUMBER.

23 TITLE. REACTOR COOLANT PUMP SEAL FAILURES AFFECTED DOCUMENTS PROBLEM / RESOLUTION (1) THE F Oll DWING REPORTS HAVE BEEN ISSUED-h0NE.

NUREG/CH-1077, " REACTOR COOLANT PUMP SHAFT SEAL BEHAVIOR" NUREG/CR-4294, " LEAK RATE ANALYSIS OF THE WESTINGHOUSE REACTOR COOLANT PUMP" NUREG/CR-4821, " REACTOR COOLANT PUMP SHAFT SEAL STABILITY DURING STATION BLACMOUT" NUREG/CR-4643,

• EVALUATION OF CORE DAMAGE SEQUENCES INITIATED BY LOSS OF REACTOR COOLANT PUMP SEAL COOLING" NUREG/CR-4400, "THE IMPACT OF MECHANICAL AND MAINTENANCE-INDUCED FAILURE OF MAIN REACTOR COOLANT PUMP SEALS ON PLANT SAFETY" NUREG/CR-4544, "RE ACTOR COOL ANT PUMP SE AL-RE L ATED INSTRU-MEN 1ATION AND OPERATOR RESPONSE" NUREG/CR-4948, " TECHNICAL FINDINGS RELATED TO GI-23, REACTOR COOLANT PUMP SEAL FAILURES" NUREG/CR-5167,

• COST BENEFIT ANALYSIS FOR GI-23, REACTOR COOLANT PUMP SEAL FAILURE" NUREG/CR-5918 " ANALYSIS OF PUBLIC COMMENTS ON GI-23, REACTOR COOLANT PUMP SEAL FAILURE" (IN PREPARATIONI (2) RULEMAKING RM-333 (3) REGULATORY GUIDE DG-1008 ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE TAP ISSUED FOR COMMENT 04/83 03/83 TAP APPROVED BY DSI DIR 10/83 10/83 ISSUED REQUEST FOR PROPOSAL TO BNL FOR 11/83 11/83 COMPONENT COOLING WATER PRA TRANSFER RESOLUTION REPONSIBILITY FROM DSI TO C6/84 06/84 DE TRANSFER RESOLUTION RESPONSIBILTY FROM DE TO 05/85 05/85 DST /GIB AS OF FY93 QUARIER 4 O

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\\

d RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

7 ISSUE NUMBER: 23 TITLE: REACTOR COOLANT PUMP SEAL FAILURES ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE bbhPLkTh bbbbkkh bF bkbMbRbbhD PkhT Ohhhh 12h8h SEAL FAILURES, INCLUDING LER SEARCH,REV 0F INDUST. EXP.& REV.0F BWR SCR.(TASK 1)

EVAL RCP SEAL COOLING, INCL DETERM. EFFECT 12/84 08/86 0F LOSS COOLING, EVAL RELIA 8.

OF COOLING SYS.

AND REV. RCP SEAL COOLING INSTR- (TASK 21 4

EVALUATE MECHANICAL AND MAINTENANCE-INDUCED 01/85 01/88 FAILURE MECHANISMS (TASK 3)

DRAFT SCIENTECH REPORTS TO IDENTIFY MOST 03/E5 01/89 EFFECTIVE FIX. (TASK al REVIEW & FINALIZE SCIENTECH REPORTS 05/89 03/90 DTR PACKAGE COMPLETE 07/85 04/90 DIVISION DIRECTOR REVIEW COMPLETED 08/85 05/90 ACRS REVIEW OF DTR COMPLETE 11/85 09/90 CONCURRENCE BY OTHER OFFICES 09/85 10/90 DTR SENT TO CRGR 10/85 10/90 CRGR REVIEW OF DTR COMPLETE 11/85 03/91 FRN OF ISSUANCE OF PROPOSED RESOLUTION FOR 12/85 04/91 PUBLIC COMMENT DRAFT PERFORMANCE 07/91 08/91 PUBLIC COMMENT PERIOD ENOS 09/91 11/91 COMPLETE REVIEW AND COMPILATION OF PUBLIC 04/86 02/92 COMMENTS RECEIPT OF GUIDANCE FROM EDO ON RULEMAKING 05/92 11/92 AS OF FY93 QUARTER 4

. _.. _....... _. _. _... ~ _. _, _... _. _

RUK DATE. 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE.

8 ISSUE NUMBER.

23 TITLE: REACTOR COOLANT PUMP SEAL FAILURES ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE PkbPbSkD PPkbEbHkbhkkFbkhbkMLbPhkkhkbh

((/hh

[h/hh PREPARE PROPOSED RULE

.09/92 05/93 DIVISION DIRECTOR REVIEW OF PROPOSED RULE 10/92 06/93 COMPLETED CONCURRENCE BY OTHER OFFICES OF PROPOSED 11/92 10/93 RULE LETTER TO NRR FOR BWR SFALS UNDER 580 05/93 10/93 ACRS AND CRGR REVIEW OF PROPOSED RULE 12/92 10/93 COMPLETE DRAFT RESOLUTION OF TECHNICAL 03/92 12/93 COMMENTS AND PREPARE RESPONSES TO ALL COMMENTS PROPOSED RULE TO ED0/ COMMISSION 02/93 12/93 FRN OF ISSUANCE OF PROPOSED RULE FOR PUBLIC 04/93 01/94 COMMENT PUBLIC COMMENT PERIOD ENDS 06/93 03/94 RESOLVE PUBLIC COMMENTS 08/93 06/94 PREPARE FINAL RULE 10/93 07/94 DIVISION DIRECTOR REVIEW COMPLETED 11/93 08/34 CONCURRENCE BY OTHER OFFICES 12/93 09/94 ACRS AND CRGR REVIEW OF FTR COMPLETED 01/94 10/94 FTR SENT TO ED0/ COMMISSION 03/94 11/94 FRN OF ISSUANCE OF FTR 04/94 12/94 AS OF FY93 OUARTER 4 O

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RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

9 ISSUE NUMBER: 24 TITLE: AUTOMATIC EMERGENCY CORE COOLING SWITCHOVER TO RECIRCULATION IDENTIFICATION DATE: 03/53C PRIORITIZATION DATE: 07/91C TYFE: GSI PRIORITY: M TASK MANAGER: G.

BURDICK OFFICE / DIVISION /DRANCH: RES /DSIR/SAIB ACTION LEVEL: ACTIVE STATUS:

TAC NUMBERS:

RESOLUTION DATE: 08/94 WORK AUTHORIZATION: MEMORANDUM FROM E. BECKJORD TO W.

MINNERS ON JULY 23, 1991 FIN CONTRACTOR CONTRACT TITLE L5hh4 hkk~

kbibM kkb~ Ebbs hhkhbhbVkk kb RkbkRbbLkhkbk WDRK SC0PE kEbbLbkhbh bk kbkh bbbk hhLi bE kbbbhPLkbhkb bh hbbtbbbbhfhhhhbhbEhhkkhkhhkbRkLibEhkEbkbhhhhklLkbbb REEVALUATION OF THE STUDY PERFORMED IN 1981 USING UP-TO-AN AUTOMATIC SWITCHOVER CONTROL SYSTEM THESE RESULTS WILL DATE HUPtAN RELI ABILITY AND AUTOMATED EQUIPMENT PRA BE USED TO PROVIDE THE BASES FOR A STAFF RECOMMENDATION TO ANALYSIS METMODS TO DETERMINE THE CORE DAMAGE FREQUENCY AND THE COMMISSION REGARDING WHETHER OR NOT PWR'S THAT CURRENTLY-RISK CHANGES (AND UNCERTAINTY) THAT WOULD RESULT FROM RELY ON A MANUAL SWITCHOVER SYSTEM SHOULD BE REQUIRED TO CHANGE 0VER TO AN AUTOMATIC SWITCHOVER CONTROL SYSTEM.

THIS INSTALL AN AUTOMATIC SWITCHOVER SYSTEM REEVOLUATION WILL ALSO INCLUDE MAKING AN ESTIMATE OF WHAT IT STATUS CONTRACT WORK UNDERWAY.

FIRST LETTER REPORT (TASK 4.01, DECEMBER 1992.

-MODEL FOR MANUAL SWITCHOVER) GUBMITTED DURING LAST WEEK OF AFFECTED DOCUMENTS PROBLEM / RESOLUTION PbhENhkkLbHkNbhhhbhRP hbRKhkbbE[khhbkkhhkRhkhbbbkhbhkbhkkkkbhbIPPRbVkL OF HUMAN FACTORS CONSULTANT. WORK HAS RECENTLY (1/5/93)

BEEN DELAYED BY NRC REQUEST FOR ADDITIONAL WORK REGARDING-JUSTIFICATION FOR HUMAN FACTORS METHOD SELECTED BY REPLACE '

I MENT HUMAN FACTORS CONSULTANT. SEA DRAFT REPORT WAS LATE.

ADDITIONAL ANALYSES AND EXTENSIVE REVISION OF THE DRAFT DOCUMENT ARE RFOUIRED. A SECOND DRAFT MUST BE SUDMITTED, t

AS OF FY93 QUARTER 4 i

i I

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RUN DATE. 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

10 1

6 ISSUE NUMBER: 24 TITLE: AU10MATIC EMERGENCY CORE COOLING SWITCHOVER TO RECIRCULATION ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE PRktkhihERYbbbhbbkbkkkbh/hkbbkkkkkbh5.2' hk)hh hk/hh SEA PREPARE DRAFT TASK ACTION PLAN 03/92 05/92 RFP TO SEA 04/92 04/92 l

ACCEPT SE A PROPOSAL (BEGIN WORK j 08/92 08/92 l

COMPLETE HF METHODS EVAL. (TASK 1) 10/92 12/92 APPLY TECHNIQUE (TASK 2) 10/92 03/93 DEST EST. COST OF CONVERSION (TASK 5) 01/93 01/93 DETERMINE CDF (TASK 3) 12/92 04/93 DETERMINE RELEASE (TASK 4) 12/92 04/93 DRAFT REPORT SUBMITTAL (TASK 6) 02/93 05/93 STAFF COMMENTS TO SEA 03/93 09/93 SUBMITTAL OF REDRAFT 11/93 11/93 STAFF COMMENTS TO SEA 12/93 12/93 SUBMIiTAL OF CAMERA-READY COPY (TASK 8) 04/93 01/94 siAFF-PREPARED RESOLUTION DOCUMENT --

06/93 02/94 l

RES DIRECTOR CONCUR STAFF-PREPARED RESOLUTION DOCUMENT --

08/93 03/94 ACRS AND CRGR REVIEW STAFF-PREPARED RESOLUTION DOCUMENT --

12/93 05/94 PUBLIC COMMENTS INCORPORATED STAFF-PREPARED RESOLUTION DOCUMENT --

01/94 06/94 EDO APPROVAL AS OF FY93 QUAR TE R 4 l

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l

.I RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

11 ISSUE NUMBER: 24 TITLE: AUTOMATIC EMERGENCY CORE COOLING SWITC:40VER TO RECIRCULATION I

ORIGINAL CURRENT ACTUAL j

HILESTONES DATE DATE DATE STAFF-PREPARED RESOLUTION DOCUMENT --

03/94 08/94 NRC APPROVED

- r e

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1 t

4 I

f AS OF FY93. QUARTER 4 i

6

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RUN DATE. 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE.

12 ISSUE NUMBER 57 TITLE EFFECTS OF FIRE PROT. SYS. ACTUATION ON SAFETY-RELATED EQUIP.

IDENTIFICATION DATE. 09/82C PRIORITIZATION DATE. 06/88C TYPE GSI PRIORITY M TASK MANAGER.

R.

WOODS OFFICE / DIVISION /0 RANCH-RES /DSIR/SAIB ACTION LEVEL: ACTIVE STATUS:

TAC NUMBERS RESOLUTION DATE 12/93 WORK AUTHORIZATION. MEMO TO D SHERON F ROM E. BECKJORD DATED 6/8/88.

s FIN CONTRACTOR CONTRACT TITLE bkkb[

hhh khkbhEkkkhhkbhbkhkbhbkkhkkhkbhkbhkbhhhhhkkh[bkhhh)PkkLkkkkkkh/

SCOPING STUDY ONLY L1220 INEL GENERIC ISSUE $7, " EFFECTS OF FIRE PROTECTION SYSTEM ACTUATION ON SAFETY-RELATED EQUIPMENT" LI]34 SNL GENERIC ISSUE 57, " EFFECTS OF FIRE PROTECTION SYSTEM ACTUATION ON SAFE TY-RE L ATED EQUIPMENT" L1592 NIST GENERIC ISSUE $7, EFFECTS OF FIRE PROTECTION SYSTEM ACTUATION ON SAFETY RELATED EQUIPMENT.

W0RK SC0PE kbhbhkbbkbkkkhkPRbhEbhkbhkhhikkbikPhkhhkhkbbhkb PL hk hkLkbbbkh kkkk hbhE khb hkhkL kkkk bkLhhkhI DAMAGE TD PLANT EQUIPMENT WITH CONSIDERABLE FREQUENCY AND CUTSETS DEVELOPMENT, RISK E STIMATES, AND VAL UE -IMPACT SAFETY IMPLICATIONS. A PROGRAM TO RESOLVE GI-57 WAS ANALYSES OF POTENTIAL BACKFITS, INCLUDING UNCERTAINTY AND INITIATED IN FY 1989 INVOLVING THE EVALUATION OF FOUR PLANTS SENSITIVITY ANALYSES.

A TASK TO DEVELOP AND APPLY A AND THE COLLECTION OF GENERIC PLANT DATA TO SUPPORT A DECISIONMAKING UNDER UNCERTAINTY ANALYSIS METHOD WAS ADDED GENERIC EVALUATION OF THE SAFETY CONCERNS OF GI-57 THESE IN RESPONSE TO ACRS COMMENTS ON USE OF PRA'S.

EVALUATIONS INVOLVE REVIEWS OF FPS DESIGNS AND LAYOUTS, STATUS kbbkhkkbhbkbkkhLkkPbkhkbhkhkhkhPLkkhkVlbkhkbhhkh bkbkhbkR khkh PRbPbbEbkEbbLbhkbhkhibbbkhkbkhhhk RECEIVED FOR PUBLICATION IN SEPTEMBER 1992 THE DRAFT PRINCIPAL CDF-CONTRIBUTING EVENTS AS PART OF THE IPEEE AND FINAL GENERIC EVALUATION RE POR T WAS RECE IVED IN AUGUST RESOLVE ISSUE 57 WiTH NO NEW REQUIREMENTS. FINAL PACKAGE 1992 AND WAS PUBLISHED AS A SERIES OF NUREG/CR REPORTS IN WITH RESOLUTION IN NRR FOR CONCURRENCE.

AFFECTED DOCUMENTS PROBLEM

--......-.................../ RESOLUTION AS OF FY93 QUARTER 4 O

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13 ISSUE NUMBER 57 TITLE: EFFECTS OF FIRE PROT. SYS, ACTUATION ON SAFETY-RELATED EQUIP.

ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE DEVELOP PRA SCOPE OF WORK 10/88 10/88 COMPLETE RISK ANALYSIS 02/89 04/89

^

DEVELOP TAP 02/89 06/89 PRELIMINARY DISCUSSION OF DRAFT STATEMENT OF 06/89 06/89 WORK WITH CONTRACTOR (S)

DEVELOP S0W AND WORK AUTHORIZATION 07/89 07/89 ISSUE CONTRACTS 08/89 08/89 EPRI DRAFT REPORT ON EFFECTS OF FIRE 09/89 11/89 SUPPRESSANTS LOADING OF PRA MODEL DATA FOR IP-2 EVALUATION 11/89 11/89 (W PLANT]

DRAFT REPORT ON IP-2 EVALUATION (INEL) 05/90 05/90 DRAFT REPORT SNL/INEL ON SURRY/IP-2 EVALUA-07/90 05/90 TIONS EQE SUBCONTRACT REPORT TO SNL 08/90 10/90 FINAL DRAFT CONTRACTOR REPORT TO RES FOR TWO 01/91 01/91 WESTINGHOUSE PLANTS DECISION ON B&W OR CE PLANT EVALUATION 01/91 01/91 DRAFT CONTRACTOR'S REPORT TO RES FOR GE PLANT 05/91 06/91 DRAFT SNL NUREG/CR FOR B&W PLAN 1 08/91 02/92 DRAFT SNL NUREG/CR FOR GENERIC EVAL.

05/92 08/92 REGULATORY ANALYSIS COMPLETE 06/92 10/92 PROPOSED RESOLUTION TO DD 11/92 04/93 AS OF FY93 QUARTER 4

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14 ISSUE NUMSER 57 TITLE. EFFECTS OF FIRE PROT. SYS ACTUATION ON SAFETY-RELATED EQUIP.

ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE COMMUNICATION TO NRR RE MOST VULNERABLE

.07/93 07/93 PLANT COMPLETE ACRS REVIEW 07/91 08/93 MEMD TO NRR RE MOST VULNERABLE PLANT 10/93 10/93 l

ISSUE CLOSE00T MEMO FROM RES DIRECTOR TO EDO 07/92 12/93 AS OF FY93 QUARTER 4 4

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15 ISSUE NUMBER:

67.5.1 TITLE: REASSESSMENT OF SGTR DESIGN BASIS IDENTIFIC% TION DATE: 06/83C PRIORITIZATION DATE: 03/85C TYPE: LI PRIORITY:

TASK MANAGER: J. HOPENFELD OFFICE / DIVISION / BRANCH: RES /DSIR/EIB ACTION LEVEL: ACTIVE STATUS: 5 TAC NUM0ERS: NONE RESOLUTION DATE: 02/94 WORK AUTHORIZATION: MEMO TO R. BERNER0 FROM H. DENTON DATED 3/25/85 i

FIN CONTRACTOR CONTRACT TITLE kh8hh khkl kkhk khhhbkkkkb khb k hPkbhkhM hF hbhk khbkhEhhh B0832 ORNL STEAM GENERATOR TUBE RUPTURE WDRK SC0PE RkkhkLbkikhbkhEkhbbhkEkkkhh5hbbkFhkkEbbkkhkbLLbbkhb bbkhbhkbhkhhhkkhkbbbEth kbkkhikhkbbkkkbkhkbhbkbhhk A STEAM GENERATOR TUBE RUPTURE.

COMPLETE THE EXPERIMENTS SRP.

RESOLUTION OF GI 67.5.2 IS INCLUDED IN THE SCOPE OF ON IODINE PARTITION COEFFICIENTS. EVALUATE THE VALIDITY THIS ISSUE.

OF SRP IODINE SPIKE REQUIREMENTS IN LIGHT OF RECENT DATA STATUS THE'ORNL EXPERIMENTS 70 DETERMINE THE IODINE PARTITION INEL EVALUATION OF PROPOSED MODEL MODIFICATIONS ON OFFSITE COEFFICIENT ARE COMPLETE.

THE INEL EVALUATION OF PLANT DOSE HAS DEEN COMPLETED. A DRAF T RESOLUTION PACKAGE HAS IGDINE SPINING DATA HAS BEEN COMPLETED, INEL ANALYSIS OF BEEN PREPARED AND IS UNDER MANAGEMENT REVIEW.

SECONDARY SYSTEM PH FOLLOWING AN SGTR HAS BEEN COMPLETED.

AFFECTED DOCUMENTS PROBLEM / RESOLUTION.

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ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE PREPARE DRAFT TAP 06/81 06/87 AS OF FY93 QUARTER ~4' r

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17 ISSUE NUMBER: 67 5.1 TITLE: REASSESSMENT OF SGTR DESIGN BASIS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE TRANSMIT TO ACRS RESOLUTION WITH SRP 06/93 08/93 REVISION RECOMMENDATIONS ACRS PRESENTATION 08/93 12/93 RES MEMO TO NRR TRANSMITTING SRP 09/93 01/94 REVISION RECOMMENDATIONS RESOLUTION TO EDO 09/93 02/94 l

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I'8 ISSUE NUMBER: 78 TITLE: MONITORING OF FATIGUE TRANSIENT LIMITS FOR REACTOR COOLANT IDENTIFICATION DATE: OS/83C PRIORITIZATION DATE: 07/92C TYPE:

PRIORITY-TASK MANAGER: S. DIAB 0F F ICI / DIVISION /BR ANCH: RES /DSIR/EIB ACTION LEVEL; ACTIVE STATUS: 4 TAC NUMBERS:

RESOLUTION DATE. _ _ _ _

WORK AUTHORIZATION. JULY 10, 1992, MEMORANDUM FROM E.

DECKJORD TO W MINNERS FIN CONTRACTOR CONTRACT TITLE W6077 ANL STATISTICAL ANALYSIS OF FATIGUE DATA WDRK SC0PE TO DEVELOP GUIDANCE ON POTENTIAL FATIGUE DEGRADATION OF GUIDANCE IS APPLICADLE TO THOSE REMAINING YEARS OF PLANT COMPONENT OF THE RCPB FOR ALL OPERATING PLANTS.

THIS OPERATION UNDER THE CURRENT 40-YEAR LICENSE-STATUS bkb bbb kbb bRkbkhkl bkkkbb hkkkb bh hbh RkkbhbR bbbLkbh khkLhbhb bh RElkVkbh bb bP$hb$bkiE hkh5bbk b hk WbEbkbk PRESSURE BOUNDARY {RCPB) DID NOT ACCOUNT ADEQUATELY FOR THE ANL STATISTICAL STUDY OF FATIGUE IS COMPLETED FINAL EFFECTS OF THE REACTOR COOLANT HARSH ENVIRONMENTS DURING CONCLUSIONS CAN BE MADE ABOUT RISK SIGNIFICANI COMPONENTS OPERATION ON THE RCPB FATIGUE RESISTANCE, GENERIC ISSUE 78 FROM THE FATIGUE STANDPOINT.

ALSO, THE STUDY RESULTS MAY BE WAS ESTABLISHED TO ASSESS THE INCREASE IN RISK DUE TO OPERA-USED IN VALUE-IMPACT ANALYSES, IF NECES$ARY, TO SUPPORT ANY TION UNDER THE HARSH ENVIRONMENT.

POSSIBLE BACKFIT REQUIREMENTS BY THE STAFF.

A DRAFT PRA PARAMETRIC STUDY WAS CONDUCTED TO ASSESS THE GENERIC ISSUE 166 ENTITLED " MONITORING OF FATIGUE RISK CONTRIBUTION OF VARIOUS COMPONENTS OF THE RCPB.

THAT TRANSIENT LIMITS FOR REACTOR COOLANT" WAS INITIATED BY AN STUDY WAS ISSUED FOR PEER REVIEW AND COMMENT ON NOVEMBER 20, NRR MEMORANDUM FROM T. MURLEY TO J. SNIEZEK, DATED APRIL 1, 1992.

THE DRAFT PRA STUDY TENTATIVELY IDENTIFIED SOME 1993.

HIGH RISK RCPB COMPONENTS.

ALSO, THE DRAFT PRA STUDY THE OUTCOME OF THE CONTRACTUAL STUDY BY ANL UNDER GI-78 IDENTIFIED SOME AREAS WHERE THERE IS A LACK OF INFORMATION.

WILL BE INTEGRATED IN THE NRR WORK SCOPE AS IT DEVELOPS.

THESE AREAS ARE CURRENTLY LUNDER STUDY BY ANL (CONTRACT THE PROGRESS AND THE DETAILS OF THE ONGOING ANL WORK WILL BE FIN-6077-3).

THE ANL CONTRACT INCLUDES A STATISTICAL MONITORED UNDER GI-78 AFFECTED DOCUMENTS PROBLEM / RESOLUTION

• • • TC BE DETERMINED ***

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RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

20 ISSUE NUMBER-83 TITLE: CONTROL ROOM HABITABILITY IDENTIFICATION DATE: 11/83C PRIORITIZATION DATE: 06/84C TYPE GSI PRIORITY:

TAS6 MANAGER-C FERRELL OFFICE / DIVISION / BRANCH: RES /DSIR/SAIB ACTION LEVEL. ACTIVE STATUS: NR TAC NUMBERS:

RESOLUTION DATE: 12/93 WORK AUTHORIZATION: MEMO FOR H.

DENTON FROM W. DIRCMS, DATED 8/15/83-s FIN CONTRACTOR CONTRACT TITLE A2328 ANL IN PLANT REVIEWS ON CONTROL ROOM HABITABILITY A2334 ANL IN. PLANT REVIEWS ON CONTROL RODM HABITABILITY B2929 PNL MATH. MODELS CONTROL ROOM HABITABILITY D2096 SAIC CONTROL ROOM VULNERABIf ITIES L2560 PNL CONTROL ROOM HABITABILITY SYSTEM REVIEW MODELS W0RK SC0 PE ASSESS ADEQUACY OF HABITABILITY CRITERIA NRR REVIEW, SUMMARIZING RESULTS AND PROVIDING RECOMMENDATIONS, PLANT SYSTEMS AND COMPONENTS AND TESTING PRodEDURES TWO TASKS (DEVELOP MODELS OF CHALLENGES TO HABITABILITY RELATIVE TO CONTROL ROOM HABlTABILITY. INCLUDING THOSE AREAS AND REVIEW PROCEDURES) HAVE BEEN ADDED OF ACRS CONCERN.

A FINAL REPORT WILL BE PREPARED STATUS FINAL REPORT FROM SAIC ON " CONTROL ROOM HABITABILITY SYSTEM NRR GENERIC LETTER IN CONCURRENCE. PNL HABITABILITY MODEL REVIEW MODELS" (NUREG/CR-5659) ISSUED IN DECEMBER 1990.

RECEIVED: BEING CHECKED.

PNL CONTRACT EXTENDED UNTIL FINAL REPORT FROM PNL ON EXTRAN COMPUTER CODE APRIL 1994 TO COMPLETE NUREG/CR AND PROVIDE CONSULTATION 10 (NUREG/CR-56561 ISSUED IN MARCH 1991.

PNL CONTRACTOR NRR.

REPORT ON T0XICITY LEVELS ISSUED JULY 1991 (NUREG/CR-5669).

AFFECTED DOCUMENTS PROBLEM / RESOLUTION kRP b 4$ h54$k kh$b h$b k$ h$b$ h hIk h hIb PhbPbbkbbLHkkhkkhPLkbkbbbHbLb$

9.5 1: RGS 1.78, 1.95} 1.29 1.52, 1.101, 1 140; NUREG-0737 ITEM lII D 3.4, II B.

10 CFR 50:

50.48 APPENDIX R TO 10 CFR 50; NUREG-6700; NUREG-0737 SUPPLEMENT 1.

AS OF FY93 QUARTER 4 4

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la ISSUE NUMBER: 83 TITLE: CONTROL ROOM HABITABILITY ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE AWARD OF CONTRACT 02/84 01/84 VISIT TO INITIAL PLANT 03/84 05/84 REPORT ON CRH CRITERIA TO NRR DIRECTOR 06/84 06/84 COMPLETION OF CONTRACTOR VISITS TO 08/84 08/84 OPERATING AND NTOL PLANTS S0W WRITTEN FOR 12-PLANT SURVEY AND 11/84 10/84 GENERIC STUDIES RFP SENT TO POTENTIAL CONTRACTOR (S) 12/84 11/84 RECEIPT OF PROPOSAL (S) 02/85 03/85 INITIATE PROGRAM TO VISIT 12 09/85 09/85 ADDITIONAL OPERATING PLANTS COMPLETE VISIT TO 11 OPERATING REACTORS 09/86 01/87 ISSUE TRANSFER MEMO TO RES-03/87 12/87 SDW SENT TO PNL FOR 04/88 04/88

" MATHEMATICAL MODELS OF CONTROL ROOM HABIT-ABILITY SYSTEMS EFFECTIVENESS *.(FIN B2929-8)

S0W SENT TO SAIC FOR " CONTROL ROOM VULNER-04/88 04/88 ABILITIES" FIN 020969 REQUEST FOR PROCUREMENT ACTION SENT TO CHANGE 05/88 05/88 NRR CONTRACT WITH SAIC TO INCLUDE T/A IN MODELING CONTROL ROOM VULNERABILITIES (D2096)

RECEIPT OF PROPOSAL 06/88 06/88 DRAFT CODE FPFP 10/88 11/88 AS OF FY93 QUARTER 4 l.

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2'2 ISSUE NUMDER-83 TITLE: CONTROL ROOM HABITABILITY ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE DRAFT CODE EXTRAN 10/88 12/88 DRAF T REPORT ON T0XIC LEVELS

.11/88 01/89 PNL CONTRACT EXTENDED ON "NO-COST BASIS" 10/89 10/89 UNTIL 03/90 ISSUE SAIC CONTRACT 03/89 10/89 REVISE TASK ACTION PLAN 10/89 03/90 RECOMMENDED REVISED DOSE ASSESSMENT MODELS 09/89 06/90 FINAL REPORTS ON MODELS STUDY 02/89 07/91 DRAFT CLOSEOUT MEMO 07/91 05/93 ISSUE MEMO TO ACRS 07/91 10/93 ACRS REVIEW 08/93 12/93 CLOSE00T MEMO 09/93 12/93 PNL UPDATE COMPUTER CODE DOCUMENTATION 09/92 01/94 I

+

AS OF FY93 QUARTER 4 O

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y n-RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

23 ISSUE NUMBERr 105 TITLE: INTERFACING SYSTEMS LOCA AT LWRS IDENTIFICATION DATE: 10/84C PRIORITIZATION DATE: 06/85C TYPE-GSI PRIORITY: H TASK MANAGER: G.

BURDICK OFFICE / DIVISION / BRANCH: RES /DSIR/SAIB ACTION LEVEL. ACTIVE STATUS: 3B TAC NUMBERS.

RESOLUTION DATE: 06/93C-WORK AUTHORIZATION. MEMO FOR R. BERNER0 FROM H. DENTON DATED 6/11/85.

FIN CONTRACTOR CONTRACT TITLE A3829 BNL INTERFACING SYSTEMS LOCA B5699 INEL INTERSYSTEM LOCA (GI-105)

W0RK SC0PE PERFORM A DETAILED IS-LOCA SPECIFIC PRA FOR 3 PWR PLANTS TO VALVES IN SERIES AT EACH INTERFACE SEPARATING THE HIGHER DETERMINE CORE. MELT FREQUENCIES AND RISK CONTRIBUTED BY PRESSURE RCS FROM ATTACHED LOW PRESSURE SYSTEMS, SHOULD BE FAILURE OF REACTOR COOLANT PRESSURE BOUNDARY AS CAUSED BY PERIODICALLY LEAK-RATE TESTED OR VISUALLY INSPECTED. SOME FAILURE OF PRESSURE ISOLATION VALVES (PIVS) AND RESULTING OLDER PLANTS DO NOT PERFORM SUCH TESTS ON ALL PIV'S.

INTERFACING SYSTEMS LOCA.

WHEN SUFFICIENT PROGRESS IS MADE STUDIES HAVE BEEN PERFORMED TO ATTEMPT TO DETERMIME IF ON PWR ST UD IE S, AND IN LIGHT OF INSIGHTS THUS GAINED. THE IMPOSING SUCH PERIODIC TESTING ON ALL PIV'S IN ALL PLANTS IS BWR WORK SCOPE WILL BE FORMULATED. DEVELOP NEW LICENSING JUSTIFIED.

THESE STUDIES SUPPLEMENT THOSE ONGOING TO CRITERIA IF NECESSARY FOR THE GENERIC RESOLUTION.

IT HAS IDENTIFY SIGNIFICANT HARDWARE AND HUMAN CONTRIBUTIONS TO BEEN PROPOSED THAT PRESSURE ISOLATION VALVES, WHICH ARE TWO RISK OF IS-LOCA OUTSIDE CONTAINMENT FROM 3 FWR'S.

STATUS THE RESOLUTION OF GI-105 WILL ENCOMPASS GI-96, "RHR NUREG/CR-5744 AND NUREG/CR-5745 FOR WESTINGHOUSE AND CE SUCTION VALVE 1ESTING.*

THE PERTINENT MILESTONES FROM PLANTS RESPECTIVELY. PUBLISHED IN MAY WAS NUREG/CR-$862 GENERIC ISSUE II.E.6.1 HAVE BEEN TRANSFERRED TO GENERIC

" SCREENING METHODS FOR DEVELOPING INTERNAL PRESSURE ISSUE 105 AND REVISED.

NUREG/5IO2, " INTERFACING SYSTEM LOCA CAPACITIES IN SYSTEMS INTERFACING WITH NUCLEAR POWER PLANT IN PWR'S," AND NUREG/5154, " INTERFACING SYSTEM LOCA IN REACTOR COOLANT SYSTEMS." - RESOLUTION PACKAGE DELIVERED TO BWR'S." ARE COMPLETE.

ETEC HAS ALSO COMPLETED A STUDY OF ACRS AND NRR.

PACKAGE CONSISTS OF INFORMATION NOTICE, THE EFFECTIVENESS OF LEAK-RATE TESTING AS AN INDICATION OF FINAL NUREG/CR, AND REGULATORY ANALYSIS. ADVANCED REACTOR VALVE CONDITION.

NUREG/CR-5604, " ASSESSMENT OF IS-LOCA SRP DRAFT SENT TO NRR.

ACRS MEETING HELD, AND ACRS RISK-METHODOLOGY AND APPLICATION TO A BABCDCK AND WILCOX CONCURRLNCE LETTER RECEIVED.

RESOLUTION MEMORANDUM SENT, NUCLEAR POWER PLANT," WAS PUBLISHED IN APRIL 1992 AS WERE AND EDO CONCURRENCE RECEIVED, 'THE ISSUE IS RESOLVED.

AS OF FY93 QUARTER 4

_ - _..-._.~..-, _ _

RUN DATE-10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

24 ISSUE NUMBER 105 TITLE: INTERFACING SYSTEMS LOCA AT LWRS AFFECTED DOCUMENTS PROBLEM / RESOLUTION MILEST0NES ORIGINAL CURRENT ACTUAL DATE DATE DATE (Rkh/khbhRkVhEWkkbPRbPbbkLbFbR PREhkbRk bhh84 h5hhk ISOLATION VALVE LEAK TESTS & OTHERS. PROVIDE RECS TO RES FOR REVS TO TEST SCOPE / LAB SEL.

