ML20215K311
| ML20215K311 | |
| Person / Time | |
|---|---|
| Issue date: | 10/23/1986 |
| From: | Grimsley D NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Burton T CHICAGO TRIBUNE, CHICAGO, IL |
| References | |
| FOIA-86-669 NUDOCS 8610280107 | |
| Download: ML20215K311 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSt!N N c sotu.tou si Nuussms
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i ,e.ee. / INFORMATION ACT (FOIA) REQUEST OCT 2 31986 pChie %vate 5. ur a:t cao.e D. OMM 'M PART l.-RECORDS hELEASED OR NOT LOCATED (See enecaea conesi No agency tocords subrect to the request have been located.
No addetonal agency records subsect to the request have been located.
Agency records subrect to the request that are identifed in Appendas are stready avedabie for public inspecten and coowng a the NRC Public Document Room.
1717 H Street. N W Washington. OC. "
Agency records subrect to the request that are adentsfeed m Apoend's F- are bemg made avadable for public inspection and copyeg en the NRC Public Document Room.1717 H Street. N W., Washmgton. OC, m a folder under this FOIA number and requester name.
The nonpropnetary version of the proposaust that you agreed to accoot m a telephone conversation wth a member of my staff is now beeg made evadable for pubhc msoection and coymg at the NRC Pubbe Document Room.1717 H Street N W., Washmgton. OC. in a folder under this FOIA number and reauester name.
Enclosed e information on how you may obtaen access to and the charges for copymg records placed in the NRC Public Document Room,1717 H $treet. N W., Washmgtor* DC Agency roCords subfect to the request are enclosed. Any apphCabee Charge for Codes of the recoros provided and payment procedures are noted in tne comments section
<.co,ds sub-t ,o .. ,eo..s, e.e b n .e,.n.d .o ano.., Fede. agency..s, ,or .e..ew and d.re_ ,es.s. ,o you.
In v'ew of NRC's response to this reouset no further action a banng taken on appealletter dated PART ll.A-INFORMATION WITHHELD FROM PUBLIC DISCLOSURE Certain enformaten e the requested records is being wthheld from publec deciosure pursuant to the FOIA esemptions desenbed in and for the reasons stated in Part 11. sec-tions 8. C. and D. Any re4 eased comons of the documents for which only part of the record is bemg withheld are bemg made avadabie for pubhc inspection and cocvmg in the NRC Pubhc Document Room 1717 H Street. N.W., Washmgton. DC. in a folder under this FOIA number and requester name.
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Re: F01A-86-669 a
APPENDIX B DATE DOCUMENT DESCRIPTION
- l. 12/83 NUREG-0933, "A Prioritization of Generic Safety Issues" '
- (777 pages) - AN0 8401230657
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._ Re: F0IA-86-669 APPENDIX C DATE DOCUMENT DESCRIPTION
- 1. 08/01/86 Generic Issue Management Control System - Third Quarter FY-86 Update (270 pages)
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Re: F01A-86-669 APPENDIX C I
DATE DOCUMENT DESCRIPTION ~
j i 1. 08/01/86 Generic Issue Management Control System - Third Quarter J
FY-86 Update (270 pages) i i
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UNITED STATES NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C. 20555 s.,...+/
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AUG 01 1986 MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation
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FROM: Themis P. Speis, Director Division of Safety Review & Oversight
SUBJECT:
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM - THIRD QUARTER FY-86 UPDATE Enclosed is the Third Quarter FY-86 update of the Generic Issue Management Control System (GIMCS) for your information and use. This quarter's report
, contains the following highlights:
(1) Three issues were resolved: New Generic Issue Nos. 3 and 36 and TMI Action Plan Item No. III.D.3.1.
(2) Ten issues completed the prioritization process none of which were important enough to require GIMCS schedules.
(3) Thirty-two new issues were added to the list of issues to be
.. prioritized. The majority of these issues are the long term actions that resulted from the Davis-Besse event of June 9,1985.
(4) Seven issues are scheduled for resolution in the fourth quarter of FY-86.
(5) A number of issues have schedules "To be Determined - TBD." Sche-dules for all DSR0 managed issues will be included in the Fourth Quarter FY86 update.
Schedules for several USIs have been further considered and updated since the end of the 3rd quarter. New estimated current resolution dates are: (1) USI A-40: 12/87, (2) USI A-44: 8/87, (3) USI A-45:
2/89, (4) USI A-47: 12/87. The date for A-45 presented in Table 4A is the projected date of issuance for public comment.
No updates were provided for human factors issues since DHFT is currently reassessing the relationship between the Human Factors Program Plan items and other generic human factors issues.
_v uz ug I L uq /
' AUG 01 1986 Harold R. Denton This quarter's report contains data sheets for ten open TMI Action Plan items that were identified in NUREG-0933 for RES and NRR/0HFT action. These issues were determined to be Licensing issues and are listed separately in Table 9 of this report. DSR0 will be collecting information on the status of these items during the fourth quarter of FY-86 in order to complete the NRC report to Congress on the status of G TMI Action Plan items.
. /4 ce n 9 J' ,
t-tu du
/ Themis P. Speis, Director Division of Safety Review & Oversight
Enclosure:
Generic Issue Management
, Control System cc: See next page
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i GENERIC ISSUE MANAGEMENT CONTROL SYSTEM THIRD QUARTER J
, FY-86 UPDATE
- 0FFICE OF NUCLEAR REACTOR REGULATION i JULY 1986 i
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TABLE OF CONTENTS (a) Generic Issue Management Control System (1) Description (2) Abbreviations (b)) Table 1 -
Generic Safety Issues Scheduled for Resolution, New Generic Issues, and Issues Resolved g (c) Table 2 -
Number of Generic Safety Issues Resolved and
) Scheduled for Resolution, 3rd Quarter FY-86 (d) Table 3 -
Generic Safety Issues Resolved by Fiscal Year (e) Table 4 -
Generic Safety Issues Scheduled for Resolution j by Fiscal Year (f) Table 4A - NRR Generic Safety, Issues Scheduled for Resolution (g) Table 48 - NRR-TMI Generic Safety Issues Scheduled for Resolution (h) Table 4C - Non-NRR TMI and Generic Safety Issues Scheduled for Resolution j (i) Table 40 - Human Factors Program Plan Generic Safety Issues Scheduled for Resolution (j) Table 5 -
Number of Generic Issues Prioritized in FY-83, l FY-84, FY-85, and 3rd Quarter FY-86 (k) Table 6 -
Generic Issues Prioritized as of 3rd
_ Quarter FY-86 (1) Table 7 -
Generic Issues to be Prioritized (m) Table 8 -
Generic Issues to be Reprioritized (n) Table 9 -
TMI Licensing Issues (o) Work Scope & Schedules for each Approved Generic Issue l
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GENERIC ISSUE MANAGEMENT CONTROL SYSTEM DESCRIPTION The Generic Issue Management Control System (GIMCS) provides appropriate infor-mation necessary to manage safety-related and environmental generic issues through technical resolution and completion. For the purpose of this manage-ment control system, technically-resolved is defined as the i.Mnt where the staff's technical resolution has been issued. Generally speaking, this occurs when the technical resolution has been incorporated into one or more of the following documents:
(a) Commission Policy Statement / Orders (b) NRC Regulations (c) Standard Review Plan (SRP)
(d) Regulatory Guide (e) Generic Letter GIMCS is part of an integrated system of reports and procedures that would manage generic safety issues, TMI-related issues, and proposed new generic issues through the stages of prioritization,_ technical resolution, development of new criteria, review and aporoval, public comments, and incorporation into the SRP, as appropriate. NUREG-0933 provides an evaluation for a recommended priority listing based on the potential safety significance and cost of imple-mentation for each issue. NRR Office Letter No. 40 provides procedures and criteria for adding new generic issues to the system. GIMCS provides proposed scheduling for resolving and completing issues on the prioritized listing.
GIMCS will provide information to manage and control: (1) generic issues that are ranked HIGH priority; (2) MEDIUM priority generic issues; (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) issues designated by the NRR Director for resources for resolution. Issues ranked as either " LOW" or "0 ROP" are not allocated resources for resolution and, therefore, are not tracked in GIMCS.
l Some new generic issues prioritized and processed in accordance with NRR Office Letter No. 40 may not have resources allocated for resolution and completion.
These issues are listed in GINCS as inactive issues. Generally, these will be MEDIUM priority issues that have no safety deficiency demanding high priority attention, but have potential for safety improvements or reduction in uncertainty i of analysis that may be substantial and worthwhile. Efforts for the resolution l 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 will be inactive until such time as resources become available to resolve them.
l The detailed schedule for resolving generic issues will be monitored by GIMCS.
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Management and control indicators used in GIMCS are defined as follows:
- 1. Item No. - Generic Issue Number
- 2. Issue Type - Safety, Environmental or Regulatory Impact, HIGH, MEDIUM, or Nearly-Resolved (Note 1 or Note 2 from NUREG-0933)
- 3. Action Level - Degree of management attention needed to process generic issues in accordance with established schedules:
L1 - No management action necessary L2 - Division Director action necessary L3 - NRR Director action necessary L4 - EDO Director action necessary LS - Commission action necessary
- 4. Office /Div/Br - First-listed has lead responsibility for resolving issue; others listed have input to resolution.
- 5. Task Manager - Name of assigned individual responsible for resolution
- 7. Title - Generic Issue Title
- 8. Work Authorization - Who or what authorized work to be done on the issue.
- 9. Contract Title - Contract Title (if contract issued).
- 10. Contractor Name/ FIN - Contractor Name and FIN. (If contract is not yet issued, indicate whether the contract is included in the FIN plan.)
- 11. Work Scope - Describes briefly the work necessary to techni-cally resolve and complete the generic issue.
- 12. Affected Documents - Identifies documents into which the technical resolution will be incorporated.
- 13. Status - Describes current status of work.
- 14. Problem /Resolutior - Identifies problem areas and describes what actions are necessary to resolve them.
- 15. Technical Resolution - Identifies detailed schedule of milestone dates that are required for completing the issue through the issuance of SRP revisions or other changes that document requirements.
Milestones - Selected significant milestones. The " original" scheduled dates remains unchanged. Changes in scheduled dates are listed under " Current."
Actual completion dates are listed under " Actual."
-v-LEGEND H - HIGH priority M - MEDIUM priority D - DROP NR - Nearly Resolved L - LOW priority LI - Licensing Issue (Non-safety)
R - Resolved RI - Reaulatory Impact Issue S() - Subsumed in another Issue (issue #)
USI - Unresolved Safety Issue L1 - No manager.t.nt action necessary L2 - Divfsfon Director action necessary L3 - NRR Director action necessary L4 - EDO Director action necessary LS - Commission action necessary NRR-OP - Operating Plan TAP - Task Action Plan TBD - To Be Developed HFPP - Human Factors Program Plan-ACA - Awaiting Commission Approval for Further Action l
TABLE 1 Generic Safety Issues Scheduled For Resolution, New Generic
, Issues and Issues Resolved FY-83 FY-84 FY-85 ISSUE GIs New GIs GIs New GIs GIs New GIs TYPE Start + Issues - Resolved = End Start + Issues - Resolved = End Start + Issues - Resolved = End USI 16 0 2 14 14 0 2 12 12 0 0 12 HFPP 0 0 0. 0 0 0 0 0 0 34 0 34 HIGH 24 2 0 26 26 1 1 26 22* 7 6 23 MEDIUM 31 2 0 33 33 4 3 34 28* 1 10 19 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 Cumulative Totals FY-86 (3rd Qtr.) FY-82 through FY-86 (3rd Quarter)
ISSUE GIs New GIs ISSUE GIs New GIs TYPE Start + Issues - Resolved = End TYPE Start + Issues = Total - Resolved = Total USI 12 0 1 11 USI 16 0 16 5 11 HFPP 34 0 0 34 HFPP 0 34 34 0 34 HIGH 23 3 1 25 HIGH 20* 13 33 8 25 MEDIUM 19 1 0 20 MEDIUM 25* 8 33 13 20 NR 19 1 3 17 NR 20 20 40 23 17 TOTAL: 107 5 5 107 TOTAL: 81 75 156 50 107
- (See Table 2 Note)
T1-1 As of 3rd Quarter FY-86
TABLE 2 NUMBER OF GENERIC ISSUES RESOLVED AND SCHEDbtLD FOR 2250LUTION Third Quarter FY-86
? Resolved--46-Scheduled For Resolution d FY-86 Quarters FY-88 ISSUE & Cumulative PRIORITY FY-83 FY-84 FY-85 1st 2nd 3rd 4th Total FY-87 FY-89 TBD Total USI 2 2 0 1 0 0 1 2 5 3 0 14 HFPP 0 0 0 0 0 0 2 2 4 0 28 34 HIGH 0 1 6 0 0 1 2 3 4 7 14 35*
MEDIUM 0 3 10 0 0 0 2 2 5 7 4 31*
NR 4 9 7 1 0 2 0 3 5 2 5 35 RI O O O O O O O O 1 3 1 5 Total: 6 15 23 2 0 3 7 12 24 22 52 154 1
NOTE-The number of new generic issues approved this Quarter, approved in previous FY Quarters and approved in previous years is shown on Tables 1 and 5.
- 0ne medium generic issue, four high priority, and five medita priority TMI issues have been superseded by nine high priority subtask issues in HF-01 (refer to table 4B for TMI issues superseded and 40 for HF-01 subtask issues).
T2-1 As of 3rd Quarter FY-86
TABLE 3 GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Type of Date Approved Date Number Title Priority Resolution for Resolution Resolved FY-83 A-11 Reactor Vessel Materials USI ' GL 82-26 01/79 10/82 Toughness >
A-16 Steam Effects on BWR Core Spray NR 'HPA-D12 NRR-OP FY83 03/29/83 Distribution A-39 Determination of Safety USI SRP Revision 01/79 10/82 Relief Valve (SRV) Pool Dynamic Loads and Temperature Limits for BWR Containment B-53 Load Break Switch NR SRP Revision NRR-0P FY83 07/28/83 II.E.5.1 (B&W) Design Evaluation NR No NRR-0P FY83 03/21/83 Requirement IV.C.1 Extend Lessons Learned From NR No NRR-OP FY83 04/15/83
- TMI to Other NRC Programs Requirement FY-84 l
12 BWR Jet Pump Integrity Medium No NRR-OP FY83 09/25/84 l Requirement l
20 Effects of Electromagnetic NR NUREG/ NRR-0P FY83 11/15/83 Pulse on Nuclear Plant Systems CR-3069 40 Safety Concerns Associated NR MPA-865 07/18/83 12/27/83 With Breaks in the BWR Scram System T3-1 As of 3rd Quarter FY-86
Table 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Type of Date Approved Date
,I Number Title Priority Resolution for Resolution Resolved FY-84 (cont'd) 45 Inoperability of Instruments NR SRP Revision 09/08/83 03/23/84 Due to Extreme Cold Weather.
50 Reactor Vessel Level NR MPA-F26 07/28/83 09/06/84 instrumentation in BWRs 69 Make-Up Nozzle Cracking in NR MPA- 12/06/83 09/27/84 B&W Plants A-1 Water Hammer USI SRP Revision 01/79 03/15/84 A-12 Steam Generator and Reactor USI SRP Revision 01/79 10/83 Coolant Pump Supports B-10 Behavior of BWR Mark III High SRP Revision NRR-OP FY83 09/10/84 1 Containments B-26 Structural Integrity of Medium No NRR-OP FY83 09/27/84 Containment Penetrations Requirement B-60 Loose Parts Monitoring NR GL NRR-OP FY83 09/25/84 Systems (LPMS)
I.A.I.4 Long-Tern Upgrading of NR New Rule NRR-OP FY83 01/01/84 Operating Personnel II.A.1 Siting Policy Reformulation Medium No NRR-OP FY83 09/20/84 Requirement II.E.5.2 (B&W) Reactor Transient NR NUREG-0667 NRR-OP FY83 09/28/84 Response Task Force III.D.2.5 Offsite Dose Calculation Manual NR NUREG/ NRR-OP FY83 01/17/84 CR-3332 T3-2 As of 3rd Quarter FY-86
Table 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Type of Date Approved Date Number Title Priority Resolution for Resolution Resolved FY-85 22 Inadvertent Boron Dilution NR GL 85-05 11/05/82 10/15/84 Events A-41 Long Term Seismic Program Medium No NRR-OP FY83 10/10/84 Requirement B-19 Thermal-Hydraulic Stability NR GL 01/03/85 05/21/85 B-54 Ice Condenser Containments Medium NUREG/ NRR-0P FY83 10/22/84 CR-4001 B-58 Passive Mechanical Failures Medium .No NRR-0P FY83 07/09/85 Requirement C-11 Assessment of Failure and Medium No NRR-0P FY83 07/09/85 Reliability of Pumps and Requirement Valves I.A.2.2 Training and Qualifications High Policy NRR-OP FY83 06/24/85 of Operating Personnel Statement No Requirement I.A.2.6(4) Operator Workshops Medium No NRR-OP FY83 09/25/85 Requirement I.A.2.7 Accreditation of Training Medium Policy NRR-OP FY83 06/24/85 Institutions Statement No Requirement l
j T3-3 As of 3rd Quarter FY-86
Table 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR ,
Issue Type of Date Approved Date Number Title Priority Resolution for Resolution Resolved FY-85 (cont'd) !
t I.A.3.4 Licensing of Additional Medium Policy NRR-OP FY83 02/12/85 Operations Personnel Statement No Requirement I.G.2 Scope of Test Program Medium No NRR-OP FY83 10/05/84 Requirement II.B.6 Risk Reduction For Operating High No NRR-OP FY83 09/25/85 Reactors at Sites With High Requirement Population Densities II.B.8 Rulemaking Proceedings on - - - -
i Degraded Core Accidents
- (a) Hydrogen Rule High Rule NRR-0P FY83 07/19/85 (b) Severe Accidents High Policy NRR-0P FY83 08/12/85 Statement II.C.1 Interim Reliability Evaluation High No NRR-OP FY83 07/09/85 Program Requirement II.C.2 Continuation of Intrim High No NRR-OP FY83 09/25/85 Reliability Evaluation Program Requirement II.E.2.2 Research on Small Break LOCAs Medium No NRR-OP FY83 D7/25/85 and Anomalous Transients Requirement III.A.1.3(2) Maintain Supplies of HR Policy NRR-OP FY83 08/15/85 Thyroid-81ocking Agent Statement
- For Public III.A.3.4 Nuclear Data Link Medium No NRR-0P FY83 06/26/85 Requirement T3-4 As of 3rd Quarter FY-86
Table 3 (Continued) .
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue Type of Date Approved Date Number Title Priority Resolution for Resolution Resolved
.FY-85 (cont'd)
III.D.2.3(1) Develop Procedures to NR ESRP NRR-0P FY83 08/28/85 Discriminate 8etween Sites / Revision Plants III.D.2.3(2) Discriminate 8etween Sites NR ESRP NRR-0P FY83 08/28/85 and Plants that Require Revision Consideration of Liquid Pathway Interdiction Techniques III.D.2.3(3) Establish Feasible Method of NR ESRP NRR-OP FY83 08/28/85 Pathway Interdiction Revision III.D.2.3(4) Prepare a Summary Assessment NR ESRP NRR-OP FY83 08/28/85 Revision IV.E.5 Assess Currently Operating High No NRR-0P FY83 09/25/85 Plants Requirement FY-86 3 Setpoint Drift in NR Reg Guide NRR-OP 05/19/86 Instrumentation Rev. No Req.
14 PWR Pipe Cracks NR No NRR-OP FY83 10/04/85 Requirements 36 Loss of Service Water SRP Revision NR 02/15/84 05/13/86 No Req.
A-43 Containment Emergency USI SRP 01/79 10/85 Sump Performance Revision III.D.3.1 Radiation Protection Plan High No NRR-OP 05/19/86 Requirement T3-5 As of 3rd Quarter FY-86
l Table 4 Generic Safety Issues Scheduled For Resolution by Fiscal Year 4th Qtr. FY-86 (7) 61 A-3,4,5 I.A.4.2(1) 121 B-55 HFPP-4.4 HFPP-4.2 FY-87s(24) 29 86 A-17 I.B.1.1(6) HFPP-3.1 75 93 A-45 I.B.1.1(7) HFPP-3.2 79 101 A-46 II.B.5(3) HFPP-3.3 82 103 A-48 II.E.4.3 HFPP-6.3 83 119.2 A-49 II.J.4.1 FY-88 and FY-89 (22) 51 A-29 I.D.3 70 A-40 I.D.5(3) 99 A-44 II.B.5(1) 105 A-47 II.B.5(2) 119.1 B-5 II.C.4 119.4 B-56 II.E.6.1 119.5 B-61 II.H.2 B-64 To Be Determined (52) 23 119.3 HFPP-1.1 HFPP-4.1 48 122.la HFPP-1.2 HFPP-4.3 49 122.lb HPFF-1.3 HFPP-4.5 65 122.lc HFPP-1.4 HFPP-5.1 66 122.2 HFPP-2.1 HFPP-5.2 67.7 124 HFPP-2.2 HFPP-5.3 68 A-30 HFPP-2.3 HFPP-5.4 77 B-6 HFPP-3.4 HFPP-6.1 84 C-8 HFPP-3.5 HFPP-6.2 .
87 I.A.3.3 91 I . F.1 94 II.F.5 MSPP-I.1 MSPP-I.4 MSPP-I.7 MSPP-Phase II MSPP-I.2 MSPP-I.5 MSPP-I.8 MSPP-I.3 MSPP-I.6 MSPP-I.9 T4-1 As of 3rd Quarter FY-86
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Table 4A NRR GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION I
Lead Date Resolution Current Issue Division / Approved for Date as of Resolution Number Title Branch Priority Resolution June FY-85 Date 23 Reactor Coolant Pump Seal Failures DSR0/EIB H NRR-0P 07/86 TBD 29 Bolting Degradation or Failures in DSR0/EIB H NRR-0P 05/86 01/87 Nuclear Power Plants 48 LCO for Class IE Vital Instrument DSR0/EIB NR 10/25/83 02/87 TBD Buses in Operating Reactors 49 Interlocks and LCOs for Class IE DSR0/EIB M 07/31/84 09/88 TBD Tie Breakers a
3 51 Proposed Requirements for Improving DSR0/EIB M 06/03/83 05/88 08/88 Reliability of Open Cycle Service Water Systems i
- 61 SRV Discharge Line Break Inside The DSR0/RSIB M 11/30/83 03/87 07/86 Wetwell Airspace of BWR Mark I &
Mark II Containments 65 Component Cooling Water System DSR0/EIB H 07/28/83 07/86 TBD
! Failure l 66 Steam Generator Requirements ORAS/BWR NR 11/16/83 11/85 TBD 67.7 Steam Generator Staff Actions- DSR0/EIB M TBD TBD TBD Eddy Current Tests 68 Loss of AFWS Due to AFW Steam HELB DSR0/RSIB H 04/24/84 10/87 TBD l
l T4-2 As of 3rd Quarter FY-86
Table 4A (continued)
NRR GENERIC SAFETY ISSDES SCHEDULED FOR RESOLUTION Lead Date Resolution Current Issue Division / Approved for Date as of Resolution Number Title Branch Priority Resolution June FY-85 Date 70 PORV and Block Valve Reliability DSR0/EIB M 05/14/84 02/87 11/87 77 Flooding of Safety Equipment DSR0/EIB H 09/08/83 08/86 TBD Compartments by Back-flow Through Floor Drains 79 Unanalyzed Reactor Vessel Thermal DSR0/EIB M 07/2$/83 09/86 10/86 Stress During Natural Convection Cooldown 82 Beyond Design Bases Accidents in DSR0/RSIB M 12/07/83 09/87 08/87 Spent Fuel Pools 83 Control Room Habitability DPL-A/PSB NR 08/83 TBD 05/87 84 CE PORVs DSR0/RSIB NR 02/27/85 TBD TBD 86 Long Range Plan for Dealing With DBL /EB NR 10/01/84 04/86 01/87 Stress Corrosion Cracking in BWR Piping 87 Failure of HPCI Steam Line Without DSR0/RSIB H 09/26/85 TBD TBD Isolation
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91 Main Crankshaft Failure In ORAS/BWR NR 07/08/85 None TBD Transamerica DeLaval 93 Steam Binding of Auxiliary DSR0/RSIB H 10/19/84 06/87 09/87 Feedwater Pumps 94 Additional Low-Temperature DSR0/RSIB H 07/23/85 None TBD Overpressure Protection for Light Water Reactors 99 RCS/RHR Suction Line Interlocks DSR0/RSIB H 08/13/85 None 10/87 on PWRs T4-3 As of 3rd Quarter FY-86
Table 4A (continued)
NRR GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION Lead Date Resolution Current Issue Division / Approved for Date as of Resolution Number Title Branch Priority Resolution June FY-85 Date 101 BWR Water Level Redundancy DSR0/RSIB H 05/06/85 09/86 09/87 103 Design For Probable Maximum DSR0/EIB NR 09/04/85 TBD 04/87 Precipitation 105 Interfacing System LOCA at BWRs DSR0/RSIB H 06/11/85 TBD 04/88 122.la Common Mode Failure of Isolation DSR0/RSIB H 01/86 --
TBD Valves in Closed Position i
122.lb Recovery of Auxiliary Feedwater DSR0/RSIB M 01/86 -- TBD 122.lc Interruption of Auxiliary DSR0/RSIB H 01/86 --
TBD Feedwater Flow 122.2 Initiating Feed-and-Bleed DHFT/HFIB H 01/86 --
TBD 124 Auxiliary Feedwater System DSR0/RSIB NR 02/86 --
TBD A-3,4,5 Steam Generator Tube Integrity ORAS/BWR USI 01/79 12/85 07/86 A-17 Systems Interaction DSR0/EIB USI 01/79 08/86 12/86 A-29 Nuclear Power Plant Design for the DSR0/RSIB M NRR-0P 05/87 09/88 Reduction of Vulnerability to Industrial Sabotage A-30 Adequacy of Safety Related DC Power DSR0/EIB H NRR-OP 01/86 TBD Supplies A-40 Seismic Design Criteria DSR0/EIB USI 01/79 06/86 10/87 A-44 Station Blackout DSR0/RSIB USI 01/79 04/86 07/88 T4-4 ,
As of 3rd Quarter FY-86
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I Table 4A (continued)
NRR GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION Lead Date Resolution Current Issue Division / Approved for Date as of Resolution Number Title Branch Priority Resolution June FY-85 Date A-45 Shutdown Decay Heat Removal DSR0/RSIB. USI 02/81 03/87 03/87 Requirements A-46 Seismic Qualification of Equipment DSR0/EIB USI 02/81 12/85 10/86 in Operating Plants A-47 Safety Implications of Control DSR0/EIB USI 02/81 12/86 11/87 Systems A-48 Hydrogen Control Measures and DSR0/EIB USI 02/81 10/86
' 09/87 Effects of Hydrogen Burns on Safety Equipment A-49 Pressurized Thermal Shock DSR0/RSIB USI 12/81 11/85 12/86 B-5 Ductility of Two Way Slabs and DSR0/EIB M NRR-0P 09/87 06/88
, Shells and Buckling Behavior of j Steel Containments i
) B-6 Loads, Load Combinations, Stress DSR0/EIB H NRR-0P 09/87 TBD l Limits B-17 Criteria for Safety-Related DHFT/HFIB M 03/22/82 Being resolved -
Operator Actions by HF-01, Issue HFPP-4.3.
I B-55 Improve Reliability of Target Rock DSR0/EIB M NRR-OP 12/85 07/86 Safety Relief Valves l B-56 Diesel Re. liability DSRO/RSIB H NRR-0P 05/86 11/87 B-61 Allowable ECCS Equipment Outage DSR0/RRAB M NRR-0P 09/87 10/88
- Periods l
i B-64 Decommissioning of Nuclear Reactors DBL /PSB NR NRR-OP 06/87 10/87
- C-8 Main Steam Line Isolation Valve DSR0/RSIB H NRR-OP 12/86 TBD Leakage Control Systems T4-5 ,
As of 3rd Quarter FY-86
Table 4B NRR THI GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION Lead Date Resolution Current Issue Division / Approved for Date as of Resolution Number Title Branch Priority Resolution June FY-85 Date I.A.2.6 Long-Term Upgrading of Training DHFT/HFIB H Being resolved - -
(1) and Qualifications - Revise by HF-01, Issue Regulatory Guide 1.8 HFPP-1.2 1.A.4.2 Research on Training Simulators DHFT/HFIB H NRR-0P 08/85 09/86 (1)
I.A.4.2 Review Simulators for Conformance DHFT/HFIB H Being resolved - -
(4) by HF-01, Issue HFPP-3.3 I.B.1.1 Organization and Management of - - - - -
Long Term Improvements I . B .1.1 Prepare Draft Criteria DHFT/HFIB M Being resolved - -
(1) by HF-01, ,
Issues HFPP-6.1 and 6.3 I.B.1.1 Prepare Commission Paper DHFT/HFIB M Being resolved - -
(2) by HF-01, Issues HFPP-6.1 and 6.3 I.B.1.1 Issue Requirements for the DHFT/HFIB M Being resolved - -
(3) Upgrading Management and by HF-01, Technical Resources Issues HFPP-6.1 and 6.3 I.B.1.1 Review Responses to Determine DHFT/HFIB M Being resolved - -
(4) Acceptability by HF-01, Issues HFPP-6.1 and 6.3 I.C.9 Long-Term Program Plan for Upgrad- DHFT/HFIB M Being resolved - -
ing of Procedures by HF-01, Issues HFPP-4.2 and 4.4 and HF-02 T4-6 As of 3rd Quarter FY-86
Table 48 (continued)
NRR TMI GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION Lead Date Resolution Current Issue Division / Approved for Date as of Resolution Number Title Branch Priority Resolution June FY-85 Date I.D.4 Control Room Design Standard DHFT/HFIB H Being resolved - -
by HF-01, issue HFPP-5.3 I.D.5(5) Disturbance Analysis Systems DHFT/HFIB H Being resolved - -
by HF-01, issue HFPP-3.4.1 II.E.4.3 (Containment) Integrity Check DSR0/RSIB H NRR-0P 04/87 07/87 II.E.6.1 Test Adequacy Study DSR0/EIB M NRR-0P 05/88 05/88 II.F.5 Classification of Instrumenta- DSR0/EIB M NRR-OP 01/86 TBD tion, Control, and Electrical Equipment l
1 1
l l T4-7 As of 3rd Quarter FY-86
Table 4C NON-NRR TMI AND GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION Lead Date Resolution Current Issue Division / Approved for Date as of Resolution Number Title Branch Priority Resolution June FY-85 Date i
! 75 Generic Implications of ATWS IE/QAVT/QAB NR 10/19/83 02/86 07/87 Events at the Salem Nuclear Plant 119.1 Piping Rupture Requirements RES/MSEB RI 09/10/85 --
01/88 and Decoupling of Seismic and LOCA Loads .
119.2 Pipe Damping Values RES/MSEB RI 09/10/85 --
11/86
T80 i
1 119.4 BWR Piping Materials RES/MEBR RI 09/10/85 --
10/87 119.5 Leak Detection Requirements RES/MEBR RI 09/10/85 --
11/87 121 Hydrogen Control for Large, RES/ ORA 0/RAMRB H 09/26/85 TBD 09/86 i Dry Containment I.A.3.3 Requirement for Operation RES/DRA0/HFSB H NRR-OP 09/85 TBD Fitness I.B.1.1 Prepare Revisions to Regulatory IE/QAVT/QAB M NRR-OP 02/86 07/87 (6) Guides 1.33 and 1.8 I.B.I.1 Issue Regulatory Guides 1.33 and IE/QAVT/QAB M NRR-0P 02/86 07/87 (7) 1. 8 I.D.3 Safety System Status Monitoring RES/DET/EEICB M NRR-0P 12/87 02/89 T4-8 As of 3rd Quarter FY-86
Table 4C (continued)
NON-NRR TMI AND GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION Lead Date Resolution Current Issue Division / Approved for Date as of Resolution Number Title Branch Priority Resolution June FY-85 Date I.D.5 On-Line Reactor Surveillance RES/DET/EEICB NR NRR-0P 09/88 09/88 (3) Systems I.F.1 Expand QA List IE/QAVT/QAB H NRR-0P 08/85 ACA II.B.5 Behavior of Severely Damaged RES/DAE/FSRB H NRR-0P 12/87 06/88 (1) Fuel II.B.5 Behavior of Core Melt RES/DAE/FSRB H NRR-0P 12/87 06/88 (2)
II.B.5 Effect of Hydrogen Burning and RES/DAE/CSRB M NRR-OP 07/87 07/87 (3) Explosions on Containment Structure II.C.4 Reliability Engineering RES/DRA0/RRB H NRR-OP 12/87 12/87 II.H.2 Obtain Technical Data on the RES/DAE/FSRB H NRR-0P 12/86 12/88 Conditions Inside the THI-2 Containment Structure l
II.J.4.1 Revise Deficiency Report IE/DEPER/EAB NR NRR-0P 07/86 02/87 Requirements I
T4-9 As of 3rd Quarter FY-86 i
Table 40 HUMAN FACTORS GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION 1
i Lead Date Resolution Current I Issue Division / Approved for Date as of Resolution Number Title Branch Priority Resolution June FY-85 Date HF-01 HUMAN FACTORS PROGRAM PLAN (HFPP) 1 HFPP Subtask Numbers 1
1.1 Policy Statement on Engineering DHFT/HFIB e H 10/01/84 TBD TBD Expertise on Shift and Evaluate Effectiveness of Policy Statement 1.2 Revise and Evaluate Changes to DHFT/HFIB H 10/01/84 08/85 TBD Regulatory Guide 1.8 1.3 Develop a Means to Evaluate DHFT/HFIB H 10/01/84 TBD TBD
, Acceptability of NPP Personnel l Qualifications Program t
i 1.4 Review and Evaluate Industry DHFT/HFIB H 10/01/84 TBD TBD
! Programs 1
I 2.1 Evaluate Industry Training DHFT/HFIB H 10/01/84 TBD TBD
! 2.2 Evaluate INPO Accreditation DHFT/HFIB H 10/01/84 TBD TBD Program 2.3 Revise Standard Review Plan DHFT/HFIB H 10/01/84 TBD TBD Section 13.2.3 3.1 Develop Job Knowledge Catalogue DHFT/HFIB H 10/01/84 TBD 10/86
- 3.2 Develop Licensing Examinations DHFT/HFIB H 10/01/84 TBD 10/86 Handbook 3.3 Develop Criteria for NPP DHFT/HFIB H 10/01/84 02/87 03/87 Simulators T4-10 As of 3rd Quarter FY-86
ll Table 40 (Continued)
HUMAN FACTORS GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION Lead Date Resolution Current Issue Division / Approved for Date as of Resolution Number Title Branch Priority Resolution June FY-85 Date IINP Subtask Numbers (Continued) i 3.4 Training Requirements Package DHFT/HFIB H 10/01/84 TBD TBD (Revise 10 CFR 55 and RGs 1.149 i and 1.8) 3.5 Develop Computerized Exam System DHFT/HFIB H 10/01/84 TBD TBD i
4.1 Inspection Module for upgrading DHFT/HFIB H 10/01/84 TBD TBD procedures 4.2 E0P Effectiveness Evaluation DHFT/HFIB H 10/01/84 02/86 09/86 4.3 Criteria for Safety-Related DHFT/HFIB H 10/01/84 TBD TBD Operator Actions (GI #B-17) 4.4 Guidelines For Upgrading Other DHFT/HFIB H 10/01/84 12/85 09/86 Procedures j 4.5 Applications of Artificial DHFT/HFIB H 10/01/84 TBD TBD l Intelligence i 5.1 Local Control Stations DHFT/HFIB H 10/01/84 TBD TBD
- 5.2 Annunciators DHFT/HFIB H. 10/01/84 TBD TBD 5.3 Evaluate Operational Aid Systems DHFT/HFIB H 10/01/84 TBD TBD 5.4 Computers and Computers Displays DHFT/HFIB H 10/01/84 TBD TBD 6.1 Development of Regulatory Position DHFT/HFIB H 10/01/84 04/86 TBD on Management and Organization 6.2 Evaluate Criteria For SALP Reviews DHFT/HFIB H 10/01/84 TBD TBD l
T4-11 As of 3rd Quarter FY-86
Table 4D (Continued)
HUMAN FACTORS GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION Lead Date Resolution Current Issue Division / Approved for Date as of Resolution Number Title Branch Priority Resolution June FY-85 Date HFPP Subtask Numbers (Continued) 6.3 Revise Standard Review Plan DHFT/HFIB H 10/01/84 11/86 11/86 Section 13.1 HF-02 MAINTENANCE AND SURVEILLANCE PRDGRAM PLAN (MSPP)
MSPP Subtask Numbers (Phase I)
I.1 Survey Current Maintenance DHFT/MTB H 03/06/85 TBD TBD Practices I.2 Maintenance Performance Indicators DHFT/MTB I.3 Monitor Industry Activities DHFT/MTB H 03/06/85 TBD TBD I.4 Participate In Standards Groups DHFT/MTB H 03/06/85 TBD TBD I.5 Maintenance and Surveillance DHFT/MTB H 03/06/85 TBD TBD Program Integration I.6 Analysis of Japanese /U.S. NPP DHFT/MTB H 03/06/85 TBD TBD Maintenance Programs I.7 Maintenance Personnel DHFT/MTB H 03/06/85 TBD TBD Qualifications I.8 Human Factors In In-Service DHFT/MTB H 03/06/85 TBD TBD Inspections I.9 Human Error in Events Involving DHFT/MTB H 03/06/85 TBD TBD Wrong Unit Wrong Train (GI #101)
MSPP Subtask Numbers (Phase II)
II.0 Phase II Tasks To Be Determined DHFT/MTB H 03/06/85 TBD TBD After Resolution of Phase I T4-12 As of 3rd Quarter FY-86
TABLE 5 NUMBER OF GENERIC TSSUES PRIORITIZE0 IN FY-83, FY-84, FY-85, and FY-86 (1st, 2nd and 3rd Qtrs.)
FY-86 Quarters Cumulative Issue Type FY-83 FY-84 FY-85 1st 2nd 3rd 4th ' Total Total Issues Identified 56 19 54 6 6 32 -
44 173 To Be Prioritized Issues Identified 19 2 0 0 0 0 -
0 21 To Be Reprioritized i Total: 75 21 54 6 6 32 -
44 194 New Issues (Entered into GIMCS)
High 2 1 7 0 3 0 -
3 13 Medium 2 4 1 0 1 0 -
1 8 Nearly Resolved 3 5 6 0 1 0 -
1 15 Human Factor 0 0 34 0 0 0 -
0 34 Issues Subtotal: 7 10 48 0 5 0 -
5 70 Resolved 4 , 0 1 2 0 0 -
2 7 Low 1 4 0 0 1 0 e
1 6 Orop 1 4 4 1 0 3 -
4 13 Regulatory Impact /LI O O 3 5 0 3 -
8 11 Subsumed 8 2 3 0 0 4 -
4 17 Total Issues 21 20 59 8 6 10 -
24 124 Prioritized -
Remaining Issues 54 1 -5 -2 0 22 -
20 70 To Be Prioritized or Reprioritized
- TS-1 As of 3rd Quarter FY-86
TABLE 6 GENERIC ISSUES PRIORITIZED AS OF THIRD QUARTER FY-86 Action Item / Identification Date Current Issue No. Title Date Prioritized Priority FY-83
- 31. Natural Circulation Cooldown 09/82 07/83 S(I.C.1)
- 32. Flow Blockage in Essential Equipment Caused 09/82 05/83 S(51) by Corbicula
- 33. Correcting Atmospheric Dump Valve Opening Upon 09/82 08/82 S(A-47)
Loss of Integrated Control System Power
- 39. Potential for Unacceptable Interaction Between 09/82 07/82 S(25) the CRD System and Non-Essential Control Air s System
- 40. Safety Concerns Associated with Pipe Breaks in 09/82 07/83 NR the 8WR Scram System
- 41. BWR Scram Discharge Volume Systems 09/82 07/83 R
- 42. Combination Primary / Secondary System LOCA 09/82 04/83 S(18)
- 45. Inoperability of Instrumentation Due to Extreme 09/82 09/83 NR Cold Weather
- 46. Loss of 125 Volt DC Bus 09/82 02/83 S(76)
- 47. Loss of Off-Site Power 09/82 04/83 R
- 50. Reactor Vessel Level Instrumentation in BWRs 09/82 07/83 NR
- 51. Proposed Requirements for Improving the Reliability of Open Cycle Service Water Systems 09/82 06/83 MEDIUM
- 52. SSW Flow Blockage by Blue Mussels 09/82 05/83 S(51)
- 56. Abnormal Transient Operating Guidelines as 09/82 02/83 S(A-45/I.D.1)
Applied to a Steam Generator Overfill Event
- 58. Inadvertent Containment Flooding 09/82 08/83 DROP
- 64. Identification of Protection System Instrument 10/82 02/83 R Sensing Lines
- 65. Probability of Core-Melt Due to Component Cool- 02/83 07/83 HIGH ing Water System Failures l
- 77. Flooding of Safety Equipment Compartments by 06/83 09/83 HIGH l Back-Flow Through Floor Drains l 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 R T6-1 As of 3rd Quarter FY-86
l TABLE 6 (CONT.)
~
GENERIC ISSUES PRIORITIZED AS OF THIRD QUARTER FY-86 l
Action Item / Identification Date Current Issue No. Title Date Prioritized Priority FY-84
- 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 j 49. Interlocks and LOCs for Redundant Class IE 09/82 07/84 MEDIUM Tie Breakers
- 53. Consequences of a Postulated Blow Blockage in 09/82 09/84 DROP Incident in a BWR
- 60. Lamellar Tearing of Reactor Systems Structural 10/82 11/83 S(A-12)
Supports
- 66. Steam Generator Requirements 06/83 11/83 NR
- 68. Postulated Loss of Aux'liary Feedwater System 06/83 04/84 HIGH-Resulting from Turbine-Driven Auxiilary Feedwater Pump Steam Supply Line Rupture
- 69. Make-up Nozzle Cracking in B&W Plants 06/83 12/83 NR
- 70. PORV and Block Valve Reliability 06/83 05/84 MEDIUM
- 75. Generic Implications of ATWS Events at the Sales 06/83 10/83 NR
, Nuclear Plants
! 80. Pipe Break Effects on Control Rod Drive Hydrau- 06/83 01/84 LOW
! lic Lines in the Drywells of BWR Mark I and II
- 82. Beyond Design Basis Accidents in Spent Fuel 08/83 12/83 MEDIUM i Pools
! 90. Technical Specifications for Anticipatory Trips 02/84 08/84 LOW
! 92. Fuel Crumbling During LOCA 04/83 07/84 LOW
! B-65 Iodine Spiking 09/82 06/84 DROP i
- T6-2 As of 3rd Quarter FY-86
TABLE 6 (CONT.)
