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l ENCLOSURE i
5 I
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM THIRD QUARTER FY-86 UPDATE OFFICE OF NUCLEAR REACTOR REGULATION JULY 1986 i
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8608110077 860801 PDR                        ORG                              NRRC PDR
  . ~ . - - , . ,, , , . - . , . . , - , . . , . . _ _ . _ , - - - , , _ _ _ - , _ _ _ - - -                        -
                                                                                                                                                ,,,----..~--.,--,,,...--._n.            ,, _ ..- ----  .-a-.,__a,-,-n. . - , - --. --                  w,-
 
                                                                                                                              ,                                    -  .. .- -. _ - --                      . ~_
1 1
TABLE OF CONTENTS (a) Generic Issue Management Control System (1) Description 1_        __
(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 by Fiscal Year (f) Table 4A -                                              NRR Generic Safety. Issues Scheduled for Resolution i                                                      (g) Table 4B -                                              NRR-TMI Generic Safety Issues Scheduled for Resolution (h) Table 4C -                                              Non-NRR TMI and Generic Safety Issues Scheduled for Resolution (i) Table 4D -                                              Human Factors Program Pian Generic Safety Issues i
Scheduled for Resolution (j) Table 5 -                                              Number of Generic Issues Prioritized in FY-83, 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
 
l l
l
                                    .                                                                                                                                          )
                                                                                - iii -                                                                                        )
Os 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 point where the staff's technical resolution has been issued. Generally speaking, this occurs when the technical resolution has been incorporated into one or more of the following documents:
(a) Commission Policy Statement / Orders                                                                                                      ,
(b) NRC RegQlations (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 resciution, development of new criteria, review and approval, 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 l                        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 HRR Director.for resources for resolution. Issues ranked as either " LOW" or " DROP" are not allocated resources for resolution and, therefore, are not tracked in GIMCS.
Some new generic issues prioritized and processed in accordance with NRR Office Letter No. 40 may not have resources allocated for resolution and completion.
These issues are listed in GIMCS as inactive issues. Generally, these will be MEDIUM priority issues that have no safety deficiency demanding high priority attention, but have potential for safety improvements or reduction in uncertainty l
of analysis that may be substantial and worthwhile. Efforts for the resolution of these issues will be planned over the next several years, but on a basis that will not interfere with work on the resolution of HIGH priority generic issues or other high priority work. Thus, some (MEDIUM priority) generic issues will be inactive until such time as resources become available to resolve them.
The detailed schedule for resolving generic issues will be monitored by GIMCS.
  - . . - - - . . . - . ,        . - , , , , _ .      .._,__,,_,,.m    , . . .  .,,.-,,.-m,_  .._,_- . _ . _ . . _ , . _ . , , _ _ . . _ _ , . . _ _ _ _ , . _ , _ - . , . ,
 
                                                          - iv -
      \
Management and control indicators used in GIMCS are defined as follows:
: 1. Item No.                  - Generic Issue Number
                                              - Safety, Environmental or Regulatory Impact, HIGH,
                        ~
,            2. Issue Type 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 l                                                schedules:
L1 - No management action necessary L2 - Division Director action necessary
<                                                  L3 - NRR Director action necessary L4 - ED0 Director action necessary L5 - Commission action necessary
: 4. Office /Div/Br              - First-listed has lead responsibility for resolving issue; others listed have input to resolution.
: 5. Task Manaaer                - Name of assigned individual responsible for resolution
: 6. TAC Number                  - TAC number assigned to the issue.
(            7. Title                      - Generic Issue Title
: 8. Work Authorizaticn          - Who or what authorized work to be done on the issue.
: 9. Contract Title              - Contract Title (if contract issuti).
: 10. Contractor Name/ FIN - Contractor Name and FIN. (If contract is not yet issued, indicate whether the contract is included in the FIN plan.)
l            11. Work Scope                  - Describes briefly the work necessary to techni-I                                              _cally resolve and complete the generic issue.
: 12. Affected Documents          - Identifies documents into which the technical resolution will be incorporated.
: 13. Status                      - Describes current status of work.
: 14. Problem / Resolution        - Identifies problem areas and describes what actions are necessary to resolve them.
l            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 l
scheduled dates are listed under " Current."
l Actual completion dates are listed under " Actual."
1
 