(RES) INITIATE CONTRACT FOR PIV LEAK RATE 05/84 10/84 TESTING (ETEC)

GSI 105 ASSIGNED TO RSB/DSI/NRR 06/85 06/85 PRELIMINARY DISCUSSION OF WORK PLAN WITH BNL BNL PRELIMINARY COST ESTIMATE OF WORK PLAN 09/85 08/E5 DEVELOP WORK PLAN AND CONTRACT PROPOSAL. DRAFT WORK PLAN TO DIRECTORS DSI. DE, DL, DHFS.AEOD INCORPORATE COMMENTS INTO WORK PLAN 10/85 10/85 FINAL WORK PLAN APPROVED BY DSI DIRECTOR AND 10/85 11/85 FORWARDED TO DST ISSUE CONTRACT TO BNL 10/85 12/85 MODIFY CONTRACT 01/86 01/86 EXPAND CONTRACT TO INCLUDE PWRS 03/86 02/86 (RES/EIB) PREPAkE GENERIC LETTER TO ALL 07/86 01/86 LICENSEES ASKING FOR PROOF OF VERIFICATION OF RCPB BY TESTING PIV'S (NRR) DIRECTOR NRR FORWARD 50.54(F) GENERIC 08/86 02/87 LETTER FOR CRGR APPROVAL (CRGR) REVIEW AND APPROVE 50.54fF) LTR TO ALL 09/86 03/87 LICENSEES RE VERIF. OF PIV*S; (NRR/DSRO)

ISSUE 10CFR50.54(F) LTR ON PIV VERIFICATION AS OF FY93 QUARTER 4 4

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25 ISSUE NUMBER.

105 TITLE: INTERFACING SYSTEMS LOCA AT LWRS c

ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE (RES/EIB) REVIEW LIC RESP TO 10 CFR 50.54(F) 01/87 10/87 ON PIV VERIF. DETERMINE PROCS. ARE ADEQUATE TO ASSURE INTEG OF RCTR COOLANT PRES BOUNDARY FINAL DRAFT REPORTS RECEIVED FROM BNL 07/86 02/88 INCLUDING VALUE/ IMPACT ANALYSIS PUBLISH NUREG REPORTS 02/89 02/89 REVISED TAP 04/89 02/90 NRR IS-LOCA AUDITS OF THREE PLANTS 04/90 08/90 COMPLETE B&W PLANT ANALYSIS 09/90 09/90 PUBLISH IMPEL COMPONENT FRAGILITY RESULTS 09/90 10/90 ACRS REVIEW B&W PLANT ANALYSIS 11/90 12/90 COMPLETE WESTINGHOUSE ANALYSIS COMPLETE CE PLANT ANALYSIS 12/90 06/91 EVALUATE IS-LOCA INSIDE CONTAINMENT 12/90 06/91 EVALUATE IS-LOCA EXTERNAL EVENT INITIATORS ENVIRONMENTAL QUALIFICATION ANALYSIS 08/91

-08/91 BWR SITE VISIT 10/91 10/91 OGCB GUIDANCE REQUESTED 04/92 04/92 ADVANCED REACTOR INSIGHTS 04/92 05/92 NRR'INFORMATION NOTICE 04/92 05/92 LEAD PM ASSIGNMENT REQUESTED 04/92 06/92 PWR AUX BLDG SURVEY 02/92 06/92 PWR ANALYSIS COST ESTIMATE 12/92

'09/92 AS'0F FY93 QUARTER 4

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j RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

26 j

ISSUE NUMBER 105 TITLE: INTERFACING SYSTEMS LOCA AT LWRS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE BWR ANALYSIS 03/92 10/92 DRAFT NUREG/CR AND PACKAGE TO ACRS 03/92 04/93 ACRS MEETINGS 10/88 05/93 FINAL NUREG/CR 03/92 06/93 i

RESOLUTION PACKAGE TO EDO 10/89 06/93 I

EDO CONCURRENCE 06/93 06/93 REG ANALYSIS PUBLISHED 07/93 07/93 PUBLISH IN 10/93 10/93 AS OF FY93 QUARTER 4 O

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106 TITLE: PIPING AND USE OF HIGHLY COMBUSTIBLE GASES IN VITAL AREAS IDENTIFICATION DATE: 10/84C PRIORITIZATION DATE: II/87C TYPE: GSI PRIORITY M TASK MANAGER:

R. WOODS OFFICE / DIVISION / BRANCH: RES /DSIR/SAIB ACTION LEVEL: ACTIVE STATUS.

TAC NUMBERS:

RESOLUTION DATE: 10/93 WORK AUTHORIZATION: MEMORANDUM FOR G. ARLOTTO FROM E.

BECKJORD DATED 11/3/87 FIN CONTRACTOR CONTRACT TITLE khk98 khkh bhhhRkbbkkbhbF HhbRbbEhhkhkhVkik[kkkkh W0RK SC0PE hkkkbhkkkhkhbkhbbkhRhkLbkhhkhkhFbkbPkkkkhbhL bikVkLUkkkbhbF khhkkhK hhbbhkkbhkhbhhbRbbkhkhbRbk SAFETY EXPERIENCE INVOLVING COM00STIBLE GASES.

EVALUATE FACILITIES USING INFORMATION FROM THE REGIONAL OFFICES RE-INFORMATION TO ESTIMATE FREQUENCY AND SEVERITY OF POSSIBLE QUESTED BY NRR, AND C) A REVISED PRA APPROACH FOR PWR'S EVENTS. ASSESS EVENTS IN TERMS OF CURRENTLY ACCEPTABLE

' BASED ON A DETAILED EVALUATION OF INDIAN POINT 2 AND SENSI-STAFF GUIDELINES FOR EQUIPMENT DESIGN AND HANDLING OF TIVITY CALCULATIONS FOR OTHER PLANTS COMBUSTIBLE GASES AND REEVALUATE RISK ASSOCIATED WITH LACK H2 STORAGE FACILITIES REMOVED FROM SCOPE IN 04/92.

OF PLANT CONFORMANCE TO CURRENTLY ACCEPTABLE GUIDELINES REASON IS NEED FOR PEER REVIEW OF NEW DETONATION AND (E.G.

INCORPORATION OF EXCESS FLOW CHECK VALVES OR BUILDING RESPONSE CALCULATIONS WHICH DO NOT USE TNT EQUIVALENT PROTECTION AGAINST H2 PIPE BREAKS)RE RESOLUTION EVALUATE EQUIVALENCY METHOD.

NEW SEPARATION DISTANCE CRITERIA NEED FOR ANY REVISION TO GUIDELINES AND PREPA SIGNIFICANTLY LARGER THAN EPRI GUIDELINE VALUES FOR LARGFR PACKAGE WITH V/I ANALYSIS.

THE SCOPE WAS EXPANDED TO SUPPLIES.

IMPACT OF NEW CALCULATIONS METHOD ON PLANTS NOT INCLUDE: A) SITE VISITS TO BWR'S AND A SCOPING ANALYSIS TO EVALUATED.

DETERMINE THE NEED FOR MORE DETAILED RISK ANALYSES OF BWR'S, STATUS MEETINGS HELD WITH Al ACRS SUBCOMMITTEE IN 07/92 B) ACRS GENERIC LETTER AND THAT SUBJECT COULD DE COVERED UNDER FULL COMMITTEE IN 07/92, AND Cl CRGR IN 09/92, dCRS IPEEE REVISED LETTER FROM EDO TO ACRS PREPARED TO REFLECT RECOMMENDED THAT PROPOSED GENERIC LETTER BE SENT TO BOTH THIS CONCLUSION. NEW GENERIC LETTER WILL BE SENT FOR BWRS AND PWRS AND THAT PLANT EVALUATIONS INCLUDE WEAKNESSES INFORMATION ONLY TO BWRS AND PWRS AND WILL REFER TO NEW OF FIRE BARRIERS IN EVALUATION OF DETONATION DAMAGE.

CRGR INFORMATION DEVELOPED UNDER GSI-IO6 AND THE STAFF INTEREST:

CONCLUDED THAT RISK IS INSUFFICIENT TO JUSTIFY BURDEN OF IN THE COVERAGE OF RISK FROM HYDROGEN IN THE IPEEE.

AS OF FY93 QUARTER 4

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28 ISSUE NUMBER.

106 TITLE: PIPING AND USE OF HIGHLY COMBUSTIBLE GASES IN VITAL AREAS AFFECTED DOCUMENTS PROBLEM

_.__......____..._____....../ RESOLUTION WORK ORIGINAL CURRENT ACTUAL MILE ST0NES DATE DATE DATE DEVELOP TAP 03/88 09/88 PRELIMINARY DISCUSSIONS WITH CONTRACTOR 08/88 09/88 DRAFT S0W ISSUED TO CONTRACTOR 09/88 09/88 ISSUE CONTRACT 08/88 12/88 TAP APPROVED 08/88 01/89 COMPLETE SURVEY OF PLANT INFORMATION 02/89 02/89 COMPLETE REPORT ON SURVEY 03/89 03/89 COMPLETE REPORT ON RECOMENDATIONS FOR 05/89 03/89 HYDROGEN SYSTEMS ISSUE REVISED TAP 10/89 12/89 COMPLETE PRELIMINARY TER ON TASK 5 WORK ON 11/89 11/89 j

TANK FARM HAZARD COMPLETE DRAFT TR ON TASK 2 (LEAK FREQ AND 01/90 01/90 POTENTIAL DAMAGE) l COMPLETE LETTER REPORT ON TASK 3 RESULTS OF 01/90 01/90 t

CONSULTATION WITH INDUSTRY COMPLETE FINAL TER ON TASK $ WORK ON TANK 02/90 04/90 FARM HAZARD l

COMPLETE DRAFT TER ON TASK 6 ON PWR PRA 04/90 04/90 AS OF FY93 QUARTER 4 l

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29 ISSUE NUMBER: 106 TITLE: PIPING AND USE OF HIGHLY COMBUSTIBLE GASES IN VITAL AREAS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE bbMPLkhkbRkFhhkRbNhkSk1kSbREhb b6hhh bhh9h BWR'S)

COMPLETE DRAFT NUREG/CR ON TASK 1 (SCOPING 02/91 04/91 PRA FOR BWRS)

COMPLETE FINAL DRAFT NUREG/CR ON PWRS 03/91 03/91 KENNEDY DRAFT REPORT COMPLETE 04/91 04/91 KENNEDY REPORT ON EXPLOSION STANDARDS 05/91 05/91 COMPLETE COMPLETE CAMERA READY COPY NUREG/CR ON PWRS 04/91

-08/91 DRAFT REGULATORY ANALYSIS COMPLETED 01/90 09/91 COMPLETE CAMERA READY COPY OF NUREG/CR TASK 03/91 12/91 1 (BWRS)

DTR PACKAGE COMPLETED 02/90 03/92 DTR PACKAGE TO ACRS 04/92 04/92 DTR PACKAGE TO NRR, AEOD, OGC FOR COMMENTS 06/92 06/92 ACRS REVIEW (SU0 COMMITTEE AND FULL 07/92 07/92 COMMITTEE 1 DTR PACKAGE TO DIRECTOR. RES 07/92 08/92 CRGR MEETING ON PROPOSED RESOLUTION 08/92 09/92' PREPARE GENERIC LETTER PKG WI1H DRAFT 10/92 11/92 REGULATORY ANALYSIS GENERIC LETTER PACKAGE SENT TO NRR FOR 10/92 12/92 ISSUANCE REGULATORY ANALYSIS ISSUED AS NUREG 11/92 06/93 AS OF FY93 QUARTER 4

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RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

31 ISSUE NUMBER:

143 TITLE: AVAILABILITY OF CHILLED WATER SYSTEM AND ROOM COOLING IDENTIFICATION DATE. 06/86C PRIORITIZATION DATE-. 03/91C TYPE: GSI PRIORITY: H TASK MANAGER; V.

LEUNG OFFICE / DIVISION / BRANCH: RES /DSIR/EIB ACTION LEVEL: ACTIVE STATUS:

TAC NUMBERS:

RESOLUTION DATE: 09/93C WORK AUTHORIZATION.

FIN CONTRACTOR CONTRACT TITLE L1915 PNL CHILLED WATER SYSTEMS W0RK SCDPE hhkkkhhbkkhbbhbkkhkbhkkbkhkkVkLhkLkkhbF hhE PkbPbhkkPPhbPRkkkkEthkkhkkkVkhhbR khPLkbEhhkhkbk bF hbE CHILLED WATER SYSTEM AND ROOM COOLING FOR THE SAFETY RELATED APPROACH.

THE DRAFT TAP INCLUDES COOLING AND VENTILATING OF EQUIPMENT. STUDIES WILL BE PERFORMED TO ASSESS THE RISK INSTRUMENTATION AND CONTROLS WITHIN THE CONTROL ROOM, AS SIGNIFICANCE OF THE UNAVAILABILITY OF THE CHILLED WATER WELL AS OTHER SAFETY RELATED AREAS VULNERABLE TO VENTILATION SYSTEM AND ROOM COOLING AND TO EXAMINE THE COST FAILURES.

EFFECTIVENESS OF APPROACHES FOR REDUCING THE RISK AND STATUS iHkkkhk[TkbhbkbklkkhbkhhhhkPbRhhkhhbbhkhhkbhhPhL hkhbkkNbbhWkhkhhbkbhh/hh Thk kkhkl RkhbLkhbkh khkLhhhh A DRAFT REGULATORY ANALYSIS HAS BEEN PREPARED: ACRS (NUREG-1427) AND CONTRACTOR TECHNICAL REPORT (NUREG/CR-6084)

APPROVED STAFF'S RESOLUTION OF THIS GENERIC ISSUE: 1.E.,"NO ARE SCHEDULED TO BE ISSUED 10/33.

ACTION" (ACRS LETTER DATED 08/11/931. THE CLOSEOUT AFFECTED DOCUMENTS PROBLEM / RESOLUTION ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE-PRIORITIZATION AND ASSIGN TASK MANAGER 03/91 03/91 AS OF FY93 QUARTER 4

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l RUN DATE 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

32 ISSUE NUMBER 143 TITLE: AVAILABILITY OF CHILLED WATER SYSTEM AND ROOM COOLING ORIGINAL CURRENT ACTUAL M ILEST0NES DATE DATE DATE l

i DEVELOP TAP 04/91 04/91 DEVELOP DRAFT STATEMENT OF WORK ($0W) WITH

.09/91 07/91 CONTRACTOR ISSUE S0W AND WORK AUTHORIZATION 07/91 07/31 EXAMINE HVAC DATA BASE (TASK 11 11/91 12/91 ISSUE TAP 07/91 01/92 SELECT REPRESENTATIVE PLANTS AND EXAMINE 05/92 06/92 RISK DUE TO HVAC F AILURES (TASK 2)

QUANTIF Y SPECIFIC RISK FOR SEQUOYAH AND 08/92 08/92 GRAND GULF (TA5K 2Al QUANTIFY SPECIFIC RISK FOR CCONEE AND PALO 09/92 09/92 VERDE (TASK 28)

DETERMINE HVAC FAILURE RISK (GENERIC) FOR 10/92 10/92 PWR AND BWR (TASK 2Cl IDENTIFY CORRECTIVE MEASURES AND PERFORM 09/92 01/93 l

VALUE/ IMPACT ANALYSIS (TASK 31 DRAFT NUREG/CR REPORT (TASK 4) 11/92 03/93 FINAL NUREG/CR REPORT FROM CONTRACTOR 12/92 04/93 (TASK $)

ISSUE DTR (TASK 51 01/93 07/93 SUBMIT OTR TO ACRS/CRGR (TASK 7) 02/93 07/93 ACRS/CRGR REVIEW 04/93 08/q3 ISSUE CLOSE00T MEMOR ANDUM ( TASK 11) 01/94 og[q3 PUBLISH REGULATORY ANALYSIS AND NUREG/CR 10/93 10/93 AS OF FY93 GUARTER 4 O

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,r-RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE.

33 ISSUE NUNCER: 145 TITLE: ACTIONS TO REDUCE COMMON CAUSE FAILURES IDENTIFICATION DATE. 07/85C PRIORITIZATION DATE: 02/92C TYPE: GSI PRIORITY: M TASK MANAGER: E CHELLIAH OFFICE / DIVISION / BRANCH: RES /DSIR/PRAB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS'.

RESOLUTION DATE: 01/94 WORK AUTHORIZATION: MEMORANDUM FROM E. S. BECKJORD TO W.

MINNERS DATED FEBRUARY 11, 1992 FIN CONTRACTOR CONTRACT TITLE L2553 BNL TECHNICAL SUPPORT TO GI-145 W0RK SC0PE hhkEhhkhhhkkhbkk[bkbkkhblVkkhE khbbk kkE M5hkMkl$ khE hhkkb kkPbRh hb kh kb hk kkbk h kVkk khlk kb Lkhhhhkkh SCOPE OF THE ISSUE IS ONLY TO COLLECT THE INFORMATION BNL COMPLETED ITS DRAFT FINDINGS (TASK 2).

AVAILABLE ON COMMON MODE FAILURES AND PUBLISH IT IN A STATUS BNL SUBMITTED AN NRC 189.

DSIR PROVIDED FUNDING TO START MAY 14, 1993.

BNL'S WORK ON APRIL 23, 1993.

BNL STARTED THE WORK ON AFFECTED DOCUMENTS

' PROBLEM /R E SOLUT ION PbhhkhlkhbRkbhbh$

hhNk ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE hhhPLkkkhhhFbkPkkhRkTkkkkkhh hhhhh 5-Okh9h COMPLETION OF TAP 04/92 04/92 ISSUE CONTRACT FUND 01/93 04/93 6

a AS OF FY93 00ARTER 4 u...