GENERIC ISSUES PRIORITIZED AS OF THIRD QUARTER FY-86 Action Item / Identi fication Date Current Issue No. Title Date Prioritized Priority FY-85
- 37. Steam Generator Overfill and Combined Primary 09/82 05/85 S(USI-A47) and Secondary Blowdown j 54. Valve Operator-Related Events Occurring 09/82 06/85 S(II.E.6.1)
During 1978, 1979, and 1980
- 59. Technical Specification Requirements for Plant 10/82 02/85 RI[S(TSIP)]
Shutdown
- 67. Steam Generator Staff Actions 06/83 03/85 MEDIUM
- 81. Potential Safety Problems Associated With Locked 11/83 10/84 DROP Doors and Barriers in Nuclear Power Plants
- 83. Control Room Habitability 11/83 NR
- 85. Reliability of Vacuum Breakers Connected 11/83 07/85 DROP to Steam Discharge Lines Inside BWR Containments
- 86. NRC Pipe Cracking Review Group Study 12/83 10/84 NR
- 87. Failure of HPCI Steam Line Without Isolation 01/84 09/85 HIGH
- 91. Transamerica Delaval Emergency Diesel 03/84 07/85 NR Generator Main Crankshaft Failure
- 93. Steam Binding of Auxiliary Feedwater Pumps 07/84 10/84 HIGH
- 94. Additional Low-Temperature-Overpressure 08/84 07/85 HIGH Protection For Light Water Reactors
- 98. CRD Accumulator Check Valve Leakage 09/84 02/85 DROP
- 99. RCS/RHR Suction Line Interlocks on PWRs 09/84 08/85 HIGH 101. BWR Water Level Redundancy 09/84 05/85 HIGH 102. Human Error in Events Involving Wrong Unit or 09/84 02/85 S(HF-02)
Wrong Train 103. Design For Probable Maximum Precipitation 10/84 09/85 NR 105. Interfacing System LOCA at BWRs 10/84 06/85 HIGH 108. BWR Suppression Pool Temperature Limits 12/84 02/85 RI(LOW) 119. Piping Review Committee Recommendations 07/85 09/85 RI(NR) 121. Hydrogen Control For Large Dry Containments 08/85 09/85 HIGH T6-3 As of 3rd Quarter FY-86
, TABLE 6 (CONT.)
i GENERIC ISSUES PRIORITIZED AS OF THIRD QUARTER FY-86 I
Action Item / Identification Date Current
{ Issue No. Title Date Prioritized Priority l FY-85(cont'd)
B-19 Thermal-Hydraulic Stability 02/83 0.1/85 NR B-50 Post Operating Basis Earthquake Inspection 02/83 04/85 RI (LOW)
B-59 N-1 Loop Operation in 8WRs and PWRs 02/83 06/85 R HF-01 Human factor Program Plan (HFPP twenty four 08/83 10/84 HIGH subtask elements) i HF-02 Maintenance and Surveillance Program Plan 04/84 03/85 HIGH
] (MSPP ten subtasks elements) i
.i FY-86 i
- 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 Exposure 09/84 10/85 R
, 111. Stress Corrosion Cracking of Presure Boundary 01/85 11/85 LI Ferritic Steels in Selected Environments i 112. Westinghouse RPS Surveillance Frequencies and 01/85 10/85 RI(R) i Out-of-Service Times -
l 114 Seismic-Induced Relay Chatter 03/85 06/86 S(USI-A46) i 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 Fcedwater System Reliability 12/85 02/86 NR 125.I.2.a PORV Reliability - Test Program 11/85 06/86 S(70) 125.I.2.b - PORV Reliability - Surveillance 11/85 06/86 S(70)
I 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(USI-A45)
Environment
- C-4 Statistical Methods for ECCS Analysis 02/83 06/86 RI(R)
C-5 Decay Heat Update 02/83 06/86 RI(R)
I C-6 LOCA Heat Sources ,
02/83 06/86 RI(R)
T6-4 As of 3rd Quarter FY-86
TABLE 7 GENERIC ISSUES TO BE PRIORITIZED Action Item / Identification Current Issue No. Title Date Schedule
- 38. Potential Recirculation System Failure as a Consequence of 09/82 11/86 Injection of Containment Paint Flakes or Other Fine Debris
- 57. Effects of Fire Protection System Actuation on Safety-Related 09/82 10/86 Equipment
- 62. Reactor Systems Bolting Applications 10/82 11/86
- 71. Failure of Resin Demineralizer Systems and Their Effects on 06/83 07/86 Nuclear Power Plant Safety
- 72. Control Rod Drive Guide Tube Support Pin Failures 06/83 01/87
- 73. Detached Thermal Sleeves 06/83 10/86
- 76. Instrumentation and Control Power Interactions 06/83 08/86
- 78. Monitoring of Fatigue Transient Limits for Reactor Coolant 06/83 10/86 System
- 88. Earthquake and Emergency Planning 01/84 09/86
- 89. Stiff Pipe Clamps 02/84 09/86
- 95. Loss of Ef fective Volume For Containment Recirculation 08/84 07/86 Spray
- 96. RHR Suction Valve Testing 04/84 04/86 100. OTSG Level 09/84 07/86 104. Reduction of Boron Dilution Requirements 10/84 03/87 106. Piping and Use of Highly Combustible Gases in Vital Areas 10/84 09/86 107. Generic Implications of Main Transformer Failures 11/84 08/86 109. Reactor Vessel Closure Failure 12/84 03/87 110. Equipment Protection Devices on Engineered Safety Features 12/84 09/86 113. Dynamic Qualification Testing of Large Bore Hydraulic Snubbers 03/85 09/86 115. Reliability of Westinghouse Solid State Protection System 04/85 07/86 4 116. Accident Management 04/85 TBD 117. Allowable Outages Times For Diverse Simultaneous Equipment Outages 05/85 05/86 118. Tendon Anchorage Failure 07/85 12/86 120. On-Line Testability of Protection Systems 08/85 04/86 123. Deficiencies in the Regulations Governing DBA and Single Failure 11/85 TBD Criterion Suggested by the Davis-Besse Incident of June 9, 1985 T7-1 As of 3rd Quarter FY-86
TABLE 7 (CONT.)
GENERIC ISSUES TO BE PRIORITIZED i Action Item / Identification Current Issue No. _ Title Date Schedule 125.I.1 Availability of the STA 11/85 08/86 -
125.I.3 SPDS Availability 11/85 07/86 125.I.4 Plant-Specific Simulator 11/85 07/86 .
125.I.5 Safety Systems Tested in All Conditions Required by Design Basis 11/85 08/86
, Analysis 125.I.6 Valve Torque Limit and Bypass Switch Settings L/85 08/86 125.I.7.a Recover Failed Equipment 11/85 08/86 125.I.7.b Realistic Hands-On Training 11/85 08/86 125.I.8 Procedures and Staffing for Reporting to NRC Emergency Response Ctr. 11/85 08/86 125.II.1.a Two-Train AFW Reliability 11/85 07/86 125.II.1.b Review Existing AFW Systems for Single Failure 11/85 07/86 125.II.1.c NUREG-0737 Reliability Improvements 11/85 07/86 125.II.1.d AFW/ Steam and Feedwater Rupture. Control System /ICS Interactions in 11/85 07/86-B&W Plants 125.II.2 Adequacy of Existing Maintenance Requirements for Safety-Related Sys. 11/85 07/86 125.II.3 Review Steam / Feed Line Break Mitigation Systems for Single Failure 11/85 07/86 125.II.4 OTSG Dryout and Reflood Effects 11/85 07/86 125.II.5 Thermal-Hydraulic Effects of Loss and Restoration of Feedwater 11/85 07/86 on Primary System Components 125.11.6 Reexamine PRA Estimates of Core Damage Risk from Loss of All Feedwater 11/85 08/86 125.11.7 Reevaluate Provisions to Automatically isolate Feedwater from Steam 11/35 07/86 Generator During Line Break 125.II.8 Reassess Criteria for Feed-and-Bleed Initiation 11/85 07/86 125.II.9 Enhance feed-and-Bleed Capability 11/85 07/86 125.II.10 Hierarchy of Impromptu Operator Actions 11/85 07/86 125.II.11 Recovery of Main Feedwater as Alternative to AFW 11/85 07/86 125.II.12 Adequacy of Training Regarding PORV Operation 11/85 07/86 125.II.13 Operator Job Aids 11/85 08/86 125.II.14 Remote Operation of Equipment Which Must Now Be Operated Locally 11/85 07/86 126 Reliability of PWR Ma'in Steam Safety 03/86 TBD 127 Testing and Maintenance of Manual Valves in Safety-Related Systems 05/86 TBD 128 Electrical Power Reliability 05/86 TBD 129 Valve Interlocks to Prevent Vessel Drainage During Shutdown Cooling 05/86 12/86 130 Essential Service Water Pump Failures at Multiplant Sites 06/86 TBD T7-2 As of 3rd Quarter FY-86
TABLE 8 GENERIC ISSUES TO BE REPRIORITIZED Action Item / Previous Identification . Current Issue No. Title , Priority Date Schedule
- 2. Failure of Protective Services on Essential Equipment M 05/83 09/86
- 24. Automatic Emergency Core Cooling System Switch to NR 03/83 12/86 Recirculation
- 55. Failure of Class IE Safety-Related Switchgear Circuit 0 09/85 12/86 Breaker to Close on Demand A-19 Digital Computer Protection System LI 02/83 09/86 B-22 LWR Fuel LI 02/83 09/86 B-29 Effectiveness of Ultimate Heat Sinks LI 02/83 08/86 B-31 Dam Failure Model RI 02/83 09/87 8-32 Ice Effects on Safety Related Water Supplies LI 02/83 03/87 C-9 RHR Heat Exchanger Tube Failures D 07/84 09/86 C-14 Storm Surge Modes for Coastal Sites RI 02/83 09/86 D-2 Emergency Core Cooling System Capability for Future Plants S (A-45) 06/83 10/86 III.D.1.1(2) Review Information on Provisions for Leak Detection I 12/82 11/86 III.D.1.1(3) Develop Proposed System Acceptance I 12/82 11/86 T8-1 As of 3rd Quarter FY-86
Table 9 TNI LICENSING ISSUES SCHEDULED FOR RESOLUTION Lead Office / Current Issue Division / Resolution Number Title Branch Date I.A.2.4 NRR Participation in Inspection Training NRR/DHFT/ TBD I.A.4.4 Feasibility Study of NRC Engineering Computer RES/ TBD III.D.3.2 Health Physics Improvements -- --
III.D.3.2(1) Amend 10 CFR 20 RES/ TBD III.D.3.2(3) Develop Standard Performance Criteria RES/ TBD III.D.3.2(4) Develop Method for Testing and Certifying Air-Purifying RES/ TBD Respirators III.D.3.5(1) Develop Format for Data to be Collected by Utilities RES/ TBD Regarding Total Radiation Exposure to Workers IV.E.1 Expand Research on Quantification of Safety Decision-Making RES/ TBD IV.E.3 Plan for Resolving Issues at the CP Stage RES/ TBD IV.E.4 Resolve Generic Issues by Rulemaking RES/ TBD IV.G.2 Periodic and Systematic Evaluation of Existing Rules RES/ TBD l
T9-1 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number - Type Level Office /Div/Br Manager TACS No.
3 Safety / Complete NRR/DSR0/RSIB L. Riani 52400 NR Title ---------------- Set Point Orift in Instrumentation.
fgy Work Authorization --- NRR FY-84 Operating Plan, (Appendix G).
Contract Title ------- None
' Contractor Name/ FIN -- None Wo rk Scope ----------- Provide technical assistance, as required,' to RES for the revision and issuance of Regulatory Guide 1.105, Revision 2.
Affected Documents --- Revise Reg. Guide 1.105, Rev. 2 (an SRP revision to incorporate the Reg. Guide revision is not anticipated).
Status --------------- Resolved. The technical resolution is identified and documented in the revision to Reg. Guide 1.105.
Problem / Resolution --- None Technical Resolution -
Milestones Original Current Actual Technical input necessary to - -
11/12/82 revise Reg. Guide 1.105 was transmitted to RES.
RES to submit CRGR package for 10/83 -
08/05/83 review.
CRGR review completed and 11/83 -
10/20/83 returned to RES with comments.
l ACRS review completed - -
11/19/83 I RES incorporated CRGR comment - -
12/12/83 and returned for approval.
CRGR review -
03/84 -
01/11/84 CRGR meeting - -
03/12/85 Issue Memorandum to NRR to 08/84 -
05/06/85 establish basis for R.G.
Position.
3-1 As of 3rd Quarter FY-86
Generic Issuo #3 Milestones Original Current Actual NRR response to Position 07/85 -
06/27/85 memorandum ACRS review complete 10/84 -
10/85 Reg. Guide 1.105 Rev. 2 05/85 -
02/86 issued.
Issue transfer memo to NRR/ICSB 01/86 -
03/11/86 NRR assessment of Reg. Guide 06/86 -
05/19/86*
impact on SRP and Issue ~
close-out memo or expand schedule.
i i
l l
^ Memorandum from H. R. Denton to T. Speis, dated May 19, 1986.
3-2 As of 3rd Quarter FY-86
GENERfC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task
, Number Tyge_ Level _ Office /Div/Br Manager TACS No.
23 Safety / Active-L1 NRR/DSR0/EIB J. Jackson 49716 High Title ---------------- Reactor Coolant Pump Seal Failures.
Work Authorization --- NRR FY-84 Operating Plan, (Appendix G).
1 Contract Title ------- 1) Reactor Coolant Pump (RCP) Seal Integrity
- 2) Assessment of Effect of Mechanical and Maintenance-Induced
- - RCP Seal Failures on Risk
- 3) Evaluation of the Adequacy of Current RCP Seal Instrumen-tation and Operator Responses to Possible RCP Failures
- 4) RCP Shaft Seal Behavior During Station Blackout
- 2) BNL/A-3771 I 3) BNL/A-3806 l 4) INEL/A-6322
- 5) Energy Technology Engineering Center /B-3049 Work Scope ----------- The TAP for this issue has been revised to incorporate work task necessary to complete Generic Issue 65. Review PWR RCP seal failures caused by mechanical failures and loss of seal cooling to ascertain if increased NRC require-ments are necessary to minimize seal failures. Evaluate the effects of system design, materials, operation, testing, and maintenance on seal failure mechanisms. Review the reliability of seal cooling systems and identify methods to minimize the effects of loss of seal cooling. Perform a risk assessment of seal failure from maintenance and mechanical effects.
This program will determine what steps the NRC should take, if any, to reduce RCP seal failure to an acceptable level commensurate with the potential safety consequences of seal failure. The program consists of the following major tasks:
Task 1 - Determine actual seal failure mechanisms.
Task 2 - Evaluate RCP seal cooling for all modes of oper-4 ation for which seal cooling is required using the reliability of typical RCP seal cooling system designs.
Task 3 - Review mechanical and maintenance-induced failure mechanisms.
The TAP is currently being reviewed to assure that ACRS comments (August 14, 1984 ltr. J. Ebersole to W. Dircks) regarding conversion of Generic Issue 23 to a USI are being incorporated.
23-1 As of 3rd Quarter FY-86
Generic Issua #23 Affected Documents --- Issue NUREG- (To be Determined)
Review and Issue SRP Section 9.2.2 (To Be Determined)
Revise and Issue SRP Section 9.3.4 (To Be Determined)
Issue New Regulatory Guide and SRP Section (To Be Determined)
Status --------------- Work is currently in progress on Tasks 1, 2, and 3 as follows: RSB has provided imput to Task 1 (Assemble background information on seal failures). This work includes subtasks to: (1) perform an LER search, (2) review industry experience, and (3) perform a BWR screening review. BNL has completed additional work on this task under FIN A-3771 which was published as NUREG/CR-4400.
EIB is currently working on Task 2 (subtask 2.1). EIB's task is to evaluate the effects of loss of seal cooling.
RES is providing input through contracts with AECL and ETEC. The AECL contract work has been completed and NUREG/
CR-4077, " Reactor Coolant Pump Shaft Seal Behavior During Station Blackout" has been issued. The ETEC contract work has been completed and NUREG/CR-4294, " Leak Rate Analysis of the Westinghouse Reactor Coolant Pump" has been issued.
Additional concerns regarding seals which were discovered through research at AECL are to be investigated through a follow-on contract at AECL. Completion date is not yet available.
EIB, under technical assistance contract (FIN A-3751) with BNL, is working on Task 2 (subtask 2.2). The purpose of this subtask is to evaluate the reliability of cooling water systems. Subtask 2.2 has been completed and BNL draft report has been reviewed by the staff and is currently being revised by BNL.
EIB, under technical assistance contract (FIN A-3771) with BNL, is working on Task 3 (subtask 3.1). The purpose of this subtask is to evaluate the effect of mechanical i
and maintenance induced RCP seal failures or risk.
l
' Subtask 3.1 has been completed and NUREG/CR-4400 has been issued.
l EIB, under technical assistance contract (FIN A-3806) with l
BNL is working on Task 2 (subtask 2.3) and Task 3 l (subtask 3.2). The purpose of these subtasks are to evaluate the adequacy of current RCP seal and seal cooling system instrumentation to detect RCP seal degradation and failures; to evaluate the adequacy of current automatic actions and manual operator responses to prevent RCP seal LOCAs or other unacceptable events and to propose possible j instrumentation changes, automatic sctions or manual operator responses which could improve the current RCP seal safety procedures. Subtasks 2.3 and 3.2 have been completed and the BNL draft report has been reviewed by the staff and is currently being revised by BNL.
23-2 As of 3rd Quarter FY-86
(
Generic Issue #23 Problem / Resolution --- The staff is still waiting for Westinghouse to make the results of the French RCP seal test available and to respond to the staff concerns regarding their submittal WCAP-10541 on RCP seal performance during station blackout.
The Westinghouse report containing this information is currently scheduled to be submitted to the staff by 4/15/86. Additional concerns regarding all types of RCP seals were raised as a result of the AECL test program.
RES is extending their test program at AECL to further investigate these concerns. A revised schedule will be developed for this issue. The revised milestones will incorporate the results of the French test and the AECL work to the extent possib,la at this time.
Milestones Original Current Actual GI Action Plan issued For 04/83 -
03/31/83 Comment Action Plan Approved by 10/83 -
10/26/83 Director, OSI.
Transferred Resolution 3 06/15/84 Responsibility from .
DSI to DE Transferred resolution - -
05/13/85 responsibility from DE to DST /GIB Complete documentation of 05/85 -
10/17/84 background past seal failures, including LER search, review of industry experience, and review of BWR screening (Task 1).
Complete ew 'vetion of RCP 12/84 12/85* -
seal cooling. including determining effect of loss of cooling, evaluating reli-ability of cooling systems, '
and reviewing RCP seal cooling instrumentation (Task 2)
Issued request for proposal - -
11/02/83 to BNL for component cooling water PRA.
Complete evaluation of mechani- 01/85 -
09/85 cal and maintenance induced ;
failure mechanisms (Task 3).
Complete feasibility study to 03/85 10/85* -
identify most effective fix.
23-3 As of 3rd Quarter FY-86
Generic Issue #23 Milestones Original Current Actual Technical resolution complete. 07/85 10/85* -
Division Director approval of 08/85 10/85* -
CRGR package. Sent for Division Director comments.
Comments incorporated. CRGR 09/85 10/85* -
package sent to Director NRR.
Director, NRR review complete. 10/85* - -
Package sent to CRGR.
CRGR review complete. 11/85* - -
ACRS review complete. 11/85* - -
E00 approval. 12/85* - -
Federal Register Notice issued 12/85* - -
for public comment.
OMB Clearance. 04/86* - -
Incorporation of comments 04/86* - -
Package sent to Director, NRR.
Director, NRR review complete. 05/86* - -
CRGR review complete. 06/86* - -
EDO approval. 06/86* - -
FR Notice of issuance of SRP 07/86* - -
Change.
(Note: Tasks 1, 2 and 3 are not sequential as they will be worked,on simultaneously.)
, " Schedule will be reevaluated and adjusted based on results received from the l French Reactor RCP seal testing and the additional AECL test results.
l 23-4 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
~
Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
29 Safety / Active /L1 NRR/DSR0/EIB R. Johnson 52454 High Title ---------------- Bolting Degradation or Failures in Nuclear Power Plants Work Authorization --- NRR FY-84 Operating Plan (Appendix G).
Bolting Applications Requirements Contract Title -------
Contractor Name/ FIN -- BNL/A-3359 and A3782 Work Scope ----------- 1. Development of the technical bases for bolting application requirements by MTEB through its contractor at BNL.
- 2. Review licensee's responses to IEB No. 82-02, " Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary of PWR Plants.3
- 3. Draft staff recommendation for proposed criteria / guidelines to be incorporated into SRP.
- 4. Develop a proposed icplementation plan for management consideration.
Affected Documents --- SRP revision.
S ta t u s ------ -- - --- - - - Transfer of lead to DSR0/EIB was effected following the NRR reorganization. Revision of the Technical Resolution plan and program Hilestones is being held in abeyance penoing the final actions on USI A-45. Since the proposed USI A-45 add-on DHR includes small break makeup and decay heat removal capabili-ties, implementation of the proposal might preclude the need fo.' a bolt replacement program. Also, reevaluation of the GI-29 prioritization of the proposal might be called for. If the safety significance of GI-29 were reduced substantially, i
the need to resolve the issue might change. Rather than pre-i pare revisions prematurely, we will let USI A-45 set the pace.
l Reports in preparation by the AIF in collaboration with EPRI and the MPC-sponsored Bolting Technology Council (BTC) have not yet been issued. The BTC meeting, held in early April, pro-duced nothing meaningful relative to resolving GI-29.
Problem / Resolution --- Revisions to the plan for technical resolution and to the program milestones will be held in abeyance pending final ac-
' tion on USI A-45 and review of the AIF/EPRI documents. Either could result in a reevaluation of the issue.
l l 29-1 As of 3rd Quarter FY-86 l
l l
Generic Issue #29 Technical Reolution --
Milestones Original Current Actual Issue contract to BNL - -
03/15/83 Draft NUREG/CR report 07/83 -
07/15/83 received from contractor Staff review of draft 07/83 -
03/06/84 NUREG/CR report Draft Staff Position 07/84 -
08/10/84 (Revision SRP Section)
Value/ Impact Statement 08/83 -
05/85 prepared Final CRGR package 09/83 03/86 -
prepared for Division review Final CRGR package 10/83 04/86 -
forwarded for NRR divisions ,
review NRR Director Review 12/83 05/86 -
completed Review Package:to CRGR 01/84 06/86 -
CRGR review completed 02/84 07/86 -
EDO approval 03/84 07/86 -
Federal Register Notice of 03/84 08/86 -
Issuance of Proposed SRP Raised for Public Comment Division review of public 07/84 11/86 -
comments completed NRR Director review 08/84 12/86 -
completed I
CRGR review completed 08/84 12/86 -
E00 approval 08/84 12/86 -
Federal Register Notice of 09/84 01/87 Issuance of SRP Milestones revisions will be considered when the impact of USI A-45 on GI-29 can be evaluated.
29-2 As of 3rd Quarter FY-86 m- , _ . . _ ., _ _
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
35 Safety / Complete NRR/DSR0/RSIB L. Riani 54482 NR Title ---------------- Loss of Service Water (Calvert Cliffs Unit 1).
Work Authorization --- Memorandum to R. J. Mattson from H. R. Denton dated February 15, 1984.
NRR FY-84 Operating Plan (Appendix G).
Contract Title ------- Nc..e Centractor Name/ FIN -- None Wo rk Scope ----------- Revise SRP Sections 9.2.1 and 9.2.2 to incorporate concerns of interaction between safety and nonsafety-related portions of SW and CW systems which result in inoperability of safety-related portions, including possibility of entrance of air resulting in air binding of pumps.
Affected Documents --- SRP Sections 9.2.1, 9.2.2.
Status -------------- Resolved. CRGR agreed that revision to the SRP could be
. issued without review.
Problem / Resolution -- Schedule slipped 3 months (see memo T. Speis from R. Bernero dated September 13, 1984).
Technical Resolution -
Milestones Original Current Actual ASB completes SRP Revision 09/84 -
08/85 Package.
OSI Division Director Approval. 10/84 -
08/12/85 SPEB Review and Package sent to 10/84 -
09/20/85 CRESS for Final Typing.
SRP Revision Package Returned - -
10/03/85 (Revision Tape Missing) to DST.
Final SRP Revision Package 11/84 -
04/86 for Office Director Approval.
Notify CRGR and ACRS of Intent 02/85 -
05/13/86 to Publish.
Issue FR Notice for SRP Change 03/85 -
06/86*
Memorandum from H. R. Denton to T. Combs dated June 1986 issued the FR Notice which resolved this issue.
36-1 As of 3rd Quarter FY-86
i l
l GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
48 Safety / Active-L1 NRR/DSR0/EIB D. Thatcher 55223 NR Title ---------------- LCO for Class IE 120V AC Vital Instrument Buses in Operating Reactors.
Work Authorization --- Memorandum to D. G. Eisenhut from H. R. Denton dated October 15, 1983.
Memorandum to R. J. Mattson from T. S. Speis dated March 1, 1984, " Transfer of Lead Responsibility for Generic Issue No. 48 from DL to DSI."
NRR FY-84 Operating Plan, (Appendix G).
Contract Title ------- PWR 120V AC Vital Instrument Buses and Inverter Technical Specifications Contractor Name/ FIN -- LLNL/UCID 19469 Wo rk Scope ----------- Review LLNL TER containing the technical finding to the above issue. Determine if there is any need for additional work to be performed by the staff or staff contractor. Prepare package containing the. resolution of the issue for CRGR review. After CRGR approval issue generic letter requesting all licensees to propose technical specifications limiting the time the 120V AC vital buses may be energized from a source other than its Class 1E DC bus and associated inverter.
Affected Documents --- Plant Technical Specifications Status --------------- RRAB has completed its review of the LLNL report and deter-mined additional work is required to complote this study.
RRAB has requested plant specific information to perform a new analysis on this issue.
Problem / Resolution --- RRAB concluded that the original analysis was inadequate.
Technical Resolution -
Milestones Original Current Actual Generic Issue 48 assigned to - -
10/15/83 DL by Director, NRR l
Generic issue lead responsibility - -
03/01/84 transfer from DL to OSI Request to RRAB for technical 10/84 -
05/01/84 assistance to review PRA done by LLNL 48-1 As of 3rd Quarter FY-86
Generic Issue #48 Milestones Original Current Actual Complete review of LLNL report 02/85 -
10/15/84 by the RRAB RRAB requested for plant specific - -
04/11/85 information to complete new study Collect information from selected -
TBD -
licensees on 120V AC vital instrument busses Information received from -
TBD -
licensees ICSB evaluation of the licensee -
TBD* -
information Complete revised technical 03/85 TBD* -
resolution of the issue by RRAB Technical resolution identified. 04/85 TBD* -
Prepare review package for CRGR Division Director approval of 06/85 TBD* -
CRGR package. Package to other division directors for comments.
Other division comments 07/85 TBD* -
incorporated. Package sent to Director, NRR.
Director, NRR review complete. 08/85 TBD* -
Package sent to CRGR.
CRGR review complete. 09/85 TBD* -
EDO approval. 10/85 TBD* -
OMB clearance. 01/86 TBD* -
Issue close-out memorandum 02/86 TBD* -
(generic letter to all operating plants)
Technical resolution complete 02/86 TBD* -
- EIB is currently in the process of integrating this issue and some other issues related to power supplies (e.g., GI-49, A-30) into a single program. During the integration effort, EIB is reevaluating the schedule.
48-2 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
49 Safety / Inactive-L1 NRR/DSR0/EIB D. Thatcher TBP Medium Title ---------------- Interlocks and LCOs for Class 1E Tie Breakers.
Work Authorization --- Memorandum to Daniel Muller from Harold Denton, dated July 31, 1984.
Contract Title ------- To be determined.
Contractor Name/ FIN -- To be determined.
Wo rk Scope ----------- Prepare generic letter to all licensees requesting electrical interconnection design information. Prepare contract proposal for evaluation and assimilation of electrical interconnection design information. Prepare contract proposal for determining benefit / detriment of electrical interconnection. Evaluate staff contractors finding to determine if additional work needs to be performed by staff or staff contractor. Prepare package containing resolution findings for CRGR review. Issue generic letter, as necessary, requesting all licensees to implement technical resolution.
Technical resolution will include: .
, 1. Prepare a generic information request for transmittal to all operating plants to identify extent and design of electrical interconnections between Class 1E buses at operating plants. Solicit a contract proposal for evaluation and assimilation of this design information.
- 2. Determine benefit / detriment in permitting electrical interconnections between Class IE buses by performing a comparative PRA. Prepare and solicit a con, tract proposal for resolution.
- 3. Identify cost / benefit for each technical resolution (hard-ware, procedures, etc.). Prepare a listing of all tech-nical resolutions and solicit a contract proposal to obtain cost / benefit for each resolution identified.
Affected Documents --- None S ta t u s - -- - - - ---- --- - - Inactive during FY 84 and FY 85.
Problem / Resolution --- None Technical Resolution -
Milestones Original Current Actual Generic information request 11/85* TBD* -
to DL for comment 49-1 As of 3rd Quarter FY-86
G:n:ric Issue #49 Milestones Original Current Actual Request CRGR review and comment 12/85* - -
CRGR review complete 01/86* - -
Generic information request to OL 02/86* - -
G neric letter to all OR's from 03/86* - -
DL Request RRAB comments on 04/86 - -
contract proposal RRAB comments received 05/86 - -
Contract proposal solicited 06/86 - -
Contract proposal evaluated 09/86 - -
and accepted Generic information received 09/86 - -
from OR Draft report from contractor 01/87 - -
Request RRAB comments on draft 02/87 - -
NUREG/CR report Comments received from RRAB 04/87 - -
Staff review of draft NUREG/CR 06/87 - -
reports Technical resolution complete 08/87 - -
CRGR package to NRR Division 12/87 - -
Directors for review CRGR Package to NRR Director 02/88 - -
Review Package to CRGR 03/88 - -
CRGR review completa 04/88 - -
EDO approval complete 05/88 - -
OMB clearance 08/88 - -
Issue generic letter as 09/88 - -
necessary to all operating plants
- EIB is currently in the process of integrating this issue and some other issues related to power supplies (e.g. , GI-48, A-30) into a single program. During the integration effort EIB is re-evaluating the schedule.
49-2 As of 3rd Quarter FY-86 I
l
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type level Office /Div/Br Manager TACS No.
51 Safety / Active-L1 NRR/DSR0/EIB C. Hickey 53338 Medium T i t l e ---------------- Proposed Requirements for Improving Reliability of Open Cycle Service Water Systems Work Authorization --- Memorandum to R. J. Mattson from H. R. Denton dated June 3, 1983.
NRR FY-84 Operating Plan, (Appendix G).
Contract Title ------- Improving Reliability of Open-Cycle Water Systems.
Contractor Name/ FIN -- PNL/B-2977.
Wo r k Scope ----------- The detailed work scope is provided in TAP for resolution of Issue 51 (Memorandum from R. Mattson to T. Speis, et al dated 01/11/84). In summary, the scope of this task will be to evaluate the adequacy of surveillance and control methods and to propose the use of those methods which will assure the continued reliability of open cycle service water systems against various forms of fouling.
Affected Documents --- To Be Determined .
S ta t u s - -- --- - - - - - - -- - The TAP was revised and issued on 10/3/84. The statement of work (50W) was revised on 5/9/85 to incorporate RES project Task V into NRR's technical assistance project. The TAP was revised to be consistent with the 50W and to assure that it incorporated milestones necessary to process CRGR SRP packages through issuance and use. The first 4 tasks associated with this issue are tied to RES project 82463 and are complete.
Based upon the results of this research which deals with biofouling, DSRO will adapt, where possible, methods for surveillance and control of biofouling to fouling by mud, silt and corrosion products.
The contractor is operating under an FY85 carryover budget of
$65K that will run out in May 1986. DSRO has withdrawn tech-nical assistance support from its medium priority issues for FY86. Unless funding can be found, the contractor's efforts will terminate and no final report or guidance document will be produced.
A modified PNL proposal dated October 1985 was received incor-porating several new tasks. The contractor will deter-mine the applicability of biofouling surveillance and control methods contained in NRC furnished materials to open cycle water systems in nuclear power plants. Preparation of the final contractor report is scheduled for April 30, 1987.
Coordination of this project with RES is document d in a Memorandum from R. Mattson to F. Arsenault, dated 01/23/84.
51-1 As of 3rd Quarter FY-86
Generic Issue #51 Problem / Resolution --- Due to budget contraints, RES was not be able to provide all of the technical assistance originally planned. In particular, the:
could not fund Task V of FIN 82463; Task V celled for preparatior, of a final report and guidance document consolidating the results of the previous four tasks. NRR has established a technical assistance contract (FIN 82977) that will use the results of Tasks I-IV of RES FIN 82463 to develop methods for surveillance and control of fouling by mud, silt and corrosion products. A staff guidance will be prepared.
Technical Resolution -
Milestones Original Current Actual Task action plan Approved by 01/84 -
01/11/84 Director, OSI.
Revised work plan approved and - -
10/03/84 issued Proposals solicited 07/84 -
10/31/84 PNLs response to request For - -
12/21/84 Proposal and 50W
~
Revised 50W to incorporate - -
05/09/85 RES Task V Proposal Evaluated and 02/85 -
08/85*
)
Accepted Contract Schedule 03/85 -
10/85 Draft NUREG/CR report from 07/86 03/87 -
contract consultant Staff review of draft NUREG/CR 08/86 03/87 -
report Staff review of final NUREG/CR- 09/86 05/87 -
report Value/ Impact Statement prepared 10/87 08/87 -
Final report prepared by 11/87 09/87 -
Division Final report forwarded to DSR0 11/87 10/87 -
for processing NRR Director Review completed 12/87 11/87 -
Review Package to CRGR** 12/87 12/87 -
" Subcontractor may revise proposal to incorporate additional work required by Task V of Research Project B-2463.
- If required 51-2 As of 3rd Quarter FY-86
GIneric Issue #51 Milestones Original Current Actual CRGR review completed ** 01/88 01/88 -
EDO approval 02/88 02/88 -
Federal Register Notice of 05/88 03/88 -
Issuance of SRP for Public Ccament OM8 Clearance, if applicable 06/88 04/88 -
Division review of public 07/88 05/88 -
comments completed NRR Director review 07/88 06/88 -
completed CRGR review completed ** 08/88 07/88 .
ED0 Approval 09/88 08/88 -
Federal Register Notice 09/88 08/88 -
of Issuance of SRP i
- If required i
51-3 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
61 Safety / Active NRR/DSR0/RSIB A. Serkiz 55224 Medium Title ---------------- SRV Discharge Line Break Inside the Wetwell Airspace of BWR Mark I and Mark II Containments Work Authorization --- Memorandum to R. J. Mattson from H. R. Denton dated November 30, 1983.
NRR FY-84 Operating Plan (Appendix G)
Contract Title ------- Steam Bypass in Mark I and II Containments Oue to Postulated SRV Discharge Failure Contractor Name/ FIN -- BNL/A-3793 Wo r k S cope ----------- Assess probability of discharge line break or stuck open vacuum breaker coincident with a stuck open SRV. Assess consequences including containment pressure and effect on core cooling systems.
Affected Documents --- BNL-NUREG-31940, NUREG/CR-4594 Status --------------- Resolved. Published BNL-NUREG-31940 and NUREG/CR-4594,
" Estimated Safety Significance of Generic Issue 61,"
June 1986.
Problem / Resolution --- None Technical Resolution - None Milestones Original Current Actual Issue assigned to OSI. 11/83 -
11/03/83 Task Action Plan approved by 01/84 -
01/11/84 4
Director, DSI.
i Complete review of BNL-NUREG- 03/85 -
12/14/84 31940 BNL Draft Report 02/86 -
02/25/86 Review BNL Report 03/86 -
05/22/86 BNL Final Report 04/86 -
05/30/86 Draft Regulatory Analysis 04/86 -
04/30/86 Issue Reg. Analysis for comment 05/86 -
N/A i
l I
61-1 As of 3rd Quarter FY-86
G:neric Issu2 #61 Milestones Original Current Actual Issue BNL Report 06/86 - -
Issue Closecut memorandum 06/86 06/86* -
. Complete feasibility study to 10/85 N/A -
identify the most effective fix to reduce containment failure due to SRV line break in air-space region of the suppression pool.
Technical resolution identified. 01/86 N/A -
Prepare CRGR package or close-out documentation. -
Division Director approval of 02/86 N/A -
CRGR package. Package sent to NRR Divisions and others for comment.
Other Division Directors' 03/86 N/A -
comments incorporated.
Package sent to Director, NRR. ,
Director, NRR review complece. 05/86 N/A -
package sent to CRGR.
CRGR review. 06/86 N/A -
ACRS review. 07/86 N/A -
EDO approval. 08/86 N/A -
FR Notice of draft NUREG for 08/86 N/A -
public :omment.
OMB Clearance (if needed). 10/86 N/A ,
Incoporate public comments. 11/86 N/A -
Final issuance of NUREG. 03/87 N/A -
l Issue Generic Letter to all 03/87 N/A -
operating BWR plants with Mark I and Mark II containments.
i 1
- Closeout memo submitted to NRR Director for approval on June 30, 1986.
(
61-2 As of 3rd Quarter FY-86 l _
~
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
!ssue Issue Action Task Number Type. Level Office /Div/Br Manager TACS No.
65 Safety / Scheduled NRR/DSR0/EIB J. Jackson 49716 High with GI 23 Title ---------------- Component Cooling Water System Failures l Work Authorization --- Memorandum to R. J. Mattson from H. R. Denton dated i September 8, 1983.
NRR FY-84 Operating Plan (Appendix G).
- Contract Titic ------- Reactor Coolant Pump Seal Integrity Contractor Name/ FIN -- BNL/A-3751 Work Scope ----------- The consequences of loss of component cooling water relative to reactor coolant pump (RCP) seal degradation, will be i determined. The reliability of existing and proposed seal 4
cooling systems will be assessed to determine if additional licensing requirements are required. This work comprises Task 2 of Generic Issue 23, " Reactor Coolant Pump Seal Failures."
i Interruption of seal cooling may lead to RCP seal failure and subsequent loss of primary coolant to containment, i.e. , a small LOCA. Where the component cooling water system is also used for cooling reactor coolant system makeup pumps, makeup capability could be lost coincident with the seal leakage and
- core melt could result.
The program will determine what steps the NRC should take, if f any, to ensure increased reliability of the component cooling water system relative to its RCP seal r.ooling function. Test data will be reviewed to determine the time to failure of seals i
without seal cooling and the leak rate resulting from this type of failure. A probabilistic risk assessment will be performed to identify the major contributors to component cooling water system unreliability and the contribution to core melt proba-bility due to loss of RCP seal cooling systems. A review will be performed of instrumentation available to the operator as well as automatic or manual actions which can be taken to minimize interruptions of RCP seal cooling or prevent unacceptable consequences from loss of seal cooling.
Affected Documents --- Issue NUREG- (To Be Determined)
Revise and issue :2.0 Section 9.2.2 (To Be Determined)
Revise and issue SRI Section 9.3.4 (To Be Determined)
Issue New Regulatory Guide and SRP Section (To Be Determined)
Status --------------- A revised TAP has been developed for Issue 23 which includes work for Issue 65. A PRA of component cooling water system reliability is being performed by BNL under a technical assistance contract (FIN A-3751).
Problem / Resolution --- None.
65-1 As of 3rd Quarter FY-86
,----v-r--ww---,--ww--~---,y ---,,---.,rm---------_ -
,~---v-- _,w--cww---c,
-- - - - - , - - + - ,. w-,, %-
Generic Issue #65 Technical Resolution - Refer also to Generic Issue No. 23.
Milestones Original Current Actual Task Action Plan for Generic Issue -- --
10/26/83 23, " Reactor Coolant Pump Seal Failure" was revised to incorporate GI-65 tasks and was issued.
Issued Request fo'r Proposal to BNL -- --
11/02/83 for component cooling water PRA.
For milestone necessary to Resolve and complete this issue refer to i Milestone for Generic Issue No. 23, l Task 2 i
4 65-2 As of 3rd Quarter FY-86 i
.e
,,,-_._-._.4 ~ __ .,, _ _. . _ - - .
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
66 Safety / Active-L1 NRR/0 RAS /BWR E. Murphy T8P NR Title ---------------- Steam Generator Requirements (Integrated Program for Resolution of USIs A-3, A-4 and A-5 Regarding Steam Generator Tube Integrity).
Work A'u thorization --- Memorandum to D. G. Eisenhut from H. R. Denton dated November 16, 1983 NRR FY-84 Operating Plan (Appendix G).
Contract Title ----=-- None Contractor Name/ FIN -- None Work Scope ----------- Technically resolved Unresolved Safety Issues A-3, A-4, and A-5 Regarding Steam Generator Tube Integrity.
Affected Documents --- Issue NUREG-0844, "NRC Integrated Program for the Resolution of Unresolved Safety Issue A-3, A-4, and A-5 Regarding Steam Generator Tube Integrity."
Status --------------- The staff has provided the Commission with an assessment of licensee responses to Generic Letter 85-02 (SECY 86-XX, dated March 24, 1986).
The staff is currently preparing the final version of NUREG-0844 to reflect the above assessment and also to reflect public comments on the draft version of NUREG-0844. With final publi-cation of NUREG-0844, the USIs will be considered to be tech-nically resolved.
An additional milestone has been added to this USI program as a result of the staff assessment above; namely, the staff will provide its plant-specific assessments to the individual utilities. The staff will identify areas where the utility program appear to fall short of the staff recommendations in i
Generic Letter 85-02 and will continue to encourage utilities to implement the staff's programs.
Problem / Resolution --- None Technical Resolution -
Milestones Original Current Actual ACRS review complete - -
10/18/83 CRGR review complete - -
10/29/83 Commission Paper on Proposed USI - -
01/11/84 resolution (SECY 84-13) 66-1 As of 3rd Quarter FY-86
Generic Issue #66 Milestones Original Current Actual Revised Commission Paper on 07/84 -
09/07/84 proposed USI resolution (SECY 84-13A)
Commission Meeting 02/84 -
09/10/84 (a) Issue SECY 84-138 -
11/05/84 (c) Issue SECY 85-62 - -
02/22/85 Issue generic letter 03/84 -
04/17/85 (85-02)
Issue FR' Notice for public 03/84 -
04/22/85 comment on NUREG-0844 (For Comment)
Issue report to Commission 02/86 -
03/24/86 regarding responses to generic letter Division incorporation of public 07/84 04/85 -
comments.
Issue FR Notice for Formal 09/84 05/86 -
determination by staff of USI resolution NUREG-0844 Issue plant-specific letters TBD - -
describing staff assessment of response to Generic Letter 85-02 1
4 66-2 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
67.7 Safety / Active-L1 NRR/DSR0/EIB K. Shaukat 59303 Medium Title ---------------- Steam Generator Staff Actions - Eddy Current Tests Work Authorization --- Memorandum To J. Knight From H. Denton dated March 28, 1985 Contract Title ------- ASME Code Provisions For Eddy Current Testing Contractor Name/ FIN -- ORNL/A-9476 Work Scope ----------- Review current ASME Code requirements with respect to licensing l
~
needs for eddy current inservice inspection of steam generator tubes. Provide a critique of current code requirements. For-mulate recommendations for improving code provisions for eddy current testing. Perform confirmatory testing as required to substantiate technical validity of existing or proposed code pro-visions. Attend and participate in pertinent Code subcommittee and subgroup meetings of both Sections V and XI. In the event that the Code is unable to incorporate those improved eddy current testing provisions deemed necessary, provide recommendations for a Draft Regulatory Guide.
Affected Documents --- To Be Provided Later Status --------------- Proposal received from ORNL on September 16, 1985.
Problem / Resolution --- Issuance of contract to ORNL suspended pending discussions with RES on the incorporation of this program into ongoing i PNL/RES program on steam generators. Delays in this generic issue have resulted because of RES stated needs for additional furding, possibly from NRR, to accelerate work to meet a schedule acceptable to NRR.
Technical' Resolution -
Milestones Original Current Actual l Generic Issue Assigned - -
03/28/85 i Preliminary discussions of - -
04/10/85 work plan with ORNL l
ORNL provides preliminary - -
06/28/85 l outline of work plan I
Request for proposal submitted 09/85 -
08/20/85 to ORNL Contract Incorporated in 09/85 -
09/85 FIN Plan 67-1 As of 3rd Quarter FY-86
Generic Issue #67.7 Milestones Original Current Actual Proposal Evaluated 09/85 -
09/85 and Accepted Issue Contract TBO* - -
to ORNL ORNL Issues Report TBO* - -
on Recommendations for Improved Code Provisions and Action Plan ORNL Issues Report TBO* - -
Recommending ASME Code Endorsement and/or .
recommendations for Regulatory Guide Endorsement with Exceptions Issue close-out memorandum TBO* - -
from Director NRR recommending Code Endorsement or Endorsement with Exceptions
- EIB is currently in the process of integrating this issue, and some other issues l related to Steam Generator Tube Rupture, into a single issue. During this inte-gration effort, EIB plans to evaluate the need for further work on Eddy-Current testing. A new schedule will be provided after reevaluation.
i i
67-2 As of 3rd Quarter FY-86 i
6
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
68 Safety / Active-L1 NRR/OSR0/RSIB S. Diab 55225 High Title ---------------- Loss of AFWS Due to AFW Steam HELB W' o rk Authorization --- Memorandum to R. J. Mattson from H. R. Denton dated April 24, 1984 Contract Title ------- None Contractor Name/ FIN -- None Wo rk Scope ----------- Assess risk due to failure of AFW turbine steam line.