                .                    .__ .          _        .  ~. .  .
4
                                            .y.
LEGEND H        - HIGH priority M        - MEDIUM priority 0        - DROP NR      - Nearly Resolved L        - LOW priority LI    - - Licensing Issue (Non-safety)
R        - Resolved RI      - Regulatory Impact Issue S()      - Subsumed in another Issue (issue #)
USI      - Unresolved Safety Issue L1      - No management action necessary                          .
L2      - Division Director action necessary L3      - NRR Director action necessary L4      - EDO Director action necessary L5      - 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 o
O
 
O                                                      O                                                          O 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 l  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 4
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
 
s                                                        s TABLE 2 NUMBER OF GENERIC ISSUES RESOLVED AND SCHEDULED FOR RESOLUTION                                      ,
Third Quarter FY-86                                            ,
3    '
                #                              Resolved-ale-Scheduled for Resolution          d FY-86 Quarters                  FY-88                                    t ISSUE                                                                          &                  Cumulative PRIORITY  FY-83    FY-84  FY-85  1st  2nd    3rd  4th    Total  FY-87  EY-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 i
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 medium priority TMI issues have been superseded by nine I      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
 
f TABLE 3 GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue                                                    Two of      Date Approved    Date Number          Title                      Priority    Resolution    for Resolution  Resolved
                                                                                                                        }
FY-83 I
A-11    Reactor Vessel Materials          USI          GL 82-26    01/79            10/82                    1 Toughness A-16    Steam Effects on BWR Core Spray NR              MPA-D12      NRR-OP FY83      03/29/83 Distribution l
A-39    Determination of Safety            USI          SRP Revision  01/79            10/82                    i Relief Valve (SRV) Pool Dynamic Loads and Temperature Limits for BWR Containmen*
B-53    Load Break Switch                  NR          SRP Revision  NRR-OP FY83      07/28/83                  ]
II.E.5.1 (B&W) Design Evaluation            NR          No            NRR-OP FY83      03/21/83 Requirement IV.C.1  Extend Lessons Learned From        NR          No            NRR-OP FY83      04/15/83 TMI to Other NRC Programs                      Requirement FY-84 12      BWR Jet Pump Integrity            Mediurs      No            NRR-OP FY83      09/25/84 Requirement 20      Effects of Electromagnetic          NR          HUREG/        NRR-0P FY83      11/15/83 Pulse on Nuclear Plant Systems                  CR-3069 40      Safety Concerns Associated          NR          MPA-965      07/18/83          12/27/83 With Breaks in the BWR Scram System T3-1                          As of 3rd Quarter FY-86
 
O                                                                O Table 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR Issue                                                                  Type of          Date Approved            Date      .
;            Number                    Title                            Priority  Resolution      for Resolution          Resolved *I FY-84 (cont'd)
;            45                  Inoperability of instruments            NR        SRP Revision    09/08/83                03/23/84 Due to Extreme Cold Weather.                                      '
i l            50                  Reactor Vessel Level                    NR        MPA-F26          07/28/83                09/06/84 1                                Instrumentation in BWRs 69                  Make-Up Nozzle Cracking in              NR        MPA-            12/06/83                09/27/84 j          .
B&W Plants l
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 i                                Coolant Pump Supports B-10                Behavior of BWR Mark III                  High      SRP Revision    NRR-OP FY83              09/10/84 s                                Containments B-26                Structural Integrity of                  Medium    No              NRR-OP FY83              09/27/84 Containment Penetrations                            Requirement 1
i            B-60                Loose Parts Monitoring                    NR        GL              NRR-OP FY83              09/25/84
;                                Systems (LPMS)
)              I.A.1.4            Long-Tern Upgrading of                    NR        New Rule        NRR-OP FY83              01/01/84 Operating Personnel l
II.A.1            Siting Policy Reformulation              Medium    No              NRR-OP FY83              09/20/84 Requirement 1
II.E.5.2            (B&W) Reactor Transient                  NR        NUREG-0667      NRR-OP FY83              09/28/84 l                              Response Task Force f
4 III.D.2.5          Offsite Dose Calculation Manual NR                  NUREG/          NRR-OP FY83              01/17/84 l                                                                                    CR-3332 T3-2                            As of 3rd Quarter FY-86 1
 