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RUN DATE. 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE-34 ISSUE NUMBER:

145 TITLE: ACTIONS TO REDUCE COMMON CAUSE FAILURES ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE bbkhkbhbkIhbhFhFkhbkhbh bbhhh

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~bhhh3 CONTRACTOR'S FINAL FINDINGS 09/92 11/93 STAF F 'S F INDINGS (DSIR) 10/92 11/93 DECISION ON STAFF *S FINDINGS TO PUBLIC 11/92 01/94 CLOSEOUT ISSUE 01/93 01/94 l

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35 ISSUE NUMBER: 147 TITLE: FIRE. INDUCED ALTERNATE SHUTDOWN / CONTROL ROOM PANEL INTERACTIONS IDENTIFICATION DATE: 06/89C PRIORITIZATION DATE: 08/92C TYPE: LI PRIORITY:

TASK MANAGER: J. CHEN OFFICE / DIVISION / BRANCH: NRR /DSIR/SAIB ACTION LEVEL: ACTIVE STATUS: 5 TAC NUMBERS:

RESOLUTION DATE: 10/93 WORK AUTHORIZATION: MEMORANDUM FOR W.

MINNERS FROM E. BECKJORD DATED AUGUST 26 1992 FIN CONTRACTOR CONTRACT TITLE WDRK SC0PE kbbkhkLbPbbkbkhbhhbR khkhTkkhhkhkkhbkLkbkhkkkkhkkk hhbhbbWh/bbkkkblkbbMPkhkkkhkkkkbkkbbh SUBMITTALS IN THE AREA RELATED TO FIRE-INDUCED ALTERNATE STATUS kkkK RkkhhkbhEb kb hkkb kh kkhkbkRh 993$

1 AFFECTED DOCUMENTS PROBLEM / RESOLUTION kbhkbkkkkMkhkb$

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ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE GI-147 ASSIGNED TO RES/DSIR/EIB 09/92 09/92 REA5 SIGNED TO SAIB 02/93 02/93 DRAFT STAFF REVIEW GUIDANCE ON FIRE. INDUCED 08/93

/93 ALTERNATE SHUTDOWN / CONTROL ROOM PANEL.

gq/

INTERACTION AS OF FY93 QUARTER 4

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RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

36 ISSUE NUMBER: 147 TITLE: FIRE-INDUCED ALTERNATE SHUTDOWN / CONTROL ROOM PANEL INTERACTIONS ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE STAFF IPEEE REVIEW GUIDANCE FOR GI-147 10/93 10/93 4

AS OF FY93 QUARTER 4 O

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37 ISSUE NUMBER:

148 TITLE: SMOKE CONTROL AND MANUAL FIRE-FIGHTING EFFECTIVENESS IDENTIFICATION DATE: 04/39C PRIORITIZATION DATE: 08/92C TYPE: LI PRIORITY:

TASK MANAGER: J. CHEN OFFICE / DIVISION / BRANCH: RES /DSIR/SAIB ACTION LEVEL: ACTIVE STATUS:

TAC NUMBERS:

RESOLUTION DATE:'I1/93 WORK AUTHORIZATION. MEMORANDUM FROM E. S. BECKJORD TO W.

MINNERS DATED AUGUST 26 1992

.i FIN CONTRACTOR CONTRACT TITLE W0RK SC0PE TO DEVELOP STAFF GUIDANCE FOR THE REVIEW OF LICENSEES' MANUAL FIRE-FIGHTING EFFECTIVENESS.

IPEEE SUBMITTALS RELATED TO THE EFFECTS OF SMOKE AND STATUS TASK REASSIGNED TO SAIB/SECTION B IN FEBRUARY 1993.

AFFECTED DOCUMENTS

__........................../. RESOLUTION PROBLEM POSSIBLE NUREG/CR.

NONE.

ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE-GI-148 ASSIGNED TO RES/DSIR/RPSI-09/92 09/92 REASSIGNED TO SAIB 02/93 02/93 DRAFT STAFF REVIEW GUIDANCE RELATED TO SMOKE 09/93 11/93 AND MANUAL FIRE-FIGHTING EFFECTIVENESS AS 0F FY93 QUARTER 4 u

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RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

38 ISSUE NUMBER.

148 TITLE: SMOKE CONTROL AND MANUAL FIRE-FIGHTING EFFEOTIVENESS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE bhkkhkVkE5bbkbkhbEkbkbk-5kk

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9 RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

39 ISSUE NUMBER:

153 TITLE: LOSS OF ESSENTIAL SERVICE WATER SYSTEM IN LWRS IDENTIF ICATION DATE. 05/90C PRIORITIZATION DATE: 02/91C TYPE; GSI PRIORITY: H TASK MANAGER:

T.

M.

SU OFFICE / DIVISION / BRANCH: RES /DSIR/SAIB ACTION LEVEL: ACTIVE STATUS:

TAC NUMBERS: L1843 RESOLUTION DATE. 06/93C WORK AUTHORIZATION: MEMO TO R.

Y.

LOWRY FROM W.

MINNERS. DATED 03/2T/91 FIN CONTRACTOR CONTRACT TITLE L1843 SNL LOSS OF ESSENTIAL SERVICE WATER IN LWR $ (GI-135)

L1854 SEA W0RK SC0PE l

THIS ISSUE DEALS WITH POTENTsAL UNAVAILABILITY OF THE UNAVAILABILITY EXCEPT THOSE ($UCH AS 810 FOULING) WHICH ARE ESSENTIAL SERVICE WATER SYSTEM IN ALL OPERATING PLANTS CONSIDERED TO BE RESOLVED BY IMPLEMENTING THE REQUIREMENTS EXCEPT THOSE WHICH HAVE BEEN STUDIED UNDER GI-130.

THIS SPECIFIED IN GENERIC LETTER 89-13.

l ISSUE WILL INCLUDE ALL POTENTIAL CAUSES FOR THE ESW SYSTEM

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$TATUS k kbPbbbb REbb[Uhibh PkbKkbh kbk hhkh bkhkkkb khhbk kb REbbLbhkbhbFbkNER$bikhbk[h3[bi$[53h LbbhbFkhkkhhkk(

REVIEWED AND CONCURRED BY NRR STAFF ON MAY 12, 1993.

IN A SERVICE WATER IN LWR'S " WAS ISSUED.

INSIGHTS FROM THE MEMORANDUM DATED MAY 24, 1993 THE ACRS INDICATED THAT NO GI-153 STUDY WAS PUBLISHED AS NUREG-1461, " REGULATORY FORMAL REVIEW OF THE PACKAGE iS NEEDED.

ON JUNE 14, 1993, A ANALYSIS FOR THE RESOLUTION OF GI-153 " LOSS OF ESSENTIAL MEMORANDUM FROM ERIC S. BECKJORD DIRECTOR or RESEARCH, TO SERVICE WATER IN LWR *S."

THIS ISSUE iS CONSIDERED JAMES M.

TAYLOR. EXECUTIVE DIRECT 0R FOR OPERATIONS,

SUBJECT:

" RESOLVED," AND NO FURTHER ACTION IS NEEDED.

AFFECTED DOCUMENTS PROBLEM / RESOLUTION ORIGTNAL CURRENT ACTUAL M I L E.S T O N E S DATE DATE DATE PRIORITIZATION 11/90 02/91 AS OF FY93 QUARTER 4 l

RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE.

40 ISSUE NUMBER-153 TITLE: LOSS CF ESSENTIAL SERVICE WATER SYSTEM IN LWRS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE kbSUh PHkbk k bbW FbR bbNhRkbhbR b4/bh bb/bk ISSUE PHASE I AND II TAP

_02/91 07/91 DRAFT CONTRACTOR REPORT ON PHASE I STUDY 10/91 12/91 DECISION ON INTERIM RESOLUTION 12/91 02/92 DECISION ON TECH SUPPORT 04/92 04/92 FINAL CONTRACTOR (SNL) REPORT ON PHASE I 06/92 08/92 STUDY DTR PACKAGE PREPARED 07/92 12/92 CONTRACTOR (SEAL REPORT ON PHASE I 08/92 01/93 SUPPLEMENTAL STUDY RES DIRECTOR REVIEW OF DTR PACKAGE 08/92 02/93 COMPLETED DTR PACKAGE REVIEWED BY OTHER OFFICES (NRR, 09/92 04/93 AE00 OGC)

DTR SENT TO ACRS 10/92 04/93 ACRS REVIEW DTR COMPLETED 11/92 05/93 ISSUED CLOSE00T MEMO 06/93 06/93 PUBLISH REGULATORY ANALYSIS 07/93 08/93 AS OF FY93 QUARTER 4 O

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41 ISSUE NUMBER; 155.1 TITLE: MORE REALISTIC SOURCE TERM ASSUMPTIONS IDENTIFICATION DATE: 03/79 PRIORITIZATION DATE: 02/92C TYPE; GSI PRIORITY:

TASK MANAGER-L.

SOFFER OFFICE / DIVISION / BRANCH: RES /DSIR/SAIB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS:

RESOLUTION DATE: 01/94 WORK AUTHORIZATION: MEMO FOR W. MINNERS FROM E. BECKJORD DATED 2/26/92 FIN CONTRACTOR CONTRACT TITLE B0854 ORNL IODINE CHEMICAL FORMS L1535 BNL RADIONUCLIDE RELEASE CHARACTER L1611 INEL TIMING ANALYSIS OF FUEL FAILURES L2035 SNL SOURCE TERM REMOVAL MECHANISMS W6067 ORNL CHEMICAL FORM OF SOURCE TERMS W0RK SC0PE bEhE[bP k kkVkbEb kbbkbEhk bbbkbE kkkh kb kkPLkbh kHkT

~ Ekb kbbkhk bHEhkhkkhI khPLEhEbh REVkkkb kbbkbEhk bbbhbh GIVEN IN TID-14844, MAKING USE OF CURRENT RESEARCH TERM TOGETHER WITH SEVERE ACCIDENT INSIGHTS, IN A REVISION INSIGNTS ON FISSION PRODUCT TIMING. COMPOSITION, MAGNITUDE, OF 16 CFR PART 50.

STATUS kkhkLkkPbkkhbhkbbkhEbhbbkbbkbkkkhbkkhkhbthbRkb/bk kkhkhkbkbbkbkhkhbbkbhkkkhhEVkhkEhkkhbkb Ebbkhkkhibh 5732 AND NUREG/CR-5787) HAVE BEEN ISSUED. DRAFT REPORT MEETING WAS HELD ON APRIL 20 1992.

NUREG-1465 ISSUED ON FISSION PRODUCT COMPOSITION AND MAGNITUDE (NUREG/CR-5747)

JULY 28, 1992.

BNL AND ORNL REVIEW OF PUBLIC COMMENTS HAS BEEN ISSUED. CONTRACTOR STUDIES ON FISSION PRODUCT RECEIVED APRIL 27 1993.

ORNL REPORT ON MELCOR RESULTS REMOVAL MECHANISMS ARE CONTINUING. A COMMISSION PAPER (NUREG/CR-5942l HdS BEEN ISSUED-,

(SECY-92-127) AND DRAFT PROPOSED NUREG REPORT CONTAINING A AFFECTED DOCUMENTS PROBLEM / RESOLUTION R.G.

1.3, 1.4 SRP 15.6.5 DELAYS AT BNL AND SNL IN COMPLETING NUREG/CR REPORTS. ~

R.G.

1.7, 1.25 SCHEDULE ALSO IMPACTED BY DETAIL OF TASK MANAGER TO OFFICE OF THE CHAIRMAN, AS OF FY93 QUARTER 4

RUN DATE-10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

42 ISSUE NUMBER.

155.1 TITLE: MORE REALISTIC SOURCE TERM ASSUMPTIONS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE kbbkNb)fibkbhEbbLkTbbbIbibbkbh bk)hh b5hhh PRA BASED SOURCE TERM PAPER TO COP 94ISSION

.05/90 05/90 FISSION PRODUCT TIMING PAPER TO COMMISSION 07/90 08/90 REVISED BNL DRAFT REPORT 07/90 08/90 TID REPORT SCHEDULE - IODINE CHEMICAL FORM 12/90 07/91 REPORT ISSUED FOR COMMENT PROPOSED REV. TO TID TO RES DIRECTOR 07/91 09/91 PROPOSED REVISION TO NRR/0GC 09/91 09/91 DRAFT TID TO ACRS 11/91 12/91 COMPLETE ACRS REVIEW 12/91 01/92 0FFICE CONCURRENCE 04 TID 10/91 04/92 DRAFT BNL REPORT ISRULD FOR COMMENT 07/91 02/92 TID TO EDO 01/92 04/92 TID TO COMMISSION 02/92 04/92 FISSION PRODUCT TIMING REPORT ISSUED FOR 12/90 03/92 COMMENT (INEL)

ISSUE REVISED TID FOR COMMENT 02/92 07/92 ISSUE ORNL IODINE REPORT AS FINAL 04/92 04/92 SNL REPORT ON POOL DF NUREG/CR ISSUED FOR 08/92 09/92 COMMENT ISSUE INEL REPORT FINAL 08/92 09/92 END COMMENT PERIOD ON DRAFT SOURCE TERM 08/92 10/92 NUREG AS OF FY93 QUARTER 4 O

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43 ISSUE. NUMBER.

155.1 TITLE: MORE REALISTIC SOURCE TERM ASSUMPTIONS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE RESPONSE TO SRM ON IMPACT OF INCREASED 09/92 11/92 AMOUNT OF RADIATION (WITS 9200124) -- DRAFT COMMISSION PAPER AVAILABLE

-- RES CONCURRENCE 09/92 12/92

-- COMMISSION PAPER TO EDO AND OFFICE 10/92 01/93 CONCURRENCE

-- COMMISSION PAPER TO COMMISSION 11/92 02/93 SNL SPRAY NUREG/CR ISSUED FINAL 11/92 06/93 ORNL NUREG/CR ON MELCOR ISSUED 09/93 09/93 SNL NUREG/CR ON MELCOR ISSUED 11/93 11/93 SNL REPORT ON POOL OF NUREG/CR ISSUED FINAL 11/92 10/93 ISSUE BNL REPORT FINAL 06/92 10/93 SNL SUPP-POOL NURE0/CR ISSUED FINAL 03/93 II/93 SNL AEROSOL NUREG/CR ISSUED FINAL 03/93 12/93

+-

COMPLETE REVISED DRAFT SOURCE TERM NUREG 11/92 12/93 (FOR USE WITH PART 50 REVISION)

TRANSMIT CLOSEOUT MEMO TO ACRS 11/92 12/93 ISSUE CLOSEOUT MEMO 12/92 01/94 4'

AS OF FY93 QUARTER 4-

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RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

4 '4 ISSUE NUMBER:

166 TITLE: ADEQUACY OF FATIGUE LIFE OF METAL COMPONENTS IDENTIFICATION DATE: 04/93C PRIORITIZATION DATE: 06/93C TYPE. GSI PRIORITY:

TASK MANAGER: J.

FAIR OFFICE / DIVISION / BRANCH: NRR /DE /EMEB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS: M86344 RESOLUTION DATE: _ _ _ _ _ _

WORK AUTHORIZATION: APRIL 1, 1993, MEMORANDUM FROM T. MURLEY TO J. SNIEZEK FIN CONTRACTOR CONTRACT TITLE WDRK SC0PE EVALUATE FATIGUE ADEQUACY OF OPER ATING PLANT COMPONENTS.

STA TUS kbhhbh PLkh PPRbVhb bkb Rb hElbPbbthbhEhhkhbbh Rkkkkkbhbbbbbkt[PVRbhbhbbhbbkkf2 kh93 N

SEPTEMBER 17, 1993.

STAFF TO MEET WITH ASME PRESSURE VESSEL AFFECTED DOCUMENTS PROBLEM / RESOLUTION ORIGINAL CURRENT ACTUAL MILEST0NE$

DATE DATE DATE MEET WITH INDUSTRY 09/93 09/93 PROGRAMMATIC REVIEW 12/93 12/93 INFORM COMMISSION 02/94 02/94 RISK ASSESSMENT 03/94 03/94 AS OF FY93 QUARTER 4 O

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45 ISSUE NUMBER: 166 TITLE: ADEQUACY OF FATIGUE LIFE OF METAL COMPONENTS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE bEkkbbLLkChkbhkhbkhkLhbkb bh/hk bh/hk TECHNICAL ISSUES 05/94 05/94

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RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

46 ISSUE NUMBER:

168 TITLE: ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT IDENTIFICATION DATE: 04/93C PRIORITIZATION DATE: 06/93C TYPE: GSI PRIORITY-TASK MANAGER:

G.

HUBBARD OFFICE / DIVISION / BRANCH: NRR /

/SPLB ACTION LEVEL: ACTIVE STATUS. NR TAC NUMBERS.

M85648 RESOLUTION DATE:. _. _., _

WORK AUTHORIZATION: APRIL 1, 1993. MEMORANDUM FROM T. MURLEY TO J.

SNIEZEK FIN CONTRACTOR CONTRACT TITLE A2336 ANL RISK IMPACT OF EQ E2095 SCIENTECH EQ FOR OPERATING REACTORS W0RK SC0PE k

kb bkkhhh hEVkkh khb kV lbkkk bPkhkkkhb kkPkhkEbbk kEbbbkbkh kh khk Pkkkbkh hbk bh kb kbkhb kkVkkhh DATA AND ECUIPMENT REPLACEMENT SCHEDULES FOR NUCLEAR POWER 2.