Affected Documents --- Standard Review Plan Status --------------- Include assessment of the loss of all AFW due to a failure of the AFW turbine steamline into the reliability analysis to be required by GI-124.
Problem / Resolution --- None Technical Resolution - None Milestones Original Current Actual Prepare Draft TAP 12/84 -
12/84 Incorporate Comments 03/85 -
04/85 Issued reprioritization memo for comments - -
05/85 OSI comments received - -
05/11/85 Incorporated comments OSI comments - -
06/85 kssuedraftriskevaluation 05/85 - - -
Issue closecut memo based
- on results 09/85 06/86* -
Issue TAP - Approval by Director, DSRO 05/85 N/A -
Technical Resolution 01/86 N/A -
1
- Final close-out memorandum has not been issued by OSI. If reevaluation of schedule shows that close out is not feasible by June 1986, then the remaining milestone dates will be revised to reflect a new resolution date.
l 68-1 As of 3rd Quarter FY-86
. - - - - - ~ _ .-. _ . - - -
Generic Issue #68 Milestones Original Current Actual Draft NUREG/CR 03/86 N/A -
Staff review of draft NUREG/CR report 06/86 N/A -
Value/ Impact' Statement prepared (coordinated with SPEB and RRAB as applicable) 08/86 N/A -
Final report prepared by Division (include SPEB preliminary comments and SRP revision) 10/86 N/A -
Final report forwarded to DST for processing 11/86 N/A -
CRGR Package to NRR Director for Review 11/86 N/A -
OMB Clearance obtained con-currently if applicable 12/96 N/A -
t Review package te CRGR 01/87' N/A -
CRGR review and EDO approval completed 02/87 N/A -
. - Federal Register Notice of Issuance of SRP for Public Comment 03/87 N/A -
Division review of public comments completed 06/87 N/A -
Comments incorporated and transmitted to DSR0 for processing 06/87 N/A -
Final CRGR package to NRR Director for review 07/87 N/A -
Review Package to CRGR 08/87 N/A -
CRGR review and E00 approval completed 09/87 N/A -
Federal Register Notice of Issuance of SRP 10/87 N/A -
l 68-2 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type _ Level Office /Div/Br Manacer TACO No.
70 Safaty/ Active-L1 NRR/DSR0/EIB R. Kirkwood SS226 Medium Title ---------------- PORV and Block Valve Reliability Work Authorization --- Memorandum to R. Mattson from H. R. Denton dated May 14, 1984.
Contract Title ------- Estimation of Risk Reduction from Improved PORY (GI-70)
Contractor Name/ FIN BNL/A-3807 l Work Scope ----------- Identify fundamental safety requirements of the PORVs and block valves. PRAs will be used to determine core melt frequencies and risk contributed by malfunction of PORV and block valves associated with various accidents and plant protection features including SGTR events, LTOP, PORV-LOCA, RCS vents and BTP RSB 5-1. Based on the results from the PRA work, maximum risk reduction will be evaluated which will consequently identify the maximum amount of ecaey that could be spent on PORV/ block valve improvements. Potential improve-ments with the maximum amount of money that c0J1d be spent will be identified in the areas of design, equipment qualifica-tions, QA and QC, maintenance programs, technical specifica-tions, and testing requirements.
Affected Documents --- Develop new requirements for PORVs, incorporate into SRP or regulatory guide Status --------------- Task action plan was issued on April 30, 1935. A report to
, the Commission on the status of staff work was issued on
! February 18, 1986. Recently available information with respect to radiation levels, anticipated funding, and schedule changes indicate that data from disassembly of the PORY from TMI-2 would not be available for approximately 12 months. In addition, there is considerable uncertainty as to whether the PORV in its present condition (severely corroded from exposure of seven years in a high humidity, high radiation environment) would provide any conclusive evidence as to the cause of the i March 1979 failure to close. Taking these factors into account, it was concluded that the resolution of this issue should be completed without the data from the THI-2 PORV. Comments were furnished to RES on ORNL draft report, " Operating Experience Review and Analysis of Failures of Pilot-Operated Relief Valves and Block Valves in Nuclear Power Plants," dated,
- September 30, 1985. Upon resolution of staff comments, a l final version will be issued as a NUREG/CR report. Comments were also furnished on BNL draft report, " Estimation of Risk Reduction from Improved PORV Reliability in PWRs," dated September 1985. Upon resolution of staff comments and com-pletion of the remaining issues associated with this task, a l
70-1 As of 3rd Quarter FY-86 i _ .- _ _ _ _ _ _ _ _ _
Generic Issue #70 final version of the report will be issued as a NUREG/CR report.
A meeting was held on April 10, 1986 with representatives of Dresser Industries to discuss PORV problems. Meetings with other PORV manufacturers will be scheduled for the 4th Quarter FY-86.
Justification of schedule slippage The GI-70 schedule slipped because the recent NRR reorgani-zation required that higher priority work, such as, licensing actions of NTOLs be completed by those reviewers previously assigned to these actions.
Problem / Resolution --- None Technical Resolution -
Milestones Original Current Actual Draft Action Plan to Ofrector, 12/84 -
12/84 DSI Draft Action Plan approved by 01/85 -
02/85 Director, DSI and forwarded to other Division Directors for comment Incorporate comments to Action 03/85 -
03/28/85 Plan .
Final Action Plan approved by 06/84 -
04/30/85 Director, OSI and forwarded to DST Assemble background information 09/85 09/86 -
PORVs and block valves Determine fundamental safety 12/85 09/86 -
requirements of PORVs and block valves Identify the potential improve 11/85 10/86 -
ment on PORV/ block valvt.6 Report to the Commission on 07/85 -
02/18/86 status of the staff work on GI 70 Estimation of risk reduction 01/86 08/86 -
from improved PORV/ block valve reliability Identify the recommended 04/86 11/86 -
improvements based on value/ impact assessment and other safety considerations 70-2 As of 3rd Quarter FY-86
Generic Issue #70 Milestones Original Current Actual CRGR review package completed 03/86 12/86 -
Division Director approval of 04/86 01/87 -
CRGR package. Package to other division directors for comments.
Other division comments 04/86 01/87 -
incorporated.
CRGR Package to NRR Director 05/86 02/87 -
for Review OM8 Clearance obtained con 06/86 03/87 -
currently if applicable Review Package to CRGR 06/86 03/87 -
CRGR review and E00 approval 07/86 04/87 -
completed Federal Register Notice of 08/86 05/87 -
Issuance of SRP for Pubife Comment Division review of public 09/86 06/87 -
comments completed Comments incorporated and 10/86 07/87 -
transmitted to DST for processing Final CRGR package to NRR 11/86 08/87 -
Director for review Review Package to CRGR 12/86 09/87 -
CRGR review and EDO approval 01/87 10/87 -
completed Federal Register Notice of 02/87 11/87 -
Issuance of SRP 70-3 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
75 Safety / Active-L1 IE/QAVT/QA8 M. Malloy None Subtask 1 NR Title ---------------- Generic Implications of ATWS Events at the Salem Nuclear Plants - Quality Assurance Work Authorization --- Memorandum from H. Denton to R. C. DeYoung, " Schedule for Resolving and Completing Generic Issue No. 75," dated October 19, 1983.
NRR FY-84 Operating Plan, (Appendix G).
Contract Title ------- N/A Contractor Name/ FIN -- N/A Work Scope ----------- Revise Reg. Guide 1.33 " Quality Assurance Program Require-ments (Orerations)" to contain more detailed guidance for operational QA programs. The staff will consider backfitting this Reg. Guide revision. The work scope of the TMI Items I.B.1.1(6) and I.8.1.1(7) has been subsumed by this generic issue subtask. ,
Affected Documents --- ANS-3.2 (1982)
Status --------------- Due to the accumulation of significant operating events since ANS-3.2 was published, tha OIE Director decided in 10/85 that, to the maximum extent possible, the lessons learned from that operating experience, as well as inspections, be included in the revised guide. In doing so, the revised guide would be-come a "best practices" guideline for all new applicants which current licensees could chose to adopt. Further, the Director decided to issue the guide for a 60-day regional and other NRC program office review and then for public comment in order to gather the operating and inspection experience ' input. In February 1986, IE issued a package for 60-day regional and other program office review. The review request package con-tained the current version of the guide, the draft regulatory l
analysis, and the summary and resolution of interoffice com-ments obtained in 1985. The 60-day staff and region review period ended on April 11, 1986. A total of 31 comments were received from ADM, ELD, NRR, NMSS, RES, RM, the five regions, and the IE staff. The staff has resolved these comments and generated the first draft of a document which summarizes the comments and lists proposed dispositions. In general, the comments were mixed with regard to identifying the revised guide as a "best practices" document. In addition, no com-ments identified the need for significant, new regulatory 75-1 As of 3rd Quarter FY-86
Generic Issue #75 positions or the need to include a more detailed, content-oriented listing of QA record retention times. The summary and disposition of comments is being reviewed and should be finalized in late June or July 1986. In May 1986, it was decided that the analyses necessary to the development of burden estimates would be performed by IE staff personnel and that work is currently under way. The staff plans to delay scheduling a specific CRGR review date for the guide until this work has progressed satisfactorily and is closer to ccmpletion. Pending issuance of the final guide licensee requests for the QA 8 ranch licensing staff will review FSAR Chapter 17 revisions comitting to ANS-3.2-1982 on a case-by-case basis.
Problem / Resolution --- See Status above.
Technical Resolution -
Milestones Original Current Actual Issued memorandum to W. Dircks, 07/84 -
07/26/84 EDO subsuming Task Action Plan Item I.B.1.1 subtasks 6 and 7 Issued draft R.G. 1.33 for - -
02/85 division comments Prepare package for CRGR Review 09/84 -
Deleted (include backfit issue study plan)
CRGR Review completed 10/84 -
Deleted ACRS Review completed 11/84 -
Deleted Public comments on 3rd proposed 01/85 -
Deleted Rev. 3 Re-issue draft R.G.1.33 for 01/86 -
02/86 division comments Prepare package for CRGR Review 04/86 TBD -
CRGR Review completed 06/86 - -
ACRS Review completed 07/86 - -
End of 60-day public comment 09/86 - -
period Resolve comments and prepare 09/85 01/87 -
Regulatory Analysis Package for CRGR Review CRGR Review completed 10/85 03/87 -
75-2 As of 3rd Quarter FY-86
Gen:ric Issue #75 Milestones Oriainal Current Actual ACRS Review completed 12/85 04/87 -
EDO Approval 01/86 05/87 -
Issue Federal Register 02/86 07/87 -
Notice on issuance and availability of Rev. 3 to Regulatory Guide 1.33 Issue Close-out memo to - 02/86 07/87 -
Director, NRR f
4 75-3 As of 3rd Quarter FY-86
, r n - - - - -
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number h Level Office /Div/Br Manager TACS No.
77 Safety / Active-L1 NRR/DSR0/EIB D. Thatcher 52397 High Title ---------------- Flooding of Safety Equipment Compartments by Back-Flow Through Floor Drains Work Authorization --- Memorandun, to R. J. Mattson from H. R. Denton dated September 8, 1983. -
NRR FY-84 Operating Plan, (Appendix G).
Contract Title ------- None Contractor Name/ FIN -- None Work Scope ----------- This generic issue will evaluate operating plants licensed prior to issuance of the SRP for compliance with SRP Sections 9.3.3, " Equipment and Floor Drainage Systems" and 10.4.5,
" Circulating Water System" regarding flooding protection in connection with backflow through drains. The work will consist of a re-review of the previous flooding information and evalu-ations for nine (9) representative plants. The cause of the flooding will not be evaluated, but this issue will account for flooding resulting from both internal and external sources.
The need to backfit further protective measures against flooding of safety-related equipment compartments due to backflow through drainage systems will then be determined and the appropriate backfit package prepared.
Affected Documents --- Since the present SRP criteria in this area is considered to be adequate, no documents will be affected.
l S ta t u s - ----- -- ---- --- Information to conduct a re-review of previous flooding infor-l mation and evaluations for nine selected representative plants is not currently available due to the reluctance of some of the selected utilities to provide the required information.
This issue will be temporarily halted pending the final resolution of USI A-17, " Systems Interactions." The draft resolution of USI A-17 proposed to subsume this issue.
Problem / Resolution --- Information to conduct a re-review of previous flooding infor-mation and evaluations for about ten selected representative plants was requested to be provided on a voluntary basis.
Only four or five of the selected plants indicated that they would provide the requested information on a voluntary basis.
This information should be available by January or February of 1986. The remaining selected plants indicated that they would not voluntarily provide the requested information. Considera-tion is now being given to issuing a confirmatory order to 1
77-1 As of 3rd Quarter FY-86 t
Generic Issue #77 these plants to obtain the required in*armation. The addi-tional effort required to obtain the re. quested information will result in approximately a 15-month delay in the resolu-tion of this issue.
Using FSAR drawings, floor ::,d equipment drainage system draw-ings and previous reviews of flooding of safety equipment com-partments at operating plants, determine the adequacy of the previous reviews for 9 plants. Where necessary, elicit from the licensee additional information regarding the measures taken to prevent flooding of safety-reisted equipment compartments due to backflow through the drainage systems.
Technical Resolution - Since the present SRP is indicated as being acceptable, this issue involves a determination that actual features in plants are adequate to assure protection assinst flooding of safety-related compartments through the floor and equipment drains.
Licensing Divisions' assistance may be required to assist in acquiring existing information and gathering information from licensees.
Task No. Title / Milestones Starting / Completion Date
- 1. Select nine (9) plants to be included Start - October 1984 in the review effort. Complete - November 1984 .
- 2. Review information and previous evaluations Start - November 1984 for nine (9) plants in order to assess Complete - March 1985 the adequacy of existing protection provided against backflow through drains.
- 3. Determine the need for and efficacy of Start - May 1985 various corrective measures that can be Complete - August 1985 taken to detect, prevent and limit the consequences of backflow through the drainage systems.
- 4. Prepare CRGR package for backfit of any Start - August 1985 proposed modifications. Complete - August 1986 Milestones Original Current Actual Issue assigned to DSI 09/83 -
09/08/83 TAP Approved by Director, DSI 01/84 -
01/10/84 Incorporate Division Comments 09/84 -
09/09/84 Revise and Rrtissue Approval 10/84 -
10/31/84 Work Plan Task 1-Plant feiection. 10/84 -
11/84 77-2 As of 3rd Quarter FY-86
Generic Issue #77 Milestones Original Current Actual Task 2-Information review 12/84 12/86* -
Task 3-Assessment of backfit 05/85 01/87* -
Task 4-Regulatory requirements 08/85 02/87* -
development Value/ Impact Statement prepared 08/85 02/87* -
Final report prepared, CRGR 11/85 03/87* -
package approved by Director, OSRO. Sent to others for comment.
Comments from other Division 01/86 04/87* -
Directors incorporated. Package sent to Director, NRR.
Package sent to CRGR. 02/86 05/87* -
CRGR review. 03/86 06/87* -
EDO approval. FR Notice issued 03/86 06/87* -
for public comment.
Public comments incorporated. 05/86 08/87* -
OMB Clearance, if needed.
Final CRGR package to Director, 06/86 09/87* -
NRR.
Review package to CRGR. 07/86 10/87* -
CRGR review. EDO approval. 08/86 10/87* -
Regulatory requirements issued.
- It is anticipated that the balance of this work will not be completed as planned.
It has been proposed to subsume GI-77 in the resolution of USI A-17 as currently drafted. The resolution of GI-77 will be suspended pending the resolution of USI A-17.
77-3 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
79 Safety / Active-1 NRR/DSR0/EIB J. Page 52140 Medium Title ---------------- Unanalyzed Reactor Vessel Thermal Stress During Natural Convection Cooldown - PWR Work Authorization --- (1) Memorandum to R. Vollmer from H. Denton dated July 25, 1983.
(2) NRR FY-84 Operating Plan, (Appendix G).
Contract Title ------- Unanalyzed Reactor Vessel Thermal Stress Contractor Name/ FIN -- BNL/A-3822-5 Work Scope ----------- (1) PWR NSSS will provide thermal-hydraulic, heat conduction and ASME III stress analysis of the reactor vessel.
(2) RSB will verify acceptability of thermal analyses.
(3) MEB will verify acceptability of stress analyses, evaluate results, and determine resolution of the issue.
Affected Documents --- Potential SRP change and/or NUREG reports.
~
Status --------------- Contractor has been obtained to perform review.
Problem / Resolution --- By letters dated February 12 and March 7, 1986, the contractor requested additional details to complete the review of the B&W analyses (Document Nos. 32-1151155-00 and 77-1152846-00) which were provided by letter dated October 15, 1984. This request has been transmitted to the B&W Owners Group (BWOG) by letter dated March 27, 1986. Requested information included 12 references, 4 of which were not received in easily repro-ducible form. Additional hard copies have been requested from BWOG.
Technical Resolution -
Milestones Original- Current Actual Meeting with B&W to clarify 11/83 -
03/84 issue Receipt of initial B&W analyses 08/84 -
12/84 Prepare request for proposal for 06/85 -
06/85 technical assistance contract Initiate contract and commence 09/85 -
09/85 review Completion of audit calculations 05/86 07/86 -
79-1 As of 3rd Quarter FY-86
Generic Issue #79 Milestones Original Current Actual Preliminary technical evaluation 07/86 09/86 -
for staff review Final technical evaluation 03/86 10/86 -
completed Close-out memorandum issued
- 09/86 10/86 -
l l
l
- It is anticipated th'at vendor analysis will demonstrate acceptability of current i designs. The milestone schedule is based on this assumption. No changes in
- regulatory requirements will be needed providing this assumption proves valid.
l However, if new regulatory requirements are needed the Schedule will have to be expanded by 12 months.
1 79-2 As of 3rd Quarter FY-86
GENERfC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No 82 Safety / Active-L1 NRR/DSR0/RSIB E. Throm 53347 Medium Title ---------------- Beyond Design Bases Acciderats in Spent Fuel Pools Work Authorization --- Memorandum to R. J. Mattson from H. R. Denton dated December 7, 1983 NRR FY-84 Operating Plan, (Appendix G).
Contract Title ------- Study of Beyond Design Bases Accidents in Spent Fuel Pools (Generic Issue 82)
Contractor Name/ FIN -- BNL/A-3786 Work Scope ----------- Work scope approved in TAP. See memorandum from R. Mattson to T. Speis, dated February 2, 1984.
RES has verified the possibility of igniting zircaloy cladding in the event relatively fresh spent fuel is uncovered due to pool failure. The circumstances of ignition and propagation, and the consequences and likelihood of severe spent fuel pool accident will be assessed. Should the risk from such an acci-dent be judged unacceptable on a cost / benefit basis, then preventative and mitigative measures must be devised and considered.
EG&G, through INEL & RES, will perform hand calculations to assess temperature history of uncovered fuel, and the oxida-tion rate of zircaloy cladding to be expected. ASTP0 will provide an estimate of fission product release, predicated upon the earlier computations, i
If assessments indicate that risk levels provide the bases for fixes with positive cost / benefits, corrective actions are to be pursued. The range of fixes which appear technically feasible include delaying storage of fresh assemblies, or the placement of fresh assemblies only near older ones. An SER will be prepared describing safety issues and cost / benefits analysis associated with alternative fixes. If fixes are warranted, a regulatory requirements package will be prepared for CRGR review and issuance.
Affected Documents --- SRP' Sections 9.1.2, 9.1.3 and 15.7.4.
~
Status --------------- Milstones for this generic issue were revised in May 1984, based upon the results of preliminary work by RES. Assessing i
the probability of pool failure due to earthquake.
82-1 As of 3rd Quarter FY-86
Generic Issue #82 Problem / Resolution --- Delays encountered due to need fo'. broad-scale structural analysis, consideration of refueling cavity water seal failure (re: Haddam Neck) type events.
No additional funding available in FY-86 to support broad-scale structural analyses. BNL will complete original work scope and estimate the likelihood of loss of spent fuel pool integrity.
No fragility curves for spent fuel pools have been found for beyond design bases events. Zion data (NUREG/CR-3558) will be used by BNL for confidence level estimates. The probability of spent fuel pool failure will be estimated based on available fragility data for other structures. Uncertainties in the risk profile may be large.
Consideration of the refueling cavity water seal failure type event will not be addressed as part of this issue. A request for prioritization of this type of event was forwarded to SPEB/DSR0 on 04/01/86.
Technical Resolution -
Milestones Oriainal Current Actual Generic Issue 82 assigned to 12/83 -
12/07/83 DSI.
Tentative agreement reached with 01/84 -
01/23/84 RES to include under existing contractual effort, a task to determine whether zircaloy igni-tion and source term release are possible in the event of a spent fuel pool failure.
Task Action Plan approved by 02/84 -
02/02/84 Director, DSI.
Receive RES Contractors' 04/84 -
05/21/84 assessment.
RES Contractors' assessment 05/84 -
05/05/84 sent to OL, DST, DE and DSI:
CPB and DSI:ASB for review and comment.
Complete PID for inclusion of 04/84 -
06/84 technical assistance support for GI 82 in FY-85 budget.
Issue RFP 08/84 -
08/27/84 Issue tech assistance contract 09/84 -
11/84 82-2 As of 3rd Quarter FY-86
Generic Issue #82 Milestones Original Current Actual Complete Tasks 1 & 2a of tech 04/85 -
05/85 assistance contract and receive contractor preliminary assess-ment of likelihood and consa-quences of loss of pool integrity for the most vulnerable design.
Prbpare preliminary expanded 07/85 -
11/85 work scope for risk study.
Evaluate contract results. 08/85 -
11/85 Determine whether probabilities and phenomena warrant risk study. ,
Issue RFP for Structural 10/85 -
05/07/86 Evaluation and Risk Study of Spent Fuel Pools with High Seismic Vulnerability Risk Assessment of Reactor Cavity Seal Failure.
Task 1 - Initiating 07/86 07/86 -
Events / Frequencies Task 2 - Zircaloy 07/86 07/86 -
Oxidation Evaluation Task 3 - Consequences / 09/86 09/86 -
Radionuclide Inventory Task 4 - Preliminary 09/86 09/86 -
Risk Profile Task 5 - Evaluate 09/86 09/86 -
Alternatives Authorize Fragility 10/86 10/86 -
Studies Task 6 - Fragility 05/87 05/87 -
Studies l Task 7 - Value/ Impact 06/87 06/87 -
} Evaluation Draft Regulatory Analysis 07/87 07/87 -
Evaluate future Schedule 08/87 08/87 -
82-3 As of 3rd Quarter FY-86 i
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
83 Safety / Active-L1 NRR/DPL-A/PSB J. Hayes 42235 NR Title ---------------- Control Room Habitability (CRH).
Work Authorization --- Dircks letter to Denton, 8/15/83.
Contract Title ------- In-Plant Reviews on Control Room Habitability.
Contractor Name/ FIN -- ANL/A-2328 Work Scope ----------- Assess adequacy of habitability criteria, NRR review, plant systems and components, and testing procedures relative to control room habitability, including those areas of ACRS con-cern. A report will be prepared summarizing results and pro-viding recommendations.
Affected Documents --- 10 CFR 50, Appendix A, GDC 2, 3, 4, 5, 19, 60; SRP i 4, 9.4.1, 12.3, 6.5.1, 2.3, 2.2.1-2.2.3, 18, 9.5.1; RGs 1.78, 1.95, 1.29, 1.52, 1.101, 1.140; NUREG-0737, Item III.D.3.4, II.B.2, 10 CFR 50: 50.48, Appendix R to 10 CFR 50; NUREG-0700; NUREG-0737, Supplement 1.
S ta tu s -- - - ----------- A program of survey visits to a total of 12 plants was initi-ated in September 1985. Visits to 5 operating plants have been completed. Preliminary visits to 2 additional plants have been made. Survey visits will be conducted at each of these plants. Completion of visits to 12 operating plants has been delayed due to assistance being provided to Regions III and V for resolution of plant-specific problems related to control room habitability. DSRO was notified of delay in completion of survey and intends to provide assistance to PWR-A to assure timely completion of survey.
l Problem / Resolution --- The original TAP for GI 83 contained a number of subtasks for implementation of the recommendations in the June 1984 Control Room Habitability Report. Work on implementation of these l
recommendations has been halted due to management concerns over (1) lack of resources to perform independent verification of acceptability of applicants' submittals and the degree of safety gain to be achieved, (2) reluctance to devote resources to updating SRPs and pertinent reg guides in the absence of new plant orders, and (3) implementation recommendations that might be interpreted as backfitting without proper backfit analysis.
The implementation of the recommendations in the June 1984 report will be reevaluated in light of the above concerns.
Reevaluation will be performed upon completion of survey of 12 plants. A revised TAP will be prepared after the reevaluation 83-1 As of 3rd Quarter FY-86
Generic Issue #83 is complete. Upon completion of the 12 plant survey and issuance of a report on the results of the survey, DSR0 will assume responsibility for completion of this generic issue.
Technical Resolution -
Milestones Original Current Actual Workshop on CRH 11/83 -
11/30/83 Award of Contract 02/84 -
01/26/84 Visit to Initial Plant 03/84 -
05/02/84 Report on CRH criteria to Director, NRR - -
06/01/84 Completion of contractor - -
08/23/84 visits to operating and NTOL plants Statement of Work written 11/84 -
10/29/84 for 12 plant survey and generic studies Request for proposal sent 12/84 -
11/15/84 to potential contractor (s)
Receipt of proposal (s) 02/85 -
03/04/85 Initiate program to visit 09/85 -
09/85 12 additional Operating Plants
! Complete visit to 12 09/86 12/86 -
operating reactors Report (NUREG/CR) 01/87 03/87 -
DSR0 to Revise TAP based on 03/87 05/87 -
reevaluation and provide milestones necessary to resolve issues including initiation of work on j generic studies l
i 83-2 As of 3rd Quarter FY-86 l
I
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
84 Safety / Inactive-L1 NRR/DSR0/RSIB S. Diab TBP NR Title ---------~------ CE PORVs Work Authorization --- Memorandum to R. M. Bernero from H. R. Denton dated February 27, 1985.
Contract Title ------- ,N/A Contractor Name/ FIN -- N/A Work Scope ----------- To be provided.
Affected Documents --- To be provided.
Status --------------- Awaiting final resolution of USI A-45 with respect to PORV requirements.
Problem / Resolution --- To be provided.
Technical Resolution - To be.provided.
Milestones Original Current Actual Schedule to be developed following the completion of USI A-45 aork.
84-1 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
86 Safety / Active-L1 NRR/ DBL /EB W. Hazelton 07419 NR T i tl e ----- ----------- Long Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping Work Authorization --- Memorandum to R. H. Vollmer from H. R. Denton dated October 3, 1984 Contract Title ------- None Contractor Name/ FIN -- None Work Scope ----------- Long Range Plan for dealing with pipe cracking is contained in SECY-84-301, July 1984:
(1) Issue NUREG-1061, Vol. 1 for comment (2) Issue NUREG-0313, Rev. 2 (3) Issue generic letter incorporating NUREG-0313, Rev. 2 (4) ?ursue ASME Code changes Affected Documents --- NUREG-0313, Rev. 1 Status --------------- Draft NUREG-0313, Revision 2 and proposed implementing Generic Letter has been issued.for public comment. ASME Code changes desired by the staff have been made.
Problem / Resolution --- Primary reasons for schedule slippage were associated with NRR Director review, resolution of concerns regarding the new backfit rule, and resolution of CRGR comments and suggestions, primarily on the content of the proposed Generic Letter.
These problems have all been resolved and the package has been issued for public comments. No further schedule slippage is anticipated, although the scheduling has been changed by one month to accommodate a 60-day comment period instead of the 30 days originally provided for in the schedule.
I Technical Resolution -
Milestones Original Current Actual SECY 84-301, NUREG-1061 07/84 -
07/30/84 i to Commission Publish NUREG-1061, Vol.'I 09/84 -
09/20/84 End of Comment Period 11/84 -
11/7/84 l
Complete preparation of Draft 01/85 -
09/85
, NUREG-0313, Rev. 2 I
86-1 As of 3rd Quarter FY-86
, , . , . ~ , - - . - . . . . - - - _ _ _ _ . _ . _ . _ _ _ _ _ _ . , . . - - - - _ - . - - , - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ . _ - - _ _
Genaric Issua #86 Milestones Original Current Actual Proposed Generic Letter 09/85 -
02/85 and staff position in Draft NUREG-0313, Rev. 2, circulated for NRR Div. Dir. review Proposed Generic Letter 10/85 -
04/86 and staff position in Draft NUREG-0313, Rev. 2, reviewed and endorsed by CRGR.
Draft NUREG-0313, Rev. 2, and 11/85 -
06/86 Generic Letter issued for public comment.
Draft NUREG-0313, Rev. 2, 02/86 09/86 -
revised to reflect public comments.
Commission Paper on staff 03/86 10/86 -
implementation plan and staff position (NUREG-0313, Rev. 2) reviewed and endorsed by CRGR.
Commission Paper on staff 04/86 12/86 -
implementation plan and staff position (NUREG-0313, Rev. 2) submitted for approval.
Issue Generic Letter and 05/86 01/87 -
close-out memorandum l
l l
i i
l l
86-2 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Tyge. Level Office /Div/Br Manager TACS No. !
l 87 Safety /High Active-L1 NRR/DSR0/RSIB H. Woods 60058 Title --------------- Failure of HPCI Steam Line Without Isolation Wo r k -- - - - - - - - - - - -- - - Memorandum to R. Bernero from H. R. Denton dated September 26, 1985 Contract Title ------
None. May incorporate certain subtasks of RES-sponsored
" Mechanical Equipment Qualification Research Program,"
A-6322.
Contractor Name/ FIN -- None work Scope ---------- Determine types / sizes /models of valves involved on HPCI, RCIC, RWCU (and any other) system where valves might not be qualified to close in the event of a downstream break and would cause an unacceptable high risk of core-melt if break not isolated (due to inventory loss and/or other safety-related equipment exposed to environment beyond its qualification).
Affected Documents -- To Be Provided Later Status -------------- " Licensing Need" letter sent March 11, 1986 to R. Minogue from H. Denton, RES is providing help regarding identifi-cation of valves / operators in the HPCI and RCIC system.
Effort is being coordinated with IEB 85-03 and Generic Issue II.E.6.1.
l Problem / Resolution -- No resources assigned to task. Assigned Task Manager has unexpectedly found large part of his time still required on another (largely completed) assignment, Pressurized Thermal Shock, and has been unable to spend the scheduled amount of time on this task to date.
Technical Resolution -
Milestones Oriainal Current Actual Send Licensing Need Letter 03/86 -
3/11/86 to RES Receive Reply 04/86 - -
Develop TAP to accomplish 06/86 08/86 -
above work scope Perform tasks in TAP To be provided - -
after 8/86 S7-1 As of 3rd Quarter FY-86 l
i
--rw -
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Ty;te Level Office /Div/Br Manager TACS No 91 Safety / Active-L1 NRR/ORAS/BWR E. Murphy TBP NR Title ---------------- Main Crankshaft Failures in Transamerica DeLaval Emergency Diesel Generators Work Authorization --- Memorandum to R. Bernero from H. Denton dated July 8, 1985
, Contract Title ------- Ascessment of Diesel Generator Operability / Reliability l
Contractor Name/ FIN -- PNL/B-2952, B-2963 Work Scope ----------- Resclve concerns relating to the reliability / operability of TDI diesel engines for nuclear services Affected Documents --- Staff will issue generic SER identifying an acceptable technical resolutian of the TDI engine issue.
Status --------------- PNL has documented its findings in the following reports:
(1) PNL-5600, " Review of Resolution of Known Problems in Engine Components for Transamerica Dalaval Inc. Emergency Diesel Generators," December 1985.
(2) PNL-5336, " Review of Design Review and Quality Revalidation Report for the Transamerica Delaval Diesel Generators at Shoreham Nuclea- Power Station Unit 1," October 1985.
(3) PNL-5444, " Review of Design Review and Quality Revalidation Report for the Transamerica Delaval Diesel Generators at Comanche Peak Steam Electric Station Unit 1," October 1985.
(4) PNL-5718, " Review of Transamerica Delaval Inc. Diesel Generator Owners Group Engine Requalification Program -
Final Report," December 1985.
The staff has prepared a draft SER incorporating the PNL reports. This draft SER is being reviewed by the staff.
Problem / Resolution --- None Technical Resolution -
Milestones Original Current Actual
, Contractor Review Complete - -
12/85 Prepare draft SER - -
03/13/86 Issue final SER 04/86 04/86 -
91-1 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
93 Safety / Active-L1 NRR/DSR0/RSIB A. Spano 56291 High -
Title ---------------- Steam Binding of Auxiliary Feedwater Pumps Work Authorization --- Memorandum to R. Bernero from H. Denton dated October 19, 1984.
Contract Title ------- None Contractor Name/ FIN -- None Work Scope ----------- Generic preventive maintenance or monitoring measures may have to be implemented at all PWRs to reduce the potential for backleakage of steam and hot water to the Auxiliary Feedwater (AFW) system from the steam conversion system via isolation valves in the AFW system. It is expected that these measures will reduce the likelihood of steam binding of the AFW pump (s) and possible common mode failure of the AFW system by ensuring that the valves perform their intended function.
Development of Guidelines: Solicit recommendations from interested interagency staff such as resident inspectors, ORAS staff, Engineering and Plant Systems staff in the Divisions of PWR licensing, etc. for resolving the identi-fied concerns. Develop guidelines based on the above recommendations, summary of reported backleakage events into the AFW system, findings and recommendations given in the AE00 study, recommendations given in the INPO SOER, and recommendations and corrective actions identified in IE Bulletin 85-01.
Evaluation of Plant-Specific Responses: Using the guide-lines from above, evaluate plant-specific information obtained from IE Temporary Instruction 2515/67 and IE Bulletin 85-01 concerning actions taken by individual licensees relating to preventive maintenance measures, surveillance programs for monitoring the AFW system fluid conditions, and performance of corrective operator actions when needed.
Development of Plant-Specific Requirements: Based on the above plantspecific review, develop additional and/or alternative generic or plant specific modifications, pro-cedures, and revisions to plant TS as necessary. Addi-tionally, develop interim measures as necessary to be adopted for the applicable plants until the proposed back-fits are completed.
93-1 As of 3rd Quarter FY-86
Generic Issue #93 Affected Documents --- Standard Technical Specifications (STS) change for NSSS vendors. SRP Section 10.4.9 acceptance criteria relating to the AFW system is considered to be adequate and may not need any revision.
Status --------------- Some staff and industry effort relating to the potential problem of steam binding of the AFW pumps has already been completed. Previous work on this problem is detailed in the work plan.
Comments on the draft TAP have been received. IE issued Bulletin 85-01 on October 29, 1985. The Bulletin requires all PWR cps and 28 operating PWRs to develop procedures for: (1) a simple means of monitoring the AFW system temperature regularly such as touching the applicable pipe during each shift to ensure that the fluid temperature at the AFW pump discharge is maintained at about ambient temperature, and (2) recognizing steam binding and restoring the system to OPERABLE status, should steam binding occur. IE has concluded that the 30 remaining operating PWR facilities do not pose a serious safety problem requiring short-term corrective actions, as iden-tified in the Bulletin.
Problem / Resolution --- Evaluation of plant-specific information for adequacy of procedures will not be completed until April 1986. Mile-stone dates for technical resolution have slipped 3 months.
Technical Resolution -
Milestones Original Current Actual Issue assigned to DSI 10/84 10/19/84 Prepare Draft TAP 12/84 12/84 Draft TAP approved by DSI 12/84 01/22/85 Director Incorporate comments by 02/85 -
06/85 various Divisions Revise and reissue approved TAP 07/85 -
06/25/85 Development of guidelines for 10/85 -
05/86 resolving the identified concerns relating to this generic issue Evaluation of plant-specific 01/86 07/86 information for adequacy of procedures and actions dealing with this concern using the guide-lines developed.
l 93-2 As of 3rd Quarter FY-86
Generic Issue #93 Milestones Oriainal Current Actual Generic or plant-specific 04/86 09/86 -
preventive maintenance measures, surveillance requirements and corrective actions including cost-effective backfits and TS revisions when needed determined based on evaluation of plant-specific information.
Regulatory Requirements 02/86 09/86 -
Development Value/ Impact Statement prepared 05/86 10/86 -
Final report prepared, CRGR 07/86 12/86 -
package approved by Director, DSRO. Sent to NRR Divisions and others for comment Comments from other Division 09/86 02/87 -
Directors incorporated. Package sent to Director, NRR Package sent to CRGR 10/86 02/87
. CRGR review and EDO approval 11/86 03/87 -
completed Federal Register Notice of 12/86 04/87 -
issuance of regulatory require-ments for PWRs in this regard for public comments Public comments incorporated. 02/87 06/87 -
OMB clearance, if needed Final CRGR package to Director, 03/87 07/87 -
NRR l
Review package to CRGR 04/87 07/87 CRGD review and EDO approval 05/87 08/87 -
completed.
I sue regulatory requirements 06/87 09/87 -
fcr PWRs (generic letter if required).
93-3 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number M Level Office /Div/Br Manager TACS No.
94 Safety / Active-L1 NRR/DSRO. GIB E. Throm 59465 High Title ---------------- Additional Low Temperature Overpressure Protection For Light Water Reactors Work Authorization --- Memorandum to R. Bernero from H. Denton dated July 23, 1985.
Contract Title ------- Low Temperature Overpressure Protection Systems Evaluation for Pressurized Water Reactors.
Contractor Name/ FIN -- PNL/B-2998 Work Scope ----------- Evaluate current operating data, applying STS to all systems, updating LTOP set points to current Appendix G curves, prohibiting operation with either LTOP train out of service or HPI pump in service while water solid, lim-iting start of the reactor coolant pump, using RHR relief valves, requiring the LTOP to be " safety grade" and value/
impact of these alternatives.
Affected Documents --- SRP 5.2.2, BTP RSB 5-2, STS Status -------------- . The TAP and RFP have been drafted.
Problem / Resolution --- T/A funds deleted from budget. Work scope, resources, schedule need to be reassessed.
Technical Resolution -
Milestones Original Current Actual _
Generic Issue #94 assigned - -
7/23/85 to RSB/DSI/NRR Draft of TAP Completed 11/85 -
5/08/86 Final TAP approved 02/86 05/86 -
by Director, DSRO Model TS developed 03/86 N/A -
Received results of PRA 03/86 N/A -
analyses for Generic Issue #99 Draft report completed 04/86 TBD -
CRGR package prepared 05/86 TBD -
94-1 As of 3rd Quarter FY-86.
GGneric Issue #94 Milestones Original Current Actual CRGR package approved by 06/86 TBD -
Director, DSRO and sent to other Divisions for comment Package sent to CRGR 07/86 TBD -
Issue close-out memorandum 10/86 TBD -
from Director, NRR to Licensing Divisions (Generic
' Letter to Licensees and changes to BTP RSB 5-2) i t
i 94-2 As of 3rd Quarter FY-86
, +.--r-r- -, -----. -
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM l
Issue Issue Action Task Number Typ_e Level Office /Div/Br Manaaer TACS No.
99 Safety / Active-L1 NRR/DSR0/RSIB A. Spano 59653 1 High l
Title ---------------- RCS/RHR Suction Line Interlocks on PWRs Work Authorization --- Memorandum to R. Bernero from H. Denton dated August 13, 1985.
Contract Title ------- RHR System Operability and Interlocks Contractor Name/ FIN -- None Work Scope ----------- Operating experience shows that a change in the auto-closure feature on the valves that isolate the inlets of the RHR System from the RCS is needed to prevent losses of residual heat removal. The autoclosure feature on these valves was designed to provide the double, high pressure boundary that is needed for the RCS to conform to GDC 14 of 10 CFR 50, Appendix A.
The scope of this task is to find the best way to change the autoclosure feature to reduce the losses of RHR with-out increasing the risk of failure of the RCS boundary.
Technical Resolution-- PRAs will be perfcrmed for the following:
(1) The present autoclosure interlock system.
(2) The present autoclosure system with various modifications to the administrative controls.
(3) Removal of the autoclosure interlocks.
(4) Installation of RHR pump low-suction trip devices.
(5) A rewiring of the control switches so that pressing a single switch closes both of the two in-series motor-operated valves.
(6) Various combinations of the preceding items.
l The effects of making these modifications will be compared.
An optimum modification will be selected and a cost-benefit analysis performed.
Affected Documents --- None l Status --------------- (See Milestones)
Problem Resolution --- A contract will be negotiated to provide PRAs for various alternatives to the present autoclosure interlocks between the RHR and RCS systems. The results of these PRAs will be used to find the best method for reducing RHR system failures without increasing the risk due to an intersystem LOCA. Initiation of work on this issue has been delayed due to the transfer of review responsibilities resulting from the NRR reorganization.
99-1 As of 3rd Quarter FY-86
Generic Issue #99 Technical Resolution -
Milestones Original Current Actual Generic Issue #99 assigned to RSB/DSI/NRR - -
08/13/85 Preliminary discussion of 02/86 -
04/86 work plan with BNL Draft BNL work plan 03/86 -
05/86 Final BNL work plan approved 04/86 -
05/86 Issue contract to 8NL '
05/86 -
06/09/86 Based on INPO, EPRI, AE00 08/86 08/86 -
and others staff recommendations develop guidelines for resolution of identified concerns.
Regulatory requirements 09/86 09/86 -
development Prepare initial phase of 09/86 09/86 -
Regulatory Analysis (Statement of Problem, Proposed Licensee Actions and Alternatives).
Final report from BNL 02/87 04/87 -
Final report prepared, CRGR 04/87 06/87 -
package approved by Director, DSR0, and sent to other divisions for comment ,
Comments from other Division 05/87 07/87 -
Directors incorporated.
Package sent to Director, NRR Package sent to CRGR 06/87 08/87 -
Issue close-out memorandum 08/87 10/87 -
i 99-2 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
101 Safety / Active-L1 NRR/DSR0/RSIB J. Joyce 57749 High Title ---------------- BWR Water Level Redundancy Work Authorization --- Memorandum to R. Bernero from H. Denton dated May 6, 1985.
Contract Title ------- BWR Water Level Redundancy Contractor Name/ FIN -- INEL/D-6020 Work Scope ----------- Perform a detailed survey of all BWR plants to determine types of water level instrumentation. Compile failure data of instrument piping leaks / break and instrument failures for all BWR plants from LERs. Perform simplified risk analyses postulating instrument piping leaks, single failure in instruments and feed water control system failure to determine which BWR plants would have problem with existing water level instrumentation. Make recommen-dations to resolve this issue.
Affected Documents --- To Be Provided Later Status --------------- INEL proposal for technical assistance on this project was accepted on 11/29/85 and work began on March 1, 1986.
Problem / Resolution --- INEL is in the process of evaluating plant-specific data.
The contractor's report will not be completed until March 1987.