m 1
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 Baron Dilution        NR        GL 85-05        11/05/82        10/15/84 Events
,  A-41      Long Term Seismic Program          Medium    No            NRR-OP FY83        '9/10/84 Requirement B-19      Thermal-Hydraulic Stability        NR        GL            01/03/85          05/21/85 j  B-54      Ice Condenser Containments        Medium    NUREG/        NRR-OP FY83        10/22/84 CR-4001 B-58      Passive Mechanical Failures        Medium    No            NRR-OP FY83      07/09/85 Requirement C-11      Assessment of Failure and          Medium    No            NRR-OP FY83      07/09/85 Reliability of Pumps and                      Requirement Valves i
;  I.A.2.2    Training and Qualifications        High      Policy        NRR-OP FY83      06/24/65
!            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 T3-3                          As of 3rd Quarter FY-86
 
Table 3 (Continued)
GENERIC SAFETY ISSUES RESOLVED BY FISCAL YEAR                                            .
Issue Number                                Title                  Priority Type of Resolution Date Approved for Resolution Date Resolved
                                                                                                                                                    .{
FY-85 (cont'd)
I.A.3.4        Licensing of Additional                        Medium    Policy                  NRP.-OP FY83      02/12/85
{                            Operations Personnel                                      Statement            .
No Requirement i            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 l              II.B.8        Rulemaking Proceedings on                      -            -                        -                -
;                            Degraded Core Accidents (a) Hydrogen Rule                              High      Rule                    NRR-OP FY83        07/19/85
:                            (b) Severe Accidents                          High      Policy                  NRR-OP FY83        08/12/85 Statement 1
l              II.C.1        Interim Reliability Evaluation                High      No                      NRR-OP FY83        07/09/85 j                            Program                                                  Require?ent                                '
i
!              II.C.2        Continuation of Intrim                        High      No                      NRR-OP FY83        09/25/85 Reliability Evaluation Program                            Requirement II.E.2.2      Research on Small Break LOCAs                  Medium    No                      NRR-OP FY83        07/25/85 and Anomalous Transients                                  Requirement III.A.1.3(2)  Maintain Supplies of                          NR        Policy                  NRR-OP FY83        08/15/85 Thyroid-Blocking Ngent                                    Statement l                            For Public III.A.3.4      Nuclear Data Link                              Medium    No                      NRR-OP FY83        06/26/85 Requirement T3-4                                    As of 3rd Quarter FY-86
 