TO PERFORM A DETAILED ASSESSMENT OF THE RISK PLANTS TO PROVIDE INSIGHT AS TO WHERE NRC SHOULD F OCUS ITS ASSOCIATED WITH EQ ISSUES STATUS k PkELkhkkkkh kkhk hbbPkhb khhkhhhhh hkh khhhhb bh khbbkhkhbkhb kbbkhhkbhbR kbhhPLhkhhkVkkhkhbbPkRkkkhb MARCH 30, 1993.

USER NEED MEMO WAS ISSUED TO RESEARCH ON EXPERIENCE AND WILL PROVIDE A REPORT ON EQ-RELATED EVENTS BY APRIL 22, 1993.

COMMISSION WAS INFORMED ON MAY 28, 1993.

DECEMBER 31, 1993.

A CONTRACTOR FOR SPSB IS REFINING THE NRR AND RES MET WITH NUMARC ON JUNE 16, 1993, REGARDINU THE PRELIMINARY RISK ASSESSMENT.

RES/DE WILL HOLD A WORKSHOP ON EQ TASK ACTION PLAN.

THE EQ TASK ACTION PLAN WAS ISSUED TO NOVEMBER 15-16 TO GATHER INFORMATION ON PRE-AGING, EQ THE COMMISSION ON JULY 1, 1993.

THE PROGRAMMATIC REVIEW TESTING. OPERATING EXPERIENCE. AND CONDITION MONITORING.

AFFECTED DOCUMENTS PROBLEM

..................._......../. RESOLUTION ISSUED IN 92 81 AND 93 33.

NONE, ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE INFORM COMMISSION 05/93 05/93 AS OF FY93 QUARTER 4 O

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47 ISSUE NUMBER: 168 TITLE: ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE MEET WITH INDUSTRY t

PROGRAMMATIC REVIEW 06/94 06/94 DATA COLLECTION AND ANALYSIS 08/94 08/94 RISK ASSES $ MENT 10/94 10/94 TECHNICAL ISSUES 10/94 10/94

-a OPTIONS FOR RESOLUTION IMPLEMENTATION t

9 Z

AS OF FY93 QUARTER 4

RUN DATE. 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

48 ISSUE NUMBER:

B-17 TITLE. CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS IDENTIFICATION DATE. 06/78C PRIORITIZATION DATE 11/83C TYPE GSI PRIORITY: M TASK MANAGER J,

KRAMER OFFICE / DIVISION / BRANCH-RES /OSR /HFB ACTION LEVEL-ACTIVE STATUS:

TAC NUD8ERS-RESOLUTION DATE: 09/94 WORK AUTHORIZATION. NRR FY-84 OPERATING PLAN (APPENDIX G)

FIN CONTRACTOR CONTRACT TITLE A0465 LLNL INTEGRATION OF HUMAN PERFORMAN E FACTORS FULLY INTO THE RELIABILITY EVALUATION PROCESS (TASKS S AN 6l WDRK SC0PE THE WORK SCOPE INCLUDES:

(1) DEVELOP TIME CRITERION MANUAL OPERATOR ACTION OR AUTOMATIC ACTION.

THE SCOPE OF FOR SAFETY RELATED OPERATOR ACTIONS: (2) DETERMINE WHETHER THIS GENERIC ISSUE COVERS DESIGN BASIS ACCIDENTS OR EVENTS.

OR NOT AUTOMATIC ACTUATION WILL BE REQUIRED; AND (3) DEVELOP CRITERIA FOR SAFETY RELATED OPERATOR ACTIONS DURING SEVERE GUIDANCE AND REVIEW CRITERIA FOR LICENSEE PROPOSALS TO USE ACCIDENTS WILL DE COVERED UNDER THE SEVERE ACCIDENT PROGRAM.

STATUS THIS ISSUE WAS TRANSFERRED FROM NRR TO RES WITH THE 4/87 NRC WORK WAS COMPLETED BY NRR ON THIS ISSUE. WORK HAS BEGUN REORGANIZATION (4/10/87 MEMO FROM W.

RUSSELL TO T.

SPEIS).

WHICH SHOULD LEAD TO RESOLUTION OF THIS GSI BY ENDORSING NO WORK HAD BEEN COMPLETED ON THE ISSUE PRIOR TO TRANSFER _

ANSI /ANS 58.8.

THIS STANDARD IS BEING REVISED BASED ON NEW DURING 1983 AND 1984, RES WORMED ON THIS ISSUE.

DURING INDUSTRY DATA.

LLNL BEGAN WORK TO MANAGE THE TECHNICAL THAT TIME DATA WERE COLLECTED BY RES CONCERNING OPERATOR EFFORT INVOLVING EPRI AND A SUBCONTRACTOR TO EPRI IN MARCH RESPONSE TIMES ANSI /ANS 58.8 WAS PUBLISHED IN SEPTEMBER 1989.

1984.

THE GENERIC ISSUE WAS LATER TRANSFERRED TO NRR.

NO AFFECTED DOCUMENTS PROBLEM / RESOLUTION TbObhRbVkbkbLkER kbbhbbbkHkhhLkPPhbbbkkbSLkPPkhkkhkNbbbhEbbLhhbR APPROVAL OF STANDARD ANSI /ANS 58.8_

ALSO, SINCE NRC ENDORSEMENT WILL BE IN THE FORM OF A REGULATORY GUIDE.

TIME IS NEEDED TO GO THROUGH THE REGULATORY GUIDE APPROVAL PROCESS.

AS OF FY93 QUARTER 4 O

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49 ISSUE NUMBER:

B-17 TITLE: CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE MEET 5khHkhhk/kNbShIh bhhhh bhhhh DEVELOP TAP 08/87 06/89 NUPPSCO SUBMITS DRAFT OF 58.8 04/92 04/92' COMPLETE DRAFT OF 58.8 08/92 08/92 NUPPSCD BALLOTS DRAFT STD 58.8 10/92 03/93 NUPPSCO ISSUES FINAL $8.8 08/93 12/93 (SCHEDULE DEPENDS UPON ISSUANCE OF ANS 58.8 REVISION BY END OF 10/93.]

ISSUE DRAFT REG. GUIDE FOR 90-DAY COMMENT 12/93 12/93 PERIOD ACRS REVIEW 04/93 02/94 CRGR REVIEW 04/93 02/94 REVISE REG. GUIDE TO REFLECT PUBLIC COMMENTS 05/94 05/94 ACRS REVIEW 07/94 07/94 CRGR REVIEW 07/94 07/94 ISSUE FINAL REG. GUIDE 09/94 09/94 CLOSE OUT ISSUE 09/94 09/94 AS OF FY93 QUARTER 4

.., ~, -, - - -..,... -

RUN DATE. 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

50 ISSUE NUMBER:

8-55 TITLE: IMPROVE RELIABILITY OF TARGET ROCK SAFETY-RELIEF VALVES IDENTIFICATION DATE: 06/78C PRIORITIZATION DATE: II/83C TYPE. GSI PRIORITY: M TASK MANAGER: F CHERNY OFFICE / DIVISION / BRANCH: RES /DSIR/EI8 ACTION LEVEL: ACTIVE STATUS:

TAC NUMBERS:

RESOLUTION DATE: 08/93C WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN, (APPENDIX G)

FIN CONTRACTOR CONTRACT TITLE W0RK SC0PE

~ 'hhVhkhbhRbh1LhhYkPhRbkbHkhhbkhbkkkhkhbhRV

~bbhrbRMkhbhhbhhhhVkhbhR kN kbb bh (2

RELIABILITY TO OBTAIN SUFFICIENT DATA BASE TO SUPPORT DEMONSTRATING SUFFICIENT RELIABILITY OF 2-STAGE VALVES THE CONCLUSION THAT THIS ISSUE HAS BEEN RESOLVED.

AFTER DESIGN AND/OR SYSTEM MODIFICATIONS, AND (3)

THE UTILITY APPROACHES MAY INCLUDE: (I) DEMONSTRATING USING DIFFERENT VALVES AND DEMONSTRATING THEIR SUFFICIENT RELIABILITY OF 3-STAGE VALVES BY STRICT RELIABILTY.

STATUS WHILE INITIAL PERFORMANCE WITH THE PH I3-8 MO REPLACE-IS VERY EFFECTIVE IN REDUCING OXYGEN CONCENTRATION AT THE MENT DISCS INDICATED AN~ IMPROVEMENT, ADDITIONAL PERFORMANCE VALVE DISK / SEAT INTERFACE.

PILOI VALVE CYCLING TESTS DATA MADE IT APPARENT THE NEW DISCS ARE NOT PROVIDING THE THAT DEMONSTRATE CATALYST ADHERENCE TO THE TREATED IMPROVED PERFORMANCE THAT WAS ORIGINALLY EXPECTED.

THE SURFACES HAVE ALSO BEEN SUCCESSFULLY COMPLETED.

A DESIGN BWROG CONCLUDED THE PH 13-8 MO REPLACEMENT DISCS ARE NOT A SPECIFICATION FOR THE ALLOY COATING AND THE TREATED VIABLE SOLUTION FOR ELIMINATING SETPOINT DRIFT AND RECOM-SURFACES HAS BEEN SUBMITTED TO THE BWROG FOR APPROVAL.

THE MENDED THEY NO LONGER BE INSTALLED TO RESOLVE THIS PROBLEM.

PILOT VALVE CONTACT SURFACES ARE A STELLITE TO STELLITE THE BWROG IS CURRENTLY WORKING ON THE DESIGN OF CATALYSTS HATERIAL WITH THE PLATINUM-STELLITE ALLOY COATING APPLIED (OPTION I) FOR THE TARGET ROCK 2-STAGE SRV*S.

INSTALLATION TO THE PILOT VALVE DISK AND THE STABILIZER DISK.

HOWEVER, OF REDESIGNED SRV'S WITH CATALYSTS IS SCHEDULED FOR THE AT THE FEBRUARY 1993 BWROG MEETING, IT WAS DECIDED TO APPLY FALL OF 1993 THEY ARE ALSO WORKING ON A PARALLEL THE ALLOY COATING TO THE PILOT VALVE DISK ONLY AND NOT TO CONTINGENCY OPTION 2; 1.E THE USE OF PRESSURE SWITCHES THE STABILIZER DISK.

IT WAS ALSO DECIDED TO GIVE EQUAL SIMILAR TO THOSE USED ON BWR/6 PLANTS.

THE BWROG HAS STATUS TO SOTH THE CATALYST OPTION AND THE PRESSURE SWITCH MODIFIED THE SCHEDULE WITH THE CATALYST DESIGN FOR THE OPTION THIS IS IN APPARENT RECOGNITION OF THE FACT ThAT TARGET ROCK 2-STAGE SRV*S.

THE STAFF MET WITH THE BWROG ON SOME OF 's H E BWROG MAY BE LOSING INTEREST IN THE CATALVST AUGUST II, 1992 AND DISCUSSED DETAILS OF THE CATALYST DESIGN OPTION DUE TO THE LONG LEAD TIME TO O8TAIN THE CATALYTIC 1

(OPTION II AND ALSO THE PROGRESS ON THE PARALLEL CONTINGENCY COATED VALVE PARTS.

A LICENSING TOPICAL REPORT ON THE OPTION 2.

AN INDE PE NDENT DESIGN REVIEW HAS BEEN COMPLETED PRESSURE SWITCH OPTION AND A DETAILED LETTER STATUS FROM IN THE THIRD QUARTER OF FY '92 FOR OPTION 1.

LABORATORY THE BWROG HAD BEEN SCHEDULED FOR SUBMITTAL TO THE NRC IN TESTING IS COMPLETE AND DEMONSTRATES THAT THE ALLOY COATING APRIL 1993.

AS OF FY93 QUARTER 4 O

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51 ISSUE NUMBER:

B-55 TITLE: IMPROVE RELIABILITY OF TARGET ROCK SAFETY-RELIEF VALVES STATUS IN A TELECON ON JUNE 30, 1993, THE BWROG ADVISED THAT

2) NRR REVIEW OF THE PRESSURE SWITCH LICENSING THE SCHEDULE FOR SUBMITTAL OF BOTH THE LICENSING TOPICAL TOPICAL REPORT.

REPORT AND THE STATUS LETTER HAD SLIPPED THE BWROG SINCE MOST OF THE NRC STAFF EFFORT RELATED TO THE BALANCE ADVISED THAT UTILITY APPROVALS WERE EXPECTED SOON AND OF THE GENERIC RESOLUTION OF THIS GI IS EXPECTED TO BE THAT BOTH ITEMS SHOULD BE SENT TO THE NRC IN JULY 1993.

UNDERTAKEN WITHIN NRR, AND SINCE ANY PLANT MODIFICATIONS SINCE THE LAST UPDATE DISCUSSIONS WERE HELD BETWEEN THE RESULTING FROM THE RESOLUTION OF THIS ISSUE ARE EXPECTED TASK MANAGER AND DSIR MANdGEMENT REGARDING THE TO BE EITHER VOLUNTARY OR JUSTIFIED ON A " COMPLIANCE

• ADMINISTPATIVE ASPECTS OF MANAGING THIS GI FOR THE BALANCE BASIS, RES HAS FORMALLY REQUESTED THAT THE ISSUE BE OF THE GENERIC RESOLUTION PERIOD.

TWO GENERIC RESOLUTION TRANSFERRED TO NRR FOR THE BALANCE OF THE GENERIC TASKS REMAIN:

RESOLUTION PERIOD AND SUBSEQUENT PLANT SPECIFIC IMPLEMENTA-

1) INSTALLATION OF TRIAL CATALYST MODIFIED PILOT TION.

A TRANSFER MEMORANDUM WAS TRANSMITTED TO NRR VALVES ON A NUMBER OF PLANTS OVER APPROXIMATELY ON AUGUST 3, 1993.

THE NEXT THREE YEARS.

AFFECTED DOCUMENTS PROBLEM / RESOLUTION ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE MEETING WITH BWR OWNERS SETPOINT DRIFT 12/83 11/83 COMMITTEE BWR OWNERS REPORT SUBMITTED 07/84 06/84 BOSTON EDISON REPORT SUBMITTED 08/84 COMPLETION OF NRR EVALUATION OF OWNERS 10/84 10/84 GROUP AND BOSTON EDISON REPORTS COMMUNICATION TO OG RE: NRC 03/85 COMMENTS / CONCERNS OG PRESENTATION TO THE STAFF 10/85 10/85 STAFF RECEIVES OWNERS' PROGRAM FOR 10/85 10/85 ELIMINATING SET POINT DRIFT AS OF FY93 QUARTER 4

- -. _, _ __._... _ _. ~ ~...

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52 ISSUE NUMBER-B-55 TITLE: IMPROVE RELIABILITY OF TARGET ROCK SAFETY-RELIEF VALVES ORIGINAL CURRENT ACTUAL MILESTONES DATE DATE DATE bbhERhhhbkhTb~kkhT LLEbb3ktbkbkhKh hk/8h hk/8h TO TEST IN PLANT FOR ONE FUEL CYCLE ISSUE STATUS REPORT ON INDUSTRY EFFORTS

~12/87 01/88 ISSUE PROGRESS REPORT ON INDUSTRY EFFORTS 11/88 11/88 BWROG APPROVAL FOR FUNDING CATALYST / PRESSURE 06/90 06/90 SWITCH PROGRAM BWROG SELECT / DESIGN CATALYST 03/91 02/91 NRC STAFF ISSUE STATUS REPORT ON INDUSTRY 06/91 08/91 PROGRESS BWROG COMPLETES FINALIZING DESIGN AND 04/92 07/92 LABORATORY TESTING NRC STAFF ISSUE STATUS REPORT ON INDUSTRY 03/92 08/92 PROGRESS l

REASSESS ISSUE 03/93 05/93 l

REASSIGN TO NRR 08/93 08/93 i

AS OF FY93 QUARTER 4 l

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53 ISSUE NUMBER:

B-56 TITLE. DIESEL GENERATOR RELIABILITY IDENTIFICATION DATE: 06/78C PRIORITIZATION DATE: 11/83C TYPE-- GSI PRIORITY: H TAsh MANAGER.

A.

SERKIZ OFFICE / DIVISION / BRANCH: RES /DSIR/EIB ACTION LEVEL: ACTIVE STATUS: 3A TAC NUMBERS:

RESOLUTION DATE: 06/93C WORK AUTHORIZATION: NRR FY-83 OPERATING PLAN (APPENDIX Gl.

FIN CONTRACTOR CONTRACT TITLE 5806 hhk bbhbkL$hkb kbh khkkb bkkkkk bkhkkkkbk kbbh kkLkkbhLkkh PRbbk hk B2937 PNL AGING CONSIDERATIONS-DIESEL GENERATOR R LIABILITY PROGRAM W0RK SC0PE hbkhbkkhbbhkhkbSh6 khbLbbkLhbbbRbkhkkkbhkhHkHk LEVkLbhktkbhkbkbkkkbPbhhkkbkbEkbbkb[k(10bkkh0 RESOLUTION OF USI A-44, STATION BLACKOUT.

RESOLUTION OF SECTION 50.63).