Technical Resolution -
Milestones Original Current Actual Generic Issue 101 assigned to - -
05/06/85 R$B/DSI/NRR Preliminary Discussion of our - -
05/24/85 work plan with INEL INEL will provide preliminary 06/85 -
06/11/85 cost estimate of work plan Develop work plan and contract 06/85 -
07/26/85 proposal Draft work plant to Director, 06/85 -
08/01/85 DSI Incorporate Comments to work 09/85 -
10/15/85 plan 101-1 As of 3rd Quarter FY-86
Genoric Issue #101 Milestones Original Current Actual Final work plan approved by 09/85 -
10/15/85 Director, DSI and forwarded to DST Issue contract to INEL 10/85 -
11/29/85 Assemble plant-specific 07/86 07/86 -
instrumentation informaiton Categorize all BWRs into J8/86 08/86 --
groups Single Failure Analysis 09/86 09/86 -
Probabilistic Risk Assessment 10/86 10/86 -
Value/ Impact Analysis 12/86 12/86 -
Draft report from INEL to NRR 01/87 01/87 -
Final report from INEL to NRR 03/86 03/87 -
~
Final report prepared, CRGR 05/86 05/87 -
package approved by Director, DSRO. Sent to other Divisions for comment Comments from other Division 06/86 06/87 -
Directors incorporated. Package sent to Director, NRR Package sent to CRGR 07/86 07/87 -
Issue close-out memorandum from 09/86 09/87 -
Director, NRR to DBL (Generic Letter to BWR Licensees) 101-2 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
103 Safety / Active-L1 NRR/DSR0/EIB L. Heller T8P NR Title ---------------- Design for Probable Maximum Precipitation Work Authorization --- Memorandum to J. P. Knight from H. R. Denton dated September 4, 1985 Contract Title ------- To Be Determined Contractor Name/ FIN -- To Be Determined Work Scope ----------- Revise SRP Sections 2.4.2 and 2.4.3 incorporating the most recent National Weather Service procedures for determina-tion of Probable Maximum Precipitation (PMP). Prepare regulatory analysis (value/ impact) for use of most recent PMP determination. Prepare a package for review by CRGR.
Develop recommendations regarding backfit application of the most recent PMP determinations. Obtain necessary review and approvals, then publish Revision 3 of SRP Sections 2.4.2 and 2.4.3.
Affected Documents --- SRP Sections 2.4.2 and 2.4.3 Status --------------- Draft SRP revisions issued for division comments Problem / Resolution --- Immediately following the NRR reorganization, a three-month delay due to task manager assignment to higher priority work was incurred. During the 2nd quarter of FY86, an additional 2-month delay was incurred due to administrative problems in transferring the draft CRGR package to the new task manager.
Technical Resolution -
l Milestones Oriainal Current Actual Identification of Potential - -
05/08/84 Generic Requirement Concerning Design for PHP/ Memorandum V. Stello to H. R. Denton Prepare draft revisions of - -
07/85 SRP Sections 2.4.2 and 2.4.3 CRGR package sent DST, DL, DSI, - -
07/12/85 and PPAS for Division Review CRGR package reviewed by - -
08/22/85 Divisions DST comments on CRGR package - -
09/13/85 103-1 ,
As of 3rd Quarter FY-86
Generic Issue #103 Milestones Original Current Actual Revised CRGR package based on - -
10/85 comments -
CRGR package reviewed and 11/85 09/86 -
approved by Director, NRR CRGR review and approval 12/85 10/86 -
Milestones on Backfit Issue 12/85 10/86 -
to be provided Federal Register Notice of 01/86 11/86 -
Issuance of Rev. 3 to SRP
^
Sections 2.4.2 and 2.4.3 for -
public comment.
CRGR package revised incorpo 04/86 02/87 -
rating public comment Revised CRGR package reviewed 05/86 03/87 -
and approved by CRGR Federal Register Notice Issuing 07/86 04/87 -
Rev. 3 to SRP Sections 2.4.2 and 2.4.3 103-2 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Tyge Level Office /Div/Br Manager TACS No.
105 Safety / Active-L1 NRR/DSR0/RSIB H. Woods 57979 High Title ---------------- Interfacing Systems LOCA.
Work Authorization --- Memorandum for R. Bernero from H. Denton dated June 11, 1985 Contract Title ------- Interfacing Systems LOCA.
Contractor Name/ FIN -- BNL/A-3829a Wo rk Scope ----------- Perform a detailed PRA for 3 BWR and 3 PWR plants to determine core-melt frequencies and risk contributed by interfacing systems LOCA. Develop new licensing criteria if necessary for the generic resolution.
Affected Documents --- To Be Provided Later S ta t u s ---- -- -- --- - --- BNL proposal for technical assistance on this project was accepted on December 2, 1985, and modified on Jan. 24, 1986. The work is underway and on schedule.
Problem / Resolution --- The BNL contract has been modified to include a more complete PRA and an analysis of 3 PWRs, in addition to 3 BWRs.
' The schedule has been extended to recognize the time that will be needed to include the 3 PWRs and to develop any new licensing requirements that may be indicated or neces-sary by the BNL PRA reports.
Technical Resolution -
Milestones Original Current Actual Generic Issue 105 assigned to - -
06/11/85 RSB/DSI/NRR Preliminary Discussion of our - -
06/17/85 work plan with BNL BNLs preliminary cost estimate 09/85 -
08/85 of work plan Develop work plan and contract 09/85 -
08/85 proposal Draft work plan to Directors, 09/85 -
08/21/85 DSI, DE, DL, DHFS, and AEOD Incorporate Comments into 10/85 -
10/85 work plan 105-1 As of 3rd Quarter FY-86 g- ,
. . . . . ,m, -.s u
Generic Tssue #105 Milestones Original Current Actual Final work plan approved by 10/85 -
11/18/85 Director, DSI and forwarded to DST Issue contract to SNL 10/85 -
12/02/85 Modify contract - -
01/86 Expand contract to include PWRs 03/86 -
03/86 Final report from BNL to NRR 07/86 12/86 -
including Value/ Impact Analysis Final report prepared, CRGR 12/86 05/87 -
package approved by Director, DSRO. Sent to other Divisions for comment Comments from other Division 01/87 07/87 -
Directors incorporated. Package sent to Director, NRR ,
Package sent to CRGR 02/87 08/87 -
Issue close-out memorandum 07/87 04/88 -
from Director, NRR to Licensing Divisions (Generic Letter to Licensees or SRP Changes, etc.)
105-2 As of 3rd Quarter FY-85
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
~
119.1 Regulatory Active-L1 RES/DET/MSEB J. A. O'Brien None l Impact /NR Title ---------------- Pipe Rupture Requirements and Decoupling of Seismic and LOCA Loads.
Work Authorization --- Memorandum to R. Minogue from H. Denton dated September 10, 1985 Contract Title ------- Load Combinations Contractor Name/ FIN -- LLNL/A-0133 Wo r k S c op e ----------- Prepare regulatory analysis associated with proposed SRP revisions.
Affected Documents --- (1) 10 CFR 50, Appendix A, Criterion 4.
(2) SRP Section 3.6.2 Status --------------- Required research has been completed; Federal Register Notice of Final Limited Scope Rule published; draft revisions of SRP section3has been prepared by RES and approved by NRR.
Problem / Resolution --- Work on CRP Section 3.9.3 was suspended. Revising SRP Section 3.9.3 without revising SRP Sections 3.8.1 through 3.8.4 would introduce an inconsistency into the SRP that would require rulemaking. RES recommends that deviation in SRP Section 3.9.3 continue to be used and that rulemaking to revise GDC-2 be initiated in parallel.
Milestones Original Current Actual Revise GDC-4 EDO Approval to Begin Rulemaking- - -
12/84 Federal Register Notice of - -
, 07/85 Proposed Limited Scope Rule Federal Register Notice of 04/86 07/86 -
Proposed Broad Scope Rule Federal Register Notice of Final Limited Scope Rule 04/86 -
04/85 Federal Register Notice of 02/87 02/87 -
l Final Broad Scope Rule l
119-1 As of 3rd Quarter FY-86
Generic Issue #119.1 Milestones Original Current Actual Revise SRP 3.6.2 Piping Review Committee final - -
05/85 report containing recommendations for decoupling LOCA and SSE and arbitrary intermediate pipe breaks issued to the EDO.
SRP revision and regulatory 04/86 -
04/86 analysis complete CRGR package to Division 05/86 -
05/86 Directors for review Division Director review 06/86 06/86 -
complete Comments resolved, CRGR 07/86 07/86 -
package to NRR Office Director for review HRR Office Director review 08/86 08/86 -
complete, package sent to CRGR _
CRGR review complete, package 10/86 10/86 -
sent to ACRS ACRS review complete 12/86 12/86 -
EDO approval 01/87 01/87 -
Federal Register Notice 01/87 01/87 -
issued for public comment Public comments resolved, 05/87 05/87 -
final CRGR package to Division Directors for review Division Directors review 06/87 06/87 -
complete Comments resolved, final CRGR 07/87 07/87 -
package to NRR Office Director for review NRR Of# ice Director review 08/87 08/87 -
complete package sent to CRGR
, CRGR review complete, package 10/87 10/87 -
sent to ACRS l
119-2 As of 3rd Quarter FY-86
Generic Issue #119.1 Milestones Original Current Actual ACRS review complete 12/87 12/87 -
EDO approval 12/87 12/87 -
Federal Register Notice of 01/88 01/88 -
, Issuance of SRP 119-3 As of 3rd Quarter FY-86
G;neric Issue #119.1 l
l THIS PAGE LEFT BLANK INTENTIONALLY 119-4 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number h Level Office /Div/Br Manager TACS No.
119.2 Regulatery Active-L1 RES/DET/MSEB D. Guzy None Impact /NR Title ---------------- Pipe Damping Values Work Authorization --- Memorandum to R. Minogue from H. Denton dated September 10, 1985 u Contract Title ------- 1. Pipe Damping
- 2. Pipe Damping for Time-History Analysis
- 3. Pipe Design Criteria for Nonseismic Loads Contractor Name/ FIN -- 1. INEL/A-6316
- 2. Undesignated
- 3. Undesignated Work Scope ----------- 1. Collect Data and conduct expert ents to obtain pipe damping values.
- 2. Provide basis for pipe damping criteria used in time-history analysis.
- 3. Develop pipe design criteria for nonseismic dynamic loads.
Affected Documents --- (1) Regulatory Guides 1.84 and 1.61.
(2) SRP Section 3.9.2.
Status --------------- Revision 24 to Regulatory Guide 1.84, endorsing ASME Code Case N-411 (PVRC recommended damping values) is underway.
Problem / Resolution --- None Milestones Original Current ActJal Revise Regulatory Guide 1.84 .
Issue Rev. 24 of Regulatory 05/86 06/86 -
Guide 1.84, endorsing ASME Code Case N-411 Revise Regulatory Guide 1.61 and SRP Section 3.9.2 Establish initial NRC positions 10/87 10/86 -
on non-seismic and time-history pipe damping Develop schedule to revise 11/87 11/86 -
Regulatory Guide 1.61 and SRP Section 3.9.2 119-5 As of 3rd Quarter FY-86
Generic Issu2 #119.2 THIS PAGE LEFT BLANK INTENTIONALLY 119-6 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
119.3 Regulatory Active-L1 RES/ORPES/ESB A. Murphy None Impact /NR Title ---------------- Decoupling OBE from SSE Work Authorization --- Memorandum to R.' Minogue from H. Denton dated September 10, 1985 Contract Title ------- To Be Determined Contractor Name/ FIN -- To Be Determined Work Scope ----------- To Be Provided Later Affected Documents --- 10 CFR 100, Appendix A, a list of other documents to be provided later Status --------------- Rulemaking to start in 1988.
Problem / Resolution --- None Technical Resolution -
Milestones To be provided later.
119-7 As of 3rd Quarter FY-86 1
- - - - - - - - - - - - - - - - . - , - , - - , - - w -,,. ,, - -~,o ------,y-
THIS PAGE LEFT BLANK INTENTIONALLY l
1 t
119-8 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
119.4 Regulatory Active-L1 RES/DET/MEBR A. Taboada None Impact /NR Title ---------------- BWR Piping Materials Work Authorization --- Memorandum to R. Minogue from H. Denton dated September 10, 1985 Contract Title ------- Environmentally Assisted Cracking in LWRs Contractor Name/ FIN -- ANL/A-2212 Work Scope ----------- Determine the acceptability of proposed fixes to mitigate intergranular stress corrosion cracking (IGSCC).
Affected Documents --- Regulatory Guide 1.44 and NUREG-0313, " Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping."
Status --------------- NUREG-0313 is in the process of being revised by NRR. .
Problem / Resolution --- Note that NUREG-0313 revision is controlled by NRR and not RES.
Milestones Original Current Actual Revise NUREG-0313 SECY-84-301 to Commission 07/30/84 -
07/30/84 Publish NUREG-1061 Vol. 1 09/84 -
09/84 i Publish NUREG-1061 Vol. 5 04/85 -
04/85 Complete draft of NUREG-0313 09/85 -
09/95 Rev. 2 Office Review 01/86 -
01/86 l s l CRGR Review 03/86 -
04/86 Issued for Public Comment 04/86 -
06/86 Revision of Draft to Reflect 07/86 09/86 -
Public Comments CRGR Review 09/86 11/86 -
l , Commission Paper for Approval 12/86 02/87 - -
t i
119-9 As of 3rd Quarter FY-86 i
GCneric Issue #119.4 Milestones Original Current Actual Generic Letter issued 04/87 02/87 -
Revise Regulatory Guide 1.44 Rescind Regulatory Guide 1.44 12/87 10/87 -
119-10 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
119.5 Regulatory Active-L1 RES/DET/ME3R A. Taboada None Impact /NR Title ---------------- Leak Detection Requirements Work Authorization --- Memorandum to R. Minogue from H. Denton dated September 10, 1985 Contract Title ------- Leak detection /IPIRG.
Contractor Name/ FIN -- ANL/A-2250 and BCL/D-1658 Work Scope ----------- Survey existing operating plant practices and current advanced methods to determine the adequacy of leak detection systems.
Affected Documents --- (1) Regulatory Guide 1.45 (2) SRP Section 5.2.5 (3) NUREG-0313, " Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping."
S ta t u s --------------- NUREG-0313 is in the process of being revised by NRR.
Problem / Resolution --- Research project on leak detection started in FY86 but drastically reduced due to budget cuts (Gramm/Rudman). Report will be completed in FY86 only on limited assessment of current practice in plants. Funding for any continued effort needs to be reevaluated.
l Milestones Original Current Actual Revise NUREG-0313 SECY-84-301 to Commission 07/30/84 -
07/30/84 Publish NUREG-1061 Vol.1 09/84 -
09/84 Publish NUREG-1061 Vol. 5 04/85 -
04/85 Complete draft of NUREG-0313 09/85 -
09/95 Rev. 2 Office Revies 01/86 -
01/86 CRGR Review 03/86 -
04/86 l
Issued for Public Comment 04/86 -
06/86 119-11 As of 3rd Quarter FY-86
Generic Issu) #119.5 Milestones Original Current Actual Revision of Draft to Reflect 07/86 09/86 -
Public Comments CRGR Review 09/86 11/86 -
Commission Paper for Approval 12/86 02/87 -
Generic Letter issued 04/87 02/87 -
Revise Regulatory Guide 1.45 Develop Schedule 01/88 11/87 -
Revise SRP Section 5.2.5 Develop Schedule 01/88 11/87 -
i
)
119-12 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
121 Safety / Active-L1 RES/DRA0/RAMRB M. R. Fleishman None High Title ---------------- Hydrogen Control for Large, Dry PWR Containments Work Authorization --- Memorandum to F. Gillespie from T. Speis dated September 26, 1985 Contract Title ------- None Contractor Name/ FIN -- None Work Scope ----------- Establish a technical position on the need for hydrogen control for LWRs with large, dry containments and make recommendations to the Commission regarding ruleeaking.
Affected Documents --- Possible new amendments to 10 CFR Part 50.44 S ta t u s -- - ------------ At the Commission meeting on December 10, 1984 and in SECY-83-357B, the staff indicated that recommendations for rulemaking related to LWRs with large, dry contair.ments would be provided at the conclusion of ongoing research in mid-1986. Work has been proceeding and staff meetings were held in November 1985 to review the progress. Current indications are that the various research tasks will be completed during the first half of calendar year 1986. It is expected that a recommendation can be made to the Commission during the mid-1986 time period.
Problem / Resolution ---
Technical Resolution -
Milestones Original Current Actual Research Complete 06/86 - -
Transmit Recommendations 08/86 - -
Issue Closeout Memorandum 09/86 - -
l to NRR or Provide Milestone Necessary to Implement Recommendations 121-1 As of 3rd Quarter FY-86
THIS PAGE LEFT BLANX INTENTIONALLY l
l l
1 f
i 122-2 As of 3rd Quarter FY-86 1
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
122.1.a Safety / Active-L1 NRR/DSR0/RSIB S. Diab 61730 High Title ---------------- Common Mode Failure of Isolation Valves in Closed position.
Work Authorization --- Memorandum for T. Speis and W. Russell from H. Denton dated January 28, 1986.
Contract Title ------- To Be Determined Contractor Name/ FIN -- To Be Determined Work Scope ----------- See GI-124 Affected Documents --- To Be Determined Status --------------- See GI-124 Problem / Resolution --- See GI-124 Technical Resolution - See GI-124 Milestones Oriainal Current Actual 122-1 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Tyge Level Office /Div/Br Manager TACS No.
122.1.b Safety / Active-L1 NRR/DSR0/RSIB S. Diab 61731 High Title ---------------- Recovery of Auxiliary Feedwater Wo rk Authorization --- Memorandum for T. Spets and W. Russell from H. Denton dated January 28, 1986.
Contract Ti tle ------- To Be Determined Contractor Name/ FIN -- To Be Determined Work Scope ----------- See GI-124 Affected Documents --- To Be Determined Status -------------"- See GI-124 Problem / Resolution --- See GI-124 Technical Resolution - See GI-124 Milestones Oriainal Current Actual 9
122-3 As of 3rd Quarter FY-86
THIS PAGE LEFT BLANK INTENTIONALLY l
122-4 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Tyge Level Office /Div/Br Manager TACS No.
122.1.c Safety / Active-L1 NRR/DSR0/RSIB 5. Diab 61732 High Title ---------------- Interruption of Auxiliary Feedwater Flow Work Authorization --- Memorandum for T. Speis and W. Russell from H. Denton dated January 28, 1986.
Contract Title ------- To Be Determined Contractor Name/ FIN -- To Be Determined Work Scope ----------- See GI-124 Affected Documents --- To Be Determined Status --------------- See GI-124 Problem / Resolution --- See GI-124 Technical Resolution - See GI-124 Milestones Original Current Actual l
122-5 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type _ Level Office /Div/Br Manager TACS No 124 Safety /NR Active-L1 NRR/DSR0/RSIB S. Diab 60460 Title --------------- Auxiliary Feedwater System Reliability Work Authorization -- Memorandum for T. Speis fr'om H. Denton dated February 5, 1986 Contract Title ------ None Contractor Name/ FIN -- None l Work Scope ----------- Because of the significance of the AFWS in reducing core-
- melt frequency, the staff has determined that all PWRs should meet the reliability criterion specified in SRP Section 10.4.9. That SRP Section was not applied to operat-ing reactors. In order to achieve and maintain a high degree of reliability for the AFWS or alternate decay heat removal means, the following should be completed
- (1) PWR 1,1censees and applicants should demonstrate, using reli-ability analyses, that the AFWS is of high reliability, 10 4 to 10 5 unavailability per demand; (2) the staff is to review the reliability analyses and/or any necessary system modifications and procedural or maintenance changes. As a result of (1) and (2) above, determine whether it is neces-
- sary to require that plants upgrade their AFWS to the safety-related standards. Based on the staff evaluation of W, CE, and B&W plant AFWS (NUREG-0611, NUREG-0635, B&W plant SERs),
i the staff has determined that the AFWS of the following plants are not sufficiently reliable and should be upgraded:
(1) Prairie Island 1 (2) Prairie Island 2 (3) ANO-1 (4) ANO-2 (5) it. Calhoun (6) Crystal River (7) Rancho Seco Elements of Generic Issues 68, " Loss of AFWS due to AFW Steam High Energy Line Break," 93, " Steam Binding of Auxiliary Feedwater Pumps," and 122. " Loss of All Feed-water," will be integrated into GI-124 as appropriate. This will be provided later.
Affected Documents -- To Be Determined i S ta tu s -- -- - -- -- - - --- A regulatory analysis package is being made ready for NRR comment.
Problem / Resolution --- None 124-1 As of 3rd Quarter FY-86
Generic Issue #124 Technical Resolution -
Milestones Original Current Actual Phase I Issue proposed resolution 03/86 -
05/86 for NRR comment Present proposed resolution 04/86 06/86 -
to NRR Director ACRS meeting 05/86 09/86 -
Review package sent to CRGR 06/86 10/86 -
Issue proposed resolution 07/86 11/86 -
for public comment Phase II TBD TBD -
I i
124-2 As of 3rd Quarter FY-86
GENERIC TSSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
A-3,4,5 USI Active NRR/0 RAS /BWR E. Murphy T i t l e ----- ----------- Steam Generator Tube Integrity Work Authorization --- To be provided Contract Title ------- To be provided "
Contractor Name/ FIN -- To be provided Work Scope ----------- To be provided Affected Documents --- To be provided S ta t u s ---- - - -- --- - -- - To be provided Problem / Resolution --- To be provided Technical Resolution - To be provided Milestones . Original Current Actual Draft Technical Resolution Issued by DSR0 for Staff 11/82 -
11/24/82 Comment Staff Comments to DSR0 12/82 -
12/08/82 Completed Package to 06/83 -
06/13/83 Director, NRR Package to CRGR 09/83 -
09/10/83 CRGR. Review Complete 10/83 -
10/24/83 Issued for Public Comment 04/85 -
04/17/85 Issue Staff Recommended Actions 04/85 -
04/17/85 (Generic Letter 85-02)
Assessments of Licensees 12/85 -
02/21/86 Responses to Generic Letter Final Technical Resolution Commission Paper Approved by 02/86 -
02/21/86 Director, NRR (Evaluation of Responses to GL 85-02)
A3-1 As of 3rd Quarter FY-86
Generic Issuo #A-3,4,5 Milestones Original Current Actual EDO Returned Commission 03/86 -
03/07/86 Paper with Comments Commission Paper to EDO 03/86 -
03/24/86 EDO Approval 04/86 -
03/24/86 Issue Final Resolution 04/86 07/86 -
(NUREG-0844) 4 A3-2 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number hpe level Office /Div/Br Manager TACS No.
A-17 USI Active NRR/DSR0/EIB D. Thatcher 20151 Title ---------------- System Interactions in Nuclear Power Plants Work Authorization --- Commission designation of system interactions as a USI.
Contract Title ------- Survey and Evaluation of System Interaction Events and Sources Contractor Name/ FIN -- ORNL/B-0789 Work Scope ----------- The scope of work to resolve the issue includes: (1) search for common cause events; (2) trends / patterns of common cause events; (3) Indian Point comparison; (4) screen events for safety significance; (5) review-define search methods; and (6) compare / evaluate methods.
Affected Documents --- The following technical reports have been or will be published:
(1) NUREG/CR-1321, " Final Report - Phase I, Systems Interac-tion Methodology Applications Program," Sandia National Laboratories (SAND 80-0884), April 1980.
(2) NUREG/CR-1859, " Systems Interactions: State-of-the-Art Review and Methods Evaluation," Lawrence Livermore Nation-al Laboratory, January 1981.
(3) NUREG/CR-1896, " Review of Systems Interaction Methodologies," Battelle Memorial Institute, January 1981.
(4) NUREG/CR-1901, " Review and Evaluation of Systems Interac-tions Methods," Brookhaven National Laboratory,1981.
(5) NUREG/CR-2915, " Initial Guidance on Digraph Matrix Analy-sis for Systems Interaction Studies," Lawrence Livermore National Laboratory (UCID-19457), March 1983.
(6) NUREG/CR-3593, " Systems Interaction Results from the Digraph Matrix Analysis of a Nuclear Power Plant's High Pressure Safety Injection Systems," Analytic Information Processing and Lawrence Livermore National Laboratory, July 1984.
(7) NUREG/CR-3922, " Survey and Evaluation of System Interac-tion Events and Sources," Cak Ridge National Laboratory, January 1985.
(8) NUREG/CR-4179, " Digraph Matrix Analysis for Systems Inter-
. actions at Indian Point Unit 3, Abridged Version," Vol.1, to the published; Vols. 2-6 vill be available in the NRC Public Document Room,1717 H Street, N.W. , Washington, 0.C. , Lawrence Livermore National Laboratory.
(9) NUREG/CR-4207, " Fault Tree Application to the Study of Systems interactions at Indian Point 3," Brookhaven Na-tional Laboratory, April 1985.
A17-1 As of 3rd Quarter FY-66
. . . . = . . .. _ _ _ _ -
Generic Issue #A-17 I
(10) NUREG/CR-4261, " Assessment of System Interaction Experi-
) ence in Nuclear Power Plants," Oak Ridge National Labora-tory Unpublished.
(11) NUREG/CR-4306, " Review and Evaluation of Spatial System Interaction Programs," Oak Ridge National Laboratory, Unpublished.
A proposed resolution of system interactions consisting of regulatory analysis and supporting NUREG will be issued for public comment.
Status --------------- Meeting were held with CRGR in April 1986 and with the ACRS in June 1986 to review the draft of the proposed resolu-tion. CRGR basically agreed with the approach but con-cluded that the package needed to be revised to reflect the discussions at the meeting. ACRS did not agree with the
, proposed resolution and in a May 13, 1986 letter to the EDO outlined rather broader concerns.
The staff is in the process of addressing the ACRS 'stter.
Because of the nature of the ACR$ concerns, it is expected that major changes will be required to satisfy their
, concerns.
] Problem / Resolution --- The ACRS May 13, 1986 letter outlined a number of broad concerns. The staff is making some major program changes to attempt to address the ACRS concerns.
Technical Resolution -
4 Milestones Original Current Actual Draft Technical Resolution i
Issue by DSRO for Staff 03/30/85 -
08/14/85 Comment Staff Comments to OSR0 04/30/85 -
. 11/08/85 Completed Package to 12/30/85 -
03/06/86 Director, NRR Package to CRGR 03/86 -
03/21/86 CRGR Review Complete 05/86* - -
Issue for Public Comment. 05/86* - -
{ Final Technical Resolution Received Public Comments 07/86* - -
l Schedule being reassessed due to major program changes in response to ACRS.
i i
A17-2 As of 3rd Quarter FY-86 I
t .
4
,r> e-,-v-,,,--.- - , . - - m-,,.-_---,--.._,,-, __._....,.--,--.m .---.m. .- . - - - _ , - - - - - - . - - - - - - - - -
Generic Issuo #A-17 Milestones Original Current Actual Final Technical Resolution Submit for Staff Review 08/86* - -
Final Package to NRR 09/86* - -
Director Package to CFGR 10/86* - -
Issue Final Resolution 12/86? - -
1 Schedule being reassessed due to major program changes in response to ACRS.
i
?
l A17-3 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
A-29 Safety / Active-L1 NRR/OSR0/RSIB A. Serkiz 20465 Medium Title ---------------- Nuclear Power Plant Design for the Reduction of Vulnerability to Industrial Sabotage Work Authorization --- NRR FY84 Operating Plan, (Appendix G)
Contract Title ------- Evaluation of the Probability of Nuclear Plant Sabotage Contractor Name/ FIN -- PNL/B-2995 Work Scope ----------- Generic Issues A-29 deals with the vulnerability of nuclear power plant systems to insider tampering and sabotage, and the risk resulting from such actions. The results of prior studies by BNL and PNL are reported in NUREG/CR-4392 and NUREG/CR-4462, respectively. The currently planned effort extends the prior work to obtain: (a) a better estimate of the probability of sabotage utilizing field experience (Task 1); (b) a ranking of those systems most vulnerable and possible methods to offset such potential sabotage (Task 2); and (c) an estimate of CMF and risks for the most important systems (Task 3). The results of these tasks (i.e., estimated CMFs and releases) will be a key factor in establishing the need for a detailed Regulatory Analysis which would include an extensive cost estimating effort.
Affected Documents --- To be determined Status --------------- 189a Proposal has been received.
Problem / Resolution --- FY-86 and FY-87 funding commitments are unresolved; schedule for completion is therefore unknown at this tim (
Technical Resolution -
Milestones Original Current Actual
. TAP issued for comment - -
08/26/83 Final TAP Issued 01/84 -
01/14/84 1
Contractor Support (a) Proposal Solicited 02/84 -
02/02/84 (b) Proposal Evaluated 03/84 -
08/27/84 (c) Contract Issued 04/84 -
08/27/84 i
A-29-1 As of 3rd Quarter FY-86
G:n ric Issue #A-29 Milestones Original Current Actual Task 1 - Refinement of Previous 10/86 10/86 -
Sabotage Models, Data bases and Estimates
- Task 2 - Assessment of Plant 03/87 03/87 -
Design and Layout Vulnerabilities
- Task 3 - Estimation of CMFs and 09/87 09/87 -
Releases Associated with Sabotage Actions
- Estimation of Costs Associated 03/88 03/88 -
with Deterrents Preparation of a Regulatory 06/88 06/88 -
Analysis Proposed Resolution (i.e., 09/88 09/88 -
CRGR Package) i These tasks are work identified by PNL under FIN B-2995 (189a dated May 1986).
Finding as yet uncommitted.
i i
I A-29-2 As of 3rd Quarter FY-86 i
GENERIC ISSUE c%NAGEMENT CONTROL SYSTEM
. Issue Issue Action Task l
Number Type Level Office /Div/Br Manaaer TACS No. 1 A-30 Safety / Active-L1 NRR/DSR0/EIB 0. Thatcher 04587 High 20470 l Title ---------------- Adequacy of Safety-Related DC Power Supplies
- Work Authorization --- NRR FY-84 Operating Plan (Appendix G)
! Contract Title ------- None -
! Contractor Name/ FIN -- None 1
i Wo rk Scope ----------- The staff's initial study of the adequacy of DC power supplies
] was documented in NUREG-0305, " Technical Report on DC Power i
Supplies in Nuclear Power Plants," (July 1977). This study recommended the performance of a quantitative reliability
' assessment. This assessment was performed and documented in NUREG-0666, "A Probabilistic Safety Analysis of DC Power Supply
! Requirements for Nuclear Power Plants," (April 1981). With the
! aid of a technical assistance contract, the NUREG-0666 recom-i . .
mendations were being converted into proposed requirements.
- Affected Documents --- Issue Information Notice i
Status --------------- Implementation guidelines were developed and discussed with the ACRS on 03/82 and 09/82. A review meeting was held with the Director, NRR on 09/30/83 to go over the CRGR package.
) As a result of this meeting, the Director, NRR requested that
! four additional issues be considered prior to transmitting j! the A-30 package to CRGR. It was anticipated that this new work would take approximately four months to complete. A j revised schedule was approved by the Director, OSI.
t
\ As a result of a meeting between INPO, the Director, OSI, and the A0/ CPS on 12/14/83, NRC agreed to review current INPO efforts regarding DC power supply systems to determine the l
' acceptability of this guidance to licensees in lieu of issuing separate A-30 requirements. NRC review resulted in determining
! that INP0 guidance was not sufficient and that the A-30 CRGR package would go forward.
4 CRGR package sent to Director, NRR on 01/31/84. However, additional modifications were requested. Director, NRR approval obtained on 03/08/84. As a result of this change,
, all follow-on milestones wre changed by one month.
The CRGR met to review NRR recommendations on Generic Issue
! A-30 on 5/9/84. The CRGR requested that revisions be made
! to the cost / benefit section of the package. The cost / benefit revisions requested by CRGR involve performing a more detailed PRA instead of the single minimum DC power system of the NUREG-0666 study. This additional work has been conducted by i
l j A30-1 As of 3rd Quarter FY-86 I
i
Generic Issue #A-30 RRBR of RES, GIB of OST, and PSB. Because of key personnel turnover, RRBR was unable to complete this work as scheduled. l Also, a peer review of the cost / benefit analysis was added to ensure that it was consistent with NRC guidelines. The peer i review of the revised draft cost / benefit package has been completed and comments sent to RES/RRBR on January 29, 1985.
Because of key personnel turnover again, RRBR is unable to prepare the final cost / benefit package as scheduled. The milestones for resolution of this generic issue will be revised when the final revised cost / benefit package is received from RES.
Problem / Resolution --- RRBR has not delivared the revised cost benefit package as yet.
RRBR indicated a revised completion schedule of 12/31/85 for the Cost / Benefit package; however, it has not been received.
Technical Resolution - NUREG-0666 presents the technical resolution of this. generic issue.
Milestones Original Current Actual Issue NUREG-0305. - -
07/77 Issue NUREG-0666. - -
04/81 Acceptance criteria and implemen- - -
02/83 tation guidelines prepared from NUREG-0666 recommendations are incorporated into SRP Section 8.3.
Technical resolution package for - -
02/28/83 CRGR review complete Division Director approval of 04/83 -
04/08/83 CRGR package. Packagesentto DST and OL.
OST and OL comments incorporated. 05/83 -
08/12/83 Package sent to Director, NRR.
Package returned to incorporate - -
09/20/83 new tasks requested by Director, NRR.
Package sent to Director, NRR 01/84 -
01/31/84 Director NRR review complete 06/83 -
03/08/84 Package sent to CRGR CRGR review complete 07/83 -
05/09/84 i Transmitted memorandum to DST - -
09/07/84
- and RES/RRAB requesting con-currence on their input schedule.
Memorandum to RES/RRAB requesting - -
04/27/85 completion date A30-2 As of 3rd Quarter FY-86
Generic Issue #A-30 Milestones Original Current Actual ACRS review complete 07/83 -
NA E00 approval 09/83 -
NA FR Notice issued for public 09/83 -
NA comment on proposed SRP Change OM8 Clearance, (if applicable) 12/83 -
NA Division incorporation of public 12/83 -
NA -
comments. '
Director, NRR review complete. 01/84 -
NA CRGR review complete. 02/84 -
NA E00 approval. 03/84 -
NA FR Notice of issuance of SRP 04/84 -
NA change.
Second CRGR pkg cost /benzfit -
12/85*** -
revisions complete (RRBR)
NRR Divisions review complete -
TBO*** -
Director NRR review complete -
TBO*** -
Second package'sent to CRGR -
TBO*** -
Issue Information Notice to -
T80*** -
licensees Second CRGR review complete -
TBO*** -
l l
l
' *By Memorandum for T. Spets.from R. Mattson dated April 24, 1984.
- Milestone Date and subsequent dates were based on receipt of the final value/ impact package for GI A-30 from RRBR/RES by end of the first quarter FY-86.
- EIB is currently in the process of integrating this issue and some other issues related to power supplies (e.g., GI-48, GI-49) into a single program. During the integration effort EIB, is reevaluating the schedule.
I A30-3 t
As of 3rd Quarter FY-86
_ . - _ - _ ~ _ . _ - .
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
A-40 USI Active NRR/DSR0/EIB K. Shaukat 20334 Title ---------------- Seismic Design Criteria Work Authorization --- Commission designation of seismic design criteria as a USI.
Contract Title ------- Value/ Impact Assessment for Seismic Design Criteria Contractor Name/ FIN -- LLNL/A-0441 P
Wo rk Scope ----------- The program for resolution of USI A-40 consists of two phases: (1) tasks concerning seismic input definitions, and (2) tasks concerning the response of structures, systems, and com-ponents. All technical work has been completed on both phases.
The technical work accomplished on each of the tasks described below is summarized and evaluated in NUREG/CR-1161, "Recom.nend-ed Revisions to Nuclear Regulatory Commission Seismic Design Criteria." This report was prepared by LLNL for the NRC.
Reference to technical reports documenting completion of A-40 tasks and other pertinent technical work is included in i
NUREG/CR-1161. In developing the specific recommendations, the LLNL staff and their team of expert consultants considered all available and appropriate technical literature in addition to the results of USI A-40 tasks. In some cases, recommenda-tions were developed by consensus of expert opinion and stemmed from unpubitshed data, research, and experience.
A review of the recommendations by the NRC staff has been made and a proposed staff position developed in a form of recom-mended SRP revisions. In some cases, the recommendations have already been incorporated into the SRP in a general revision in 1981.
A value/ impact analysis has been completed for the assessment of the safety impact of implementing the SRP changes proposed as a result of the technical findings (NUREG/CR-3480). The supporting documents required for review by the CRGR have been prepared and include alternatives to the staff position on Soil-Structure Interaction (SSI). A workshop on the subject of SSI is planned in June 1986 by RES with coordination by NRR to be held in the Washington, D.C. metropolitan area. The objectives of this planned SSI workshop are to review the al-ternatives suggested by the staff on SSI and related licensing l concerns jointly by regulators, practitioners, researchers, i utilities and other interested groups, and to discuss sugges-tions to improve the licensing criteria on SSI. The outcome of s
A40-1 As of 3rd Quarter FY-86
.G:neric Issue #A-40 the SSI workshop is expected to help the staff decide the li-censing criteria to be included in the proposed revision to the SRP. The CRGR package which includes the technical findings 1
(NUREG/CR-3480), and the proposed SRP changes will be submit-
- ted to CRGR for review and approval. Following approval by CRGR, the proposed requirements will be submitted for public comment prior to implementing.
Af fected Documents --- The following technical reports have been published:
(1) NUREG/CR-1161, " Recommend Revisions to Nuclear Regulatory Commission Seismic Design Criteria," May 1980.
(2) NUREG/CR-1717 " Soil-Structure Interaction Methods SIM Code," September 1979.
(3) NUREG/CR-4182, " Verification of Soil-Structure Interaction Methods," May 1935.
(4) NUREG/CR-4329, " Reliability Evaluation of Containments Including Soil-Structurc Interaction," December 1985.
(5) NUREG/CR-3480, "Value/ Impact Assessment for Seismic Design Criteria, USI A-40, " August 1984.
(6) A NUREG/CR report on the proceeding of the SSI Workshop will be published for staff and public comments.
Revisions to SRP Sections 2.5.2, 3.7.1, 3.7.2, 3.7.3, and 3.7.4 will be issued as the final resolution of USI A-40.
Status --------------- Based on NRR staff comments, the CRGR package has been revised to include the modified SRP requirements with suggested op-tions and acceptance criteria for SSI analysis. A workshop on SSI was in the Washington, D.C. area in June 1986 to discuss the current state of knowledge. Utilities, regulators, researchers, university professors, practitioners and other interested groups including people from foreign countries participated. The proceedings of the SSI Workshop will be published as a NUREG/CR by BNL. The staff is currently working to finalize the CRGR package based on the outcome of the SSI workshop.
Problem / Resolution --- None Technical Resolution -
Milestones Original Current Actual Draft Technical Resolution Issued by DST for Staff Comment 09/IS/83 -
03/16/83 i Staff Comments to DST 10/20/83 -
10/20/83 1
l A40-2 As of 3rd Quarter FY-86
Genoric Issue #A-40 Milestones Original Current Actual Completed Package to Director, 11/22/83 -
12/10/84 NRR Revised Staff Position 03/86 -
04/30/86 SSI Workshop to Support 06/86 -
06/18/86 Resolution Finalize CRGR Package 07/86 07/86 Submit for NRR Review Review 08/86 08/86 -
Package to CRGR 09/86 09/86 -
CRGR Review 10/86 10/86 -
I Issue for Public Comment 11/86 11/86 -
Final Technical Resolution
~
End of Public Comment Period 02/87 07/87 -
Issued by 05RO for Staff 04/87 04/87 - l Comment 4
Staff Comments to DSR0 05/87 05/87 -
Completed Package to Ofrector, 06/87 06/87 -
Package to CRGR 07/87 07/87 -
CRGR Review Complete 08/87 08/87 -
Issue Final Resolution 10/87 10/87 -
1 i
A40-3 As of 3rd Quarter FY-86 i
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number M Level Office /Div/Br Manager TACS No.
A-44 USI Active-L5 NRR/DSR0/RSIB A. Rubin 20153 Title --'------------- Station Blackout Work Authorization --- Commission designation of station blackout as a USI Contract Title ------- (1) Reliability of AC Power Supplies (2) Station Blackout Accident Analysis ,
Contractor Name/ FIN --- (1) ORNL/B-0744 (2) SNL/A-1302 Work Scope ----------- The scope of work to resolve the issue includes:
(1) Evaluating the expected frequency and duration of offsite power losses at nuclear pcwer plants.
(2) Estimating the reliability and evaluating the dominant factors affecting the reliability of onsite emergency AC power supplies.
(3) Performing statistical correlation and trend analysis of diesel generator reliability data and losses of offsite power data.
(4) Evaluating risks posed by station blackout accidents and assessing the effectiveness of safety improvements in reducing those risks.
(5) Evaluating risk reduction and costs of various fixes to perform value/ impact analysis.
Affected Documents --- The following technical reports have been published:
(1) NUREG-CR/2989, " Reliability of Emergency AC Power Systems at Nuclear Power Plants," July 1983.
(2) NUREG-CR/3992, " Collection and Evaluation of Complete and Partial Losses of Offsite Power at Nuclear Power Plants,"
February 1985.
l (3) NUREG-CR/3226, " Station Blackout Accident Analyses," May 1983.
(4) NUREG-CR/4347, " Emergency Diseel Generator Operating Experience, 1981 - 1983," December 1985.
(5) NUREG-1032, " Evaluation of Station Blackout Accidents at Nuclear Power Plants, Technical Findings Related to USI A-44," Oraft, May 1985.
(6).NUREG-1109, " Regulatory Analysis for the Resolution of
, Unresolved Safety Issue A-44, Station Blackout," Draf t,
)
January 1986. ,
A44-1 As of 3rd Quarter FY-86 l
I
Gen:ric Issue #A-44 A proposed rule and a draft regulatory guide on station blackout were published for public comment in the Federal Register on March 21 and April 3, 1986, respectively. The regulatory guide provides guidance on acceptable means to comply with the proposed rule.
Status --------------- Meetings were held with CRGR in March and April 1984 to review the proposed resolution. CRGR recommended that the proposed rule, the proposed Regulatory Guide, and the draft staff NUREG-1032 be issued for public comment after making modifications to reflect CRGR comments.
The technical basis and recommendations were revised based on updated data on loss of offsite power experienced at nuclear power plants. These revisions are included in the proposed rulemaking package which was swnt to the Commission on May 6, 1986 (SECY-85-163). NUREG-1032 was published for public comment in May 1985. A Nuclear Utility Group on Station Blackout (NUGSBO) submitted in May 1985 a proposal to NRC for the t
resolution of USI A-44. The staff submitted its review of this proposal to the Commission in September 1985 (SECY-85-163A).
The Nuclear Utility Management and Resource Committee (NUMARC) has formed a subcommittee to develop an industry position on the resolution of USI A-44.
Meetings were held in September and November 1985 with the Commission to discuss the staff's proposed resolution. The staff submitted a backfit analysis to the Commission in January 1986 (SECY-86-28). By a vote of 5-0, the Commission approved promulgation of the proposed rule. The staff revised the Federal Register notice in accordance with Commission instructions and issued it for publication on March 17, 1986. The public comment period on the proposed rule expired on June 19, 1986.
Problem / Resolution --- None Technical Resolution -
Milestones Original Current Actual Draft Technical Resolution Issued by DST for Staff Comment 10/83 -
12/01/83 Staff Comments to DST 11/83 -
12/02/83 Completed Package to Director, 11/83 -
12/21/83 NRR Package to CRGR 12/83 -
03/06/84 CRGR Review Completed 01/84 -
05/08/84 A44-2 As of 3rd Quarter FY-86
Generic Issue #A-44
, Milestones Original Current Actual Proposed Rule to Commission 02/85 -
05/06/85 Evaluation of NUGS80 Proposal - -
09/C4/85 Commission Meeting 04/85 -
09/11/85 Commission Meeting 04/85 -
11/14/85 Complete Backfit Analysis - -
01/28/86 Commission Decision to Issue 08/85 -
03/05/86 Rule
, Issue Proposed Rule for Comment 09/85 -
03/17/86 Final Technical Resolution
- End of Public Comment Period 12/86 -
06/19/86 Issued by OSR0 for Staff Comment 03/86 11/86 -
Staff Comments to OSRO -
12/86 -
Completed Package to Director, 04/86 01/87 -
NRR Package to CRGR 05/86 03/87 -
I CRGR Review Completed 06/86 05/87 -
Final Rule to Commission 08/86 07/87 -
Commission Decision 11/86 06/88 - -
Issue Final Rule 12/86 07/88* ,
Schedule is being revised to reflect the E00's proposal for issuing a final rule in 1987.
i l
1 A44-3 As of 3rd Quartrr FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number , Type Level Office /Div/Br Manager TACS No.