b\
1          \
Q
]
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) j            III.D.9.3(1)  Develop Procedures to                NR        ESRP          NRR-OP FY83      08/28/85 Discriminate Between Sites /                  Revision Plants III.D.2.3(2)  Discriminate Between Sites          NR        ESRP          NRR-OP FY83      08/28/85 4
and Plants that Require                        Revision Consideration of Liquid
!                          Pathway Interdiction Techniques III.D.2.3(3)  Establish Feasible Method of        NR        ESRP          NRR-OP FY83      08/28/85 Pathway Interdiction                          Revision III.D.2.3(4)  Prepare a Summary Assessment        NR        ESRP          NRR-OP FY83      08/28/85 Revision
;            IV.E.5        Assess Currently Operating          High      No      . NRR-OP FY83      09/25/85 Plants Requirement FY-86 3              Setpoint Drift in                    NR        Reg Guide    NRR-OP          05/19/86 j                          Instrumentation                                Rev. No Req.
l          14            PWR Pipe Cracks                      NR        No            NRR-OP FY83      10/04/85 l                                                                        Requirements i
36            Loss of Service Water                NR      . SRP Revision  02/15/84          05/13/86 No Req.
!            A-43          Containment Emergency                USI      SRP          01/79            10/85 j
Sump Perfomance                                Revision l            III.D.3.1    Radiation Protection Plan            High      No            NRR-OP          05/19/86 Requirement l                                                                    T3-5                        As of 3rd Quarter FY-86 i
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-87 (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              HF'P-5.4 77                                                    B-6                                          HFPP-3.4              HFi'-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
 
I O                                                        O                                                    O l                                                            Table 4A
!                                  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
;  23      Reactor Coolant Pump Seal Failures      DSR0/EIB          H    NRR-OP            07/86        TBD 29      Bolting Degradation or Failures in      DSR0/EIB          H    NRR-OP            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 1E        DSR0/EIB          M    07/31/84          09/88          TBD Tie Breakers 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 i  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 i                                                                                                                      ,
i 14-2                      As of 3rd Quarter FY-86 j
 
                                                                                                            ~
l                                                                                                    Table 4A (continued)
NRR GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION l                                                                                                    Lead                        Date            Resolution    Current
* l                                        Issue                                                    Division /                Approved for        Date as of    Resolution Number                        Title                      Branch        Priority    Resolution          June FY-85        Date*I 70    PORV and Block Valve Reliability                  OSRO/EIB          M      05/14/84            02/87          11/87            ;
l                                        77    Flooding of Safety Equipment                      DSR0/EIB          H      09/08/83 08/86          TBD l                                                Compartments by Back-Flow Through l                                                Floor Drains I                                                                                                                                                                                  .
:                                        79    Unanalyzed Reactor Vcssel Thermal                  DSRO/EIB          M      07/2S/83            09/86          10/86            l l                                                Stress During Natural Convection Cooldown l
l 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 j                                        84    CE PORVs                                          DSR0/RSIB          NR    02/27/85            TBD            TBD I
j                                        86    Long Range Plan for Dealing With                  DBL /EB            NR    10/01/84            04/86          01/87 j                                                Stress Corrosion Cracking in BWR j                                                Piping 1
I                                        87    Failure of HPCI Steam Line iiithout                DSR0/RSIB            H    09/26/85            TBD            TBD
]                                                Isolation 91    Main Crankshaft Failure In                        ORAS/8WR            NR    07/08/85            None          TBD Transamerica DeLaval l                                        93    Steam Binding of Auxiliary                        DSR0/RSIB            H    10/19/84            06/87          09/87 l
Feedwater Pumps l
;                                        94    Additional Low-Temperature                        DSR0/RSIB            H    07/23/85            None          TBD Overpressure Protection For i                                              Light Water Reactors 99    RCS/RHR Suction Line Interlocks                    DSR0/RSIB            H    08/13/85            None          10/87 i                                              on PWRs i
1 I                                                                                                            T4-3                          As of 3rd Quarter FY-86 i
 
O                                                                  O 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 122.1b  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-OP            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 l        Supplies i A-40    Seismic Design Criteria              DSR0/EIB          USI      01/79            06/86              10/87 i
A-44    Station Blackout                      DSR0/RSIB        USI      01/79            04/86              07/88 I
T4-4                            As of 3rd Quarter FY-86
 