USI A-44 INCLUDES AMONG OTHER THINGS, THE NEED FOR A DIESEL THE CONCLUDING EFFORTS ON B-56 WILL BE DIRECTED AT RELIABILITY PROGRAM TO MAINTAIN THE RELIABILITY LEVEL OF CARRYING OUT ACTIONS RELATED TO THE SRM IN RESPONSE TO EMERGENCY DIESEL GENERATORS (EDG) AT OR ABOVE RELIABILITY SECV-93-044.

STATUS THE COMMISSION DIRECTED THE STAFF (SRM COMJC-91-001/001-A TION OF THE MAINTENANCE RULE 10 CFR 50 65 THE COMMISSION APPROVED THE STAFF {S RECOMMENDA DATED JUNE 26, 1991) TO REVISE THE SB0 RULE TO ADDRESS EDG IONS ON RELIABILITY THROUGH A RESULTS-ORIENTED APPROACH UTILIZING 03/25/93. THE MAINTENANCE RULE REGULATORY GUIDE WAS THE FAILURE TO START AND LOAD-RUN TRIGGERS OUTLINED IN ISSUED JUNE 1993.

NUMARC'S INITIATIVE 5A, A REVISED RULE AND ACCOMPANYING THE NRC HAS WITHDRAWN THE RULE AMENDMENT (58 FR 37884)

REGULATORY GUIDE (RG 1.9, REV. 3) WAS ISSUED FOR COMMENT TO 10 CFR 50 63 PROPOSED IN APRIL 1992 WHICH WOULD HAVE ON APRIL 21, 1992 REQUIRED LICENSEES TO TEST AND MONITOR EMERGENCY DIESEL NUMARC AND INDUSTRY RESPONDEES OPPOSED THE NEED FOR THIS GENERATORS AGAINST SPECIFIED CRITERIA (58 FR 37884).

IN RULE CITING CURRENTLY INDUSTRY-WIDE EDG RELIABILITY LEVELS ADDITION, REVISION 3 LO REGULATORY GUIDE 19 " SELECTION.

OF 99% AND RECOMMENDED THAT THE PLANN(D MAINTENANCE RULE DESIGN, QUALIFICATION AND TESTING OF EMERGENCY DIESEL GUIDANCE BE USED TO MAINTAIN CURRENT LEVELS OF EDG GENERATOR UNITS USED AS CLASS 1E ONSITE ELECTRIC POWER RELIABILITY.

SYSTEMS AT NUCLEAR POWER PLANTS." JULY 1993. WAS ISSUEp THE STAFF EVALUATED COMMENTS RECEIVED AND SUBMITTED A THESE TWO ACTIONS CONSTITUTE RESOLUTION OF GENERIC SAFETY RECOMMENDATION TO THE COMMISSION THAT THE PROPOSED RULE ISSUE B-56

" DIESEL GENERATOR RELIABILITY."

AMENDMENT DE WITHDRAWN (SECY-93-044).

IN PLACE OF THE THIS REVISION TO REGULATORY GUIDE 1.9 INTEGRATES INTO PROPOSED RULE. THE STAFF RECOMMENDED THAT GUIDANCE FOR A SINGULAR REGULATORY GUIDE PER TINENT GUIDANCE PREVIOUSL Y MONITORING EDG PERF ORMANCE AGAINST TARGET LEVELS SELECTED ADDRESSED IN REVISION 2 0F REGULATORY GUIDE 1.9, REVISION 1 FOR THE 580 ANALYSES BE INCORPORATED INTO THE REGULATORY OF REGULATORY GUIDE 1.108 AND GENERIC LETTER 84-15.

THE GUIDE AND GUIDANCE BEING DEVELOPED BY NUMARC FOR IMPLEMENTA-GUIDANCE FOR THE MONITORING AND MAINTAINING OF EMERGENCY AS OF FY93 QUARTER 4

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54 ISSUE NUMBER B-56 TITLE: DIESEL GENERATOR RELIABILITY STA TUS DIESEL PERFORMANCE AGAINST VALUES SELECTED BY LICENSEES THE EFFECTIVENESS OF MAINTENANCE AT NUCLEAR POWER IN THEIR STATION BLACK 0UT COPING ANALYSES HAS BEEN PLANTS," JUNE 1993.

INCORPORATED INTO REGULATORY GUIDE 1.160

" MONITORING

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AFFECTED DOCUMENTS PROBLEM / RESOLUTION

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ORIGINAL CURRENT ACTUAL MILEST0NES

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DATE DATE DATE bik~ibEhhkFkkb[~khbkbby~bbkb5kkbibkFbR~

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STAFF COMMENT PACKAGE TO NRR DIRECTOR 04/83 03/83 PACKAGE TO CRGR (29);

05/83 07/83 CRGR REVIEW COMPLETE SCOPE OF ISSUE MODIFIED TO COORDINATE 09/83 09/83 TECHNICAL RESOLUTION OF B-56 WITH USI A-44 SCOPE OF ISSUE MODIFIED TO CONSIDER NUMBER OF 11/83 11/83 COLD FAST START SURVEILLANCE TESTS COORDINATED GSI B-56 AND USI A-44 CRGR PACK-02/84 01/84 AGE SENT TO NRR DIRECTOR REVISED PACKAGE TO CRGR - ACTUAL DATE 03/84; 05/84 05/84 CMGR REVIEW COMPLETE ISSUED 50.54(F) GL 84-1S TO LICENSEES 06/84 07/84 RECEIVED PUBLIC COMMENTS 09/84 11/84 ISSUED T/A CONTRACT TO BNL 06/85 06/85 AS OF FYg3 QUARTER 4 f

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55 ISSUE NUMBER:

B-56 TITLE: DIESEL GENERATOR RELIABILITY ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE PbbLhhhbbkhRbTbRhkPbkTbkLkbkhSEk bk/hk 04/k6 ~

RESPONSE TO 50.54tF)

REVISE SRPS AND REG. GUIDES (NRR) 03/88 05/88 DEVELOP DIESEL GENERATOR RELIABILITY PROGRAM 10/86 04/88 GUIDELINES CRGR PACKAGE TO RES DIRECTOR 01/87 07/88 PACKAGE TO CRGR/ACRS (53) 03/87 08/88 CRGR REVIEW COMPLETE 05/87 09/88 ACRS REVIEW COMPLETE; ISSUE FOR PUBLIC 06/87 11/88 COMMENTS PUBLISH NUREG/CR-5078 VOL 2 11/88 01/89 RECEIVE PUBLIC COMMENTS 08/87 03/89 FTR TO RES DIRECTOR: FTR TO CRGR/ACRS 09/87 08/89 RECEIVE NUMARC APPENDIX D SUBMITTAL 04/90 05/90 REVISE CRGR PACKAGE i

NRR & OGC CONCURRENCES 06/90 06/90 CRGR/ACRS MEETINGS (ACRS MEETING HELD IN 07/90 07/90 AUGUST OF 1990)

. COMMISSION PAPER TO EDO

-10/90 10/90 RECEIVE B-56 SRM 07/91 06/91 REVISE SB0 RULE, R;G.

1.9, REV. 3; PREPARE 07/91 11/91 DRAFT FRN PACKAGE TO ACRS 10/91 11/91 i

AS OF FY93 QUARTER'4

.. ~.

RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

56 ISSUE NUMBER:

B-56 TITLE: DIESEL GENERATOR RELIABILITY ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE CRGR AND ACRS MEETINGS

_09/91 11/91 ISSUE LETTER TO NUMARC ON ACCELERATED 10/91 11/91 TESTING SUBMIT DRAFT PACKAGE TO EDO

~

10/91 01/92 PACKAGE TO COMMISSION (SECY-92-025) 01/92 01/92 COMMISSION RESPONSE 12/91 03/92 ISSUE PACKAGE FOR COMMENT 12/91 04/92 END T5-DAY PUBLIC COMMENT PERIOD 02/92 07/92 REVISE PACKAGE AND SUBMIT TO RES DIRECTOR 03/92 11/92 FORWARD B-56 PACKAGE TO ACRS 11/92 11/92 ACRS REVIEW 12/92 12/92 CRGR REVIEW 12/92 01/93 FORWARD RECOMMENDATION TO EDO 01/93 01/93 COMMISSION REVIEW 02/93 03/93 ISSUE MAINTENANCE RULE REG. GUIDE (WITH EDO 06/93 06/93 GUIDANCEI CLOSE00T MEMO TO EDO 06/93 06/93 WITHDRAW SB0 RULE AMENDMENT 08/93 07/93 AS OF FY93 QUARTER 4 O

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RUM DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

57 ISSUE NUMBER:

B-61 TITLE: ALLOWABLE ECCS EQUIPMENT OUTAGE PERIODS IDENTIFICATION DATE: 06/78C PRIORITIZATION DATE: II/83C TYPE: GSI PRIORITY: M TASK MANAGER: A.

BUSLIK OFFICE / DIVISION / BRANCH: RES /DSR /PRAB ACTION LEVEL: ACTIVE STATUS:

TAC NUMBERS:

RESOLUTION DATE: 12/94 WORK AUTHORIZATION: NRR FY-84 OPERATING PLAN (APPENDIX G)

FIN CONTRACTOR CONTRACT TITLE W0RK SC0PE IN GENERAL, PLANTS WILL BE CLASSIFIED SUCH THAT OF SUPPORT SYSTEM OUTAGES MUST BE INCLUDED. DCTAILS IN EACH CLASS SIMILAR ECCS OUTAGE UNAVAILABILITIES OF THE WORK SCOPE ARE CONTAINED IN THE DRAFT ACTION WILL HAVE SIMILAR IMPACTS ON RISK.

THE EFFECT OF A PLAN.

BECAUSE CUMULATIVE OUTAGE TIMES ON COMPONENTS OTHER GIVEN ECCS AVAILABILITY ON RISK WILL BE DETERMINED, THAN ECCS COMPONENTS APPEAR IMPORTANT, THE WORK SCOPE HAS FOR EACH CLASS OF PLANT, AS WELL AS THE IMPACTS OF ANY BEEN EXPANDED TO INCLUDE ALL SAFETY-RELATED COMPONENTS.

CHANGES IN ALLOWABLE ECCS OUTAGE PERIOD. CONSIDERATION STATUS TASK I HAS BEEN COMPLETED.

AFFECTED DOCUMENTS PROBLEM / RESOLUTION kkbbkkbklbPhbkFkbkkkbhbhkbhbkkhPbbbkbLk THh kkhbR PhbLEMkbkbbkkEbWhTHkHkkhbbtbkkbhbF bhk REVISED INSPECTION GUIDANCE FOR VOLUNTARY ENTRY INTO IS AN ANALYSIS OF THE COSTS AND BENEFITS OF THE IMPOSITION LCO'S.

OF A CUMULATIVE OUTAGE REQUIREMENT. BOTH THE FRENCH AND GERMANS USE AN APPROACH TO CUMULATIVE OUTAGE REQUIREMENT, APPLYING THE CUMULATIVE OUTAGE REQUIREMENT ONLY TO SCHEDULED MAINTENANCE. A STUDY OF THE NEED FOR CONTROL OF CUMULATIVE OUTAGE IS BEING PERFORMED IN. HOUSE. WORK IS BEING COORDINA.

TED WITH THE WORK ON THE REGULATORY GUIDE FOR THE MAINTE-NANCE RULE, AND IT MAY BE DETERMINED THAT NO FURTHER ACTION OTHER THAN THAT SPECIFIED IN THE MAINTENANCE RULE AND THE REGULATORY GUIDE IS REQUIRED, AN INITIAL RECOMMENDATION FOR STAFF COMMENTS WAS TO BE COMPLETED AS OF FY93 QUARTER 4

RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTPOL SYSTEM PAGE:

58 ISSUE NUMBER:

B-61 TITLE: ALLOWABLE ECCS EQUIPMENT OUTAGE PERIODS AFFECTED DOCUMENTS PROBLEM

...............___...._...../ RESOLUTION IN TECHNICAL SPECIFICATIONS IS NEEDED, THIS ISSUE WILL BE CLOSED OUT.

THE SCHEDULE GIVEN BELOW ASSUMES THAT A CHANGE IN TECHNICAL SPECIFICATIONS IMPLEMENTING SOME FORM OF CUMULATIVE OUTAGE' REQUIREMENT WILL BE REQUIRED. CURRENTLY. THERE IS NO TECHNICAL ASSISTANCE CONTRACT ON THIS ISSUE, NOR IS ONE CURRENTLY PLANNED:

ALL WORK IS BEING PERFORMED IN-HOUSE.

THE ORIGINAL SCHEDULE FOR AN INITIAL RECOMMENDATION FOR STAFF COMMENTS HAS BEEN DELAYED BY OTHER WORK;N ORIGINALLY ALSO, THE COST-BENEFIT ANALYSIS IS TAKING MORE TIME THA ANTICIPATED.

THE DRAFT TECHNICAL RESOLUTION HAS BEEN SUBMITTED FOR MANAGEMENT REVIEW NO TECHNICAL SPECIFICATION CHANGES ARE RECOMMENDED, BUT REVISED INSPECTION GUIDANCE ON VOLUNTARY ENTRY INTO LCO S IS RECOMMENDED.

NO WORM WAS PERFORMED ON THIS ISSUE DURING FY '93 QUARTER 2 OR 3 BECAUSE OF HIGHER PRIORITY WORK.

COMMENTS ON THE DRAFT TECHNICAL RESOLUTION WERE RECEIVED FROM IMMEDIATE MANAGEMENT IN AUGUST 1993 REVISIONS WILL BE MADE TO THE COST-BENEFIT ANALYSIS TO MAKE IT CONSISTENT WITH THE RECENT DRAFT FOR COMMENT OF THE REGULATORY ANALYSIS GUIDELINES.

ORIGINAL CURRENT ACTUAL MILE $ TONES DATE DATE DATE DRAFT TAP ISSUED FOR DD APPROVAL 01/84 01/84 COMPLETE COORDINATION OF TECHNICAL RESOLUTION 04/84 08/84 WITH RES TAP APPROVED BY DIVISION DIRECTOR 05/84 07/84 TASM I-METHODOLOGY REVIEW AND 11/84 04/85 DEVELOPMENT COMPLETED TASK II-APPLY TO A PWR OR BWR 02/85 02/92 DEVELOP AN INITIAL RECOMMENDATION FOR STAFF 08/87 09/92 COMMENTS AS OF FY93 QUARTER 4 O

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59 ISSUE NUMBER:

B-61 TITLE. ALLOWADLE ECCS EQUIPMENT OUTAGE PERIODS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE PPL kkTHbbbLbbhhbkhhlkbhkbhbhPLkkkh hh/hh hh/hh PREPARE DTR 04/86 11/93 PREPARE CRGR PACKAGE 06/86 12/93 REVIEW OF CRGR PACKAGE BY DIVISION 07/86 01/94 DIRECTORS RES DIRECTOR REVIEW COMPLETE /

08/86 02/94 PACKAGE TO CRGR CRGR REVIEW AND EDO APPROVAL COMPLETED 09/86 03/94 ISSUANCE OF'FRN FOR PUBLIC COMMENT 11/86 04/94 SIXTV-DAY COMMENT PERIOD ENDS 01/87 06/94 DIVISION REVIEW OF PUBLIC COMMENTS 02/87 08/94 COMPLETED, AND FINAL CROR PACKAGE COMPLETED RES REVIEW OF CRGR PACMAGE COMPLETED 04/87 10/94 (DIVISION REVIEW AND RES DIRECTOR REVIEW)

ACRS REVIEW 09/93 11/94 CRGR REVIEW AND EDO APPROVAL COMPLETED 05/87 12/94 CLOSE OUT ISSUE 09/93 12/94 4

AS OF FY93 QUARTER 4

=.

-. m...

. _ _. _... _. -....... _ - _. _.. _. ~.. _. _ _ _ _ _ -..,. - -

4

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60 ISSUE NUMBER:

B-64 TITLE: DECOMMISSIONING OF REACTORS IDENTIFICATION DATE: Ob/T8C PRIORITIZATION DATE: II/83C TYPE. GSI PRIORITY.

TASK MANAGER' L.

BELL OFFICE / DIVISION / BRANCH: NHSS/LLWM/LLRB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS-RESOLUTION DATE-10/93 WORK AUTHORIZATION-NRR FY-84 OPERATING PLAN, ( APPENDIX G).

FIN CONTRACTOR CONTRACT TITLE hh34h PhL bkbbkhkkbkhkbhkkbbEbbkkikkihkihbRkVhEW W0RK SC0PE DEVELOP A GENERAL DECOMMISSIONG POLICY, PREPARE THE DECOMMISSIONING. AND ESTABLISH GUIDANCE FOR FACILITATION ATTENDENT CHANGES IN REGULATIONS, DEVELOP THE DETAILED OF DECOMMISSIONING.

INFORMATION NEEDED FOR USE IN LICENSING DECISIONS FOR STATUS FINAL RULE CHANGES VERE AFFIRMED BY THE COMMISSION ON TO NHSS NMSS IS PREPARING THE SRP THE SRP HAS DEEN SENT MAY 12, 1988 AND PUBLISHED IN THE FR ON JUNE 2T 1988 FOR OFFICE CONCURRENCE PRIOR TO SUBMITTAL TO CRGR.

MEMO NRC DECOMMISSIONING RESPONSIBILITIES WERE TRANSFERRED TO BE ISSUED TO TRACK SRP ISSUANCE IN SRP TRACKING SYSTEM.