A-45 USI Active-L1 NRR/DSR0/RSIB A. Marchese 43516 Title ---------------- Shutdown Decay Heat Removal Require'ments Work Authorization --- May 10, 1982 - Contract Implemented Contract Title ------- Shutdown Decay Heat Removal (DOE Interagency)
Contractor Name/ FIN -- SNL/A-1309 Work Scope ----------- Technical Assistance Contract to provide overall project management technical direction and integration for the entire Task A-45 program, including selection and management of subcontractors Affected Documents --- (1) NUREG/CR-2883, Study of Impact and Value of Alternative Decay Heat Removal Concepts for LWRs (SANDIA)
(2) SECY 84-134 PORVs for CE Plants (3) TBD: Reg Guides, SRP, Policy Status --------------- A proposed resolution package is in preparation.
Problem / Resolution --- Insufficient funds to complete V/I Report for Trojan.
Further internal and industry comments continue to result in additional analyses and delay in providing a technical resolu-tion and also require more resources.
Technical Resolution -
Milestones Original Current Actual Final Value/ Impact 07/85 -
08/23/85 Report for Quad Cities Final Value/ Impact 10/85 -
11/15/85 Report for Point Beach Oraft Value/ Impact 11/85 -
12/16/85 Report for Cooper Draft Value/ Impact 11/85 -
02/28/85 Report for Turkey Point Draft Value/ Impact 01/86 On Hold -
Report for Trojan Draft Value/ Impact 04/86 06/86 -
Report for St. Lucie A45-1 As of 3rd Quarter FY-86
l Generic Issue #A-45 Milestones Original Current Actual Draft Value/ Impact 05/86 07/86 -
Report for ANO-1 i Contractor Draft Summary 06/86 07/86 -
Report of All Plants OSRO Oraft Regulatory 08/86 08/86 -
Analysis and Technical Finding Report Issued for Staff Comments 1
- Staff Comments to DSR0 09/86 09/86 -
Completed Resolution '10/86 10/86 -
Package to Director, NRR Resolution Package to 11/86 11/86 -
CRGR CRGR Review Complete 01/87 01/87 -
Proposed Resolution 03/87 03/87 -
Issued For Public Comment i
c i
l I
i t
I A45-2 As of 3rd Quarter FY-86 l
l GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number g Level Office /Div/Br Manaaer TACS No.
A-46 USI Active NRR/DSR0/EIB T. Y. Chang 43517 Title --------------- Seismic Qualification of Equipment in Operating Plants Work Authorization -- Commission approval of USI A-46 in December 1980 Contract Title ------ (1) Correlation of In-Service Seismic Experience Data in Non-Nuclear Facilities with Seismic Equipment Qualifi-cations in Nuclear Power Plants.
(2) Investigation of In-Situ Test Methods (3) (a) Identification of Seismic-Sensitive Systems and Equipment (b) Development of Methods to generate Generic Floor Response Spectra (4) Resolution of Unresolved Safety Issue A-46, Seismic Qualification of Equipment for Operating Plants.
Contractor Name/ FIN -- 1. LLNL/A-0423 -
(Completed)
- 2. INEL/A-6474 -
(Completed)
- 3. BNL/A-3397 -
(Completed)
- 4. SNL/A-1318 -
(Ongoing)
Work Scope ---------- Technical assistance contracts with LLNL, INEL and BNL have been completed. Contract with SNL is still ongoing. Exten-sive interface with Seismic Qualification Utility Group (SQUG),
EPRI, Senior Seismic Review and Advisory Panel (SSRAP) on USI A-46 is still continuing.
Af fected Documents -- (1) NUREG/CR-3017, Correlation of Seismic Experience Data in Non-Nuclear Facilities with Seismic Equipment Qualifica-tion in Nuclear Plants (LLNL).
(2) NUREG/CR-3875, The Use of In-Situ Procedures for Seismic Qualification of Equipment in currently operating plants
' (INEL).
(3) NUREG/CR-3357, Identification of Seismically Risk Sensi-tive Systems and Components in Nuclear Power Plants (BNL).
(4) NUREG/CR-3266, Seismic and Dynamic Qualification of Safety-Related Electrical and Mechanical Equipment in Operating Nuclear Power Plants - Development of a Method to Generate Generic Floor Response Spectra (BNL).
(5) Use of Past Earthquake Experience Data to Show Seismic I
1 Ruggedness of Certain Classes of Equipment in Nuclear Power Plants, SSRAP Report, January 1985.
(6)NUREG-1030,SeismicQualificationofEquipmentinOperat-ing Nuclear Power Plants, USI A-46, August 1986.
(7) NUREG-1211, Regulatory Analysis for Proposed Resolution of USI A-46, August 1986.
t A46-1 As of 3rd Quarter FY-86
Generic Issue #A-46 Status -------------- Public coments on the proposed resolution package have been resolved and incorporated in the revised proposed resolution package. This package is under NRR review and will be for-warded to CRGR and ACR$ in August.
The resolution of A-46 is mainly based on work completed by the SQUG and EPRI using the seismic experience data approach and reviewed and endorsed by SSRAP and the NRC staff. The scope of review is narrowed down to equipment required to bring the plant to hot shutdown and maintain it there for a minimum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. A walk-through of the plant is required to inspect equipment in the scope. Evaluation of equipment will include: (a) adequacy of equipment anchorage, (b) func-tional capability of essential relays, (c) outliers (i.e. ,
equipment with non-standard configurations).
Problem / Resolution --- None .
Technical Resolution -
Milestones Original Current Actual Issue Interim Report 09/83 - -
Draft Technical Resolution Issue by OSR0 for Staff 02/15/84 -
03/06/84 Coment Staff Coments to DSR0 02/29/84 -
09/07/84 Completed Package to 03/15/84 -
09/24/84 Director, NRR Package to CRGR 04/15/84 -
10/31/84 CRGR Review Complete 05/1E/84 -
12/03/84 DSRO Revised Oraft 02/28/85 -
02/28/85 Complete Staff Coments on Revised 03/08/85 -
04/08/85 Oraft to DSR0 Revised Package to 03/15/85 -
04/14/85 Director /NRR Revised Package to CRGR 03/31/85 -
06/11/85 CRGR Review Complete 05/15/85 -
07/08/85 Issued for Public Coment 06/15/85 -
09/12/85 1
A46-2 As of 3rd Quarter FY-86
Generic Issue #A-46 Milestones Original Current Actual Final Technical Resolution Available for staff 05/86 -
06/86 comments .
Staff comments to DSRO 05/86 05/86 -
Completed package to 06/86 06/86 -
Director, NRR Package to CRGR 07/86 07/86 -
CRGR Review Complete 08/86 08/86 ,-
Issue Final Generic Letter 10/86 10/86 -
and NUREG A46-3 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type _ Level Office /Div/Br Manager TACS No.
A-47 USI Active-L1 NRR/DSR0/EIB A. J. Szukiewicz 43518 Title ---------------- Safety Implications of Control Systems Work Authorization --- Commission approval of USI A-47 in December 1980 Contract Title ------- (1) Safety Implications of Control Systems A-47 (INEL)
(2) Safety Implications of Control Systems (ORNL)
(3) Risk Analysis of Significant Control Systems Failures (PNL)
Contractor Name/ FIN -- INEL/A-6477 ORNL/8-0467, B-0816 PNL/8-2386 Work Scope ----------- The scope of work to resolve this issue includes:
(1) Evaluate control system failures on four reference plant designs (one for each of the NSSS Vendors) that could:
(1) cause transients or accidents to be potentially more severe than those identified in the FSAR analysis; (2) adversely affect any assumed or anticipated operator action during the course of a transient or accident; (3) cause technical specification safety limits to be exceeded; or (4) cause transients or accidents to occur at a frequency in excess of those established for abnormal operational transients and design basis accidents.
(2) Evaluate risks posed by potentially significant control system failures identified during the review and assess the effectiveness of improvements in reducing those risks.
(3) Evaluate risk reduction and costs of various fixes to perform value/ impact analysis. .
(4) Evaluate the generic applicability of the failures identified during the review of the reference plants.
Af fected Documents --- The following technical reports have been published:
(1) NUREG/CR-4262, " Effects of Control System Failures on Transients and Accidents at a General Electric Boiling Water Reactor," Volumes 1 and 2, May 1985.
(2) , NUREG/CR-4326, " Effects of Control System Failures on Transients and Accidents at a 3-Loop Westinghouse Pressur-ized Water Reactor," Volume 1, August 1985, Volume 2, October 1985.
(3) NUREG/CR-4047, "An Assessment of the Safety Implications of Control at the Oconee 1 Nuclear Plant Final Report,"
March 1986. #
A47-3 As of 3rd Quarter FY-86
Gen:ric Issue #A-47 (4) NUREG/CR-3991, " Failure Modes and Effects Analysis (FMEA) of the ICS/NNI Electric Power Distribution Circuitry at the Oconee 1 Nuclear Plant," October 1985.
(5) NUREG/CR-3692, "Possible Modes of Steam Generator Overfill Resulting from Control System Malfunctions at Oconee-1 Nuclear Plant," July 1984.
(6) NUREG/CR-4449, "A PWR Hybrid Computer Model for Assessing the Safety Implications of Control Systems," March 1986.
(7) NUREG/CR-4265, "An Assessment of Safety Implications of Control at the Calvert Cliffs 1 Nuclear Plant," Volume 1, April 1986.
(8) NUREG/CR-4387, " Effects of Control System Failure on Tran-sient, Ace' ant and Core-Melt Frequencies at a General Electric Boiling Water Reactor," December 1985.
(9) NUREG/CR-4385, " Effects of Control System Failures on Tran-sients, Accidents, and Core-Melt Frequencies at a Westing-house PWR," November 1985.
(10) NUREG/CR-4386, " Effects of Control System Failures and Core-Melt Frequencies at a Babcock and Wilcox Pressurized Water Reactor," December 1985.
(11) NUREG/CR-3958, " Effects of Control System Failures and Core-Melt Frequencies at a Combustion Engineering Pressur-ized Water Reactor," March 1986.
'A draft staff report on the technical findings related to USI A-47 and the regulatory analysis report will be issued for public comment.
Status --------------- A proposed resolution package is in preparation. The draft technical findings report and the regulatory analysis is under management review.
Problem / Resolution---- The recent Rancho Seco event initiated additional studies of B&W plants by the staff and the B&W Owners' group. Completion of some of the activities being conducted by the Owners' group may be needed before final resolution of USI-47.
Technical Resolution -
Milestones Oriainal Current Actual Draft Technical Resolution Issue by OSR0 for Staff 09/86 09/86 -
Comment Staff Comments to DSR0 10/86 10/86 -
Completed Package to Director, 11/86 11/86 -
NRR A47-2 As of 3rd Quarter FY-86
Generic Issu2 #A-47 Milestones Original Current - Actual Package to CRGR 01/87 01/87 -
CRGR Review Complete 02/87 02/87 -
Issue Draft Resolution for 03/87 03/87 -
Public Comment Final Technical Resciution End of Public Comment Period 05/87 ' 05/87 -
Issued by OSR0 for Staff 06/87 06/87 -
Comment Staff Comments to DSR0 07/87 07/87 -
Completed Package to Director, 08/87 08/87 -
NRR Package to CRGR 09/87 09/87 -
CRGR Review Completed 10/87 10/87 -
Issue Final Resolution 11/87 11/87 -
A47-3 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br ManaQer TACS No.
A-48 USI Active NRR/DSR0/EIB C. Ferrell 43519 Title --------------- Hydrogen Control Measures and Effects of Hydregen Burns on Safety Equipment Work Authorization -- Commission Designation of Hydrogen Control as a USI ~
in December 1980.
Contract Title------- Review and Analysis of Nuclear Energy and Regulatory Issues Contractor Name/ FIN --- National Academy of Sciences /8-8686 Wo rk Scope ---------- The Energy Engineering Board of the National Academy of Sciences will assess the technical issues related to the fate and control of hydrogen generation in severe LWR acci-dents in order to further improve our knowledge of such phenomena for possible use in plant evaluations. To carry out the study, the Board will establish a committee of ap-proximately six experts requiring expertise in reactor safe-
. ty engineering, chemical engineering, effects of combustion (fire damage), combustion, and related disciplines.
The evaluation will include the following:
- 1. Scale-up
- a. Evaluate experimental data from various test fa-cilities (FITS, VEGES, NTS) with respect to the following questions: (i) how typical are the combustion mechanisms in small enclosures as com-pared with full-size containments? (ii) how well can they be scaled to full-size containments?
- b. Evaluate the ability to scale the instrument tem-peratures obtained from small-scale tests through analytic codes to the temperatures predicted for full-size reactor containments.
- 2. Completeness Evaluate SNL's program and the programs sponsored by industry with respect to the question of whether all important areati have been properly covered.
- 3. Detonation
- a. Comment on the need for extending experimental work to include effects of detonation on equip-ment, recognizing that most work to date has A48-1 As of 3rd Quarter FY-86
1 l
Generic Issue #A-48 concentrated on deflagration, in view of the difficulty of detunation work and the low probability ascribed to such an event,
- b. Provide an independent assessment of the following research:
Recent research by SNL has established lower limiting concentrations of hydrogen (approximately 13-1/2%) in air which would support a detonation. Furthermore, addition-al testing with steam in the debated detona-tion tube facility has provided results indicating that steam addition to hydrogen-air mixtures had little effect on the detonability of mixtures.
- 4. Jet Flames Develop inferences and comment on the quality of the inferences with respect to the following ques-tion: What are the conditions under which auto ignition of jet flames might occur, for release of a steam-hydrogen or hydrogen jet into an ambient mixture? .
- 5. Suspended Water Evaluate the influence of suspended water droplets on hydrogen combustion in a hydrogen-nitrogen-oxygen-steam mixture with respect to the following questions: (i) What is the influence of suspended water as a function of droplet size and volumetric density on the limiting concentrations for hydrogen deflagrations and detonations? (ii)
What is the nature of suspended water formed as a result of bulk condensation of steam in the subject mixtures? (iii) What are initial droplet sizes and what are the effects of coagulation?
Af fected Documents --- None
. Status --------------- The Commission held a mid year review of hydrogen research programs on April 21-22, 1986. The review status of five projects at SNL (Albuquerque, N.M. , and Livermore, CA) and LANL was presented. The final report will be sent to the Commission after normal Academy review on July 31, 1986.
Problem / Resolution -- The 1/4 scale tests sponsored by the Mark III Hydrogen Control Owners Group have slipped for at least a year from the original July 1985 date. Data from these tests are needed to resolve a number of open items.
i A48-2 As of 3rd Quarter FY-86
G:neric Issue #A-48 The licensing review for Sequoyah (ice condenser) is expect-ed to be completed in September 1986. The licensing review for Grand Gulf (Mark III) is expected to be completed in March 1987.
Technical Resolution -
Milestones Original Current Actual Complete EPRI Hydrogen Test 11/83 -
01/84 Program Issue. Hydrogen Rule 07/83 -
02/25/85 Complete Sequoyah Licensing 09/86 - --
Review for Hydrogen Control Complete Grand Gulf Licensing 03/87 - --
Review for Hydrogen Control National Research Council 07/86 07/86 --
Hydrogen Report on Findings Pecommendations Issue Generic Summary Report Issued by DSR0 for ' Staff Comment 06/87 06/87 --
Staff Comments to OSRO 07/87 07/87 --
Completed Package to Director, 08/87 08/87 --
NRR Package to CRGR N/A N/A --
CRGR Review Complete N/A N/A --
Issue Summary Report 09/87 09/87 --
A48-3 As of 3rd Quarter FY-86
. . - . . . - - . - , , , - , , . . - - -- . w .~. -- ,----.. , . . - ---
{
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Tyge Level Office /Div/Br Manager TACS No.
A-49 USI Active-L1 NRR/OSR0/RSIB H. Woods 48307 Title ---------------- Pressurized Thermal Shock Work Authorization --- Memorandum to William J. Dircks from Samuel J. Chilk dated December 28, 1981, Designation of PTS as an USI (SECY-81-687).
Contract Title -------
Pressurized Thermal Shock Program Assistance Contractor Name/ FIN -- PNL/8-2510 Work Scope ----------- Issue the PTS Regulatory Guide detailing how licensees are to meet the requirements of the PTS rule (10 CFR 50.61) that was promulgated July 23, 1985.
Affected Documents --- PTS Regulatory Guide (Format and Content of Plant-Specific PTS Safety Analysis Reports for PWRs), 1/86 Task SI 502-4.
Status --------------- Concurrence package with final Regulatory Guide for CRGR review is being cirquiated in NRR and will be circulated in RES soon. Public comments are now included in this package.
Problem / Resolution --- None Technical Resolution - None Milestones Original Current Actual Schedule for Final Rulemakina Issued by DST for Staff Comment 06/84 -
07/06/84 Staff Comments to DST 07/84 -
07/20/84 Completed Package to Director, 07/84 -
08/29/84 NRR Package to CRGR 08/84 -
09/14/84 CRGR Review Complete 09/84 -
11/07/84 Issued for Implementation 06/85 -
07/23/85 i
A49-1 As of 3rd Quarter FY-86
Generic Issue #A-49 Milestones Original Current Actual Schedule for Regulatory Guide Issue by DST for Staff Comment 02/86 - -
Staff Comments to-OST 03/85 -
07/15/85 Completed Package to 05/85 -
07/29/85 Director /NRR Package to CRGR 06/85 -
08/05/85 CRGR Review Complete 09/85 -
11/04/85 Issued for Public Comment 01/86 -
01/17/86 Public Comments Received 04/86 -
04/86 Revised Guide to Director /NRR 07/86 07/86 -
Package to CRGR 08/86 08/86 -
CRGR review complete 09/86 09/86 -
Issued (Final) 12/86 12/86 -
I A49-2 As of 3rd Quarter FY-86 l
l l
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Tyoe Level Office /Div/Br Manager TACS No.
B-5 Safety / Active-L1 NRR/DSR0/EIB L. Heller 07419 ,
Medium l
Title ---------------- Buckling Behavior of Steel Containments Work Authorization --- NRR FY-84 Operating Plan, (Appendix G)
Contract Title ------- None Contractor Name/ FIN -- None Wo rk Scope ----------- A containment structure is an asymmetrical shell due to large penetrations. The current staff position allows use of a symmetrical shell model fc.' buckling strength evaluation. To compensate for the uncertainty in this symplifying assumption, the staff requires a reduction factor of 25% on buckling strength. However, there is no guidance given by the staff as to what constitutes proper reinforcing. There are widely varying methods used. A combined analytical experimental pro-gram is needed to address this problem.
Af fected Documents --- SRP revision.
Status --------------- Results from a technical assistance contract and input from RES were used to prepare a draft staff position. The staff previously planned to develop an SRP revision based on this position. It is now recognized that this position is not sufficiently complete for general use in licensing. Develop-ment of a technical resolution for this generic issue will require some basic research to be conducted. Research agreed to redirect related research on buckling and this research will form the basis for revising the SRP.
Problem / Resolution --- Because of budget reductions, the Buckling Research Program has been essentially terminated. This has resulted in a 9-month delay in obtaining the results needed to prepare the proposed SRP revision.
Technical Resolution -
l Milestones Original Current Actual Results received from RES 07/86 07/86 -
Proposed SRP revision prepared. 06/85 11/86 -
Value/ Impact Statement prepared. 07/85 02/87 -
Final CRGR package forwarded to 09/85 04/87 -
DSR0 for processing.
B5-1 As of 3rd Quarter FY-86 i
l
Generic 1ssue #B-5 Milestones Original Current Actual NRR Director Review completed. 10/85 07/87 -
Review Package to CRGR. 11/85 08/87 -
CRGR review completed. 12/85 09/87 -
EDO approval. 01/86 09/87 -
Federal Register Notice of 02/86 10/87 -
Issuance of Proposed SRP Raised -
for Public Comment.
OMB Clearance (if applicable) 03/86 11/87 -
Division review of public 05/86 01/88 -
comments completed.
NRR Director review completed. 06/86 02/88 -
CRGR review completed. 07/86 04/88 -
EDO approv,al. 08/86 05/88 -
Federal Register Notice of 09/86 06/88 -
Issuance of SRP i
B5-2 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
B-6 Safety / Active-L1 NRR/DSR0/EIB J. Page 20179 High Title ---------------- Loads, Load Combinations, Stress Limits Work Authorization --- NRR FY-84 Operating Plan (Appendix G)
Contract Title ------- None Contractor Name/ FIN -- None Work Scope ----------- This generic issue is complete except for decoupling the LOCA and SSE events. The decoupling involves developing a more rational. approach to the design of components and supports to withstand a spectrum of events, and events in combination, the effects of low probability postulated events of varying proba-bilities, such as SSE plus LOCA. This plan will proceed with the necessary action to decouple the SSE-LOCA load combinations using probabilistic methods. One possible alternative approach is to reduce the postulated pipe break area using deterministic fracture mechanics procedures.
Affected Documents --- SRP Section 3.9.3.
Status ---------------- An ongoing research program for W and CE plants has completed the investigation of the probabiTity of having a LOCA induced directly by seismic loads, and found it to be 7 x 1012/ year for the large LOCA and 4 x 1012/ year for the small LOCA. The probability of having LOCA induced indirectly by structure or support failures under seismic loads was found to be 10 7/ year.
Research results and decoupling hypothesis were discussed in ACRS meetings on 03/29/83 and 06/09/83. At these meetings, the staff proposed a position which would decouple SSE and LOCA for all PWR primary loops based on the results of the research pro-gram. The ACRS letter of 06/14/83 concludes that the technical work supports decoupling for mechanical components which include instrumentation and controls and their supports. Similar research work for decoupling of LOCA and SSE for B&W and GE plants is proceeding and is expected to conclude in early 1986.
I Preliminary indications are that pipe rupture probabilities in GE reactor coolant loops are substantially greater than in any of the PWR vendors. In addition, a separate CRGR package on a limited application of the leak-before-break hypothesis for PWR main coolant loops in 16 W owners group plants, based on deterministic fracture mechanics analysis, has been approved under Generic Letter 84-04 issued by DL.
Problem / Resolution --- Revision of SRP Section 3.9.3 is being performed by RES in accordance with the " Plan to Implement the PRC Recommendations."
This revision will only permit decoupling of SSE and LOCA for PWR primary loop piping. A recommendation regarding decoupling B6-1 As of 3rd Quarter FY-86
Generic Issue #8-6
)
for BWRs will be made by RES at the conclusion of the researc.
study on GE plants. If this recommendation indicates that decoupling on certain classes of BWRs should be permitted by the SRP, the milestone schedule will have to be revised. The Piping Review Committee recommendations have been categorized as Generic Issue 119.
The Task Manager is preparing a memorandum recommending tnat Generic Issue B-6 be subsumed by Generic Issue 119.
Tnecefore, future tracking of this issue will be under Issue 119 along with other related piping issues.
Technical Resolution - For decoupling of SSE and LOCA loads, the probability of a LOCA occurrence due to an earthquake was under review to provide the probabilistic technical basis for the revision of SRP Section 3.9.3. In addition, a parallel effort has been proceeding to utilize the results of the ongoing leak-before-break studies to justify deterministically the reduction of the postulated pipe break area. The technical resolution has been identified.
The NRC Piping Review Committee evaluated all the research re-suits and provided recommendations on needed regulatory actions on licensing requirement changes as a part of an overall resolu-tion to nuclear piping design problems.
Milestones Original Current Actual Issued NUREG-0484 which contain - -
05/80 guideline or dynamic response combination methodology.
Revised SRP Section 3.9.3 to - -
07/81 incorporate criteria and guide-lines for load combination's and stress limits.
ACRS subcommittee on leak-before- - -
03/29/83 l break and decoupling.
ACRS full Committee meeting 05/83 -
06/09/83 Piping Review Committee to 02/85 -
02/85 provide recommendation for decoupling.
Confirmation from ELD that 04/85 -
04/85 l
change to GDC 2 not required.
Piping review committee final - -
5/85 report containing recommenda-tions for decoupling issued to EDO.
86-2 As of 3rd Quarter FY-86
Gtneric Issue #B-6 Milestones Original Current Actual Completion of draft SRP - -
09/85 Section 3.9.3 revision Completion of regulatory 03/86 -
03/86 analysis for SRP Section 3.9.3 revision CRGR review 04/86* 04/86* -
Publication of Federal Register 05/86* 05/86* -
Notice Public comment period closes 07/86* 07/86* -
Evaluation of public comments 09/96* 09/86* -
completed CRGR review of revised 11/86* 11/86* -
regulatory package completed EDO approval 12/86* 12/86* -
Final Federal Register Notice 01/87* 01/87* -
of Issuance of SRP revision
- All work on this project has been suspended pending guidance from CRGR.
Schedules indicated above will be revised by RES once work has resumed.
t t
?
9 B6-3 As of 3rd Quarter FY-86'
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Nunber Type. Level Office /Div/Br Manager TACS No.
B-17 Safety / Active-L1 NRR/DHFT/HFIB TBD TBD Medium Title ---------------- Criteria for Safety Related Operator Actions idork Authorization --- NRR FY-84 Operating Plan (Appendix G)
Contract Title ------- To Be Determined Contractor Name/ FIN -- To Be Determined Work Scope ----------- The work scope and milestones necessary to complete this are provided in HF-01 issue HFPP-4.3.
Affected Documents --- To Be Provided Later Status --------------- To Be Provided Later Problem / Resolution --- To Be Provided Later Technical Resolution -
Milestones Original Current Actual Milestone being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
I B17-1 As of 3rd Quarter FY-86
(
1 1
l _ _ _ _ _. _. .-.
_g .. __ _ _ - . ___ _-. __
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action . Task Number h Level Office /Div/Br Manager TACS No.
B-55 Safety / Active-L1 NRR/DSR0/EIB F. Cherny 48771 Medium Title ---------------- Improve Reliability of Target Rock Safety-Relief Valves Work Authorization --- NRR FY-84 Operating Plan, (Appendix G)
Contract Title ------- None Contractor Name/ FIN -- None Wo rk Scope ----------- Review BWR utility approaches to increasing SRV reliability to
- obtain sufficient data base to support the conclusion that this issue has been resolved. The utility approaches may include
(1) demonstrating sufficient reliability of 3-stage valves by strict conformance to NSSS vendor instructions; (2) demon-
,' strating sufficient reliability of 2-stage valves after design and/or system modifications, and (3) using different valves and demonstrating their reliability.
Affected Documents --- None Status --------------- A report was submitted by the Owners Group (OG) in June 1984 that was expected to resolve the issue. A subsequent Boston Edison report on experience at Pilgrim indicated that the recommenda-tions of the OG report were not sufficient to resolve this issue. The OG has recognized the need to pursue this problem
, further and has evaluated several potential new pilot disk l materials that could eliminate excessive setpoint drift l resulting from stuck pilot disks. They have assembled a material selection panel composed of experts in both materials technology and nuclear valve design. The panel has selected PH 13-8Mo stainless steel as the candidate material to be tested in sever.a1 plants during upcoming fuel cycles. The results of this effort will be evaluated by the OG over a two year period. In January 1986, Carolina Power and Light (CP&L) reported the controversial results of recently com-plated Brunswick 2 SRV tests. Six of eleven SRVs failed to open at 10 percent or more above normal setpoint. On May 7, 1986, CP&L submitted an LER which documented the SRV failure data. In addition, the LER included the results of analyses that indicate that, taking the large setpoint drift into account for the worst case design basis transient, Brunswick 2 would still have met the applicable ASME pressure limit. The NRR staff is in agreement with the OG that the selection of new pilot disk material is an acceptable way to resolve the stuck pilot disk concern. Based upon the assumption that PH 13-8Mo pilot disks will eliminate the stuck pilot disk concern, a draft resolution memorandum has been prepared and was distri-buted to NRR and IE for comments on June 4, 1986. It is anticipated that the final resolution memorandum can be issued by June 30, 1986.
B55-1 As of 3rd Quarter FY-86
. . , _ . - - - - _ _ _ _ . - . _ , _ , _ , . _ _ - , , , , . _ , _ - -, . . _ _ _ . _ - _ _ _ , ~ , - _ . - - - . - . _ . - _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _
i Generic Issuo #B-55 Problem / Resolution --- The resolution of this issue is aimed at increasing the reli-ability of these valves to meet the current plant Technical Specifications. Pilot Disks of PH 13-Mo will be tested in certain plants with the objective of eliminating excessive setpoint drift. The actions taken thus far by the OG and the ,
OG program are responsive to the issue. We expect that this 1 issue will be resolved with minimum staff effort needed only to monitor their program. We will work with the OG and pro-vide them with our evaluation of their program and indicate our intent to rely on their program to resolve the issue. A generic issue close-out memorandum will reflect this under-standing. At the completion of the OG program, which is not expected until 1987, the staff will review the industry resolution. NRR will establish a new generic issue only if the resolution is inadequate or if not implemented properly by the utilities involved.
Technical Resolution -
Milestones Original Current Actual Meeting with BWR Owners 12/83 -
11/83 Setpoint Drift Committee BWR Owners Report submitted 07/84 -
06/84 Boston Edison Report submitted - -
08/84 Completion of NRR evaluation of 10/84 -
10/84 Owners Group and Boston Edison reports l
Communication to OG re: NRC - -
03/85 comments / concerns.
l OG presentation to the staff 10/85 -
10/85 Staff receives Owners' program 10/85 -
10/85 for eliminating set point drift Owners begin to install new 01/86 -
01/86 pilot disks to test in plant for one fuel cycle Issue close-out memorandum 12/85 07/86 -
855-2 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type, Level Office /Div/Br Manager TACS No.
B-56 Safety / Active-L1 NRR/DSR0/RSIB A. Rubin 49942 High Title ---------------- Diesel Reliability Work Authorization --- NRR FY-83 Operating Plan (Appendix G).
Contract Title ------- Actions to improve and maintain diesel ge'nerator reliability.
Contractor Name/ FIN -- BNL/A-3817 Wo rk Scope ----------- The work scope of B-56 is closely coordinated with the resolu-tion of USI A-44, Station Blackout. (Both issues are being managed by the same Task Manager). The proposed resolution of USI A-44 includes, among other things, a recommendation that the reliability level of emergency diesel generator (EDG) be maintained at or above specified acceptable reliability levels.
As a step towards meeting this objective, the NRC sent Generic Letter 84-15 to all operating reactor licensees. This letter contains the following three items: (1) The staff's approach for reducing the number of cold fast start surveillance tests; (2) Evaluate licensees submit current diesel generator reli-ability data and programs; and (3) A request that licensees submit a description of their diesel generator reliability program, if any, and example performance technical specifi-cations for diesel generator reliability.
Responses to the generic letter from all licensees have been received and reviewed.
In addition, the staff met with industry representatives including licensees, DG manufacturers and NSAC to discuss diesel generator testing. Comments have also been received from ACRS and EPRI regarding DG testing.
Evaluations of the response to the. generic letter and other comments received will be used in developing a diesel generator reliability program to resolve this issue compatible with the resolution of USI A-44.
Affected Documents --- NUREG/CR-4557, "A Review of Issues Related to Improving Nuclear Power Plant Diesel Generator Reliability," was published in i
April 1986. Standard Technical Specifications and Regulatory Guide 1.108 (as a long-term effort associated with the final resolution of USI A-44).
S ta tu s --------------- A generic letter 84-15 was sent out to all licensees on July 2, 1984, and responses have been received from all licensees.
B56-1 As of 3rd Quarter FY-86 4
Generic Issue #B-56 MPA D-19 has been established to implement Item #1 of the generic letter.
NUREG/f"t-4557 was issued in April 1986 documenting BNL's review of items 2 and 3 of Generic Letter 84-15.
A task has been added to the BNL contract to develop recommendations for a diesel generator reliability program to satisfy the proposed resolution of USI A-44 relating to maintaining highly reliable diesel generators.
Problem / Resolution --- None Technical Resolution -
Milestones Original Current Actual Draft Technical resolution - -
02/03/83 identified Issued by Director, DSI for 02/83 -
02/03/83 staff comment.
Package to Director, NRR 04/83 -
03/28/83 Package to CRGR 05/83 -
07/01/83 CRGR review complete. 06/83 -
07/27/83 Scope of issue modified to - -
09/27/83 coordinate technical resolution of B-56 with USI A-44 Scope of issue modified tn - -
11/14/83 consider number of cold fast start surveillance tests.
Coordinated GI B-56 and 02/84 -
01/24/84 USI A-44 CRGR package sent to Director, NRR.
Revised package to CRGR 04/84 -
03/06/84 CRGR review complete. 05/84 -
05/08/84 l
Issued 50.54(f) generic letter 06/84 -
07/02/84 (84-15) to licensees l
Received public comments 09/84 -
11/01/84 Issued technical assistance 06/85 -
06/20/85 contract to BNL l
l l
B56-2 As of 3rd Quarter FY-86
Generic Issue #B-56 Milestones Oriainal Current Actual Publish contractor report on 04/86 -
04/86 licensee response to 50.54(f) letter Develop diesel generator 10/86 10/86 -
reliability progrcm Final technical resolution to 11/86 11/86 -
divisions for comment Staff comments to DSR0 12/86 12/86 -
CRGR package to Director, NRR 01/87 01/87 -
Final package to CRGR 03/87 03/87 -
CRGR review complete 05/87 05/87 -
Issue for public comment 06/87 06/87 -
Received public comments 08/87 08/87 -
Final resolution to NRR 09/87 09/87 -
Director Final resolution to CRGR 10/87 10/87 -
Issue final resolution 11/87 11/87 -
I B56-3 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue , Issue Action Task Number Type Level Office /Div/Br Manager Tac No B-61 Safety / Active-L1 NRR/DSR0/RRAB A. Busiik 52715 Medium Title ---------------- Allowable ECCS Equipment Outage Periods Work Authorization --- NRR FY-84 Operating Plan (Appendix G)
Contract Title ------- To Be Determined Contractor Name/ FIN -- To Be Determined Work Scope ----------- In general, plants will be classified such that in each class, similar ECCS outage unavailabilities will have similar impacts on risk. The effect of a given ECCS availability on risk will be determined, for each class of plant, as well as the impacts 4
J of any changes in allowable ECCS outage period. Consideration of support system outages must be included. Details of the work scope are contained in the draft action plan.
Affected Documents --- Technical Specification changes are possible.
Status --------------- Task I has been completed.
Problem / Resolution --- Because of the workload at BNL, especially that related to the Operational Safety Reliability Research (OSRR) program, the work on Task II has been delayed and will not be completed until November 1986. The other milestones have slipped accordingly.
Technical Resolution -
Milestones Original Current Actual Draft Task Action Plan 01/84 -
01/30/84 issued for DD approval
! Coordinate Technical Resolution 04/84 07/84 08/21/84 with RES complete.
Task Action Plan approved 05/84 08/84 07/25/84 by Division Director Task I-Methodology Review and 11/84 04/85 04/30/85 development completed i Task II-Apply to a PWR or BWR 02/85 11/86 -
I Apply Methodology to a 08/85 07/87 -
Selection of Plants l
861-1 As of 3rd Quarter FY-86
( _
Generic Issue #B-61 Milestones Original Current Actual Develop a Licensing Position Develop an Initial 03/86 08/87 -
Recommendation for Staff Comments Final Technical Resolution 04/86 09/87 -
Prepare CRGR Package 06/86 12/87 -
Review of CRGR Package 07/86 01/88 -
by Division Directors NRR Director Review 08/86 02/88 -
Complete Review Package to CRGR CRGR Review and EDO 09/86 03/88 -
Approval Completed Issuance of Federal 11/86 04/88 -
Register Notice for Public Comment Sixty Day Comment Period 01/87 06/88 -
Ends Division Review of Public 02/87 07/88 -
Comments Completed, and final CRGR package completed NRR Review of CRGR package 04/87 08/88 -
completed (Division Review and NRR Director Review)
CRGR Review and EDO Approval 05/87 09/88 -
Completed Issuance of Proposed Changes 07/87 10/88 -
to Technical Specifications B61-2 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM i
l Issue Issue Action. Task Number h Level Office /Div/Br Manager TACS No.
B-64 Safety / Active-L1 RES/DET/CHEB K. Steyer 04765 NR Title ---------------- Decommissioning of Reactors i
Work Authorization --- NRR FY-84 Operating Plan, (Appendix G).
Contract Title ------- Decontamination and Decommissioning Review Contractor Name/ FIN -- PNL/8-2342 Work Scope ----------- Develop a general decommissioning policy, prepare the atten-dent changes in regulations, develop the detailed information needed for use in licensing decisions for decommissioning, and establish guidance for facilitation of decommissioning.
Affected Documents --- 1. 10 CFR Part 50 and 51 amendments.
- 2. Regulatory Guide 1.86 revision,
- 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.
1 Status ---------------
l Draft final rule changes and other package material are targeted for completion in November 1986.
Problem / Resolution --- The SRP schedule was previously slipped to accommodate the
! anticipated date of RES input. Schedule still dependent j on RES input (see note below).
I Technical Resolution - Published rule changes on decommissioning, issue new regula-l tory guides and revision to R.G. 1.86, issue new standard review plan on decommissioning.
t Milestones Oriainal Current Actual CRGR review completed on - -
08/08/84 decommissioning rule (Research)
EDO approval of decommissioning - - -
09/07/84 SECY-84-354 (Research)
Commission Approval of 12/84 -
12/84 SECY-84-354 (Research)
Issuance of draft rule 02/85 -
02/11/85 change for public comment Format and Content for Decosrais- 02/84* -
06/85 sioning Plans (from Research)
I i
I 864-1 As of 3rd Quarter FY-86 l -
t I _ - . _
G:neric Issue #B-64 Milestones Oriainal Current Actual Issuance of SRP Section**
Issue transfer ciemo to RES 01/86 -
01/86 SRP revision package to Div. 06/S4 - -
Director for review NRR Director Review completed 07/84 - -
Review Package to CRGR 08/84 - -
l CRGR review completed 09/84 - -
EDO approval 09/84 - -
Federal Register Notice of 10/84 - -
Issuance of proposed RG and SRP for Public Coment OMB Clearance, if applicable 01/85 - -
Division review of public 01/85 - -
comments completed NRR Director review completed 02/85 - -
CRGR review completed 03/85 - -
EDO approval 03/85 - -
Federal Register Notice of 04/85 - -
Issuance of SRP Issue Decommissioning Rule Extended public comment period 07/85 -
07/12/85 complete i
Revised draft rule incorporating 02/86 11/86 -
pubife comments ready for RES management review Revised draft rules 08/86 06/87 -
l public comments reviewed and approved by CRGR l Final rules noticed in the 01/87 10/87 -
l Federal Register 80riginal milestone dates necessary to resolve this issue were based on the receipt of input on format and content for Decommissioning Plan from RES.
- The SRP will be issued within fourteen months of the publication of the final rule. ,
864-2 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM i
Issue Issue Action . Task Number ]'ype_,_ Level Office /Div/Br Manager TACS No.
C-8 Safety / Active-L1 NRR/DSR0/RSIB L. Riani 51476 High Title ---------------- Main Steam Line Leakage Control (BWR)
Work Authorization --- NRR FY-84 Operating Plan (Appendix G).
Contract Title'------- MSIV Leakage and LCS Failure l Contractor Name/ FIN -- PNL/8-2529 Work Scope ----------- Review MSIV leakage and LCS failures with respect to plant maintenance and operating practices and equipment design and orientation. Provide an assessment of the realistic offsite doses using the LCS versus the normal steam path under LOCA conditions. The evaluation of this issue will also include utilities' efforts to reduce MSIV leakage and LCS failures. -
Affect 1td Documents --- Issue NUREG-1169. Revise and Issue Regulatory Guide 1.5 (To be determined). Revise and Issue SRP Change to Section 6.7 and 15.6.4 (To be determined). Revise and Process Plant Specific and STS Changes (To be determined).
i' Status --------------- On 06/17/86, the BWR Owners' Group (8WROG) Committee on MSIV Leakage Control made a presentation to the staff on their review and recommendations concerning future course of issue l resolution. Draft NUREG issued. The final NUREG which pro-
! vided the technical findings for this issue will be published in July 1986. A generic letter will also be issued to all BWR licensees for information only. The information letter will identify options available to licensees pending final resolu-tion of Generic Issue C-8. The issue will then be transferred from DBL to DSRO. The CRGR package will then be prepared and submitted for approval.
Problem / Resolution --- Updated scheduled will need to be assessed by DSRO once the NUREG is issued by DBL.
Technical Resolution - Allow ifcensees to delete MSLLCS from Tecn. Specs. and increase MSLIV leakage liatts.
! s j Milestones Oriainal Current Actual Task Action Plan approved by 10/83 -
10/31/83 Director, DSI.
Develop minimum design criteria 03/84 04/18/84 for alternative equipment for LOCA mitigation.
1 C8-1 As of 3rd Quarter FY-86 9
Gin:ric Issua #C-8 Milestones Original Current Actual Received Initial BWROG Submittal - -
04/09/84 Revised Work Plan based on - -
05/25/84 Submittal Revised Work Plan Approved by OD - -
06/01/84 Revised request for Technical - -
06/15/84 Assistance to DD for approval Revised TA request Approved 08/84 -
07/03/84 by DD Complete Review of Literature 08/84 -
08/15/84 search Complete Review of BWROG 09/84 -
06/14/85 recommendations Review PNL model for filling, 07/85 -
08/09/85 deposition and release processes in BWR steam lines under leaking MSIV conditions.
Complete review of Effectiveness 10/84 -
11/85 of BWROG recommendations Complete review of PRA study 11/84 -
11/85 of different alternatives.
Complete review of: (1) baseline 03/85 -
11/85 offsite dose calculations, (2) thermal-hydraulic modeling, and (3) alternate offsite dose calcu-lations to determine the effects of a LOCA and to determine maximum .
leakage rate within Part 100 for most favorable method).
Complete review of compartment 10/85 -
11/85 contamination l Complete NUREG 12/85 -
06/86 Issue memorandum to Notify 07/86 07/86 -
CRGR of intent to publish NUREG-1169 and issue a Generic Letter for information only.
Issue NUREG-1169 07/86 07/86 -
Issue generic letter to all 08/86 08/86 -
BWR licensees C8-2 As of 3rd Quarter FY-86
Generic Issue #C-8 Milestones Original Current Actual Issue transfer memo to DSR0 08/86 08/86 -
CRGR package approved by 01/86 TBD -
Director, DSRO. Sent to Division Directors for comment.
Comments incorporated. CRGR 02/86 TBD -
package sent to Director, NRR.
Director, NRR review complete. 03/86 TBD -
Package sent to CRGR.
CRGR review complete. 04/86 TBD -
ACRS review complete. 04/86 TBD -
t Federal Register Notice 05/86 TBD -
issued for public comment.
Incorporation of comments. 09/86 TBD -
Package sent to Director, NRR.
Director, NRR ieview caplete. 10/86 TBD -
Package sent to CRGR.
CRGR review complete. 11/86 TBD -
Federal Register Notice issued. 12/86 TBD -
i l
C8-3 As of 3rd Quarter FY-86
{
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type. Level Office /Div/Br Manager TACS No.
I.A.2.4 Licensing NRR/0HFT Title ---------------- NRR Participation in Inspector Training Work Authorization --- NUREG-0660 Contract Title ------- To be provided Contractor Name/ FIN -- To be provided Work Scope ----------- To be provided Affected Documents --- To be provided S ta tu s - - -- - --- -- --- - - To be provided Problem / Resolution --- To be provided Technical Resolution - To be provided Milestones Original Current Actual l
l
~
1 IA24-1 As of 3rd Quarter FY-86 i
1 ..