O Table 4A (continued)
NRR GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION Lead                                                                          Date          Resolution          Current
* l Issue                                        Division /                                                                  Approved for    Date as of          Resolutjy 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                                                    02I81            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-OP          09/87                06/88 Shells and Buckling Behavior of Steel Containments B-6    Loads, Load Combinations, Stress      DSR0/EIB              H                                                      NRR-OP          09/87                TBD Limits B-17  Criteria for Safety-Related            DHFT/HFIB            M                                                      03/22/82      Being resolved            -
Operator Actions                                                                                                                  by HF-01, Issue HFPP-4.3.
B-55  Improve Reliability of Target Rock    DSR0/EIB              M                                                      NRR-OP          12/85                07/86 Safety Relief Valves B-56  Diesel Reliability                    DSR0/RSIB            H                                                      NRR-OP          05/86                11/87 1
B-61  Allowable ECCS Equipment Outage        DSR0/RRAB            M                                                      NRR-OP          09/87                10/88          f Periods                                                                                                                                                                  1 1
B-64  Decommissioning of Nuclear Reactors DBL /PSB                NR                                                    NRR-OP          06/87                10/87          i 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
 
O Table 4B O
NRR TMI GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION i
i                                                                Lead                        Date          Resolution    Current Issue                                              Division /                  Approved for      Date as of    Resolution
!            Number                      Title                  Branch            Priority Resolution        June FY-85        Date l
l            I.A.2.6  Long-Tern Upgrading of Training        DHFT/HFIB              H  Being resolved        -            -
l            (1)        and Qualifications - Revise                                        by HF-01, Issue Regulatory Guide 1.8                                                HFPP-1.2 l            1.A.4.2    Research on Training Simulators        DHFT/HFIB              H  NRR-OP            08/85          09/86 l            (1) i I.A.4.2  Review Simulators for Conformance      DHFT/HFIB              H  Being resolved        -            -
,            (4)                                                                          by HF-01, j                                                                                          Issue HFPP-3.3 i
i            I.B.1.1  Organization and Management of                    -            -      -                  -            -
!                      Long Tern Improvements j            I.B.1.1  Prepare Draft Criteria                  DHFT/HFIB              M  Being resolved        -            -
j            (1)                                                                          by HF-01, Issues HFPP-6.1 1                                                                                          and 6.3 1
l            1. B .1.1 Prepare Commission Paper                DHFT/HFIB              M  Being resolved        -            -
.l            (2)                                                                          by HF-01,
{                                                                                          Issues HFPP-6.1 j                                                                                          and 6.3 I.B.1.1  Issue Requirements for the              DHFT/HFIB              H  Being resolved        -            -
(3)      Upgrading Management and                                            by HF-01, j                    Technical Resources                                                Issues HFPP-6.1
!                                                                                          and 6.3 I
I.B.1.1  Review Responses to Determine          DHFT/HFIB              M  Being resolved        -            -
(4)      Acceptability                                                      by HF-01, i
Issues HFPP-6.1 i                                                                                        and 6.3 I
J              I.C.9    Long-Term Program Plan for Upgrad-      DHFT/HFIB              M  Being resolved        -          -
  )
ing of Procedures                                                  by HF-01,
  !                                                                                        Issues HFPP-4.2 I                                                                                        and 4.4 and HF-02                                I l                                                                        T4-6                          As of 3rd Quarter FY-86
 
s j                                                                                                                                                    s/
Table 4B (continued)
NRR TMI GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION Lead                      Date          Resolution    Current Issue                                                Division /              Approved for    Date as of    Resolut,ijn i                              Number                    Title                      Branch      Priority  Resolution      June FY-85              Date l
l                              I.D.4    Control Room Design Standard              DHFT/HFIB        H      Being resolved      -                -
;                                                                                                            by.HF-01, l                                                                                                            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-OP          04/87          07/87 I                              II.E.6.1 Test Adequacy Study                        DSR0/EIB        M      NRR-OP          05/88          05/88
,                            II.F.5    Classification of Instrumenta-            DSR0/EIB        M      NRR-OP          01/86          TBD tion, Control, and Electrical Equipment l
I
.l l
l i
T4-7                        As of 3rd Quarter FY-86
 