AFFECTED DOCUMENTS PROBLEM / RESOLUTION

~ ~~5bbik~PkkkhShkkbhkkhkhbhEhhh$

~

hbhk$

~

~

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REGULATORY GUIDE I.86 REVISION,

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.

ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE CRGR REVIEW COMPLETED ON DECOMMISSIONING 08/84 08/84 RULE (29)

AS OF FY93 QUARTER 4 O

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PAGE, 61 ISSUE NUMBER:

B-64 TITLE: DECOMMISSIONING OF REACTORS t

l ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE kbb kPPRbVkL bF hkhb khhkbhkhb hkbh khhkk 09hkk 34-354 COMMISION APPROVAL OF SECY-84-354 12/84 12/84 ISSUANCE OF DRAFT RULE CHANGE FOR 02/85 02/85 PUBLIC COMMENT FORMAT AND CONTENT FOR DECOMMISSIONING 02/84 06/85 EXTENDED PUBLIC COMMENT PERIOD ON RULE 07/85 07/85 COMPLETE ISSUE TRANSFER MEMO TO RES (SRP) 01/86 01/86 REVISE DRAri RULE INCORPORATING PUBLIC 02/86 11/86 COMMENTS PREPARE FOR RES MANAGEMENT REVIEW REVISE DRAFT RULES /PUBLIC COMMENTS 08/86 08/87 REVIEWED AND APPROVED BY CRGR (53)

FTR TO EDO FOR TRANSMITTAL 70 COMMISSION 10/86 12/87 FRN OF FINAL RULE 01/87 06/88 ISSUE MEMO TO TRANSFER TO SRP TRACKING 10/93 10/93 SYSTEM O

AS OF FY93 QUARTER 4

-. _,,... ~. _ _ _.,. _,.

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RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE.

62 ISSUE NUMBER: HF 4.4 TITLE: GUIDELINES FOR UPGRADING OTHER PROCEDURES IDENTIFICATION DATE. 08/83C PRIORITIZATION DATE: 10/84C TYPE: GSI PRIORITY. H TASK MANAGER-J, WACHTEL OFFICE / DIVISION / BRANCH: RES /DSR /HFB ACTION LEVEL: ACTIVE STATUS.

TAC NUMBERS:

RES010110N DAT[- 01/93C WORK AUTHORIZATION: MFM0 FOR H THOMPSON FROM H DENTON DATED 10/1/84,

" HUMAN FACTORS PROGRAM PLAN

• FIN CON 1RACTOR CONTRACT TITLE b236b Pkk.

bkVkLbP bbhbkhbk khb hkbb[kkbkh kbhkbh kbR bPk k kbPh B2935 PNL VALVE IMPACT ASSESSMENT OF PLANT OPERATING PROCEDURES B2966 PNL DEVELOP GUIDANCE & REGULATORY ACTION FOR OPS & AOPS I2005 PNL DEVELOP GUIDANCE & REGULATORY ACTION FOR OPS & AOPS L1827 PNL GUIDANCE FOR REVIEW OF PROGRAMS TO UPGRADE PROCEDURE AT NUCLEAR POWER PLANTS W0RK SC0PE kkbbbhEbbkhPhbVEhkhhhkhbbbLkkR PbWkkPLkh hkbkhhkRh kbR kkbh hhPk bk Pkbbkbbkk bkhEb bh OPERATING PROCEDURES AND DEVELOP AN IMPLEMENTATION A CONTRACTOR INTERIM REPORT AND INDUSTRY PLAN FOR UPGRADING OPERATING PROCEDURES. NRC INPUTS WITH RESPECT TO COST AND BENEFITS.

WILL DETERMINE THE AMOUNT OF UPGRADE EFFORT STA TUS hbkhkhbbhhkkhR hkhkhRkb kRbh hRh hb hkh hkkh khk hkhkbkR hkh khhkbkhb khb hhk kbhEbblE bbbbEh khb hbbPE 4/12/87 NRC REORGANIZATION (4/10/87 MEMO FROM W RUSSELL WERE REVISED IN JULY 1988.

NUREG/CR-5458 WAS PUBLISHED IN TO T SPEIS).

CONTRACTOR EFFORTS ON FIN B2360/PNL AND DECEMBER 1989 AGREEMENT REACHED WITH NRR TO DEVELOP A FIN B2966/PNL WERE COMPLETED AT THAT TIME. NUREG/CR'S-PROCEDURES UPGRADE " GOOD PRACTICES

• GUIDE.

WORK TO BE 3968 AND +4613 WERE PUDLISHED IN FEBRUARY 1987 AS A INITIATED FEBRUARY 1991.

STATEMENT OF WORK FOR " GOOD RESULT OF WORK UNDER THESE FINS REVIEW OF NUREG/

PRACTICES

• PROJECT ISSUED MAY 1991.

EFFORT EXPANDED BEYOND CR'S-3968 AND -4613 PRIOR TO THE NRC REORGANIZATION NORMAL AND ABNORMAL PROCEDURES, PER NRR, TO INCLUDE PRO-INDICATED THE NEED FOR A REGULATORY ANALYSIS OF THIS ISSUE.

CEDURES DURING NONPOWER OPERATIONS. AT A MEETING WITH NRR AWARDED AN ADDITIONAL CONTRACT TO PNL IN JUNE 1987 TO J.

SNIEZEK IN NOVEMBER 1991, THE FOCUS OF THIS PROJECT *WAS CONDUCT THAT ANALYSIS UNDER FIN I-2005.

RESPONSIBILITY FOR CHANGED TO EMPHASIZE NONPOWER OPERATIONS AND MINIMIZE THE THAT CONTRACT WAS TRANSFERRED TO RES BY NOVEMBER 16, 1987 ATTENTION PAID TO NORMAL AND ABNORMAL PROCEDURES.

MEMORANDUM F ROM L. RUTH TO M.

KALTMAN.

A NEW RES TASK AS OF FY93 QUARTER 4 O

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5 RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE.

63 ISSUE NUMBER.

HF 4.4 TITLE: GUIDELINES FOR UPGRADING OTHER PROCEDURES AFFECTED DOCUMENTS PROBLEM / RESOLUTION LkTEkkkhkkkkVkkhbbbbMkhkkhbPRbbkhbkkhPRkbkkbkhkk ELkhbbbhkkhkLhbkkbbRhkkPbhLkkhkbkhbhbkhhkR h8h[

NUCLEAR POWER PLANTS.

REQUESTS FROM OTHER OFFIC S RESULTED IN MAINTAINING THIS ISSUE OPEN PENDING A RESOLUTION OF WHETHER ADDITIONAL EFFORT IS NECESSARY UNDER THIS ISSUE, AS A RESULT OF NOVE MBE R 1991 MEETING WITH J.

SNIEZEK. THE CONTRACT WAS REVISED TO ADDRESS ONLY THOSE PROCEDURES RELATED TO SHUTDOWN AND LOW POWER OPERATIONS. A RECENT NRR USER NEED LETTER (3/8/93 MEMO FROM T.

MURLEYI HAS WITHDRAWN THE NEED FOR ANY OF THE REMAINING WORK AND ACCORDINGLY THIS ISSUE WAS CLOSED OUT BASED UPON THE WORK DONE TO DATE.

ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE PUBLISH FINAL REPORT ON OPERATING 12/85 02/87 PROCEDURES PROJECT AS NUREG/CR PUBLISH FINAL REPORT ON PROCEDURES 05/86 02/87 INTERFACE PROJECT AS NUREG/CR CONDUCT REGULATORY ANALYSIS FOR OPERATING 02/87 07/89 PROCEDURES, ABNORMAL OPERATING PROCEDURES DEVELOP PLAN FOR REGULATORY GUIDANCE 06/89 09/89 PREPARE CLOSEOUT MEMO 04/93 04/93 1

CLOSE OUT ISSUE 06/89 07/93 CLOSE OUT CONTRACT BY DOCUMENTING LITERATURE 08/92 11/93 SEARCH ON PROCEDURES FOR LOW POWER AND SHUTDOWN OPERATIONS AT NUCLEAR POWER PLANTS AS OF FY93 CUARTER 4

--,.- _.,_,--,_ _, _ _ _,.. _. _ - -. - _, ~ - -

,... ~. _ _ -.. _

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64

~

ISSUE NUMBER: HF 5.1 TITLE: LOCAL CONTROL STATIONS IDENTIF ICATION DATE : 08/83C PRIORITIZATION DATE: 10/84C TYPE. GSI P"IORITY: H TASK MANAGER:

J. WACHTEL OFFICE / DIVISION / BRANCH. RES /DSR /HFB ACTION LEVEL; ACTIVE STATUS: 3B TAC NUMBERS:

RESOLUTION DATE: 06/93C WORK AUTHORIZATION: MEMO TO H.

THOMPSON FROM H.

DENTON DATED 10/1/84

• HUMAN FACTORS PROGRAM PLAN" m

FIN CONTRACTOR CONTRACT TITLE hhh2 Bhb Lbb[bbkhRbthkhkbbh W0R K SC0PE hhkkkRhhbbkkbkhhhhWbRK khkbhkkkRMkhkhhkRkhK hb RkhblVkkhkLbbklbbhhRblkhkhkbbkkhhbk hhkbbhkbhkVkbk PUBLIC HEALTH AND SAFETY RESULTING FROM HUMAN ERROR AT LOCAL THIS WORK IS TO DEVELOP A REGULATORY GUIDE ON LOCAL CONTROL CONTROL STATIONS WITHIN A NUCLEAR POWER PLANT AND THE COST STATIONS AND REVIEW GUIDELINES FOR THE EVALUATION OF LOCAL OF POTENTIAL MODIFICATIONS.

THE METHOD TO DETERMINE RISK CONTROL STATIONS. AS A RESULT OF SENIOR MANAGEMENT REVIEW OF IS THROUGH THE USE OF PROBABILISTIC RISK ANALYSIS (PRA).

THIS PROJECT ON JUNE 2, 1992. WORK SCOPE WAS REDUCED TO FOR PLANNING PURPOSES. WE ASSUME THE RESULTS OF THE ELIMINATE DEVELOPMENT OF REGULATORY GUIDANCE AND REVIEW VALUE/ IMPACT ANALYSIS WILL REQUIRE ADDITIONAL WORK TO GUIDELINES.

STATUS BY LETTER DATED DECEMBER 29, 1987 THE S0W WAS FEBRUARY 1989.

A REVISED S0W WAS DEVELOPED AND WORK BEGAN FORWARDED TO BNL.

BY LETTER DATED MARCH 25 1988 NRC APRIL 1990.

WORK TERMINATED (SEE MEMORANDUM FROM AUTHORIZED BNL TO BEGIN PROGRAM BNL BEGAN WORK IN MAY.

E.

BECKJORD TO EDO ON JUNE 29, 1993) 1988.

A ORAFT VALUE/ IMPACT REPORT WAS SUBMITTED BY BNL IN AFFECTEu DOCUMENTS PROBLEM / RESOLUTION hbkkb/bk$hhhh bbbb PRkbhkbkh kbR hhhbkhkbhbF Lbb L kbhk5 CONTROL STATIONS.

AS OF F Y93 QUARTER 4 O

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y RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

65 l

ISSUE NUMBER: HF S.1 TITLE: LOCAL CONTROL STATIONS i

ORIGINAL CURRENT ACTUAL f

i MILESTONE $

DATE DATE DATE BEGIN VALUE/ IMPACT STUDY OF LOCAL CONTROL 02/88 05/88 l

STATIONS COMPLETE PRELIMINARY VALUE/ IMPACT STUDY 07/88 02/89 NRC COMPLETE REVIEW OF STUDY RESULTS 09/88 02/89 COMPLETE PLANT-SPECIFIC VALUE-IMPACT STUDY 09/90 04/91

{

FOR EXPANDED LCS DEFINITION PREPARE CLOSE OUT MEMO 05/93 05/93 CLOSE OUT MEMO TO EDO 12/92 06/93 CONTRACTOR TO PREPARE FINAL REPORT ON 12/92 10/93 GOOD PRACTICES FOR DESIGN OF LOCAL CONTROL STATIONS

[

a 4

. [

t AS OF FY93 QUARTER 4 n,_.._,...

. -..._...; ~ -. _.. _. _.,. -,,..,,,,,..., _.,...... -.. -,. _, _. _.....

RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

6 '6 ISSUE NUMBER: HF 5.2 TITLE; REV, CRIT. FOR HUMAN FACTORS ASPECTS OF ADV CONTROLS AND INSTRUMENT.

IDE NTIFICATION DATE. 08/83C PRIORITIZATION DATE: 10/84C TYPE-GSI PRIORITY: H TASK MANAGER:

J. WACHTEL OFFICE / DIVISION / BRANCH: RES /DSR /HFB ACTION LEVEL: ACTIVE STATUS: 3B TAC NUMBERS.

RESOLUTION DATE. 06/93C WORK AUTHORIZATION. MEMO TO H.

THOMPSON FROM H DENTON DATED 10/1/84,

" HUMAN FACTORS PROGRAM PLAN" FIN CONTRACTOR CONTRACT TITLE A3967 BNL ANNUNCIATORS WDRK SC0PE hhhhkkSbEbbhbkhkhkhE khbbEbFhbhhhEbbk)Fkbhbkb bkk bk khhbRkkkkbh hhbM hbbkhbl bb kb kNhbhbkk bkh hhk PROGRAM PLAN OF

"'2 TION 1.5.2 RESULTS FROM A PRA ESTABLISHED THE MAGNITUDE OF THE RISK COMPUTER

• COMPUTER DISPLAYS INVOLVED AND THE POTENTIAL REDUCTION IN RISK EXPECTED. A I A

' B' EVALUATION OF OPERATOR AID SYSTEMS VALUE/ IMPACT ANALYSIS WAS COMPLETED AND ESTIMATED THE COST l C l ANNUNCIATOPS OF POTENTI AL MODIF ICATIONS TO ANNUNCIATORS.

l D I SAFETY STATUS INDICATION AND APPLICATIONS OF AUTO-THE RESULTS OF THE VALUE/ IMPACT ANAL YSIS REQUIRE THAT MATION AND ARTIFICIAL INTELLIGENCE ADDITIONAL EXPERIMENTAL WORK ON ANNUNCIATOR UPGRADES BE A MANAGEMENT REVIEW OF THESE ISSUES RESULTED IN A CONDUCTED ON A TTC SIMULATOR TO RESOLVE THE ANNUNCIATOR DECISION TO RETAIN ONLY THE ANNUNCIATOR ISSUE AS A GENERIC ISSUC.

IN EVALUATING ALARM REDUCTION TECHNIQUES, WE ALSD ISSUE.

THIS DECISION ALSO CONCLUDED THAT THE REMAINING PLAN TO USE THE RESEARCH RESULTS ON ADVANCED ALARM SYSTEMS ISSUES BE REASSIGNED AS RESEARCH ISSUES. A RESEARCH CONDUCTED AT THE HALDEN PROJECT.

THE RESULTS FROM THIS PROJECT ENTITLED

• REVIEW CRITERIA FOR HUMAN FACTORS ASPECTS EFFORT WILL DEVELOP GUIDELINES ON COMPUTER-BASED ANNUNCIATOR OF ADVANCED CONTROL AND INSTRUMENTAION," FIN B0852, SYSTEMS.

THESE GUIDELINES WILL SERVE AS THE BASIS FOR A ADDRESSES THESE ISSUES.

NUREG ON ANNUNCIATORS. NRR WILL INCORPORATE RESULTS OF THIS THE GOAL OF THIS WORK IS TO DETERMINE THE RISK TO WORK IN THEIR MODIFICATIONS TO THE STANDARD REVIEW PLAN.

PUBLIC HEALTH AND SAFETY RESULTING FROM HUMAN ERROR IN THE STATUS BY LETTER DATED DECEMBER 29, 1987 THE S0W FOR THE VALUE.

COMPLETED IN NOVEMBER 1988.

ALARM REDUCTION STUDY BEGAN IMPACT STUDY WAS FORWARDED TO BNL.

PROJECT AND BUDGET OCTOBER 1990 WORK TERMINATED.

(SEE MEMORA.1DUM FROM PROPOSAL FON NRC WORK (NRC FORM 189) RECEIVED MARCH 7, 1988.

E. BECKJORD TO THE EDO ON JUNE 29, 1993,1 BNL BEGAN WORK IN APRIL 1988.

VALUE/ IMPACT STUDY WAS AS OF FY93 QUARTER 4 O

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RUN DATE: 10/20/93 GENERIC ISSUE MANAGEME*si CONTROL SYSTEM PAGE:

67 ISSUE NUMBER.

HF 5.2 TITLE:,REV. CRIT. FOR HUMAN FACTORS ASPECTS OF ADV CONTROLS AND INSTRUMENT.

AFFECTED DOCUMENTS PROBLEM / RESOLUTION

....r.........

ORIGINAL CURRENT ACTUAL MILESTDNES DATE DATE DATE bEbkh~VELbEhkMPkhkhTbbhbFkhhhhbkkTbRh

~~

h2hkh bkhhh COMPLETE VALUE/ IMPACT STUDY 07/88 10/88 NRC COMPLETES REVIEW Or STUDY RESULTS 09/88 11/88 ISSUE SDW FOR ALARM REDUCTION EVALUATION 11/88 01/89 BEGIN ALARM REDUCTION STUDY 01/89 03/89 PREPARE CLOSE0VT PACKAGE-04/93 04/93 CLOSE OUT.NEMO TO EDO 06/93 06/93 COMPLETE ALARM REDUCTION STUDY 11/89 03/94 O

AS OF FY93 QUARTER 4..