I
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM i
Issue Issue Action Task Number Type _ Level Office /Div/Br Manager TACS No.
I.A.2.6(1) Safety / Active-L1 NRR/0HFT/MTB J. Persensky None High Title ---------------- Revise Regulatory Guide 1.8 Work Authorization --- THI Task Action Plan Contract Title ------- None Contractor Name/ FIN -- None W'o rk Scope ----------- The work scope and milestones necessaty to complete this issue are provided in HF-01 issues HFPP-1.2.
Affected Documents --- Same as above S ta tu s --------------- Same as above Problem / Resolution --- Same as above Technical Resolution -
Milestones Original Current Actual Milestones being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
m._
IA26-1 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
I.A.3.3 Safety / Active-L1 RES/DRA0/HFSB T. G. Ryan None-High Title ---------------- Requirements for Operator Fitness Work Authorization --- TMI Task Action Plan Contract Title ------- None Contractor Name/ FIN -- None Work Scope ----------- A rule (amending 10 CFR 50.54) is being promulgated requiring licensees with an operating license for a nuclear power unit issued under 10 CFR 50.21(b) or 50.22 to establish and implement written procedures designed to provide reasonable assurance that personnel with access to nuclear power plants are not under the influence of alcohol, other drugs or otherwise unfit for duty.
Affected Documents --- Issue policy statement.
Status --------------- On October 24, 1984, the Commission notified the staff that it would not promulgate a rule on fitness for duty for a minimum of two years, but would issue a policy state-ment on the subject (M841017). A proposed policy state-ment was submitted to the Commission on January 17, 1985, as SECY 85-21. In a separate action, a notice withdrawing the final fitness for duty rule submitted to the Commission on April 12, 1985, as SECY 85-21A. The proposed policy statement (SECY 85-21) was. reaffirmed by the staff in SECY 85-128 submitted to the Comission on August 26, 1985. SECYs 85-21, 21A, and 218 are being reviewed by the Commission for concurrence and publication, as appropri-ate in the Federal Register on or about 1 February 1986.
Technical Resolution -
Milestones Oriainal Current Actual Fitness for Duty Rule:
Issue Draft Rule for Public - -
08/82 Comment Complete Division Review - -
03/83 Complete Office Concurrence 04/83 -
06/83 Complete CRGR Review 05/83 -
07/29/83 Complete ACRS Review 05/83 -
08/05/83 IA33-1 As of 3rd Quarter FY-86
Generic Issue #I.A.3.3 Milestones Original Current Actual Complete Commission Review 06/83
- 10/24/85 Issue Final Rule Federal 07/83 * -
Register Notice Issue Final Rule 07/83 * -
~
Policy statement, SECY 85-21 - -
01/17/85 submitted to Commission for approval Withdrawal Notice, SECY 85-21A - -
04/12/85 submitted to Commission for approval Reaffrimation of policy statement - -
08/26/85 SECY 85-218, submitted to the Commission l
Commission approved policy 02/86 02/86*- -
statement and withdrawal notice Issue Federal Register Notice 02/86 02/86* -
withdrawing fitness rule Publish Policy Statement 02/86 02/86* -
Issue close-out memorandum 02/86 06/86* -
to EDO
- Final Rule will not be issued based on Commission discussion. Milestone dates necessary to complete this issue are dependent upon issuance of a Policy Statement approved by the Commission and withdrawal notice for fitness for duty rule.
. IA33-2 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM l Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
I.A.4.2(1) Safety / Complete NRR/DHFT/0LB J. Wachtel None High Title ---------------- Research on Training Simulators Work Authorization --- TMI Task Action Plan contract Ti,tle ------- Simulator Experiments Contractor Name/ FIN -- ORNL/B-0821 Work Scope ----------- This project will use experiments on nuclear power plant training simulators supported by field data collection to provide a data base of operator performance to address issues associated with the operational safety of nuclear power plants. On the basis of the data obtained, con-clusions regarding these issues can be made along with recommendations for considerations as regulatory guidance.
Affected Documents --- None Status --------------- Experiment on BWR Plant completed and ORNL TM 9327 issuesd in 12/84. PWR Experiment completed and NUREG/CR-4280 issued in 9/85.
Problem / Resolution --- None Technical Resolution -
Milestones Original Current Actual Develop FY83 Research Plan 05/83 -
06/83 Conduct.FY83 Experiment 05/83 -
09/83 Develop FY84 Research Plan 02/84 -
04/84 Prepare Report 09/84 -
12/84 Conduct FY84 Experiments 12/84 -
12/84 Prepare FY85 Simulator 09/85 -
09/P5 Experiment Report Issua close-out memorandum 06/86 06/86 -
to EDO IA42-1 As of 3rd Quarter FY-86
THIS PAGE LEFT BLANK INTENTIONALLY l
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. IA42-2 As of 3rd Quarter FY-86
-n- - - .- ., , _ _, - - - - -p- - - -
GENSRIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Tyge_ Level Office /Div/Br Manager TACS No.
I.A.4.2(4) Safety / Active-L1 NRR/DHFT/0LB B. Boger 42454 High Title ---------------- Review Simulators for Conformance to Criteria Work Authorization --- TMI Task Action Plan Contract Title ------- None Contractor Name/ FIN -- None Work Scope ---'------- The work scope and milestones necessary to complete this issue are provided in HF-01 issue HFPP-3.3.
Affected Documents --- Same as above Status --------------- Same as above Problem / Resolution --- Same as above Technical Resolution -
Milestones Original Current Actual Milestones being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
l l
l l
l l
l IA42-3 As of 3rd Quarter FY-86
i l
- GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
I.A.4.4 Licensing RES Title ---------------- Feasibility Study of NRC Engineering Computer Work Authorization --- NUREG-0660 Contract Title ------- To be provided Contractor Name/ FIN -- To be provided
-Work Scope ----------- To be provided Affected Documents --- To be provided Status --------------- To be provided ,,
Problem / Resolution --- To be provided Technical Resolution - To be provided Milestones Original Current '- Actual ~~
i _
i a
1 l
A Y
.r~~
I IA44-1 As of 3rd Quarter FY-86 l
l
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Tyge_ Level Office /Div/Br Manager TACS No.
I . B.1.1 Safety / Inactive-L1 NRR/DHFT/HFIB TBP None (1 - 4) Medium Title ---------------- Organization and Management of Long Term Improvements Work Authorization --- TMI Task Action Plan Contract Title ------- None Contractor Name/ FIN -- None Work Scope ----------- None Affected Documents --- Same as above Status --------------- All developmental work on " Organization and Management" has been suspended due to budget constraints. See also Technical Resolution.
Problem / Resolution --- Same as above Technical Resolution - The NRC is moving toward performance-based rather than prescription regulation (1986 Policy & Planning Guidance -
NUREG-0885). The NRC is approaching Management and Organi-~
zation by improving its responsiveness to licensee perfor-mance, e.g., SALP improvement.
l l
l 1811-1 As of 3rd Quarter FY-86
t 1
t THIS PAGE LEFT BLANK INTENTIONALLY .
\ %
)
's
't 1811-2 As of 3rd Quarter FY-86 .
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
I . B .1.1 Safety / Subsumed IE/QAVT/QA8 M. Malloy None (6,7) Medium Title ---------------- Prepare and Issue a Revision to Regulatory Guides 1.33 and 1.8 Work Authorization --- TMI Task Action Plan Contract Title ------- None Contractor Name/ FIN -- None Wo rk Scope ----------- Regulatory Guide 1.33 - QAVT/QAB will revise and issue a change to the guidelines contained in this Guide. GI 775 subsumed the issue, and information pertaining to the changes in the guidelines is now included in GI #75, Subtask 1.
Regulatory Guide 1.8 - HFSB will revise and issue a change to the guidelines contained in R.G. 1.8 concurrent with the work scope of HF-01 issues HFPP-1.2 and 3.4.
Affected Documents --- Regulatory Guides 1.33 and 1.8 Status --------------- Refer to GI #75 subtask 1 and HF-01 issues HFPP-1.2 and 3.4 for Status.
Problem / Resolution --- None Technical Resolution -
Milestones Original Current Actual Regulatory Guide 1.8 i
Refer to HF-01 issues HFPP-1.2 - - -
and 3.4 schedule for issuing a revision to Reg. Guide 1.8.
Regulatory Guide 1.33 Refer to GI #75(1) -
07/87 -
schedule for issuing a revision to Reg. Guide 1.33*
- By memorandum from R. DeYoung for W. Dircks dated July 26, 1984, milestones necessary to complete Task Item I.B.1.1 Subtasks 6 and 7, have been subsumed by milestones for Generic Issue No. 75 subtask 1.
1811-3 As of 3rd Quarter FY-86 l
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l
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
. q Issue Issue Action Task ;
Number Tyge_ Level Office /Div/Br Manager TACS No. j I.C.9 Safety / Active-L1 NRR/0HFT/HFIB J. Bongarra 43505 ;
Medium Title ---------------- Long-Term Program for Upgrading of Procedures hork Authorization --- TMI Task Action Plan Contract Title ------- Develop recommended interfaces among plant operating procedures.
Contractor Name/ FIN -- PNL/8-2966 Work Scope ----------- The work scope and milestones necessary to complete this issue are provided in HF-01 issues HFPP-3.4 and HF-02.
Af fected Documents --- Same as above Status --------------- Same as above Problem / Resolution --- Same as above Technical Resolution -
Milestones Original Current Actual Milestones being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
l 109-1 As of 3rd Quarter FY-86 l
l GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type level Office /Div/Br Manager TACS No.
I.D.3 Safety / Active-L1 RES/DET/EEICB S. Aggarwal 41030 Medium .
Title ---------------- Safety System Status Monitoring Work Authorization --- TMI Task Action Plan
. Contract Title ------- Verification, System Status, Automatic vs Manual Contractor Name/ FIN -- PNL/B-2360 Work Scope ----------- PNL has reviewed the effectiveness of systems and pro-cedures related to safety system status monitoring and has recommended a regulatory position on this issue. PNL findings indicate that a revision of R.G. 1.47 is neces-sary and further that this new revision should be applied to all plants. Based on the PNL recommendations, OHFS has transfered responsibility for this issue to RES
. (revise R.G. 1.47). Responsibility for issue transferred back to NRR.
! Affected Documents --- Revision to R.G. 1.47.
Status --------------- All technical reports on this issue are complete. The i
project final report has been published as NUREG/CR-3621.
This final report includes guidelines for improving system status monitoring as well as the final recommendation of PNL on a regulatory position. Their recommendation is to revise R.G. 1.47 and apply it to all plants. Supplemental work may be required of the contractor to support revision of R.G.1.47 by RES, e.g. , value/ impact analysis, resolu-tion of public comment, and development of a draft revi-sion to R.G. 1.47. PNL has submitted a proposed program fer this supplemental work.
Problem / Resolution --- Response by RES to NRR dated April 17, 1985 identifies need to coordinate plan to revise R.G. 1.47 and fund work.
The termination of human factors research funding at the l
t end of FY 1985 necessitates that this issue be reassigned to DHFS/NRR.
Technical Resolution - The technical resolution of this issue will be the develop-ment of an NRC position regarding the need to revise R.G.
1.47 and to apply this revised version to all plants for compliance /backfit.
Milestones Original Current Actual Complete draft report of - -
06/04/82 current industry practices Submit prelininary recommendation - -
09/30/82 for regulatory position 103-1 As of 3rd Quarter FY-86
Gent.ric Issua #I.0.3 Milestones Oriainal Current Actual Submit tech report on effective- - -
11/30/82 ness of existing systems Submit tech report on effective- - -
12/15/82 ness of verification procedures Submit draft acceptance criteria - -
04/01/83 Submit draft guidelines for 07/01/83 -
07/83
" interim" improvement Submit program plan for 09/30/83 -
11/30/83 i
developing " full implementation" guidelines Submit final recommendations 09/30/83 -
02/15/84 for regulatory position Draft memo transferring issue - -
06/01/84 to RES complete Transfer memo approved by DD's 07/84 -
10/84 Transfer memo to Minogue approved 08/84 -
10/30/84 by NRR, Director RES provided milestone 09/84 -
04/17/85' necessary to complete issue and outlined problems with issuing Reg. Guide revision Issued memorandum for providing - -
11/25/85 milestones RES provides new milestone 05/86 08/86 -
dates necessary to resolve issue Prepare Task Control Form (TCF) 10/85 -
03/17/86 Obtain TCF Approval 10/85 -
05/05/86 Initial Draft Complete 10/85 - -
(Info Copy to CRGR/ACRS)
Division Review Complete 10/85 03/87 -
Develop Regulatory Analysis 03/86 06/87 -
Office Concurrence of CRGR 04/86 09/87 -
Package
103-2 As of 3rd Quarter FY-86
Gen 2ric Issu) #I.D.3 Milestones Original Current Actual
] Resolution of Comments 09/86 12/87 -
Printing and Distribution 09/86 01/88 -
Authorized Printed and Issued for Comment 10/86 02/88 -
Comment Period 01/87 05/88 -
Resolution of Comments 02/87 08/88 -
Division of ELD review complete 04/87 09/88 -
CRGR review complete 07/87 10/88 -
ACRS review complete 07/87 11/88 -
Resolution of comments 09/87 12/88 -
Office concurrence obtained 10/87 01/89 -
Printed and Issued 12/87 02/89 -
I J
t 1
103-3 As of 3rd Quarter FY-86 l
. . . - _ _ -, _. - . . . _ ~ , , - _ _ _ _ _ . . . _ . _ _ . . , , _ _ __.-_.._,____________.I
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Tyge_ Level Office /Div/Br Manager TACS No.
I.D.4 Safety / Active-L1 NRR/0HFT/HFIB None None High Title ---------------- Control Room Design Standard Work Authorization --- TMI Task Action Plan Contract Title ------- None Contractor Name/ FIN -- None Work Scope ----------- The work scope necessary to complete this issue is provided in Issue HF-01 (HFPP-3.4.1)
Affected Documents --- Same as above Status --------------- On hold for the indefinite future. No NRR resources are budgeted in FY 86 or 87 for this high priority issue.
DHFT/HFIB will seek E00 concurrence with reclassifying this non-scheduled issue.
Problem / Resolution --- Same as above Technical Resolution -
Milestones Oriainal Current Actual None scheduled.
L 104-1 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Typ_e_, Level Office /Div/Br Manager TACS No.
I.D.5(3) Safety / Active-L1 RES/DET/EEICB W. Farmer 96005 NR Title ---------------- On-Line Reactor Surveillance Systems Work Authorization --- TMI Task Action Plan Form 173 No. 60-83-061 dated November 30, 1983 No. 60-83-182 dated March 17, 1983.
Contract Title ------- " Continuous On-Line Reactor Noise System Evaluations" Contractor Name/ FIN -- ORNL/B-0828.
Work Scope ----------- The objective of this effort is to perform research to determine the feasibility of detecting and diagnosing nuclear power plant operating anomalies using a continuous on-line noise surveillance system and to perform demon-strations of such a system in an NRC licensed commercial PWR plant and an NRC licensed commercial BWR plant.
Affected Documents --- None.
Status --------------- Work is in progress. A demonstration of system feasi-bility at an operating PWR has been completed. The sur-veillance instrument system has been installed at Peach Bottom Unit 2 and is to be used to demonstrate system feasibility at a BWR.
Problem / Resolution --- Determine the feasibility of the system to detect and diagnose LWR operating anomalies using continuous on-line surveillance.
Technical Resolution -
Milestones Original Current Actual I
Install System at a PWR - -
09/80 Complete PWR Data Acquisition 06/84 -
01/84 Install Systes at a BWR 04/84 -
06/85 Complete BWR Data Acquisition 04/87 12/87 -
Issue transfer memo to NRR with 04/88 04/88 -
data, recommendations and implementation NRR assessment of available 09/88 09/88 -
data, issue close-out memorandum or expand schedule 105-1 As of 3rd Quarter FY-86
THIS PAGE LEFT BLANK INTENTIONALLY l
l l
~ . -
i l
l l
l i
105-2 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Tyge_ Level Office /Div/Br Manager TACS No.
I.D.5(5) Safety / Active-L1 NRR/DHFT/HFIS None None High Title ---------------- Disturbance Analysis Systems Work Authorization --- TMI Task Action Plan Contract Title ------- None Contractor Name/ FIN -- None Work Scope ----------- The work scope necessary to complete this issue is provided in Issue HF-01 (HFPP-3.4.1)
Affected Documents --- Same as above Status --------------- On hold for the indefinite future. No NRR resources are budgeted in FY 86 or 87 for this medium priority issue.
"DHFT/HFIB will seek office concurrence with reclassifying this non-scheduled issue.
Problem / Resolution --- Same as above Technical Resolution -
Milestones Original Current Actual None scheduled.
105-3 As of 3rd Quarter FY-86
4 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task l Number h level Office /Div/Br Manager TACS No. I II.B.5 Safety / Active-L1 RES/DAE/FSRB M. Silberberg None {
j (1&2) High RES/DAE/CSRS R. T. Curtis 4
Title ---------------- Research on Phenomena Associated With Core Degradation and Fuel Melting Work Authorization --- THI Task Action Plan LRRP, Budget Authorization Document & tion
, Contract Title ------- Multiple contracts a
Contractor Name/ FIN -- SNL/INEL/BCL/PNL Work Scope ----------- Conduct an extensive experimental and analytical program on the behavior of damaged fuel, hydrogen generation, and control, j fuel structure interaction, containment analysis, and fission product release and transport as described in detail in NUREG-i 0900, Rev. 1 (April 1986), the Nuclear Power Plant Severe Accident Research Plan (Chapters 3 and 5). This program
- involves both in pile and out-of-pile tests with actual and
! simulated core and reactor structural materials and the development of codes to model the phenomena expected in the reactor.
i Affected Documents --- (1) NUREG-0900 Nuclear Power Plant Severe Accident Research Plan, Rev. 1 (April 1986).
(2) NUREG-1070 Severe Accident Policy Statement (July
] 1985).
(3) NUREG-0956 Reassessment of Technical Bases for LWR Accident Source Ters (Final expected July 1986).
(4) NUREG-1150 New Risk Profiles for Five Reference Plant l (Draft for Comment September 1986).
i Status --------------- Severe fuel damage in pile research is in progress in :
ACRR and the Canadian NRU reactors and complete in P8F.
Large scale ~ hydrogen tests are nearly complete at Sandia National Lab. Large scale out-of pile tests on core /
concrete interactions, direct containment heating and fission product transport in containment are continuing as is the development and assessment of computer codes such as SC0AP, HECTR, CORCON, MELPROG, TRAP-MELT, and CONTAIN.
Milestone charts for this work and a more complete descrip-tion of the work appears in NUREG-0900, Rev. 1. Integrated PRA analysis codes such as the Source Term Code Package i
(STCP) (complete 9/85) and MELCOR (1987) will be used for j extensive uncertainty analysis through FY 1988-89.
1185-1 As of 3rd Quarter FY-86 l
l i_ ._ - _ _ . _ _ _ _ . - - . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Generic Issue #II.B.5 (1 and 2)
Problem / Resolution --- A report (NUREG-1150) on severe accident risk rebase-lining is being prepared to assure that risk is being given appro-priate attention in the severe accident source term reassess-ment. This report is expected to be complete-September 1986.
Technical Resolution -
Milestones Original Current Actual Initial draft contractor - -
01/83 Source Term Report Source term estimates for 08/83 -
01/84 selected plants and accident sequences Thorough peer review of the 12/83 -
02/85 above scientific bases for reassessment Draft Reassessment of the 12/83 -
07/85 Technical Bases for Estimating Source Terms (NUREG-0956) d Final Reassessment of the 07/86 07/86 -
Technical Bases for Estimating Source Terms i (NUREG-0956)
Severe Accident Risk Rebase- 12/83 09/86 -
lining program draft report (NUREG-1150)
NRC Severe Accident Policy
- 11/85 -
07/85 J
Final Recommendations to the 06/84 11/87- -
Commission on Severe Accident Requirements for Operating Plans and Plants under -
Construction i
Issue close-out memo to EDO 06/88 06/88 -
I i
l IIB 5-2 As of 3rd Quarter FY-86 l
-_ _ _ _ ~ _ _ _
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number M. Level Office /Div/Br Manager TACS No.
II.B.5(3) Safety / Active-L1 RES/0AE/CSRB P. R. Worthington None Medium Title ---------------- Effect of Hydrogen Combustion on Containment Structures Work Authorization --- TMI Task Action Plan Contract Title ------- Hydrogen Behavior Program, Hydrogen Burn Survival, Hydrogen Combustion and Control Demonstration Experiment, Hydrogen Mitigation and Preventive Schemes, Hydrogen Mixing Studies.
Contractor Name/ FIN -- SNL, LANL/A-1246, A-1270, 8-8208, A-7247, and A-1336 Work Scope ----------- Provide the NRC with a better technical understanding of the threat posed by hydrogen burning during postulated lightwater reactor accidents. This work includes an understanding of deflagrations, global and local detonations, flame accelera-tion and the transition to detonation. The effect of burning on equipment and the efficiency of H2 e ntrol systems.
Affected Documents --- Severe Accident Research Plan (NUREG-0900, 8/84)
Status --------------- Programs are underway with major results expected in FY 1985 and the completion of the experimental program in early FY l 1987 and final analysis and close-out report written during FY 1987.
Problem / Resolution --- None Technical Resolution - Performing experiments and analysis for various plant and containment types to assess various scenarios and the efficiency of H 2control systems.
Milestones Original Current Actual Analysis of Sequoyah Plant 09/83 -
02/84 Review of Grand Gulf Plant 10/83 -
03/83 Hydrogen Igniter System Hydrogen Burn Equipment Survival 09/83 -
11/84 Report for Ice Condenser Effect of Sprays on Ignitors 09/83 09/86 -
Report l
l IIBS-3 As of 3rd Quarter FY-86 i
G:n:ric Issua #I1.8.5 (3)
Milestones Original Current Actual Effectiveness of Nonpowered 09/86 -
06/86 Igniters Effect of H Burns in Aerosols 10/83 10/86 -
ScopingStu$yReport Report on Possibility of Local 01/84 09/86 -
Detonation NTS Data Analysis for Premixed - -
05/85 Tests NTS Data Analysis for Continuous - -
05/85 Injection Tests NTS H 2 Demonstration Test Report 03/84 09/86 -
Large Scale Flame Acceleration 05/84 09/87 -
Tests Report MARCH-HECTR Analysis of Selected 12/83 -
02/85 Accident in an Ice-Condenser Containment Analysis of Hydrogen and Steam 02/82 -
02/84 Releases to Containment During Degraded Core Cooling Accidents HECTR Version 1.0 - -
02/85 Hydrogen-Steam Jet Flame - -
02/85 Facility and Experiments ,
HECTR Version 2.0 09/87 09/87 -
Light Water Reactor Hydrogen 05/87 05/87* .
Manual revision Research information Letter to 07/87 07/87 -
NRR and issue close-out memo to E00
" Not Funded in FY 1987.
IIBS-4 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Tyge_ Level Office /Div/Br Manager TACS No.
II.C.4 Safety / Active-L1 RES/DRA0/RR8 C. E. Johnson None
, Medium Title---------------- Reliability Engineering l Work Authorization --- TMI Task Action Plan Contract Title ------- Operational Safety Reliability Contractor Name/ FIN -- BNL/A-3282 l
Work Scope ----------- Evaluate the effectiveness of reliability program elements and techniques applicable to maintaining LWR safety during the operating life of the plant. Tasks include:
! (1) Survey generic issues and precursors to assess the
- effectiveness of reliability technology to help resolve current safety issues. .
'i (2) Visit 5 plants to identify reliability techniques that utilities have found to be effective, and identify the attributes (i.e., success criteria and reasonable applications) of successful reliability programs.
(3) Adapt reliability technology from other industries (for example, performance indicators and alert levels) for
.l trial application to LWRs.
(4) Evaluate the effectiveness of a reliability program j- through initial trial application to an example safety system at 1 plant.
] (5) Publish a technical report (NUREG/CR) that integrates j interim results from the above tasks to identify the
- essential elements of a reliability program, evaluate
! their effectiveness, and identify attributes of l successful reliability programs.
Affected Documents --- To be determined based on the results of this project.
S ta tu s --------------- The contractor is summarizing results to date in the i interim technical report (Task 5), a draft of which will be 4
completed by April 30, 1986.
l In response to a memorandum from Mr. Stallo dated February 26, 1986, RES plans to submit by June 30, 1986, in coordina-tion with NRR and IE, an evaluation of the current and poten-J tial needs for implementation of reliability assurance in j the regulatory program. Based on the conclusions of this
! evaluation, the submittal will outline a coordinated plan,
- including identification of responsibility for implementing reliability assurance.
1 Technical Resolution -
1 j . IIC4-1 As of 3rd Quarter FY-86
)
r
Generic Issue #II.C.4 !
Milestones Oriainal Current Actual Discuss with INPO the needs to 06/83 -
11/83 develop agreement (See U.S.
Nuclear Regulatory Commission Policy and Planning Guidance 1983, NUREG-08SS, Issue 2, pages 11 and 12).
Research generic reliability 12/83 -
04/84 methodology.
Survey / adaptation of reliability 06/84 -
02/85 techniques & identification of reliability program elements for detailed evaluation.
Begin trial use. 12/84 -
07/85
- Complete case study of 5 plants 02/86 -
03/86
- to identify reliability tech-niques that industry has found to be effective.
Contractor draft interim 04/86 04/86 -
technical report identifying the essential elements of a reliability program, evaluating its effectiveness and identifying practical reliability techniques and reasonable applications.
Issue draft interim report for staff review and comments.
i Staff memo to E00 evaluating 06/86 06/86 -
i regulatory needs for reliability -
assurance and outlining plan for implementation.
ACRS Subcommittee review 05/87 05/87 -
, Publish final NUREG 12/87 12/87 -
l Issue close-out memo 12/87 12/87 -
to ED0 IIC4-2 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number hpee_ Level Office /Div/Br Manager TACS No.
II.L.4.3 Safety / Active-L1 NRR/DSR0/RSIB A. Serkiz 52409 High Title ---------------- Containment Design - Integrity Check Work Authorization --- liRR FY-84 Operating Plan (Appendix G).
Contract Ti tle ------- Feasibility Study of Alternative Containment Test Methods Centractor Name/ FIN -- SNL/A-1802 Wo rk Scope ----------- To determine whether alternative or additional leakage rate tests are needed to verify containment integrity and whether improvements in plant administrative and procedural operations could improve containment integrity.
PNL (FIN B-2526) has assembled an operational containment integrity testing data base (NUREG/CR-4220). SNL (FIN A-1802) is evaluating alternative test methods for periodi-cally verifying containment integrity.
A new task dealing with an evaluation of benefits which might be gained in containment isolation through improve-ments in plant administrative and procedural operations has been identified.
Affected Documents --- Not Yet Determined Status --------------- The results of the PNL study were published in NUREG/CR-4220.
The results of the SNL study will be used by the staff to formulate the licensing bases for requiring alternative or additional containment leakage rate test. SNL has identi-fied 10 possible alternative test methods and is evaluating them along with costs for backfitting. In addition, SNL is developing a proposal for the new work.
Problem / Resolution --- FY86 funding deobitgations, uncertainties in FY87 funding levels and additional work requirements which have been identified forecast a schedule slippage of 5-7 months.
Technical Resolution - The results of the SNL efforts will be used to determine what types of containment leakage tests are most beneficial and what alternative means (i.e., plant procedural means) could be used. These findings will be integrated with RES ongoing work related to estimation of risks assocated with containment leakage and Appendix J revisions.
IIE43-1 As of 3rd Quarter FY-86
-- , - - - - , , - - , , . . ~ . --
Milestones Original Current Actual Request for Proposal for - -
01/12/E3 Tasks 1&2 Issued Evaluation of Proposal 06/83 -
06/15/83 Tasks 1&2 Completed Issue Contract to Evaluate 07/83 -
06/24/83 Reliability of Containment Integrity (Tasks 1&2)
Receive Contractor Draft Report 02/15/84 05/84* 05/18/84**
on Review of Containment Integrity (Task 1&2)
Based on Review of Part 1 of 04/15/84 -
08/08/84***
Contractor Draft Report, Issue Memorandum closing out Issue, or Proposing the Need to Develop Additional Milestones for Resolu-tion of the Issue, including the Initiation of Task 3 of the Work Scope Request for Proposal for Task 3 11/84 -
12/84 Issued Issue Contract to Evaluate 04/85 -
05/85 Feasibility of Alternative Containment Test Methods (SNL Tasks 1&2)
Interim Report on the feasi- 03/86 -
05/86 bility of alternative contain-ment leak tests Evaluate costs of alternative 08/86 11/86 -
containment leak tests Complete Evaluation of 08/86 12/86 -
Industry Testing Procedures and Alternate Methods t
I
" Revised schedule approved in Memorandum from R. Mattson to T. Speis, dated 02/24/84.
- Part 1 of Draft Report (regarding Task 1) received; receipt of Part 2 of Oraft Report (regarding Task 2) deferred to 9/84.
l *** Memorandum from R. Bernero to T. Speis, dated 08/08/84, Transmitting Finding that Further Technical Resolution of the Issue is Warranted.
IIE43-2 As of 3rd Quarter FY-86
Generic Issue #II.E.4.3 Milestones Original Current Actual Alternative Containment Leakage 03/87 03/87 Test Methods and Associated Costs Evaluation of Containment 05/87 05/87 -
Isolation through Improvements in Plant Administrative and ,
Procedural Operations Technical Findings NUREG/CR 07/87 07/87 -
CRGR Package to NRR Director 01/87 01/87 -
Review Package to CRGR 02/87 02/87 -
CRGR Review Complete 03/87 03/87 -
ACRS Review Complete 05/87 05/87 -
Issue FRN for SRP 06/87 06/87 -
End public comment period 08/87 08/87 -
Final CRGR Package to 10/87 10/87 -
NRR Director Review Package to CRGR 11/87 11/87 -
CRGR review and EDO approval 12/87 12/87 -
complete FRN for SRP 01/88 01/88 -
Receive contractors final 09/86 09/86 -
report on the Feasibility Study for Alternative Containment Test Methods
, Evaluate report on Alternative 10/86 10/86 -
l Containment Test Methods Feasibility IIE43-3 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
II.E.6.1 Safety / Active-L1 NRR/OSR0/EIB 0. Rothberg 42416 Medium Title ---------------- In-Situ Testing of Valves Work Authorization --- NRR FY-84 Operating Plan (Appendix G)
Contract Title ------- Adequacy of Current Valve Inservice Test Methods Contractor Name/ FIN -- BNL/A-3821 Work Scope ----------- (1) Survey industry pratices and requirements for design, specification, qualification, and pre-operational and surveillance testing of valves in safety-related systems.
(2) Comparison of the tests with performance requirements and specifications.
(3) Identify performance requirements that are not adequately verified by analysis or test.
(4) Evaluate alternate means of verifying performance.
(5) Develop staff positions for additional periodic valve capability tests.
Affected Documents --- Revise R.G. 1.106,10 CFR 50.55(g) and Standard Technical Specifications.
Status --------------- A complete milestone schedule has been drafted and was issued in a work plan memorandum on July 30, 1984. A contract effort has been initiated to accomplish the tasks outlined in the work scope.
As of March 1986, the schedule and milestones are being reevaluated with a view toward expediting resolution of the issue. Although funds for contractor support are less than anticipated, significant assistance i's being provided by the IE Post-San Onofre 1 Investigation-Team effort on check valve testing and information to be contained in the response to IE Bulletin 85-03 for motor-operated valves.
An industry multi-NSSS Owners Group effort has been initi-ated at the request of the E00, the purpose of which is to increase the reliability of unassisted check valves under design basis as well as operating conditions. As of June 1986, a multi-owners group organization has been formed to resolve the problem along with INPO. The EDO has indicated that the industry effort will not be duplicated by NRC.
Therefore, work under this generic issue regarding testing of check valves may be curtailed in the near future, based on the establishment of the industry effort.
IIE61-1 As of 3rd Quarter FY-86
G:n:ric Issue #II.E.6.1 Problem / Resolution --- The question is if current in-situ valve testing methods will adequately assure that safety related valves will perform their intended safety function (open, close, stay open, stay closed, any combination) under design basis conditions.
An attempt is being made to resolve the various problems now being identified with current valve in situ testing
. e thods to determine if design basis results can be ektrapolated from the current no-load tests.
Technical Resolution -
Milestones Original Current Actual Prepare Users Request for RES to 05/84 -
05/84 contract for in plant pilot programs.
Review RES supplied DOE Lab 05/84 -
05/84 proposals for pressure isolation valve leak tests and other testing. Provide recommendations to RES for revisions to test scope and selection of testing lab.
OE Project Manager prepares 07/85 -
07/85 work scope for DOE Lab contract (re: study of adequacy of current valve inservice test-ing methods) and issues RFP.
DSR0 contract initiated 10/S5 -
03/86 DSR0 contractor completes review 05/85 12/86 -
of comments to be obtained from AE00, INPO, BWR Licensees, valve manufacturers, determine tentative recommendation for revision or cancellation of R.G. 1.106, ASME Code, Standard Tech Specs to resolve Thermal Overload Protection Device Concern (TOPDC).
Issuance of ETEC 00E Lab report on PIV and MOV testing (RES contract) -- check valves 09/85 07/86 -
gate valves 09/85 02/87 -
Issuance of Novats report re 09/85 -
01/86 in-situ signature tracing tests (RES contract).
. IIE61-2 As of 3rd Quarter FY-86
. Genoric Issue #II.E.6.1 Milestones Oriainal Current Actual Completion of review of Movats 11/85 08/86 -
reports by NRR including receipt of comments from AE00.
Based on IE review of responses 10/86 10/86 -
to IE Bulletin 85-03, foriaulate staff position on verification of switch settings for motor operated valves.
Draft final staff positions and 02/86 04/87 -
proposed tech specs re addition /
modification to current valve in-situ testing based on staff evaluation of input from DSRO, RES and AE00 contracts.
Value/ Impact
- statement prepared 04/87 04/87 -
NRR Division Ofrectors Review 06/87 06/87 -
completed NRR Director Review completed 08/87 08/87 -
Review Package sent to CRGR 08/87 08/87 -
CRGR Review Completed 09/87 09/87 -
Issuance of proposed staff 10/87 10/87 -
position and tech. specs Pubite Comments resolved by 01/88 01/88 -
staff NRR Director review completed 03/88 03/88 -
Review Package sent to CRGR 03/88 03/88 -
CRGR Review completed 04/88 04/88 -
Final Register Notice issued 05/88 05/88 -
i Issue close out memo to ED0 05/88 05/88 -
i IIE61-3 As of 3rd quarter FY-86 9
- , - , _,_n - - , . _ , - _ _ _ _ , - - - - . - . . . _ . . _ . - _ - - - - - - - -
O GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number h Level Office /Div/Br Manager TACS No.
I . F.1 Safety / Active-L1 IE/QAVT/VPB E. Baker None High Title ---------------- Expand QA List Work Authorization --- TMI Task Action Plan Contract Title ------- None Contractor Name/ FIN -- None Work Scope ----------- Develop guidance for licensees to expand their QA list to cover equipment important to safety.
Affected Documents --- None Status --------------- Revising proposed rule on importance to safety issue to incorporate latest guidance from Commission.
Problem / Resolution --- No plans to expand QA list. Issue proposed rulemaking.
Technical Resolution -
Milestones Oriainal Current Actual Task 1: Develop Frame Work - -
02/83 Review NRC Internal Comments 04/83 -
07/83 on NUREG/CR-2631 (rewrite Scope /189 if necessary) and publish NUREG Task 2: Start Method 10/83 -
10/83 Development (Issue Contract to Sandia)
Completion of Task 2 09/84 -
05/85 Issued SECY 85-119, proposed - -
04/05/85 rule on importance to safety issue Commission disapproved SECY 85-119 -
ACA 12/31/85 Issue revised paper for proposed - -
05/86 rule on importance to safety issue Commission approves revised rule -
06/86 -
Issue close-out memo to E00 -
ACA -
or provide additional mile-stones necessary to complete issue based on Commission discussion.
IF1-1 As of 3rd Quarter FY-86
- = - . _ - - - - _
j GENERIC ISSUE MANAGEMENT CONTROL SYSTEM l Issue Issue Action Task j Number h Level Office /Div/Br Manager TACS No.
II.F.5 Safety / Active-L1 NRR/DSR0/EIB TBD 96005 l Medium
)
T i t l e --------------- Classification of Instrumentation, Control and Electrical Equipment l Work Authorization -- (1) TMI Task Action Plan
] (2) Jan. 15, 1982 and Nov. 8, 1982, NRC Form 173 K. R. Goller, DF0 1
Contract Title ------ Classification of Systems Important to Safety j Contractor Name/ FIN - BNL/A-3249 1
l Work Scope ---------- To develop a methodology for the classification of systems important j to safety.
1 Affected Documents -- Draft Regulatory Guide for the classification of Instrumentation, Control and Electrical Systems and Components (ICES /E) Important l to Safety.
Status -------------- Draft report by BNL was submitted in September 1984 and is awaiting review and comment by NRR.
l Problem / Resolution -- IEEE has not yet issued a standard on classification of systems j important tn safety. IEEE Std. P-827 has been abandoned in favor j of a different approach involving the development of new standard j taking into account applicable work done by other technical socia-
- ties such as ASME and ANS, NRC is participating in this effort as stipulated by Item II.F.5. The parallel NRC effort to develop a draft regulatory guide on classification of systems important to j safety has been designated as priority C and has been taken off
{
the list of active RES tasks.
- Technical Resolution - The technical resolution of this item may be achieved by the issuance l by the IEEE of a suitable standard which may subsequently be endorsed j in whole or in part by a regulatory guide, or alternatively by the issuance of a regulatory guide irrespectively of what or when IEEE might issue a standard'in this area. At this time we are continuing
- our participation in the IEEE effort to develop a draft Standard i P-1049 under IEE/NREC/SC-6.2, Working Group on System Classification.
l l Milestones 0rininal Current Actual j !ssue Reg. Guide for comment 10/83 On hold" -
i Issue transfer memo to NRR for 02/86 -
12/20/85 1 close-out.
] Issue close-out memo to ED0 05/86 07/86 -
l !ssue BM Report 12/84 T80 -
j !ssue IEEE Std. 1980 T80 -
i j " Letter from H. Denton to R. Minogue, Dec. 31, 1983.
IIF5-1 As of 3rd Quarter FY-86 i
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM j . ..
Issue Issue Action Task j Number Type, Level Office /Div/8r Manager TACS No.
II.H.2 Safety / Active-L1 RES/DAE/FSR8 R. Foulds None High Title ---------------- Obtain Technical Data on the Conditions Inside the TMI-2 Containment Structure 4
Work Authorization --- TMI Task Action Plan
- LRRP, Budget Authorization Documentation Contract Title ------- None l
Contractor Name/ FIN -- None l
Work Scope ----------- NRC is cooperating with DOE and industry on development of plans and guidance for implementation of research and i data gathering programs within the TMI-2 containment.
These programs concentrate on retrieving data which characterize the progression of the accident and the i
resulting radiological source term for this case. The
- programs address the examination of the reactor inter-nals (especially the reactor core and fuel), the primary i
' system piping and vessel, the dose reduction effort during decontamination, and various mechanical, elec-trical and instrumentation equipment. NRC primarily provides technical expertise in the program formulation
{ and implementation, the programs are generally carried j out with funds from DOE and others.
Affected Documents --- NUREG-0900 Severe Accident Research Plan (08/84).
Status --------------- More than one hundred information reports have been '
- issued by EG&G Idaho for DOE as a series of GEND reports numbered GEND-001, et, seq.-(GEND indicated:
- General Public Utilities, Electric Power Research
, Institute, Nuclear Regulatory Commission, and Depart-i ment of Energy - who are cooperating in a number of j technical working groups to manage the planning.)
i Current efforts are concentrated on TMI-2 core exami-
! nation both on-site and off-site. NRC is conducting a i series of off-site examinations of selected core i materials at a national laboratory. A planning basis for work supported by MRC and separately by DOE has been developed including a priority analysis.
Implementation within NRC depends upon availability j of samples from D0E.
2 l Problem / Resolution --- Low funding support for operations in the utility's i
recovery / cleanup program has delayed the availability j of data. An industry supported technical advisory i group is assisting the utility in the engineering projects required, to speed up the cleanup effort.
l Examination of detailed test description and i
i IIH2-1 As of 3rd Quarter FY-86 I,
Generic Issue #II.H.2 i information needs by DOE, EPRI, GPU, NRC, technical working group has delinested a priority-based plan that is being implemented by NRC and DOE within funding limits. Performance of lower priority tasks depends on DOE success in seeking foreign and industrial support.
Technical Resolution -
Milestones . Original Current Actual Revised Core examination plan 04/83 -
10/84 (DOE Responsibility) i
, Head Removal 07/83 -
07/84 i
Plenum Removal 07/85 -
05/85 Begin Defueling 10/85 -
12/85 Revise core examination plan 12/85 -
02/86 Core Drilling 07/86 07/86 -
Complete Defueling 06/87 06/87 -
Final Fuel Analysis Report 09/87 10/88 -
Issue close-out meno to EDO 12/87 12/88 -
l i
, IIH2-2 As of 3rd Quarter FY-86 i
f
- - - . _ - , - - . - - . - _ _ . _ . , - _ . . . . . . _ - . , _ , . . - - _ . _ , . .-.-__-- _ . . _ . _ , _ _ _ _ . _ _ _ . . . _ _ _ . - _ - - . . . . . - _ . _ . - _ . . _ ~ . _ . . _ . _
~
GENERICISSUEMANAGEMENTCONTR0i. SYSTEM
.T Issue Issue Action Task Number h Level Office /Div/Br Manager TACS No.
II.J.4.1 Safety / Active-L1 IE/DEPER/EAB R. Singh None NR Title ---------------- Revise Deficiency Reporting Requirements Work Authorization --- TMI Action Plan Contract Title ------- None Contractor Name/ FIN -- None Work Scope ----------- NRC will revise, as necessary, the reporting require'ments of 10 CFR part 50.55(e) and 10 CFR Part 21 to assure that all reportable items are reported promptly and that the informa-tion submitted is complete. A major objective will be to eliminate duplicative evaluation and reporting,and establish consistency with the NRC safety deficiency reporting require-ments. The reports received as a result of these rule changes will provide increased information on component failures tnat affect safety so that prompt and effective correct.ive action can be taken. The information will also be used as input to an augmented role of the NRC's vendor and construction inspec-g tion program.
Affected Documents --- 10 CFR Part 21 and 10 CFR Part 50.55(e) -
Status --------------- IE/EAB has obtained concurrences of CRGR and the EDO for the proposed revisions to 10 CFR Part 21 and 10 CFR 50.55e. The package was sent to the Commission on December 16, 1985. After l Commission approval, the proposed rule changes will be published l
in the Federal Register for public comment.
Problem / Resolution --- Schedule revised to reflect delays in Commission review.
j Technical Resolution -
- I '
- Milestones Original ~ Current Actual Office concurrence complete 04/83 -
06/85 [
Transmitted to CRGR for - -
06/05/85 review CRGR Review Complete 05/83 -
07/08/85 Paper to Commission 05/83 -
12/16/85'
~
Issue Federal Register Notice 06/83 04/86 -
of Proposed Rule changes for public comment IIJ41-1 As of' 3rd Quarter FY-86
_ - _ _ . _ _ - . . - - . - . _ - - , . _ _ ___~__.--.w._ - _ - _ - _ _ _ _ _ _ . . , ,,,--m- ,.- . _ _ _ _ _ _ . _ _ _ - . , , , __y._.