)
f                                                                              Table 4C NON-NRR TNI 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 75      Generic Implications of ATWS          IE/QAVT/QAB            NR      10/19/83          02/86        07/87 Events at the Salen Nuclear i                              Plant l
l                      119.1  Piping Rupture Requirements          RES/MSEB              RI      09/10/85            --
01/88
.                              and Decoupling of Seismic and LOCA Loads i
l                      119.2  Pipe Damping Values-                  RES/MSEB              RI      09/10/85            --
11/86 119.3  Decoupling OBE from SSE              RES/ESB                RI      09/10/85            --
TBD 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 l                      121    Hydrogen Control for Large,          RES/DRA0/RAMRB        H        09/26/85          TBD            09/86 Dry Conteineent l
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.1.1 Issue Regulatory Guides 1.33 and      IE/QAVT/QAB            M        NRR-OP            02/86          07/87 (7)    1.8 I.D.3  Safety System Status Monitoring      RES/DET/EEICB          M        NRR-OP            12/87          02/89 T4-8                                As of 3rd Quarter FY-86
 
O                                                            O
\
I Table 4C (continued)
NON-NRR TMI AND GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION Lead                      Date          Resolution    Current 1
Issue                                                  Division /                Approved for      Date as of    Resolution l                Number                          Title                  Branch          Priority Resolution        June FY-85        Date i
I.D.5          On-Line Reactor Surveillance            RES/DET/EEICB      NR    NRR-OP            09/88        09/88 J
(3)            Systems I . F.1        Expand QA List                          IE/QAVT/QAB        H    NRR-OP            08/85        ACA II.B.5        Behavior of Severely Damaged            RES/DAE/FSRB        H    NRR-OP            12/87        06/88
!                  (1)            Fuel II.B.5          Behavior of Core Melt                  RES/DAE/FSRB        H    NRR-OP            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 l                                  Structure i
.                  II.C.4          Reliability Engineering                RES/DRA0/RRB        H    NRR-OP            12/87        12/87 l                  II.H.2          Obtain Technical Data on the            RES/DAE/FSR8        H    NRR-OP            12/86        12/88
!                                  Conditions Inside the TMI-2 Contalement Structure
!                  II.J.4.1 Revise Deficiency Report                      IE/DEPER/EAB        NR    NRR-OP            07/86        02/87 Requirements I
l I
.                                                                                T4-9                            As of 3rd Quarter FY-86 I
 
i 1
Table 40 HUMAN FACTORS GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION E                                                                                                                            .
Lead                        Date            Resolution  Current i
Issue                                              Division /                Approved for        Date as of  Resolution Numbcr                        Title                Branch        Priority    Resolution          June FY-85      Date l
l                      HF-01 HUMAN FACTORS PROGRAM PLAN (HFPP) j                      HFPP Subtask Numbers j                      1.1          Policy Statement on Engineering      DHFT/HFIB          H      10/01/84              TBD      TBD Expertise on Shift and Evaluate i                                    Effectiveness of Policy Statement i                      1. 2        Revise and Evaluate Changes to        DHFT/HFIB          H      10/01/84              08/85    TBD l                                    Regulatory Guide 1.8 1.3          Develop a Means to Evaluate          DHFT/HFIB          H      10/01/84              TBD      TBD Acceptability of NPP Personnel Qualifications Program                                        -
i j                      1.4          Review and Evaluate Industry          DHFT/HFIB          H      10/01/84              TBD      TBD Programs
]
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 l                                    Section 13.2.3 i                      3.1          Develop Job Knowledge Catalogue      DHFT/HFIB          H      10/01/84              TBD      10/86 i
i                      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
 