RUN DATE-10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE 68 ISSUE NUMBER:

I D.3 TITLE. SAFETY SYSTEM STATUS MONITORING IDENTIFICATION DATE' 05/80C PRIORITIZATION DATE: II/83C TYPE. GSI PRIORITY. M TASK MANAGER: S DIAB 0FFICE/ DIVISION / BRANCH: RES /DSIR/EIB ACTION LEVEL: ACTIVE STATUS:

TAC NUMBERS:

RESOLUTION DATE. 09/93C WORK AUTHORIZATION: TMI ACTION PLAN, NUREG-0660 s

FIN CONTRACTOR CONTRACT TITLE B2360 PNL VERIFICATION, SYSTEM STATUS. AUTOMATIC VS. MANUAL W0RK

$C0PE PNL HAS REVIEWED THE EFFECTIVENESS OF SYSTEMS AND NECESSARY AND FURTHER THAT THIS NEW REVISION SHOULD BE PROCEDURES RELATED TO SAFETY SYSTEM STATUS MONITORING APPLIED TO ALL PLANTS.

BACED ON THE PNL AND HAS RECOMMENDED A REGULATORY POSITION ON THIS ISSUE.

RECOMMENDATIONS DHFS TRANSFERRED RESPONSIBILITY PNL FINDINGS INDICATE THAT A REVISION OF R.0, 1.47 IS FOR THIS ISSUE to RES (REVISE R.G.

1.4T).

STATUS ALL TECHNICAL REPORTS ON THIS ISSUE ARE COMPLETE.

THE ASSESSMENT BRANCH) PERTAINING TO PROPOSED REVISION I STAFF PROJECT FINAL REPLRT INCLUDES GUIDELINES FOR IMPROVING CONSENSUS IS HOWEVER NOT REACHED.

RESPONSIRILITY HAS DEEN SYSTEM STATUS MONITORING As WELL AS THE FINAL RECOMMENDATION TRANSFERRED TO RES/EIB IN FEBRUARY 1992.

OF PNL ON A REGULATORY POSITION. THEIR RECOMMENDATION IS TO A LETTER REPORT TO REDEFINE THE ISSUE WAS COMPLETED REVISE R.G.

1.47 AND APPLY IT TO ALL PLANTS.

STAFF PROPOSES JANUARY 1993.

ON THE BASIS OF THE LETTER REPORT, A TO APPLY NEW REQUIREMENTS FOR FUTURE PLANTS ONLY.

QUICK LOOK VALUE/ IMPACT ANALYSIS HAS BFIN PREPARED TO COMPLIANCE BY OL'S WILL BE VOLUNTARY.

DETERMINE IF THE ISSUE CAN BE CLOSED OUT ON THAT BASIS. A A DRAFT OF THE PROPOSED REVISION I TO R.G.

I.47 WAS DRAFT TECHNICAL RESOLUTION PACKAGE HAS BEEN PREPARED.

DISTRIBUTED IN JULY REVIEW.

A MEETING WAS SUBSEQUENTLY. THE FINAL RESOLUTION PACKAGE WAS ISSUED HELD ON SEPTEMBER 23,87 FOR STAFFTO RESOLVE NRR (HUMAN FACTORSWITH NO LICENSEE ACTION REQUIRED.

1981 AFFECTED DOCUMENTS PROBLEM / RESOLUTION REVISION TO R.G.

1.47.

NONE.

AS OF FY93 QUARTER 4 O

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69 ISSUE NUMBER:

I.D.3 TITLE: SAFETY SYSTEM STATUS MONITORING ORIGINAL CURREkT ACTUAL MILEST0NES DATE DATE DATE hkbbk hkbkbkbbhb b kHk kbhbk khb b5hhh h5)h2 EVALUATE THE NEED FOR REVISION TO EXISTING GUIDANCE PROVIDED IN R.G.

1.47 PREPARE TASK ACTION PLAN 06/92 06/92 TAP APPROVED BY DSIR DIRECTOR 07/92 02/92 LETTER REPORT TO REDEFINE ISSUE IN LIGHT OF 01/93 01/93 CURRENT STATUS OF SSSM PRELIMINARY VALUE IMPACT 05/93 03/93 NRR REVIEW OF RESOLUTION PACKAGE 03/94 07/93 TR PACKAGE TO DIR/DSIR 05/93 07/93 PACKAGE TO ACRS 05/94 07/93 ACRS REVIEW COMPLETE 07/94 07/93 ISSUE CLOSE0VT MEM0; DIR, RES TO EDO 12/94 08/93 CONCURRENCE BY EDO 09/93 09/93 0

AS OF FY93 OUARTER 4 u...-.-_.-_.--__-..:.__...~._u..,.__..-_.

....._:;.., _. _....., _... _. -......... _._,.<_.,-._~;-_...

2._.._,.-

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RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE:

70 ISSUE NUMBER: I D 5(3)

TITLE. ON-LINE REACTOR SURVEILLANCE SYSTEMS IDENTIFICATION DATE: 05/80C PRIORITIZATION DATE: II/83C TYPE: GSI PRIORITY TASK MANAGER-M VAGINS OFFICE / DIVISION / BRANCH: RES /DE /EMEB ACTION LEVEL: ACTIVE STATUS: NR TAC NUMBERS: NONE RESOLUTION DATE: 10/93 WORK AUTHORIZATION. TMI ACTION PLAN, NUREG-0660 FIN CONTRACTOR CONTRACT TITLE bb828 bkhL bbbkkhbbbhbkLkhkkkkbhbRhbkhkhhhhkhkVkLbkhkbbh W0RK SC0PE hhkbbhkbkkVkbkhhkhRkPbkhkhhbPkkkbkNkkhkIhbH bhkkhkhbkhkhbkVkklLkhbhkhhhkhkhbhbhkkkbkh TO DETERMINE THE FEASIBILITY OF DETECTING AND DIAGNOSING DEMONSTRATIONS OF SUCH A SYSTEM IN AN NRC-LICENSED NUCLEAR POWER PLANT OPERATING ANOMALIES USING A CONTINUOUS COMMERCIAL BWR PLANT.

STATUS k bkhbhbkkkkkbh bk hhhkkM Fkkkkb5Lkkh h kh hHkbh5khkkbRVkkLL hhkMkkhbRkhkhhhkhhhkhhHkhkbbbhkh L

OPERATING PWR (SEQUOYAH UNIT 2) HAS BEEN COMPLETED.

THE UNIT 2 PWR IN 1983/84 PLUS AVAILABLE NOISE DATA F ROM SURVEILLANCE INSTRUMENT SYSTEM WAS INSTALLED AT THE PEACH MEASUREMENTS AT THE BROWNS FERRY BWR TO DEVELOP AN BOTTOM UNIT 2, DUE TO THE LONG OUTAGE AT PEACH BOTTOM (24 ACCEPTABLE EVALUATION OF THE ON-LINE SURVEILLANCE SYSTEM MONTHS), THE EXPERIMENT WAS TERMINATED AND THE EQUIPMENT A RIL SUMMARIZING THE RESEARCH RESULTS WAS REMOVED AND PLACED IN STORAGE AT ORNL.

PREPARED, IT IS BELIEVED THAT SUFFICIENT DATA IS AVAILABLE FROM AFFECTED DOCUMENTS PROBLEM / RESOLUTION NONE A RIL WAS PREPARED SUMMARIZING THE CONCLUSIONS AND RECOMMENDATIONS FROM THE RESEARCH ON THIS ACTION ITEM.

RES MEMO SEND TO NRR PRIOR TO CLOSE0VT.

ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE INSTALL SYSTEM AT A PWR 09/80 AS OF FY93 QUARTER 4 O

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71 ISSUE NUMBER.

I.D.513)

- TITLE: ON-LINE REACTOR SURVEILLANCE SYSTEMS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE COMPLETE PWR DATA ACQUISITION 06/84 01/84 INSTALL SYSTEM AT A BWR 04/84 06/85 REMOVAL OF SYSTEM FROM PEACH BOTTOM 12/88 04/89 ISSUE RIL TO NRR WITH CONCLUSIONS AND 09/88 04/93 RECOMMENDATIONS ISSUE CLOSEOUT MEMO TO EDO 12/88 10/93 I

t b

4 e.

AS OF FY93 QUARTER 4-

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RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE-72 ISSUE NUMBER.

1.D.5(5)

TITLE. DISTURBANCE ANALYSIS SYSTEMS IDENTIFICATION DATE: 05/80C PRIORITIZATION DATE: II/83C TYPE. LI PRIORITY:

TASK MANAGER:

L.

BELTRACCHI 0FFICE/ DIVISION / BRANCH: RES /DSR /HFB ACTION LEVEL: ACTIVE STATUS: 5 TAC NUMBERS.

RESOLUTION DATE. 09/93 WORK AUTHORIZATION: TMI ACTION PLAN, NUREG-0660 FIN CONTRACTOR CONTRACT TITLE bbBhh bkkL hEh bhkh kbk hbkkh kkbhbRb khhEbhb bF kbhkhbkb bbhkhbLb k khkhRbh WDR K SC0PE THOSE FACETS OF THE DISTURDANCE ANALYSIS SYSTEM (DAS)

DIFFICULTIES IN GENERATING AND VERIFYING THE ACCURACY OF DEALING WITH UPSET DIAGNOSIS AND REMEDIAL ACTION ARE THE LOGIC MODELS MUST BE OVERCOME DEFORE APPLYING A BASED ON DETAILED LOGIC MCDELS THAT TRACE THE TIME-DAS TO A COMMERCIAL REACTOR ON A TOTAL PLANT BASIS.

DEPENDENT CONSEQUENCES OF COMPONENT FAILURES.

THE STATUS bhkEhbRkhbbhhkhkbbEbkkhhh[h)[h8hfkbR hHkMkbP5 kbhkhbkbbbbhkbLbkhbkhShRbhEhhkhkbN WLLkVkLbkhk SPCIS, FROM BRIAN W.

SHERON,

SUBJECT:

RECOMMENDED DISTURBANCE ANALYSIS SYSTEMS ALONG WITH OTHER ADVANCED CONVERSION OF GENERIC ISSUES TO RESEARCH ISSUESI SPEIS TECHNOLOGIES, SUCH AS COMPUTER-BASED OPERATOR AIDS AND AGREES WITH THE DIVISION OF REACTOR AND PLANT SYSTEMS AR TIF ICI AL INTELLIGENCE-THIS ISSUE WILL CONTINUE TO BE RECOMMENDATION THAT THIS ISSUE BE RECLASSIFIED AS A RESEARCH TRACKED AS A LICENSING ISSUE TO FOLLOW THE RESEARCH WORK, ISSUE.

THE REASON OIVEN FOR THE RECOMMENDATION IS THE NEED FINAL REPORT ISSUED: " HUMAN F ACTORS ISSUE S FOR SPECIFIC RESEARCH TO DETERMINE IF A SAFETY PROBLEM ASSOCIATED WITH ADVANCED INSTRUMENTATION AND CONTROLS EXISTS IN THIS AREA A CURRENTLY FUNDED RESEARCH PROJECT, TECHNOLOGIES IN NUCLEAR PLANTS," NUREG/CR-5439.

CLOSE FIN 0852, REVIEW CRITERIA FOR HUMAN FACTORS ASPECTS OF OUT MEMO TO BE PREPARED.

AFFECTED DOCUMENTS PROBLEM

.................----_--..../. RESOLUTION AS OF FY93 QUARTER 4 O

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73 ISSUE NUMBER:

I.D.5(5)

TITLE: DISTURBANCE ANALYSIS SYSTEMS ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE

.DATE FINAL REPORT FROM CONTRACTOR OW RESULTS OF 06/89 06/90 i

SURVEY ON HUMAN FACTORS OF ADVANCED CONTROLS /

INSTRUMENTATION e

CLOSE 0U1 ISSUE 03/91 11/93 h

I h

h 1

5 5

a AS OF FY33 QUARTER 4 L

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RUN DATE: 10/20/93 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM PAGE 74 ISSUE NUMBER II.H.2 TITLE: OBTAIN DATA DN CONDITIONS INSIDE THI-2 CONTAINMENT IDENTIFICATION DATE 05/80C PRIORITIZATION DATE: II/83C TYPE. GSI PRIORITY-H TASK MANAGER:

A.

RUBIN OFFICE / DIVISION / BRANCH: RES /DSR /AEB ACTION LEVEL: ACTIVE STATUS.

TAC NUMBERS.

RESOLUTION DATE: _____

WORK AUTHORIZATION TMI ACTION PLAN. NUREG-0660 FIN CONTRACTOR CONTRACT TITLE A2220 ANL TMI-2 CORE EXAMINATION A6899 EG&G TMI-2 LOWER HEAD COMPANION SAMPLE EXAM & ANALYSIS D2072 MPR TEST SPECIMENS FROM DAMAGED THI-2 REACTOR BOTTOM HEAD W0RK SC0PE hRbhkhbbhPkkkhkDWkhbbkkhbkhbbhikhbhkkkkkbh hbhbF bbkkhkTkRkkLh hhk Pkhbkkkh Wkkk bEhkkklLh hkkRkED AND DATA-GATHERING PROGRAMS WITHIN THE THI-2 CONTAINMENT.

OUT WITH FUNDS FROM DOE AND OTHERS EARLY IN CY88. NRC THESE PROGRAMS CONCENTRATE ON RETRIEVING DATA WHICH INITIATED ITS OWN COOPERATIVE PROGRAM TO EXAMINE THE DAMAGED CHARACTERIZE THE PROGRESSION OF THE ACCIDENT AND THE BOTTOM HEAD.

PRESSURE VESSEL WALL SPECIMENS, INS T R UME N T RESULTING RADIOLOGICAL SOURCE TERM.

PRIOR TO CY88, NRC TUBE PENETRATIONS, GUIDE TUBE SPECIMENS, AND BOTTOM HEAD PRIMARILY PROVIDED TECHNICAL EXPERTISE AND HOT-CELL EXAMINA-ONCE MOLTEN DEBRIS SPECIMENS ARE TO BE REMOVED AND ANALYZED.

STATUS PRIOR EFFORTS CONCENTRATED ON THI-2 CORE EXAMINATION FIFTEEN PRESSURE VESSEL WALL SAMPLES, 14 I NS TR UME NT TUBE BOTH ONSITE AND OFFSITE.

PENETRATIONS, AND 2 GUIDE TUBE SPECIMENS WERE OBTAINED.

TWO CORE EXAMINATIONS INDICATE A LARGE FLOW OF MOLTEN NATIONAL LABORATORIES ARE BEING UTILIZED TO EXAMINE AND MATERIAL (MORE THAN IS TONS) INTO THE LOWER PLENUM AFTER THE ANALYZE THE SPECIMENS.

ACCIDENT HAD BEEN IN PROGRESS FOR ABOUT 225 MINUTES DOE IN APRIL 1991 THE MANAGEMENT BOARD OF THE JOINT CECD HAD NOT BUDGETED FOR THE ADDITIONAL RESEARCH TO EXAMINE THE TMT VESSEL INSPECTION PROGRAM VOTED TO EXTEND THE PROGRAM EFFECTS OF THIS MOLTEN MATERIAL ON THE VESSEL BOTTOM AND FOR A PERIOD OF 18 MONTHS BEYOND THE ORIGINAL PFJGR AM. THE VESSEL COMPONENTS.

THE CHAIRMAN INDICATED THAT HE BELIEVED EXTENDED PROGRAM INCLUDES DETAILED TESTING AND EXAMINATION THIS EXAMINATION TO BE VERY IMPORTANT~

NRC ASKED DOE TO OF ALL THE VESSEL. N0ZZLE, AND GUIDE TUBE SAMPLES EXTRACTED PERFORM THE EXAMINATION BUT DOE DECLINED.

FROM TMI-2 A SCOPING ANALYSIS OF POTENTIAL REACTOR NRC INITIATED A COOPERATIVE PROGRAM JANUARY IS. 1988.

VESSEL FAILURE MODES AND MARGIN TO FAILURE WILL BE EPRI AND 10 OECD-NEA COUNTRIES PARTICIPATED PERFORMED.

THE SAMPLING EFFORT WAS COMPLETED ON MARCH 1, 1990.

AS OF FY93 QUARIER 4 9

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AFFECTED DOCUMENTS PROBLEM

............................/. RESOLUTION NONE NONE.

ORIGINAL CURRENT ACTUAL MILEST0NES DATE DATE DATE REVISED CORE EXAMINATION PLAN (DOE 04/83 10/84 RESPONSIBILITY)

HEAD REMOVAL 07/83 07/84 PLENUM REMOVAL 07/85 05/85 BEGIN DEFUELING 10/85 12/85 REVISE CORE EXAMINATION PLAN 12/85 02/86-CORE' DRILLING 07/86 03/87 LOWER HEAD SAMPLE REMOVAL I2/88 03/90 COMPLETE DEFUELING.

06/87 05/90 SAMPLE EVALUATION AND ANALYSIS REPORT 06/90 10/93 SU M RY ANALYSIS I2/90 11/93

-~

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I AS OF FY93 QUARTER 4

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