Generic Issue #II.J.4.1 Milestones Original Current Actual Comments Received 08/83 06/86 -
Comments Incorporated 10/83 07/86 -
Office concurrence for 09/86 09/86 -
Final Rule CRGR Review Complete 10/86 10/86 -
Final Rule to Commission 11/86 11/86 -
Issue Federal Register Notice 12/86 12/86 -
for issuance of Final Rule Rule is effective, issue 02/87 02/87 -
close-out memo to EDO l
l l
i IIJ41-2 As of 3rd Quarter FY-86
!s GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
III.D.3.1 Safety / Active-L1 NRR/DPL-A/PSB R. J. Serbu 42928 High Title ---------------- Radiation Protection Plans Work Authorization --- ,
NRR FY-84 Operating Plan (Appendix G).
Contract Title ------- None Contractor Name/ FIN -- None Work Scope ----------- Finalize a " Letter of Agreement" which outlines the relation-ship between INPO and the NRC during the period when INPO will actively assist licensees in implementing ALARA-integrated radiation protection programs. Develop an auditing method whereby the NRC can assess INP0/ industry progress and success in achieving ALARA integrated radiation protection programs.
Affected Documents --- 1. " Memorandum of Agreement Between INP0 and the USNRC" (April 1, 1982), Appendix Number Three, " Coordination Plan for Radiological Protection Activities" (March 3,
' 1983).
- 2. NUREG-0761 (draft March 1981) - revised into Regulatory Guide format as R.G.8.XX.
1 3. R.G. 8.XX - revise and hold for issue pending success I
of INP0/ Industry.
- 4. " Development of a Program to Evaluate Industry Efforts to Achieve Successful ALARA-Integrated Radiation Protec-tion programs," (R. J. Mattson, June 16, 1983). -
Action Plan / Assessment Method - developed to evaluate INP0/ industry progress and success in implementing ALARA integrated radiation protection programs.
- 5. " Evaluation of Industry Efforts to Achieve Successful ALARA Integrated Radiation Protection Programs" (April 23, 1985, D. R. Muller to Division Directors) - criteria, worksheets and examples for Regions to evaluate aspects of industry radiation protection programs.
- 6. " Request for the Regions to Assist in the Evaluation of Industry Success in Achieving ALARA-Integrated Radiation Protection Programs at Power Reactors" (H. L. Thompson to DRP Division Directors, May 8, 1985).
- 7. " Request for Research Assistance in Establishing a Radiological Data Base" (H. R. Denton to R. B. Minogue -
in concurrence).
- 8. " Evaluation of industry efforts to achieve successful ALARA Integrated Radiation Protection Programs - Summary
'1 Analysis of Selected Radiological Trends at Power Reactors" (D. R. Muller to DRSS Division Directors, November 19, 1985).
IIID31-1 As of 3rd Quarter FY-86
Gzn:ric Issue #III.D.3.1
- 9. " Resolution of Generic Issue III.D.3.1, ' Radiation Protection Plans'" (H. R. Denton to V. Stello, Jr.,
May 19, 1986).
Status --------------- The staff completed the resolution of III.D.3.1 with the closeout memorandum to the EDO in May 1986.
Problem / Resolution --- None Technical Resolution -
Milestones Original Current Actual Draft Proposed Revised NRC/INPO - -
01/19/83 Coordination Plan distributed for review and comment by OIE, RES, and Director, DSI.
Draft Plan to INPO Staff for - -
01/26/83 review and comment.
Staff Recommendation to EDO to - -
02/25/83 transmit proposed Coordination Plan to INPO (Follow-up to INPO (Wilkinson) letter dated August 26, 1983).
Coordination Plan signed and in - -
03/03/83 effect.
Draft auditable criteria for 04/83 -
04/15/83 i ALARA/ radiation protection evaluation of IFa0 Program, including ALAR 4 st.ecklists and evaluation criteria, distribute to IE, RES, and Regions for comment.
Revise evaluation criteria based 06/83 -
06/15/83 on comments.
Complete a topical / functional 06/83 - -
comparison of INP0 objectives, criteria and guidelines against NRC criteria.
Establish ALARA checklist- 07/83 -
06/15/83 parameter, SALP/ inspection findings, etc., tracking system.
Establish schedule of NRC 09/83 -
07/06/83 a: companied INPO Appraisals.
IIID31-2 As of 3rd Quarter FY-86
Generic Issue #III.D.3.1 Milestones Original Current Actual Draft criteria for determinatio'n 10/83 -
06/15/83 of acceptability /unacceptability of INP0/ Industry success.
Establish milestone for criteria 10/83 -
06/15/83 approved process.
Finalize criteria for deter 12/83 -
06/15/83 mination of acceptability /
unacceptability cf INP0/ Industry success.
- Receive INPO input 04/85 -
04/01/85
- Initiate radiological data base 09/85 - -
- Evaluation of INP0/ industry 03/85 -
11/85 success completed.
Radiation Protection Plan RG 03/85 - -
either issued or withdrawn based on determination of success or failure of INP0/
industry program Technical Resolution Complete. 03/85 -
05/19/86 (Issue close-out documentation memo to EDO.)
EDO Approval 06/86 -
N/A "INPO data viewed by NRC staff, but not officially submitted to NRC by INPO.
- NRC staff identified, compiled, and evaluated data and trends from solely NRC sources, duplicating INP0 efforts. An additional 2 months were needed to incor-porate this effort. Final documentation was completed in December of 1985.
IIID31-3 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br ' Manager TACS No.
III.D.3.2(1) Licensing RES Title ---------------- Amend 10 CFR 20 Work Authorization --- NUREG-0660 Contract Title ------- To be provided Contractor Name/ FIN -- To be provided W ork Scope ----------- To be provided Affected Documents --- To be provided S ta t u s --------------- To be provided
~
Problem / Resolution --- To be provided Technical Resolution - To be provided Milestones Original Current Actual IIID32-1 As of 3rd Quarter FY-86
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[
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l IIID32-2 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type, Level Office /Div/Br Manager TACS No.
III.D.3.2(3) Licensing RES Title ---------------- Develop Standard Performance Criteria Work Authorization --- NUREG-0660 Contract Title ------- To be provided Contractor Name/ FIN -- To be provided Work Scope ----------- To be provided Affected Documents --- To be provided Status --------------- To be provided Problem / Resolution --- To be provided Technical Resolution - To be provided Milestones Original Current Actual i
l IIID32-3 As of 3rd Quarter FY-E6
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I t
IIID32-4 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type, Level Office /Div/Br Manager TACS No.
III.D.3.2(4) Licensing RES Title ---------------- Develop Method for Testing and Certifying Air-Purifying Respirators Work Authorization --- NUREG-0660 Contract Title ------- To be provided Contractor Name/ FIN -- To be provided Work Scope ----------- To be provided Affected Documents --- To be provided S ta tu s --------------- To be provided Problem / Resolution --- To be provided Technical Resolution - To be provided Milestones Original Current Actual I
l IIID32-5 As of 3rd Quarter FY-86 l
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type _ Level Office /Div/Br Manager TACS No.
III.D.3.5(1) Licensing RES T i tl e - - -- -- -- - -- - - -- - Develop Format for Data to be Collected by Utilities Regarding Total Radiation Exposure to Workers Work Authorization --- NUREG-0660 Contract Title ------- To be provided Contractor Name/ FIN -- To be provided Work Scope ----------- To be provided Affected Documents --- To be provided S ta tu s --------------- To be provided Problem / Resolution --- To be provided Technical Resolution - To be provided Milestones Original Current Actual IIID35-1 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
IV.E.1 Licensing RES Title ---------------- Expand Research on Quantification of Safety Decision-Making Work Authorization --- NUREG-0660 Contract Title ------- To be provided Contractor Name/ FIN -- To be provided Work Scope ----------- To be provided Affected Documents --- To be provided Status --------------- To be provided Problem / Resolution --- To be provided Technical Resolution - To be provided Milestones Original Current Actual l
IVE -1 As of 3rd Quarter FY-86
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(
IVE -2 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type level Office /Div/Br Manager TACS No.
IV.E.3 Licensing RES Title ---------------- Plan for Resolving Issues at the CP Stage Work Authorization --- NUREG-0660 Contract Title ------- To be provided Contractor Name/ FIN -- To be provided Work Scope ----------- To be provided Affected Documents --- To be provided S tatu s --------------- To be provided -
Problem / Resolution --- To be provided Technical Resolution - To be provided Milestones Original Current Actual l
i l
IVE -3 As of 3rd Quarter FY-86
l l
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l IVE -4 As of 3rd Quarter FY-86 i
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type. Level Office /Div/Br Manager TACS No.
IV.E.4 Licensing RES Title ---------------- Resolve Generic Issues by Rulemaking Work Authorization --- NUREG-0660 Contract Title ------- To be provided Contractor Name/ FIN -- To be provided Wo rk Scope ----------- To be provided Affected Documents --- To be provided S ta t u s --------------- To be provided Problem / Resolution --- To be provided Technical Resolution - To be provided Milestones Original Current Actual t
I l
l l
IVE -5 As of ,3rd Quarter FY-86 i
I
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number
- Type Level Office /Div/Br Manager TACS No.
IV.G.2 Licensing RES Title ---------------- Periodic and Systematic Reevaluation of Existing Rules Work Authorization --- NUREG-0660 Contract Title ------- To be provided Contractor Name/ FIN -- To be provided Wb rk Scope ----------- To be provided Affected Documents --- To be provided Status --------------- To be provided Problem / Resolution --- To be provided Technical Resolution - To be provided Milestones Original Current Actual IVG2-1 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM l
i Issue Issue Action Task '
Number Type. Level Office /Div/Br Manaaer TACS No.
HF-01 Safety / Active-L1 NRR/DHFT/MTB C. Goodman TBP Subtask High HFPP-1.1 Title ---------------- Issue Policy Statement on Engineering Expertise on Shift and Evaluate Effectiveness of Policy Statement Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, .
1984, Human Factors Program Plan (HFPP)
Contract Title ------- None Contractor Name/ FIN -- None Work Scope ----------- Staff Prepare Policy Statement Affected Documents --- None Status --------------- Final policy statement approved by Commission on September 12, 1985. Published in Federal Register October 28, 1985, 50 FR 43621.
Problem / Resolution ---
Technical Resolution -
Milestones Original Current -
Actual Milestones being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
I HF01-1 As of 3rd Quarter FY-86
l THIS PAGE LEFT BLANK IkTENTIONALLY HF01-2 As of 3rd Quarter FY-86
l l
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type _ Level Office /Div/Br Manager TACS No.
HF-01 Safety / Active-L1 NRR/DHFT/MTB C. Goodman M40408 Subtask High {
M40409 1.2 M40404 Title ---------------- Revise and Issue a Revision to Regulatory Guide 1.8 !
Work Authorization --- Memorandum for H. Thompson from H. Denton dated October 10, 1984 Human Factors Program Plan (HFPP)
Contract Title ------- Task S2 - Shift Crew Qualifications Contractor Name/ FIN -- PNL B-2360 Work Scope ----------- This issue incorporates the work scope of Task Action Plan Item I.A.2.6(1). The qualifications of the operating shift crew has been the object of numerous staff papers including:
SECY-79-330-E-G, SECY-80-492, SECY-81-84 and 81-84A, SECY-82-162 and SECY-84-106, SECY-84-355 and SECY 85-50. In January, 1983, the Nuclear Waste Policy Act PL 97-425, Sec-tion 306 was signed into law. That law directed the NRC to promulgate regulations or other appropriate guidance for the qualification of NPP personnel including the opeating shift Crew.
Efforts related to the law and to close the issue of qualifi-cations include preparation of a policy statement on training and qualifications and fitness for duty in response to $306, l the industry will be responsible for (1) ensuring that per-sonnel have qualifications appropriate to the performance requirements of the jobs to which they are assigned, (2) prep-aration of a policy statement on engineering expertise on shift (3) revision of Reg. Guide 1.8 to endorse ANS 3.1-1981, and (4) completion of a contractor study on the issue of job-related educational qualifications based on the results of existing JTA data.
Affected Documents --- Reg. Guide 1.8 Policy Statement Eng. Exp. on Shift NUREG/CR-Engineering Expertise Status --------------- SECY-84-106 was submitted to the Commission in March 1984 and was rejected in November 1984. The Commission directed the staff to obtain NUMARC comments on the Final Policy statement on Engineering expertise. The Commission approved a Final Policy Statement on September 12, 1985.
It was published in the Federal Register on October 28, 1985, 50 FR 43621.
Problem / Resolution --- Regulatory Guide 1.8 may be delayed due to the extent of the revision following public comment.
HF01-3 As of 3rd Quarter FY-86 I
Technical Resolution -
Milestones Original Current Actual Recommendations of Peer Panel. - -
05/82 RES JTA Completion. 06/83 -
06/83 Draft Policy Statement on 06/83 -
07/83 Engineering Expertise on Shift Engineering Expertise on Shift 09/83 -
12/83 report Proposed Rule to Commissioners 03/84 -
03/84 concerning requirements for Senior Managers Final Policy Statement for 01/84 -
04/85 Engineering Expertise on shift Contractor report on job-related 11/84 -
12/84 educational qualifications based on JTA data bases Proposed revision to Regulatory 02/85 -
01/85 Guide 1.8 published for public comment Issue revised R.G. 1.8 for use 06/84 05/85 -
Issue close-out memorandum - * -
- Revision to Regulatory Guide 1.8 is being reviewed 'and approved as part of the 10 CFR 55 rule change package (HFPP-3.3 and 3.4).
l HF01-4 As of 3rd Quarter FY-86
I l
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM 1
I Issue Issue Action Task :
Number Type _ Level Office /Div/Br Manager TACS No.
HF-01 Safety / Active-L1 NRR/DHFT/MTB TBP TBP Subtask High HFPP-2.1 Title ---------------- Evaluate Industry Training Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title ------- None Contractor Name/ FIN -- Not applicable work Scope ----------- Use new inspection modules and Training Review Guidance to inspect utility training products and in event-basea reviews.
Af fected Documents --- Policy Statement on Training and Qualifications (SECY 85-1)
Status --------------- Inspection Modules 41400 and 41701 issued and Training Review criteria and procedures developed. Three post-accreditation reviews completed.
Problem / Resolution --- INPO objection to NRC performing post-accreditation reviews.
Technical Resolution -
Milestones Original Current Actual Milestones being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
I HF01-5 As of 3rd Quarter FY-86 l
THIS PAGE LEFT BLANK INTENTIONALLY HF01-6 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task .
Number Tyge, Level Office /Div/Br Manager TACS No.
HF-01 Safety / Active-L1 NRR/DHFT/MTB J. Persensky T8P Subtask High HFPP-1.4 Title ---------------- Review and Evaluate Industry qualification Programs Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title ------- None Contractor Name/ FIN -- Not applicable Work Scope ----------- Apply Review Guidance in post-accreditation reviews Affected Documents --- Policy Statement on Training and Qualifications (SECY 85-1)
Status --------------- On hold Problem / Resolution --- To Be Provided Later Technical Resolution -
Milestones Original Current Actual Milestones being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
HF01-7 As of 3rd Quarter FY-86 1
TilIS PAGE LEFT BLANK INTENTIONALLY HF01-8 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type _ Level Office /Div/Br Manager TACS No.
HF-01 Safety / Active-L1 NRR/DHFT/MTB J. Persensky TBP Subtask High HFPP-1.3 Title ---------------- Develop a Means to Evaluate Acceptability of NPP Personnel Qualifications Program Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title ------- To Be Determined Contractor Name/ FIN -- To Be Determined Wo rk Scope ----------- Develop Review Guidance to be used by staff in post-accreditation reviews.
Affected Documents --- Policy Statement on Training and Qualifications (SECY 85-1)
S ta tu s --------------- On hold until decision on role of accreditation is made.
Problem / Resolution - - To Be Provided Later Technical Resolution -
Milestones Original Current Actual Milestones being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
HF01-9 As of 3rd Quarter FY-86
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HF01-10 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number h Level Office /Div/Br Manager TACS No.
HF-01 Safety / Active-L1 NRR/DHFT/MTB J. Persensky TBP Subtask High HFPP-2.2 Title ---------------- Evaluate INP0 Accreditation Program Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title ------- None Contractor Name/ FIN -- Not Applicable Work Scope ----------- Monitor industry progress in achieving accreditation through observation of INP0 team visits, performing post-accreditation reviews and monitoring indicators data.
Affected Documents --- Policy Statement on Training and Accreditation (SECY 85-1)
Status --------------- Three post-accreditation reviews completed, 20% of Team visits observed. All Accreditation Board review meetings observed.
Problem / Resolution --- INPO objection to Post-Accreditation reviews.
Technical Resolution -
l Milestones Original Current Actual
.l Milestones being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
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HF01-11 As of 3rd Quarter FY-86
a fr THIS PAGE LEFT BLANK INTENTIONALLY 9
f h-p'-
t m
'O HF01-12 At of 3rd Qbart O FY-86 l
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Tyge_ Level Office /Div/Br Manager TACS No.
KF-01 Safety / Active-L1 NRR/DHFT/MTB J. Persensky TBP Subtask High HFPP-2.3 Title ---------------- Revise Standard Review Plan Section 13.2.3 Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title ------- To Be Determined Contractor Name/ FIN -- To Be Determined Wo rk Scope ----------- To Be Provided Later Affected Documents --- To Be Provided Later S ta t u s --------------- On hold until effect of Policy Statement on Training and Qualifications is determined. Issue to be closed-out.
1 Problem / Resolution --- '.o Be Provided Later Technical Resolution -
Milestones Original Current Actual Milestones being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
l HF01-13 As of 3rd Quarter FY-86 i
.)
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
- Issue Issue Action Task Number Type _ Level Office /Div/Br Manager _TACS No.
HF-01 Safety / Active-L1 ' NRR/DHFT/0LB B. Boger M40428 Subtask High HFPP-3.1 Title ---------------- Develop BWR Job-Knowledge Catalogue (NUREG-1123)
Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title ------- Developments of NRC Reactor Operator Licensing Examination Specifications Contractor Name/ FIN -- Professional Examination Service /D-1315 Work Scope ----------- Develop Job-Knowledge Catalogue using INPO BWR JTA, GE Morris Training Center, and Subject Matter Expert panel review.
Affected Documents --- None Status --------------- Contract effective June 17, 1985 3
Problem / Resolution --- None Technical Resolution -
Milestones Oriainal Current , Actual
, Draft Catalogue for panel '01/86 03/86 -
4 review J Final Draft for NRC review 03/86 06/86 -
Issue NUREG-1123 06/86 09/86 -
Issue Close-out Memorandum 07/86 10/86 -
L 3
HF01-15 As of 3rd Quarter FY-86
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HF01-16 As of 3rd Quarter FY-86
I GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type Level Office /Div/Br Manager TAOS No.
HF-01 Safety / Active-L1 NRR/DHFT/0LB B. Boger M40428 Subtask High HFPP-3.2 T i tl e - -------------- - Develop Licensing Examination Handbook (NUREG-1121)
Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title ------- Development of NRC Operator Licens',g Examinations Specifications Contractor Name/ FIN -- Professional Examination Services /01315 Wo rk Scope ----------- Review Examiner Handbook developed under FIN B-2517, evaluate pilot test; make recommendations for Examiner Standards (NUREG-1021)
Affected Documents --- Examiner Standards (NUREG-1021)
Status --------------- Contract effective June 17, 1985 Problem / Resolution --- None Technical Resolution -
Milestones Original Current Actual Pilot Test begun 10/85 -
09/85 Pilot Test con:plete 03/86 - -
l Contractor recomrrendations 07/86 07/86 -
Final Pilot Test complete 09/86 09/86 -
! Revise NUREG-1021 11/86 11/86 -
Issue Closr-out Memorandum 12/86 12/86 -
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HF01-17 As of 3rd Quarter FY-86
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HF01-18 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number h Level Office /Div/Br Manager TACS No.
HF-01 Safety / Active-L1 NRR/DHFT/0LB B. Boger 42454 Subtask High !
49618 HFPP-3.3 40435 56190 T i tl e - ----- - ------ --- Develop Criteria for NPP Simulators Work Authorization --- Memorandum for H. Thompson from H. Denton dated October 10, 1984, " Human Factors Program Plan" (HFPP)
Contract Title ------- " Development of an NRC Simulation Facility Evaluation Program" Contractor Name/ FIN -- Microanalysis and Design /D-1317 Wo rk Scope ----------- This item is addressed by activities currently underway in response to Section 306 PL 97-425, and by FIN 0-1317. Speci-fically, proposed changes to 10 CFR Part 55, recommended changes to Regulatory Guide 1.149, " Nuclear Power Plant Simulator Facilities for use in Operator License Examina-tions," and results expected from a technical assistance con-tract titled " Development of an NRC Simulation Facility Evalua-tion Program," address this issue.
Affected Documents --- None Status --------------- Contract began September 16, 1985. Steering Committee has held first meeting. Draft simulation facility evaluation methodology will be presented to Committee in January 1986.
10 CFR Part 55 and Reg. Guide 1.149 were presented to ACRS Human Factors Subcommittee (November 1985) and full ACRS Committee (December 1985).
Problem / Resolution --- None Technical Resolution - ,
Milestones Original Current Actual For 10 CFR Part 55 and RG 1.149 End of Public Comment Period 03/85 -
'03/85 Division Review 10/85 -
10/85 Office Review 12/85 - -
CRGR Review 12/85 02/86 -
HF01-19 As of 3rd Quarter FY-86
Milestones Oriainal Current Actual For D-1317:
RFP issued 03/85 -
03/85 Contract awarded 08/85 -
09/85 Eval. Plan for ANS-3.5 12/86 01/87 -
simulators Eval. Plan for Non-ANS-3.5 02/87 03/87 -
simulators 1
HF01-20 As of 3rd Quarter FY-86
4 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number h Level Office /Div/Br Manager TACS No.
HF-01 Safety / Inactive-L1 NRR/DHFT/0LB TBP TBP Subtask High HFPP-3.5 .
Title ---------------- Develop Computerized Examination System Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title ------- To Be Determined Contractor Name/ FIN -- To Be Determined Work Scope ----------- To Be Provided Later Affected Documents --- To Be Provided Later Status --------------- Deferred. No funds in FY-1985 budget.
Problem / Resolution --- To Be Provided Later Technical Resolution -
Milestones Original Current Actual Milestones being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
1 HF01-21 As of 3rd Quartpr FY-86 l -
l
i GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type _ Level Office /Div/Br Manager TACS No.
HF-01 Safety / Inactive-L1 NRR/DHFT/0LB S. Shankman None Subtask High HFPP-3.4 T i tl e ---- ---- -- ----- - Examination Requirements (Revise 10 CFR 55, RGs 1.149 and 1.8)
Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title ------- Development of Regulatory Guide and Regulatory Analysis Contractor Name/ FIN -- Analysis & Technology, NRC-03-83-107 Wo rk Scope ----------- Provide Support for resolution of Pubile Comments and develop regulatory analysis. -
Affected Documents --- None S ta t u s --------------- Complete Problem / Resolution --- None Technical Resolution -
Milestones Original Current Actual Milestones being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
i i
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HF01-23 As of 3rd Quarter FY-86 i
THIS PAGE LEFT BLANK INTENTIONALLY HF01-24 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Tyge_ Level Office /Div/Br Manaaer TACS No.
HF-01 Safety / Active-L1 NRR/DHFT/HFIB J. Bongarra T8P Subtask High HFPP-4.1 Title ---------------- Inspection Modules for Upgraded Procedures Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title ------- To Be Determined Contractor Name/ FIN -- To Be Determined Work Scope ----------- To Be Provided Later Affected Documents --- To Be Provided Later Status --------------- To Be Provided Later Problem / Resolution --- To Be Provided Later Technical Resolution -
Milestones Oriainal Current Actual Milestones being reassessed in accordance with a memorandum for J. Funche's from F. Rowsome dated June 6, 1986.
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l HF01-25 As of 3rd Quarter FY-86
THIS PAGE LEFT BLANK INTENTIONALLY HF01-26 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number h Level Office /Div/Br Manager TACS No, i
l HF-01 Safety / Active-L1 NRR/DHFT/HFIB TBP 48436 1 Subtask High HFPP-4.2 Title ---------------- E0P Effectiveness Evaluation Work Authorization --- Memorandum for H. Thompson from H. Denton dated October 10, 1984, " Human Factors Program Plan" (HFPP)
Contract Title ------- Revise the Inspection Module and Develop Associated Training for Regional Audit of E0Ps Contractor Name/ FIN -- Not applicable Work Scope ----------- Revise current I&E inspection modules to reflect changes required to audit upgraded E0Ps and E0P development programs.
Assist with training of I&E inspectors in the use of revised inspection modules.
Affected Documents --- NRC I&E inspection module. Possible revision to SRP Section 13.5.2.
Status --------------- Two E0P audit completed.
ProbleCNesolution --- Delay in ' scheduling a third E0P audit may cause schedule to change. Alternate sites being considered for third audit.
Technical Resolution -
Milestones Original Current Actual Issue revised SRP Section 13.5.2 08/84 -
08/84 Complete draft inspection module revision and forward to IE for review 09/84 -
10/85 IE comments Incorporated into revised draft 03/86 03/86 -
Assist IE in conducting inspection training 01/85 04/86 -
Implement Inspection Module 05/86 05/86 -
Issue close-out memorandum 06/86 06/86 -
HF01-27 As of 3rd Quarter FY-86 l *
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l HF01-28 As of 3rd Quarter FY-86
- - . - - .. - - - - , - - . . , - - - - . , - . - - . - - - - . . - . . - - . . - . . . ~ . _ _ . - - - . _ _ . , - . . - - , , - - , . - . . . - - - - . _ - - - - . - - . - . . .
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type _ Level Office /Div/Br Manager TACS No.
HF-01 Safety / Active-L1 NRR/DHFT/HFIB TBP TBP Subtask High HFPP-4.3 Title ---------------- Criteria for Safety Related Operator Actions (B-17)
Work Authorization --- Memorandum for H. Thompson from H. Denton dated October 10, 1984, " Human Factors Program Plan" (HFPP)
Contract Title ------- To Be Determined Contractor Name/ FIN -- To Be Determined Work Scope ----------- To Be Provided Later i
l Affected Documents --- To Be Provided Later Status --------------- To Be Provided later Problem / Resolution --- To Be Provided Later Technical Resolution -
Milestones Original Current Actual DHFS has Issued a memorandum 02/84 -
03/22/84 to RES transferring B-17 to their office. -
RES issued memorandum trans- - -
04/17/85 ferring B-17 to NRR/0HFS/PSRB Incorporate B-17 into HFPP - -
06/07/85 Milestones being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
HF01-29 As of 3rd Quarter FY-86
. *7 THIS PAGE LEFT BLANK INTENTIONALLY 1
HF01-30 As of 3rd Quarter FY-86
4 i
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Tyge_ Level Office /Div/Br Manager TACS No.
~
NF-01 Safety / Active-L1 NRR/DHFT/HFIB TBP 55402 Subtask High HFPP-4.4 Title ---------------- Guidelines for Upgrading Other Procedures Work Authorization --- Memorandum for H. Thompson From H. Denton dated October 10, 1984, " Human Factors Program Plan" (HFPP)
Contract Title ------- Develop guidance and regulatory action for ops and AOPs Contractor Name/ FIN -- PNL/B-2360, P-2 Work Scope ----------- Recommend improvements in nuclear power plant operating
- procedures and develop an implementation plan for upgrading
! operating procedures.
Affected Documents --- Not yet determined. Possible revision to SRP Section 13.5.2 S ta tu s --------------- Task 1 (Define Scope of Project and Refine Project Focus),
Task 2 (Review Existing Data Base) have been completed.
Task 3 (Define Current Industry Practices and Probless) and Task 4 (Select and Convene Project Peer Review Group) have been completed with the exception of reviewing sample plant procedures (task 3, subtask' h)
Problem / Resolution --- None Technical Resolution - NRC will determine the amount of upgrade effort necessary for 1 each type of procedure based on a contractor interia report and industry inputs with respect to costs and benefits.
l Milestones Original Current Actual Issued contract to PNL to develop - -
02/01/83
- guidelines for upgrading operat-l ing procedures.
P l Define scope of operating - -
01/31/84 procedures Submit a summary letter report - -
01/31/84 Complete review of data on - -
07/01/84 nuclear power plant operating l
procedures 4
Submit summary letter report - -
08/15/84 l
l HF01-31 As of 3rd Quarter FY-86 l
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Milestones Original Current Actual Develop discussion items for - -
01/31/84 site visits and submit to NRC ,
)
Incorporate NRC comments and - -
02/15/85 submit final letter report Complete site visits 09/84 -
02/01/85 Complete preliminary assessment - -
01/15/85 of interface problems and submit summary letter report Complete analysis of procedures 09/84 07/85 -
in operating plants Receive comments from NRC on - -
02/28/84 Peer Review Group Select and contact Peer - -
03/30/84 Review Group Convene first Peer Review Group 07/84 -
07/19/84 Convene second Peer Review Group 10/84 -
12/04/84 Submit any recommendations for 09/84 -
urgent NRC action 09/85 Submit draft report 09/84 -
09/85 Receive NRC and peer review group 01/85 -
10/85 comments Submit final report 02/85 -
11/85
, Publish final report - -
12/85' Issue close-out memorandum 06/86 06/86 -
HF01-32 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM l
Issue Issue Action Task Number Type Level Office /Div/Br Manager TACS No.
HF-01 Safety / Active-L1 NRR/0HFT/HFIB W. Kennedy 59929 Subtask High HFPP-4.5 Title ---------------- Applications of Automation Artificial Intelligence Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title ------- To Be Determined Contractor Name/ FIN -- To Be Determined Work Scope ----------- To Be Provided Later Affected Documents --- To Be Provided Later Status --------------- To Be Provided Later Problem / Resolution --- To Be Provided Later Technical Resolution -
Milestones Original Current Actual Milestones being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
HF01-33 As of 3rd Quarter FY-86
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HF01-34 As of 3rd Quarter FY-86 I
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type _ Level Office /Div/8r Manager TACS No.
HF-01 Safety / Active-L1 NRR/DHFT/HFIB R. W. Froelich 40444 Subtask High 4 HFPP-5.1 .
Title ---------------- Local Control Stations Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title ------- To Be Determined Contractor Name/ FIN -- To Be Determined j Work Scope ----------- In process. Principal issue is the extent of actual hands-on local control station human factors design review. This review process would consist of on-site analyses and reviews of local control stations conducted in nuclear power plants of cooperating utilities.
An initial step in this process would be the confirmation of
- the local control station definition that was provided in i
August 1985.
Variables still needing resolution include the number of site visits, whether or not contractor personnel would be needed, NSSS types to consider, plant designs, plant age,
- plant status, and the form and distribution of any reports prepared on an individual plant basis.
The possibility that plant reviews could be handled by industry groups (e.g., INPO) should be considered. Minimal participation of NRC/HFIB personnel would still be desirable.
A plan of work is needed that would be based on the premise that no site visits to review local control stations will be perellied.
Affected Documents --- The principal one would be NUREG-0700. One primary output i
' of the local control stations review process would be an addendum to NUREG-0700 that would provide guidelines for l industry conduct of local control station design reviews.
Status --------------- Currently going through the ORNL LER data bank retrieval
- ' system in an attempt to develop a search program that would have a high probability of selecting LERs for further review i that were based on local control station problems.
l
. HF01-35 As of 3rd Quarter FY-86 l .
l ,
i, Problem / Resolution --- None Technical Resolution -
Milestones Oriainal Current Actual Milestones being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
J i
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I i
\
i HF01-36 As of 3rd Quarter FY-86 l- --
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Tyge_ Level Office /Div/Br Manager TACS No.
HF-01 Safety / Active-L1 NRR/0HFT/HFIB D. Jones TBP Subtask High HFPP-5.2 T i tl e ---------------- Annunciators Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10,
- 1984, Human Factors Program Plan (HFPP)
Contract Title ------- 1. Human Factors in Annunciator / Alarm Systems
- 2. Computerized Man-Machine Communication Contractor Name/ FIN -- 1. SNL/A-1394
- 2. OECD Halden Project /B-7488 Work Scope ----------- 1. Recommend Annunciator / Alarm prioritization schemes.
Experimentally evaluate impact of alarm prioritization on operator performance.
- 2. Conduct experimental comparison of three computer-based alarm systems.
Status --------------- Experimental evaluation of alarm prioritization is awaiting availability of ANO simulator.
Problem / Resolution --- Availability of ANO simulator to conduct experimental evalua-tion of alars prioritization plan. Coordination with SNL underway.
Technical Resolution -
Milestones Original Current Actual Milestones being reassessed in accordance with a memorandum for J. Funches
- from F. Rowsome dated June 6, 1986.
4 HF01-37 As of 3rd Quarter FY-86
- _ . - . _ _ _ _ - .,7 .,-,_.,._-__...~___.-_,-_-.._.__m~ . . _ . _ - . _ . . . . , . . _ . _ _ _ - _ - _ _ - - . - . , _ , - - _ _ _ - . - . - - - - _ _ _ , . , _ _ _ _ _ . _ _ _ - . _ _ _ , , - _ . , -- _- ~ - . _ _ - - - -
THIS PAGE LEFT BLANK INTENTIONALLY HF01-38 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM 4
Issue Issue Action Task Number h Level Office /Div/Br Manager TACS No.
HF-01 Safety / Active-L1 NRR/0HFT/HFIB TBP TBP Subtask High HFPP-5.3 Title ---------------- Evaluate Operational Aid Systems
- Work Authorization --- Memorandum for H. Thompson from H. Denton dated October 10, 1984, " Human Factors Program Plan" (HFPP)
Contract Title ------- To Be Provided Later Contractor Name/ FIN -- INEL/A-6308 BNL/A-3254 (Completed)
Work Scope ----------- Identification of display design criteria and guidelines for the display of computer generated data to verify the technical accuracy of NUREG-0700 and NUREG-0839 for the control and display elements in the control rooms.
Affected Documents --- NUREG-0700 and NUREG-0835 Status --------------- Research began in FY81 with reports being issued annually.
Human Factors Subcommittee 7.0, Power Committee. IEEE, also is engaged in development of a human factors design standard. Decision to prepare a Rule, Guideline, or only technical reports has not been affirmed.
l Problem / Resolution --- Contract terminated at end of FY-85 i Technical Resolution -
1 Milestones Original Current Actual i Begin criteria development 09/80 - -
12/80
- research First report, NUREG/CR-1994, 04/81 -
04/81 l April 1981
< Second report, NUREG/CR-2147, 09/81 -
08/81
- September 1981 Third report, NUREG/CR-2828, 06/82 -
08/82 4
August 1982 Fourth report, NUREG/CR-2776, 09/82 -
09/82 September 1982
(
( HF01-39 As of 3rd Quarter FY-86 i
Milestones Oriainal Current Actual Fifth report, NUREG/CR-2916, 09/82 -
09/82 September 1982 Sixth report, NUREG/CR-2942, 10/82 -
10/82 October 1982 Seventh report, NUREG/CR-3103, 09/82 -
01/83 January 1983 Eighth report, NUREG/CR-3003, 09/83 -
04/83 April 1983 Ninth report, NUREG/CR-3557, 12/83 -
12/83 December 1983 Tenth report, NUREG/CR-3461, - -
01/84 January 1984 Eleventh report, NUREG/CR-3631, - -
02/84 February 1984 .
Issue report on control room 01/84 -
12/84 human engineering criteria Issue transfer memo to NRR/0HFS 06/85 -
07/03/8S DHFS memorandus provided 11/85 -
08/08/85 milestone necessary to complete issue Work scope for issue I.D.4 will 02/86 02/86 -
be integrated into HF-01 issue HFPP-5.3 HF01-40 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number h Level Office /Div/Br Manager TACS No.
HF-01 Safety / Active-L1 NRR/0HFT/HFIB TBP T8P Subtask High MFPP-5.4 Title ----------------- Computers and Computers Displays Work Authorization ---- Memorandum for H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title -------- Display Design and Evaluation Contractor Name/ FIN --- INEL/A-6308, A-6108 (Completed FY82)
Work Scope ------------ (1) Development of display design criteria for disturbance analysis system were started in FY81 and will be completed in FY84.
(2) Study adequacy of disturbance analysis methods was not started because of funding cuts.
Affected Documents ---- NUREG/CR-2118, NUREG/CR-1994, NUREG/CR-2147, NUREG/CR-2776, NUREG/CR-2711, NUREG/CR-2828, NUREG/CR-3103, NUREG/CR-2916, NUREG/CR-2942, Status ---------------- Improved display and diagnostics were installed in LOFT June 1982 and documents listed above have been produced to date. Additional research stopped because of lack of funds.
Problem / Resolution ---- Contract terminated at the end of FY-85 Technical Resolution -
Milestones Original Current Actual l
A-6308 Work Scope (2)
Development of Display Design FY81 -
FY81 Criteria Started System Design Completed 09/84 -
09/84 Issue transfer meno to NRR/0HFS 06/85 -
07/03/85 DHFS memorandum provide 11/85 -
08/08/85 Milestone necessary to complete issue Work scope for issue I.D.5 (5) 02/86 02/86 -
, will be integrated into HF-01 issue HFPP-5.4 HF01-41 As of 3rd Quarter FY-86
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N HF'01-42 As of 3rd Quarter'FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type, Level Office /Div/Br Manaaer TACS No.
HF-01 Safety / Active-L1 NRR/DHFT/HFIB TBP 55587 Subtask High HFPP-6.1 Title ---------------- Development of Regulatory Position on Management and Organization Work Authorization --- Memorandum for H. Thompson from H. Denton dated October 10, 1984, " Human Factors Program Plan" (HFPP)
Contract Title ------- Human Factors Safety Technology Program, Project M-1 Contractor Name/ FIN--- PNL/8-2360 (M1)
Work Scope ----------- This issue will be resolved by accomplishing the following objectives: (1) complete evaluation of existing management and organization assessment activities; such as INPO assistance visits, NRC Performance Assessment Team (PAT) Inspections and Systematic Assessment of Licensee Performance Program (SALP);
(2) develop technical basis for an NRC regulatory position on management and organization at operating nuclear power plants; (3) make decision on need for a new regulatory position on management and organization; and (4) develop new regulatory position, if required.
Affected Documents --- NUREG-0800, 10 CFR, NUREG-0731 Status --------------- The contractor developed report on evaluation of INP0 assistance visits to utility corporate and plant facilities has been completed. This information is currently being evaluated with information on PAT, SALP and other independent evaluators of management and organization at nuclear power plants. A staff recommendation on what the NRC positions should be concerning management and organization at operating nuclear power plants is scheduled for July 1985.
Problem / Resolution --- Close-out issue from HFPP, resolution complete due to NUMARC self-initatives and Commission decision not to issue new requirements for two years.
Technical Resolution -
Milestones Original Current Actual Contractor Evaluation of INPO 09/83 -
02/84 Review Criteria in Management and Organization.
HF01-43 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type _ Level Office /Div/Br Manager TACS No.
HF-01 Safety / Active-L1 NRR/DHFT/HFIB TBP TBP !
Subtask High HFPP-6.2 Title ---------------- Evaluation Criteria for SALP Reviews Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, i
1984, Human Factors Program Plan (HFPP)
Contract Title ------- To Be Determined Contractor Name/ FIN -- To Be Determined Work Scope ----------- To Be Provided Later Af fected Documents --- To Be Provided Later Status --------------- To Be Provided Later Problem / Resolution --- To Be Provided Later Technical Resolution -
Milestones Original Current Actual Milestones being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
HF'01-45 As of 3rd Quarter FY-86
. 'T THIS PAGE LEFT BLANK INTENTIONALLY HF01-46 As of 3rd Quarter FY-86
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue Issue Action Task Number Type _ Level Office /Div/Br Manager TACS No.
HF-01 Safety / Active-L1 NRR/DHFT/MFIB TBD 40450 Subtask High HFPP-6.3 Title ---------------- Revised SRP Section 13.1 Work Authorization --- Memorandum to H. Thompson from H. Denton dated October 10, 1984, " Human Factors Program Plan" (HFPP)
Contract Title ------- Human Factors Safety Technology Program, Project M-1 Contractor Name/ FIN -- PNL/B-2360 (M1)
Work Scope ----------- This issue will be resolved by accomplishing the following object.ives: (1) develop guidelines which describe required minimums for acceptable management and organization at nuclear power plants; (2) prepare workbook to accompany guidelines; (3) publish the guidelines and workbook for use by NRR reviewers of operating license applications; (4) train technical reviewers to effectively use workbook and improve interview skills; and (5) revise and issue SRP revision.
Affected Documents --- (1) NUREG-0731 (2) SRP Section 13.1 Status --------------- A set of guidelines and an accompanying workbook have been developed and have completed interoffice and Division concur-rence. Final versions of the guidelines and workbook were published in June 1984. The guidelines and workbook will be incorporated into a revision to SRP Sections 13.1. Action on SRP is delayed pending NUMARC initiatives in accord with Commission guidance.
Problem / Resolution --- A decision to revise the SRP is pending due to NUMARC initiatives which may eliminate the need for revision.
Technical Resolution -
Milestones Original Current Actual Develop Guidelines for OLs. 07/83 11/83 11/83 Develop Workbook for OLs. 09/83 11/83 11/83 Revise and issue a revision to SRP Sections 13.1 Complete SRP and NUREGs 01/85 -
02/85 draft changes HF01-47 As of 3rd Quarter FY-86
l MSPP I-1:BLG ;
MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 1 l
Issue Issue Action Task TAC Number h Level Office /Dir./Br. Manager Number HF-02 Safety / L2 NRR/DHFT/MTB 8.L. Grenier 56465 High P.W. McLaughlin N.B. Le J.L. Koontz Subtask: MSPP:I.1
Title:
Survey of Current Maintenance Practices Wori Authorization: MSPP/ Phase I approved for implementation by the EDO on January 11, 1985.
Contract
Title:
Survey of the Status of Maintenance in the U.S. Nuclear -
Power Industry Contractor Name/ FIN: Pacific Northwest Laboratory (PNL)/ FIN 82984
- Work Scope: This project will include a review and analysis of information needs and sources (e.g., AE00 analyses, INPO evaluations, PAT inspection reports) and development of a classification scheme for describing the characteristics of currt:nt maintenance programs and practices in the U.S. nuclear power industry.
The development, implementation, and the effectiveness of the preventive maintenance program at Salem will be evaluated as an example of a recent licensee response to a requirement for maintenance.
A maintenance review protocol will be developed for direct assessment of licensee maintenance perfomance using, e.g., a workbook, checklist, or other evaluation tool for NRC use.
Input to development of this protocol will be the experience gained from surveys of current maintenance practices. The use of the protocol will be to detemine licensee maintenance performance effectiveness and response to maintenance program improvements.
The result of this project, then, will be to assimilate data for assessing the present status of maintenance in the nuclear industry and to develop a method to describe the performance l
JUN 3 01986 l
l . _ __ - -
of the maintenance programs at nuclear power plants. Several sites (e.g., one in each Region) will be selected for evaluation by a team to determine the maintenance program effectiveness. The reviews will (1) provide baseline data as reference for the assessment of future developments due to implementation of new or revised maintenance practices, standards, etc., and (2) identify areas where improvements in maintenance programs are most needed to enhance safety of operation.
Affected Documents: Report to the EDO, April 1986 Status:
Task 1 - Maintenance Data Base and Report A draft report of the analyses performed using the infomation in the Maintenace Data Base that shows " trends and patterns" in the nuclear power plant industry for the years 1980 through 1984 was submitted by the contractor on February 14, 1986. A section of the final project report that was to have been based on this information will now be written as a separate report under this task. The draft of this report was submitted for NRC connent on March 28.
Task 2 - Review of Salem PM Program The task was completed as of February 20, 1986.
Task 3 - Questionnaire to Reafonal SRIs The " census report" of the questionnaire responses was submitted by the contractor on February 26--2 days pior to the due date. The draft report for this task was submitted for NRC conenents March 27--one day prior to the due date.
Note: Data from'the for Social Sciences (questionnaire SPSS) Data Base were entered at HARC forinto the Statistical preparation of the "Package census" report and for performing the analyses. A determination needs to be made whether these these data should be transferred to a dBase III file and whether the results of analyses will also be entered onto a dBase file for future use.
Task 4 - Maintenance Survey Protocol Effort on this task has been completed for Phase I. The MSS staff expects to incorporate changes gained from experience during Phase II.
l JUN 3 01986
. l Task 5 - Site Surveys i All trips have been completed and all final reports have been received and l distributed. This task is complete.
Task 6 - Final Report The Project report was submitted in draft for NRC comments on March 28 as scheduled. The staff is currently preparing connents.
Technical Resolutions:
Milestones Original Current Actual Pre-Contract Develop Statement of Work 2/28/85 -
2/28/85 Issue Request for Proposal 3/1/85 -
3/1/85 Select Contractor 5/1/85 -
4/20/85 Initiation of Contract 5/15/85 -
5/15/85 Task 1 - Data Base Collect and categorize NRC data and build maintenance data base structure
~
7/5/85 -
11/22/85 Input available NRC 1980-1984 data for each plant and submit data file (Background and Plant Operations and Performance Data -
only.) 7/12/85 11/27/85 Prepare and submit plan for analysis of plant operations and maintenance perfomance data (Task 1) not scheduled 11/15/85 Receive NRC consnents on Task 1 analysis plan not scheduled -
12/3/85 JUN 4u Amf6
4 Milestones .
Original Current Actual Complete trend and pattern analysis of plant operations and maintenance performance data and submit report a) draft 11/15/85 2/14/86 b) final 12/13/85 4/18/86 Prepare " final" report for Task 1 a)draftNotschedule INot b) final report Final report for Task 1 a) draft not scheduled 3/28/86 b) final not scheduled 4/25/86 Task 2 - Salem P.M.
Gather, review data and assess lesson learned on Salem Preven-tion Maintenance Program 7/6/85 -
8/20/85 Conduct Salem site visit 9/6/85 11/1/85 a) rough draft report not scheduled 11/27/85 b) NRC input & response not scheduled 12/4/85 c) draft report 9/27/85 12/23/85 d) NRC coments 1/3/86 12/31/85 e) final report 11/8/85 2/14/86 f) transmitted to Lic. P.M. not scheduled 2/20/86 Task 3 - Questionnaire Prepare and submit question-naire to be administered to Regions a) draft 8/2/85 -
7/3/85 b) final 9/6/85 11/19/85 Send draft questionnaire to SRIs 8/9/85 11/22/85 Receive draft questionnaire from SRIs 9/20/85 2/14/86 Prepare Quest. Analysis Plan not scheduled 12/19/85 Prepare Quest." Census" report not scheduled 2/26/86 JUN 3 01986
Milestones Original Current Actual Compile questionnaire results a) draft 11/15/85 3/27/86 b) final 12/13/85 4/25/86 Task 4 - Protocol Develop and submit maintenance review protocol for use on site surveys -
a) draft 7/19/85 7/19/85 b) final 8/7/85 8/23/85 Incorporate experience from site survey and update mainten- .
ance review protocol a) draft 12/30/85 cancelled b) final 1/31/86 cancelled Task 5 - Site Survey -
Kewaunee (pilot) site visit 7/26/85 8/2/85 a draft trip report 8/2/85 9/12/85 b final trip report not scheduled 11/22/85 c transmitted to Lic.
P.M. not scheduled 12/31/85 Millstone site visit 9/13/85 8/30/85 a rough draft report not scheduled 10/15/85 b NRC input & response not scheduled 10/21/85 e draft trip report 9/20/85 12/5/85 d) NRC comments not scheduled 12/18/85 e) final report 10/18/85 1/16/86 f) transmitted to Lic.
P.M. not scheduled 1/27/86 Davis-Besse(additional) not scheduled site visit 9/20/85 ap draft trip report not scheduled 11/11/85 bJ final trip report not scheduled 11/20/85 Rancho Seco site visit 10/4/85 10/4/85 '
a rough draft report not scheduled 10/21/85 b NRC input & response not scheduled 10/28/85 e draft trip report 10/11/85 11/27/85 d NRC coments not scheduled 12/16/85 e final report 11/8/85 1/3/86 f) transmitted to Lic.
P.M. not scheduled 1/8/86 JUN 3 01986
l l
l Milestones Original Current Actual ANO-2 site visit 10/25/85 11/8/85 a rough draft report not scheduled 11/19/85 l b NRC input & response not scheduled 11/22/85 )
c draft trip report 11/1/85 12/12/85 '
d . NRC connents not scheduled 12/31/85 e final report 11/29/85 1/21/86-1 f transmitted to Lic.
P.M. not scheduled 2/13/86 11/15/85 12/6/85 Turkey)Pt-4 a roughsite visitreport draft 12/13/85 12/16/85 b) NRC comments 12/19/85 12/17/85 c) draft report 11/22/85 cancelled d) NRC coments 1/10/86 cancelled e) final report 12/20/85 1/22/86 f) transmitted to Lic.
P.M. not scheduled 1/27/86 Brunswick site visit 12/6/85 1/17/86 a) rough draft report 1/24/86 1/28/86 -
b) NRC input & response 1/30/86 1/31/86 c) draft report 12/13/85 2/19/86 d) NRC coments 2/20/86 3/3/86 e) final report 1/10/86 3/14/86 f) transmitted to Lic.
P.M. 3/28/86 3/21/86~
Task 6 - Final Report Prepare Project Report a) outline not scheduled 1/9/86 b) draft from PNL as 12/27/85 3/28/86 T61 Tows:
Final Report Sections Original Current _
Executive Sumary 3/28/86 3/28/86 Section 1 - Introduction 2/21/86 2/21/86 Section 2 - Currerit Plant '
Maintenance Practices 3/21/86 3/21/86
- 1. Methodology
- 2. Organization and Administration
- 3. Facilities and Equipment i
JUN 3 01986 l
l
Final Report Sections Original Current Actual
- 4. Procedures
- 5. Personnel
- 6. Work Control Section 3 - Sumary and Conclusios 3/28/86 3/28/86
- 1. General Characteristics
- 2. Approaches to NPP Mainte-nance Program Development
- 3. Regulatory Implications Section 4 - References 3/28/86 3/28/86 Appendices A. Glossary of Terms 2/21/86 -
B. Maintenance Questionnaire Results 3/28/86 ' 3/28/86
~
Milestones Original Current Actual c) final 2/21/85 4/25/86 JUN 3 01986
I
~
MSPP I-2:BLG MAINTENANCE AND SURVEILLANCE PROGRAM PLAN
~
Phase I/ Task 2 j l
l Issue Issue Action Task TAC l Number h Level Office /Dir./Br. Manager Number NF-02 Safety / L2 NRR/DHFT/MTB B. L. Grenier 56467 High F.W. McLaughlin Subtask: MSPP:I.2
Title:
Maintenance Performance Indicators Work Authorization: MSPP/ Phase I approved for implementation by the EDO on January 11, 1985.
Contract
Title:
- Statistical Analysis of Maintenance Performance Indicators (B2980)
- Development of Maintenance Performance -
Indicators (B2986) i Contractor Name/ FIN: Pacific Northwest Laboratory (PNL)/ FIN 82980 Pacific Northwest Laboratory (PNL)/ FIN 82986 Work Scope: Preliminary investigations of plant perfomance safety indicators have shown that multiple variables may be selected which in combination, indicate the effectiveness of a nuclear utility's maintenance practices. The development of mainte-nance safety indicators will build upon preliminary analyses of variables to derive a set of indicators which may be used to describe industry maintenance performance, compare plant maintenance effectiveness, and assess maintenance trends a'nd patterns. This task will provide further baseline data as reference for industry progress in maintenance program im-provement. Alternative data sources and methods will be evaluated for applicability to maintenance performance assess-ment.
Affected Documents: Report to the EDO, April 1986 _
JUN 3 01986
l I
l Status: l A survey of non-NRC sources to identify maintenance-related data was completed. The contractor has detennined that data from these sources would not be useful for development of maintenance perfonnance indicators. A list of 20 plant and maintenance measures was developed and approved.
Presentation of plant. specific data for those measures for years 1980-1984 was submitted in a report on January 10, 1986. The report is currently under review by the staff.
Collection of 1985 plant operations and maintenance performance data has begun. Work on Tasks 3, 4, and 6 have been delayed in order to concentrate on finali:ing the Maintenance Data Base and enhancing the computer capabilities to manipulate existing data.
Problem / Resolution: None.
Technical Resolutions:
Milestones Original Current Actual FIN 82980 Development of 50W 11/11/84 11/11/84 Issuance of Contract 12/1C/84 12/10/84 and Start of Work Appointment of NRC Task Force 1/9/85 1/9/85 NRC Task Force Recommendation 1/15/85 1/15/85 and Assessment of Industry Proposed Indicators Complete Task 1 - Evaluation 1/15/85 1/15/85 of 12 NUMARC Draft Maintenance Performance Indicators Complete Task 2 - Evaluation 1/16/85 1/16/85
, of Indicators Prepared by the l NRC Maintenance Indicators Task Force Provide NRC Coments to Industry 1/21/85 1/21/85 (NUMARC)
Approval of NUMARC Indicators 5/29/85 FIN B2986 Issue Request for Proposal and 8/12/85 8/12/85 Start Work JUN 3 01986
3 Milestones (cont'd) Original Current Actual Task 1 - Identification of Data Sources and Collection Plan (a) Identify non-NRC data 9/20/85 10/17/85 sources (b) Develop potential 10/11/85 11/27/85 data elements '
(c) Develop collection plan for non-NRC data (1) draft 11/1/85 11/15/85 (2) final 12/1/85 12/3/85 Task 2 - Develop Maintenance Performance Information (a) Compile data for years '80 '84 12/6/85 12/13/85 (1) Augmented LER data, OSHA data, and thermal power cancelled (2) FERC data and additional LER data cancelled (b) Code and normalize data 12/27/85 12/27/85 (c) Submit computerized data files 1/10/86 1/10/86 NOTE: Contractor mofification processed 3/31/86 to ADD Tasks 7 and 8 and delay indefinitely Tasks 3, 4, and 6, except for tasks 4. a. and 5.
Task 3 - Develop Maintenance Performance Indicators and Reliable Indicator Models (a) Determine relationship of maintenance measures to safety performance 2/14/86 On hold (b) Determine how maintenan:e ,
performance across years affects safety performance in subsequent years 3/28/86 On hold, (c) Develop initial multi- .
variate alternative model 6/20/86 On hold (d) Develop additional alterna-tive multivariate models not scheduled On hold (e) Prepare report (1) draft 6/20/86 On hold (2) final 7/25/86 On hold JUN 3 01986
Milestones (cont'd) Original Current Actual Task 4 - Validate Models (a). Collect,sortand .
compile available data for 1985 7/11/86
~
(1)NUREG-0020 Data (outa
. data)ge and availability 3/28/86 (2)SALPScores 3/28/86 (3) 766 File (violations data) 3/28/86 (4) Exposure Data Note: data not available 'until 12/86 (5) LER Data 5/15/86 (b) Analyze data files 8/1/86 On hold (c) Comparative analysis 8/22/86 On hold (d) Prepare report 8/22/86 On hold Task 5 "On-Call Assistance" Task Assignment 1 - Prepare Maintenance Data Base (MOB)
Summary Tables by NRC Region 4/10/86 Task 6 - Prepare Final Report (a) draft 9/12/86 On hold (b) final 10/31/86 On hold Task 7 " Trends and Patterns" of Nuclear Power Plant Mainte-nance for the Year 1981 Through 1985 l a) Standardize and analyze 4/4/86 1985 plant operations and maintenance performance data b)Prepareareportoftrends j and patterns for 1981-1985:
- for 11 measures 4/11/86 for 20 measures 5/2/86 c) Prepare report (1) draft 5/9/86 i
(2) final 5/23/86 i
e JUN 3 01986
\
. . \
)
Milestones Original Current Actual Task 8 - MDB Software Enchancements a) Complete user-friendly, nemu-driven software program (1)SubmittoNRC 6/6/86 (2) Add up to 10 menus 7/11/86
.(3) Fianlize program 7/20/86 b) Prepare a User Manual (1) Complete outline 5/16/86 .
(2) Prepare draft 6/13/86 (3) Submit final 7/20/86 f
I JUN 3 01986
l MSPP I-3:BLG .
l MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 3 Issue Issue Action Task TAC Number h Level Office /Dir./Br. Manaoer Number HF-02 Safety / L1 NRR/DHFT/MTB B.L. Grenier 56469 High Subtask: MSPP:I.3
Title:
Monitor Industry Activities Work Authorization: MSPP/ Phase I approved for implementation by the EDO on January 11, 1985.
Contract
Title:
Review and Integration of Infonnation from Programs Related to the Maintenance and Surveillance Program Plan.
Contractor Name/ FIN: Support within Project 2, FIN 82984 Pacific Northwest Laboratory (PNL)
Work Scope: The Maintenance Section personnel will monitor industry progress and experience in developing strategies for improved maintenance. Coordination with INPO will be necessary to monitor the effectiveness of the INPO plant evaluations, accreditation of training, and good practices in enhancing maintenance performance in the nuclear industry. Implementa-tion of EPRI guidelines and the results of industry initiatives will be monitored and their impact assessed. In addition, industry activities such as standards development and data reporting will provide input to the NRC development of perfor-mance measurement methods, guidelines, and criteria for maintenance and surveillance.
Affected Documents: Rep' ort to the EDO, April 30, 1986 O
JUN 3 01986
2 Status: The Maintenance Section staff continuously stays abreast of on-going industry activities and are in receipt of literature for information and for comment and attend meetings when scheduled.
Approximately one week effort was spent since the last program review in November. Contacts were made with EPRI, NUS/NOMIS, and a number of industrial firms inquiring on the scope / status of the MSPP and NRC maintenance activities.
The staff has completed the writing of program sumaries of the relationship of industry programs with the MSPP for inclusion in the report to thi EDO.
I Problem / Resolution: None Technical Resolutions:
Milestones Original Current Actual Attend NUMARC/EDO Coordination 1/3/85 1/3/85 Meeting Regarding the MSPP Attend NUMARC-INPO Ccordination 2/26/85 2/26/85 Meeting in Atlanta Attend EPRI Seminar to Review 3/19-21/85 3/19-21/85 EPRI Report on " Maintain-ability" Participate in EPRI Workshop on 4/16-17/85 4/16-17/85 Maintenance Safety Related l Equipment
[
Attend ANS Maintenance Panel 6/12/85 6/12/85 Meeting, Boston Attend VEPC0 Presentation on 7/16/85 7/16/85 Team Approach to Maintenance Participate in EPRI Program 7/16/85 7/16/85 Review Meeting with NUMARC on Indicators 7/17/85 7/17/85 Review of IAEA Maintenance 8/5/85 8/5/85 Manual (Revision 2)
Attend meeting with NUMARC 10/16/85 10/16/85 and selected utilities to discuss Preventive Maintenance
, Program development and l diagnostic tools l
L JUN 3 01986
Milestones Original Current Actual Attend Workshop on Predictive Maintenance at General Physics 10/7/85 10/7/85 Note: Additional " milestones" to be added as they are identified Prepare summary of industry activities, initiatives and accomplishments for MSPP Phase I report (1) EPRI 1/28/86 1/29/86 (2) NUMARC 1/28/86 1/16/86 (3) INPO 1/28/86 1/16/86 (4) Vendors 1/28/86 3/20/86 Incorporate results in EDO report 4/30/86
. JUN 3 0 INH 5
l MSpp g.4;ggg MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 4 Issue Issue Action Task TAC Number Type Level Office /Dir./Br. Manager Number HF-02 Safety / L1 NRR/DHFT/MTB B.L. Grenier 40004 High Subtask: MSPP:I.4
Title:
Participate in Standards Groups Work Authorization: MSPP/ Phase I approved for implementation by the EDO
, on January 11, 1985.
Contract
Title:
None Contractor Name/ FIN: N/A -
Work Scope: Maintenance Section personnel participate in development of industry national standards for mainten'ance by IEEE, ASME, ANS and ANSI groups. Industry standards are perceived as a means '
of promoting maintenance program improvements without NRC regulation. NRC endorsement of industry standards will be considered during the maintenance program.
Affected Documents: Report to the EDO, April 30, 1986-Status: The Maintenance Section staff is assigned to various standards comittees associated with maintenance and surveillance testing and will attend when scheduled.
The staff has completed the writing of program sumaries of
" Standards Comittees" activities in the area of maintenance.
Problem / Resolution: None .
Technical Resolutions: . . . . . .
Milestones Original Current Actual Participate in IEEE 3.3 Goal 10/16/84 10/16/84 Setting Meeting Attend IEEE 3.3 Standards Com- 12/10/84 12/10/84 mittee Meeting to Devise Guidelines for Maintenance
" Good Practices" JUN 3 0 M
Original Current Actual Attend IEEE 3.3 Standards Com- 2/6-7/85 2/6-7/85 mittee Meeting to Devise Guidelines for Maintenance
" Good Practices" Review and Provide Comments on 4/19/85 4/19/85 IEEE Standards Committee 3.2 Draft (#338) " Periodic Surveillance Testing of NPG Systems"
- Attend IEEE Standards Committee 4/30-5/1/85 4/20-5/1/85 Committee Meeting 3.3 to .
Devise Maintenance " Good Practices" ;
Serve as Panel Member and Present 6/11/85 6/11/85 Paper to ANS Annual Meeting on
" Maintenance Program and Practices" Attend IEEE 3.3 Standards 8/6-7/85 8/6-7/85 Committee Meeting to Devise Guidelines for Maintenance
" Good Practices" Attend ASQC Meeting in 9/5/85 9/5/85 Knoxville, TN Attend ANSI /ASME NQA Sub-comittee on Operations i Meeting (WG on Maintenance, I
Repairing and Inservice Inspec-tion) to discuss Standard NQA-2 9/11/85 9/11/85 Attend IEEE WG 3.3 Meeting re:
t
" Maintenance Management" 10/22-25/85 cancelled l Attend IEEE WG 3.3 Meeting re:
" Maintenance Guidelines" 11/4-8/85 . cancelled l
i Attend IEEE WG 3.3 Meeting re:
" Good Maintenance Practices" 2/3-5/86 2/3-5/86
! Attend IEEE WG 3.3 Meeting re:
" Good Maintenance Practices" 6/3-9/86 Attend IEEE WG 3.3 Meeting re:
" Good Maintenance Practices" 9/16-17/86 i
4
1 Milestones Original Current Actual Prepare sumary on IEEE WG 3.3 activities for incorporation in MSPP Phase I report to the 1/28/86 3/14/86 EDO Incorporate results in MSPP Phase I report to the EDO 4/30/86 o
9 W
e O
4 8
I e
t t
JUN 3 01986
l MSPP I-5:BLG MAINTENANCE AND SURVEILLANCE PROGRAM FLAN Phase I/ Task 5 Issue Issue Action Task TdC Number Type _, Level Office /Dir./Br. Manager Number HF-02 Safety / L1 NRR/DHFT/MTB B.L. Grenier 56471 High Subtask: MSPP:I.5
Title:
Maintenance and Surveillance Program Integration (NRC Related Programs)
Work Authorization: MSPP/ Phase I approved for implementation by the EDO on January 11, 1985 Contract
Title:
Review and Integration of Infonnation from Programs Related to the Maintenance and Surveillance Program Plan Contractor Name/ FIN: Pacific Northwest Laboratory (PNL)/ FIN 82984 Work Scope: A number of diverse, multidisciplinary programs related to maintenance are expected to produce technical data and information that will support the goals and objectives of the Maintenance and Surveillance Program (MSPP). Some of these programs are listed in Table 3.1 of the MSPP and are described in Section 3 of the MSPP. While the scope of these programs I encompasses objectives other than maintenance, it is important l that all maintenance-related data and information available from these programs be extracted, assessed and integrated into MSPP activities and ensuing regulatory strategy to form a comprehensive technical basis for NRC decision-making regarding U.S. nuclear power plant maintenance policies.
With respect to the contractual support, task assignments will be placeo on an "as required" basis. Generally, for each task placed under the contract, the contractor will review and assess interim and final reports, plans, products, or other information (e.g., attending industry meetings) from the .
standpoints of their relationship (including possible duplica-tion of effort) and possible use in MSPP activities and proposed NRC actions.
Affected Documents: Report to the EDO, April 30, 1986
- ~ .- JUN 3 01986
Status: Most reports have been read, evaluated and sumarized for integration in the report to the EDO.
Problem / Resolution: None Technical Resolutions:
Milestones Original Current Actual Quality Assurance Program Plan (QAPP)
Contact:
Drew Persinko The Comission paper forwarding the QAPP was approved by the Commission on January 6, 1986.
Follow-up status review 9/20/85 9/20/85 Attend ACRS meeting on QA Plan 12/13/85 12/13/85 Prepare sumary for incorporation in MSPP Phase I report to the EDO 1/28/86 3/6/86 Safety Implications of Control Systems (USI A-47
Contact:
Drew Persinko Review of NUREG/CR-4326. " Effects 1/10/86 2/5/86 of Control System Failures on Transients and Accidents on -
Westinghouse 3-Loop PWRs" (Aug. 85).
Review of MUREG/CR-4262, " Effects 1/24/86 2/5/86 of Control System Failures on Transients and Accidents on BWRs" (Sept.85) ,
Review of NUREG/CR-4047, " Effects 2/7/86 not published of Control System Failures on Transients and Accidents on B&W PWRs" (Sept. 85) l S1 ,,
m 3 01986 l
Milestones (cont'd) Original Current Actual Review of NUREG/CR-(Unassigned 2/21/86 not published No.) " Effects of Control System Failures on Transients and Accidents on CE PWRs" Prepare summary for incorporation 1/28/86 2/5/86 in the MSPP Phase I report to the EDO Revisions to above summary 2/21/86 3/6/86 Technical Specifications Research
Contact:
John Jankovich Review of report " Surveillance 11/30/85 not published Test Intervals" Review of report " Application 1/31/86 not published -
Guide for Allowed Outage Times" Prepare summary for incorporation 1/28/86 1/29/86 in MSPP Phase I report to the EDO Technical Specifications Improve-ment Project (TSIP)
Contact:
John Jankovich
- Review of TSIP final report 11/15/85 11/30/85 1
! Prepare summary for incorporation 1/28/86 1/29/86
, in MSPP Phase I report to the EDO Nuclear Plant Aging Research
Contact:
Tommy Le Review of NUREG/CR-4156: Operating 7/11/85 7/11/85 Experience and Aging-Seismic Assessment of Electric Motors 1
i l : ,
o JuN &0 126
4 1
i Milestones (cont'd) Original Current Actual Review of NUREG-CR-4234: Aging 7/11/85 7/11/85 and Service Wear of Electric Motor-Operated Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plants - Part 1 Review of Draft Special Report: 8/21/85 8/21/85 Evaluation of the Motor-Operated Valves Analysis and Test System (M0 VATS) to detect degradation, incorrect adjustment and other abnormalities in Motor-Operated Yalves Review of NUREG/CR-3543: Survey 11/18/85 11/1/85 of Operating Experience from LERs to Identify Aging Trend Review of NUREG/CR-4144: Importance 11/25/85 1/28/86 Ranking based on Aging Considera-tions of Components Included in Probabilistic Risk Assessments Review of NUREG/CR-4279: Draft 12/13/85 not received 1/29/86 Report on Aging / Service Wear of Hydraulic and Mechanical Snubbers Review of NUREG/CR-4257: Inspec- 12/20/85 1/2/86 tion / Surveillance and Monitoring of Electrical Equipment inside Containment of Nuclear Power Plants - with application to Electrical Cable '
Prepare summary for incorporation 1/28/86 2/28/86 into MSPP Phase I report to the ED0 Effectiveness of Industry ALARA Programs
Contact:
Jennifer Koontz Review of RES report on 6/30/85 6/30/85 occupational dose reduction andALARA(NUREG/CR-4254)
~
JUN 3 01986
l Milestones (cont'd) Original Currey Actual Coment on Comission paper on 11/8/85 1/10/86 cooperation with INPO to evaluate industry success in achieving ALARA - integrated radiation protection programs.
Review of RES report on evaluation 12/13/85 not published of occupational dose reduction activities (RES)
Prepare sumary for incorporation 1/28/86 1/16/86 in 1/18/86 MSPP Phase I report .
to the E00 Equipment Qualification - R.G. 1.89
Contact:
Tomy Le Currently, a multi-office f
(NRR/IE/ Regions) E.Q. inspection team is conducting a series of 10 inspections to review the licensee's implementation of the E.Q. requirements of 10 CFR 50.49 for establishing and maintaining the qualification of equipment.
- The results of these inspections is to ensure equipment reliability to withstand the adverse environ-mental conditions during a design basis event. The Maintenance and SurveillanceSection(MSS)is monitoring these activities.
The following inspection reports on the plants listed below will be reviewed for findings .
pertinent to the Maintenance .
and Surveillance Program:
- 1. Calvert Cliffs 3/15/85 3/15/85
- 2. Zion 4/15/85 4/12/85
- 3. Crystal River 5/15/85 5/17/85
- 4. Fort Calhoun 6/15/85 6/14/85
- 5. Rancho Seco 7/15/85 7/12/85
- 6. Point Beach 8/15/85 8/16/85 JUN 3 01986
c,.
i '
s Milestones (cont'd) O_riginal Current Actuals '- '
~'
- 7. Brunswick 10/15/85- 12/18/85
- 8. Nine Mile Point 11/15/85 > 2/14/86 s
- 9. San Onofre- 12/15/83 not received-
- 10. Sequoyah or Browns Ferry 1/15/85 not received Prepare sunnary for incorporation < N7/86, -
in MSPP Phase I report to the -
E00 Reliability Research
Contact:
John Jankovich -
Review of NUREG/CR-2641 "The 10/25/85 11/15/85 In-Plant Reliability Data Base _
for Nuclear Power Plant Compo- -
nents: Data Collection and _
Methodology Report," July 1982
~ '
Review of NUREG/CR-2886 "The 11/8/85 11I15/85 In-Plant Roliability Data Base for Nuclear Power Plant Com-ponents: Interim Report -
the Valve Component,"
December 1983.
i Review of NUREG/CR-3154 "The 11/29/85 -
11/15/85 ~
In-Plant Reliability Data Base ~
for Nuclear Power Plant Com- '
ponents: Interim Report -
the Valve Component," '
December 1983.
Review of ORNL/TM-9066 12/13//85 11/15/85 e "In-Plant Reliability Data Base for Nuclear Plant Components: A Feasible Study on Human Error Information," March 1984 _
~
e Review of NUREG/CR-3831 "The '12/27/85 ,
11/15/85 In-Plant Reliability Data Base for Nuclear Plant Components: Interim -
Report - Ofesel Generators, Batteries, Chargers and Inverters " January 1985 JUN 3 01986
_ _ _ _ _ _ - - _ _ _ . . c_. __. -
Milestones (cont'd) Original Current Actual I
Review of NUREG/CR-3541 12/27/85 not available
" Measures of the Risk Impact .
of Testing and Maintenance Activities" Review of RES report "Appli- 12/27/85 not available cability of Reliability Program to Help Resolve Generic Issues" -
Review of RES report " Case 1/15/86 not available Studies on Attributes of Successful Reliability
. Programs" Prepare sumary for incorporation 1/28/86 1/29/86 in MSPP Phase I report to the '
EDO Training and Qualifications of Personnel
Contact:
Jennifer Koontz Review of INPO Accreditation 11 completed
. Observation Reports as of 2/86 Review of Post-Accreditation 3 completed Training Review Reports . as of 2/86 Prepare sumary for incorporation 1/28/86 1/16/86 in MSPP Phase I report to the EDO Integration of NOE Reliability and Fracture Mechanics Program
Contact:
Tom y Le Review of semi-annual program 12/13/85 not published progress report (NUREG/CR.4458 Volume III)
Review of annual program progress 2/7/86 3/28/86 report (NUREG CP 0058 Volume IV)
I JUN 3 01986
O L
Milestones (cont'd) Original Current Actual '
Prepare summary for incorpora- not scheduled 3/28/86 tion in MSPP Phase I report to the EDO Interfacing Systems LOCA at 8WRs - Generic Issue No. 105
Contact:
Tommy Le
- Comments on Task Action Plan 9/12/85 9/12/85 Comments of S0W for contract 9/27/85 9/27/85 in support of GI 105 Review of Interim Progress 1/17/86 Not received Report Prepare summary for incorporation 1/28/86~ 3/6/86 in MSPP Phase I report to the .
EDO Other NRC Programs (Miscellaneous)
Review results of Maine Yankee 11/15/85 10/21/85 PAT Report Review of Turkey Pt. 1 & 2 IE HQ 10/29/85 10/21/85 inspection of AFWS Review of NUREG/CR-3715 Report on maintainability 10/15/85 9/17/85 Integration Task Force
Contact:
John Jankovich Provide NRR input to program 1/9/81 1/8/86 concept Comple;e Integration Plan 1/31/86 2/14/86*
- The MSS staff has completed its input and IE has document for concurrence h
JUN 3 0 586
MAINTENANCE AND SURVEILLANCE PROGRAM PLAN RESOURCE UTILIZATION Phase I - Project 6 "MSPP Integration With Other NRC Related Programs" A. Staff Resources (in weeks) 6-Month Budget Expenditure Percent of (10/1/85-3/31/86) to 1/31/86 Budget 7.2 psw 6.6 psw 91%
B. Technical Assistance (in thousands)
Total Funds Expenditures Percent FIN Available (FY85+86) to 1/21/86 Expended N/A 9
e t
l ,
Jim 3 0126
Status: This project is complete. A " draft" summary of the results has been prepared for incorporation into the MSPP Phase I report to the EDO.
Note: This project was started during development of the MSPP because of the opportunity to exchange information on the subject of maintenance with Japanese at the time.
i Problem / Resolution: None Technical Resolutions:
Milestones Original Current Actual Develop Statement of Work 2/1/84 2/1/84 Obtain HFRG Approval and Forward to Contractor to Start Work .
Complete Task 1 - Assess 4/15/84 5/1/84 Differences in Operating Experience Complete Task 2 - Assess 4/15/85 5/31/85 Organization and Management Complete Task 3 - Compare / Con- 4/15/85 4/15/85 i
trast PM programs Appendix B 4/30/85 5/31/85
, Prepare report of U.S. 4/15/85 4/30/85 operating experience (additional task)
Printing NUREG/CR 3883 5/31/85 7/6/85 NUREG/CR 3883P 7/31/85 8/15/85 Prepare summary for incorporation 1/28/86 1/29/86 in the MSPP Phase I report to the EDO Incorporate results in MSPP 4/30/86 Phase I report to the EDO
.r ,
c ..
JUN 3 0 BB6
MSPP I-6:BLG MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 6 Issue Issue Action Task TAC Mumber Tyge_ Level Office /Dir./Br. Manager Number HF-02 Safety / L1 NRR/DHFT/MTB B.L. Grenier 56468 High J.P. Jankovich Subtask: MSPP:I.6
Title:
Analysis of Japanese /U.S. NPP Maintenance Programs Work Authorization: NRC/MITI International Agreement Contract
Title:
Analysis of Japanese-U.S. Nuclear Power Plant Maintenar:e Programs Contractor Name/ FIN: Pacific Northwest Laboratory (PNL)/ FIN B2550 Work Scape: The objective of of this project is to assess the degree to which differing Japanese and U.S. approaches to the regulation and practice of nuclear power plant (NPP) maintenance may explain the difference in reactor trips / scrams and safety equipment availability between U.S. and Japanese plants. This project consists of three tasks: (1) comparing and contrast-ing Japanese and U.S. NPP preventive maintenance programs, (2) assessing Japanese maintenance organizational and management practices, and (3) identification of the difference in Japanese
- U.S. NPP operating experience and factors which may account for the differenc.es.
Affected Documents: Report to the EDO, April 30, 1986 ~ _ _
9 JUN 3 01995 e
- , - - ~ - - - - - -
I Status: No contractual support will be sought in Phase I. Staff will continue to monitor the INPO Accreditation Program and industry standards group activities in this area to assess their initiatives.
Problem / Resolution: Given limited resources in view of ongoing industry efforts, no specific staff action is planned in Phase I, ,
NOTE: In the earlier version of the MSPP, this task was to have been supported (funded) by RES but was dropped by PES as a part of thei- dis:or.tinuance of su; port to the human factors areas.
Technical Resolutions:
Milestones Original Current Actual Develop Draft Statement of Work 6/30/85 -
6/10/85 Prepare summary'of asses'sment 1/28/86 1/16/86 of . industry initiatives for incorporation in the MSPP Phase I report to the EDO l
\
- t. .
l e
9 JUN 3 01986
MSPP I-7:BLG MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 7 Issue Issue Action Task TAC Number Tyge_ Level Office /Dir./Br. Manager Number NF-02 Safety / L2 - NRR/0HFT/MTB B.L. Grenier 57267 High J.L. Koontz Subtask: MSPP:I.7
Title:
Maintenance Personnel Qualifications Work Authorization: MSPP/ Phase I approved for implementation by the EDO on January 11, 1985.
Contract
Title:
Determination of Job-Relevant Maintenance Personnel Qualifications.
Contractor Name/ FIN: To be determined Work Scope: The purpose of this project is to identify from job and task analysis data, the knowledges, skills, and abilities required for the duties of electrical, mechanical, instrumentation and control, and supervisory maintenance personnel. The pertinent education and vocational training backgrounds as well as any aptitudes which provide the appropriate knowledge, skills, and abilities will be determined. The goal is to determine the -
appropriate maintenance personnel qualifications for use in developing standards and by which to assess current industry practice in ensuring the qualifications of maintenance person-i nel.
The results will provide information about the present level of maintenance personnel skills and the necessary personnel qualifications, i.e., knowledges, skills, and abilities, for correct performance of maintenance tasks. The results of this project will also be used to determine format, content, and use of -job performance aids as means of improving maintenance personnel performance.,
Affected Documents: Report to the EDO, April 30, 1986 JUN 3 01986
Status: The contractor report was submitted on the due date: February 28, 1986. The program sumary for inclusion in the EDO report has been written. This task is complete.
Problem / Resolution: None Technical Resolutions: -
Milestones Original Current Actual Develop Statement of Work 5/15/85 5/13/85 .
and Send Request for Proposal to Contractor Authorization and Start of 5/31/85 5/28/85 Work by Contractor Task 1 - Collection 7/31/85 7/19/85 of Human Factors Data from Mini-Round-Robin (MRR)
Tasks Task 2 - Analysis of MRR 10/25/85 10/31/85 Data Task - Site Visit to the 11/25/85 cancelled EPRI NDE Training Center Task - Preparation for MRR 11/22/85 cancelled Workshop Task - Conduct MRR Workshop 12/20/85 cancelled Task - Analyze Workshop Data 1/10/86 cancelled Contract Modification 9/27/85 9/24/85 Note: Contract modification subsequently cancelled Task 3 - Prepare and Submit Final Report
, a draft 11/15/85 11/20/85 l b second draft not scheduled 2/10/86 l c final 2/14/86 2/28/86
! Prepare sumary for incorporation 1/28/86 2/5/86 into the MSPP Phase I report to the EDO Incorporate Result of Work 4/30/86 in EDO Report i- g 3 c.816 l
1
. *: l MSPP I-8:BLG MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 8 Issue Issue Action Task TAC Number h Level Office /Dir./Br. Manager Number HF-02 Safety / L1 NRR/DHFT/MTB B.L. Grenier 57268 High D. Persinko Subtask: MSPP:I.8 *
Title:
Human Factors in In-Service Inspection Work Authorization: MSPP/ Phase I approved for implementation by the EDO on January 11, 1985.
Contract
Title:
Human Factors Aspects of Ultrasonic Testing / Inservice Inspection Tasks Contractor Name/ FIN: Pacific Northwest Laboratory (PNL)/ FIN B2983 Work Scope: NRC regulations (10 CFR 50.55a(g)) require that nuclear power plants have an effective ISI program in place. With respect to maintenance requirements, ISI programs may not provide sufficient data to support an effective preventive maintenance program which requires considerable data on equipment history and operation. Therefore, in order to obtain sufficient objective information to determine the practicality of trade-offs between ISI requirements and predictive / preventive maintenance requirements, a feasibility study investigating i ultrasonic testing (UT) techniques and associated human error potential will be performed. This project will be conducted in conjunction with the RES-sponsored program titled "Inte-gration of NDE Reliability and Fracture Mechanics." Identi-
. fication of probable sources of human factors problems
. contributing to ineffective UT/ISI processes and the need for and scope. of subsequent studies will be determined during Phase I.
Affected Documents:' Report to the EDO, April 30, 1986 l
JUN 3 01986
e 4
Status: The final report has been issued (ref: memo Russell to Denten dated March 13, 1986). The program summary for inclusion in the report to the EDO has also been completed. This task is completed. )
Problem / Resolution: None. -
Technical Resolutions:
Milestones Original Current Actual Identify Concern and Develop 4/17/85 4/17/85 Plan for Action for Resolution Develop Site Visit Protocol 5/1/85 5/1/85 Perform Site Surveys as Follows:
1.a. Site Visit to Dresden 5/9/85 5/9/85
- b. Prepare Trip Report 2.a. Site Visits to Surry and 6/20/85 6/20/85 North Anna
- b. Prepare Trip Report 9/20/85 9/23/85 3.a. Site Visits to Salem and 7/26/85 7/26/85 Peach Bottom
- b. Prepare Trip Report 10/31/85 12/18/85 4.a. Site Visits to Calvert 10/1/85 Cliffs cancelled
- b. Prepare Trip Report 10/18/85 5.a. Site Visits to Oconee and 10/25/85 10/25/85 McGuire
- b. Prepare Trip Report 12/20/85 3/6/86 6.a. Site Visits to D.C. Cook 11/15/85 11/15/85 and LaSalle
- b. Prepare Trip Report 1/17/85 1/10/86 1
7 a. Site Visit to Turkey Pt. 11/22/85 11/22/85 (and Browns Ferry)
- b. Prepare Trip Report 1/31/86 3/6/86 Issue Draft Report for 11/15/85 3/3/86 Management Review JUN 3 0 1986
. *7 MSPP I-9:8LG .
MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 9 Issue Issue Action Task TAC Number Type Level Office /Dir./Br. Manaoer Number HF-02 Safety / L1 NRR/DHFT/MTB B.L. Grenier 57269 High D. Persinko
- Subtask: MSPP:I.9
Title:
Human Error in Events Involving Wrong Unit or Wrong Train (Generic Issue 102)
Work Authorization: MSPP/ Phase I approved for implementation by the EDO on January 11, 1985.
Contract
Title:
None Contractor Name/ FIN: N/A Work Scope: In January 1984, the Office of Analysis and Evaluation of Operational Date (AE00) issued a special study report describing a number of events that resulted from human error in removing equipment from service or restoring equipment following maintenance that involved the wrong unit or wrong train of 1 equipment being rendered unavailable. Although the scope of the study was narrow, AE00 found that 19 out of 27 events identified resulted from human error during maintenance and surveillance testing. AE00 considered such events to be examples of events that could have high safety significance due to potential loss of safety system functions.
As part of the project, the Maintenance Section will identify existing practices that may lead to human errors involving wrong unit / wrong train and to recomend improvements that may be appropriate. The scope of this project will include review operating experience, conduct site visits, interview licensee personnel of a select number of plants to determine the extent and nature of loss of safety function resulting from errors
, involving the wrong unit / wrong train and will identify actions for resolution of the Generic Issue or for further inves-tigation.
Affected Documents: Report to the EDO, April 1986 l
l JUN 3 01986 l
e Status: Although the NRC "Model" Maintenance Program is considered to be an unofficial, "living" document, for the purpose of this task, it is complete.
Problem / Resolution: None Technical Resolutions:
Milestones Original Current Actual Development of Concept 4/29/85 4/29/85 Development of Draft Model 6/30/85 7/11/85 Prepare Final Draft of Model 10/25/85 10/2/85 -
Incorporate Model as Appendix model will not to EDO Report be incorporated in the MSPP Phase I report, to the EDO D
l JUN 3 01986
3 Milestones Original Current Actual Issue Final Report 1/15/86 3/13/86 Prepare sumary of results 1/28/86 3/7/86 for incorporation into MSPP Phase I report to the EDO Incorporate Results into 4/30/86 EDO Report
- Browns Ferry cancelled 1
0 e
i
.I O
t JUN 3 0 1986
i t
MSPP I-10:BLG MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 10-Issue Issue Action Task TAC Number Tyge_ Level Office /Dir./Br. Manager Number HF-02 Safety / L1 NRR/DHFT/NT8 8.L. Grenier 57270 High J.P. Jankovich i Subtask: MSPP:I.10
Title:
Development of an NRC Model Maintenance Program Work Authorization: MSPP/ Phase I approved for implementation by the EDO on January 11, 1985.-
Contract
Title:
None Contractor Name/ FIN: N/A -
Werk Scope: The maintenar.:e rodel to be developed will serve as a conceptual framework to allow a common interpretation for the role of maintenance between the NRC, the industry, and the standardization groups. The modelling approach will be
- similar to the instructional systems' development used in
! training by being general for overall acceptance and by providing a common basis to make plant-specific programs comparable. The model will be used to develop the site survey protocol. The modelling approach will include (1) the MSPP
- definition of maintenance, i.e., preventive, corrective, surveillance, organization, support, etc.; (2) the alignment of safety goals with the goals of the maintenance program; (3) means to compare plant-specific programs with each other for the industry assessment in Phase I of the MSPP.-
1 Affected Documents: Report to the EDO, April 1986 l
l I
i i
A I JUN 3 01986 i
_ .-__,.y._,___. _.., . . ~ . . _ _ _ _ . . _ . _ . - _ _ . _ , - _ . , - - _ . , - . . , _ _ , . _ . - _ _ _.._-- - _ -
e . I
. 1 Status: The MSS staff is continuing to write the report to the EDO on tne H5PT7hase I results and it is expected to be completed on time.
Problem / Resolution: None Technical Resolutions:
Milestones: Original Current Actual Prepare 50W to obtain 7/31/85 7/31/85 expert technical assistance Preliminary Outline 10/31/85 9/19/85 Annotated Outline and draft introductory material 11/30/85 11/7/85 I
Provide " report section" outline to contributors for " Integration" and
" Industry / Standards"
- projects 11/29/85 12/12/85 Complete Outline 12/31/85 1/2/86 First Draft Report Sections Percentage Completed I. Executive Sumary 0%(last)
II. Introduction 95%
III. Major-Findings 80%
IV. Statement of the Issues. 50%
Policy Objectives, and Recommendations JUN 3 01986
l, l
MSPP I-11:BLG MAINTENANCE AND SURVEILLANCE PROGRAM PLAN l i
' Phase I/ Task 11 Issue Issue Action Task TAC' Number Tyge_ Level Office /Dir./Br. Manager Number HF-02 -Safety / L1 NRR/DHFT/MTB 8.L. Grenier 56466 High J.L. Koontz Subtask: MSPP:1.11
Title:
Preparatien of the MSPP, Phase I Report to the EDO Work Authorization: MSPP/ Phase I approved for implementation by the E00 on January 11, 1985.
Contract
Title:
Task Assignment #2 " Review and Integration of Information from Program Related to the MSPP" Contractor Name/ FIN: Pacific Northwest Laboratory (PNL)/ FIN 82984 Work Scope: Phase I of the Maintenance and Surveillanc:. Drogram Plan consists of a minimum of 0 projects and will involve interactions with at least 10 other related NRC programs and related industry programs. Results from all of those projects and programs will produce an enormous amount or Jata and information that will need to be summarized and integrated into a meaningful report at the end of MSPP, Phase I that will contain sound recommendations concerning maintenance practices at U.S. nuclear power plants. Therefore, of primary importance in preparing and writing the Phase I Report is the extrapolation and synthesis of key information and data from all of the above sources into a policy level document.
. This task was formulated to track the resources associated with preparation of the final report.
Affected Documents: Not applicable JUN 3 01986
O VI. Appendices A. Sumary of Important Activities 80%
Related to the MSPP B. Regulatory Perspectives 95%
JUN 3 0 1986
/