l 1
l                                                Table 4D (Continued)
J                              HUMAN FACTORS GENERIC SAFETY ISSUES SCHEDULED FOR RESOLUTION                                  .
d
                                                                                                                            .g l                                                  Lead                          Date            Resolution      Current t
Issue                                        Division /                  Approved for        Date as of      Resolution Number                    Title                Branch        Priority    Resolution          June FY-85          Date HFPP Subtask Numbers (Continued)                                            -
I 3.4    Training Requirements Package        DHFT/HFIS          H        10/01/84              TBD          TBD (Revise 10 CFR 55 and RGs 1.149 and 1.8) 3.5    Develop Computerized Exam System      DHFT/HFIB          H        10/01/84              TBD          TBD          l 1  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        !
l  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
,  4.5    Applications of Artificial            DHFT/HFIB          H        10/01/84              TBD          TBD Intelligence l
5.1    Local Control Stations                DHFT/HFIB          H        10/01/84              TBD          TBD i
!  5.2    Annunciators                          DHFT/HFIB          H.      10/01/84                TBD          TBD Il 5.3    Evaluate Operational Aid Systems      DHFT/HFIB          H        10/01/84                TBD          TBD 5.4    Computers and Computers Di, splays    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 l
6.2    Evaluate Criteria For SALP Reviews    DHFT/HFIB          H        10/01/84                TBD          TBD T4-11                                As of 3rd Duarter FY-86
 
l                                                                                        Table 4D (Continued)                                                                            '
i l                                                                      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 PROGRAM PLAN (MSPP)
MSPP Subtask Numbers (Phase I) 1.1                Survey Current Maintenance                DHFT/MTB            H            03/06/85                    TBD              TBD Practices
]
I.2                Maintenance Performance Indicators        DHFT/MTB j                          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                                                                                                                      .
1 l                          I.6                Analysis of Japanese /U.S. NPP            DHFT/MTB            H            03/06/85                  TBD              TBD l                                              Maintenance Programs                                                                              _
I.7              Maintenance Personnel                    DHFT/MTB            H            03/06/85                  TBD              TBD 1                                              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 j                                              Wrong Unit Wrong Train (GI #101)
MSPP Subtask Numbers (Phase II)
  !                          II.0              Phase II Tasks To Be Determined          DNFT/MTB              H            03/06/85                  TBD              TBD l                                            After Resolution of Phase I j                                                                                            T4-12                                        As of 3rd Quarter FY-86 l
 
J                                                                    O                                                        O TABLE 5
)                                      NUMBER OF GENERIC ISSUES PRIORITIZED 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 l                                      Issues Identified                    19      2    0            0  0      0  -
0          21
.                                      To Be Reprioritized Total:                              75    21    54            6  6    32  -
44        194 New Issues (Entered into GIMCS) l 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 i                                      Human Factor                          0      0  34            0  0      0  -
0          34 l                                      Issues Subtotal:                            7    10    48            0  5      0  -
5          70 i                                      Resolved                              4      0    1            2  0      0  -
2            7 Low                                  1      4    0            0  1      0  -
1            6 Drop                                  1      4    4            1  0      3  -
4          13 Regulatory Impact /LI                O      O    3            5  0      3  -
8          11 i                                      Subsumed                              8      2    3            0  0      4  -
4          17 I
;                                      Total Issues                        21    20    59            8  6    10  -
24          124 Prioritized l
!                                      Remaining Issues                    54      1  -5          -2  0    22  -
20          70 l                                      To Be Prioritized
!                                      or Reprioritized
:                                                                                            TS-1                            As of 3rd Quarter FY-86 1
i
 
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 System
: 40.          Safety Concerns Associated with Pipe Breaks in      09/82            07/83              NR the BWR Scram System
: 41.          BWR Scram Discharge Volume Systems                  09/82            07/83              R
: 42.          Combination Primary / Secondary System LOCA        09/82            04/83              S(18)
: 45.          Inoperability of Instrumentation Due to Extreme    09/82            09/83              FR 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              MEDItM
: 52.          SSW Flow Blockage by Blue Mussels                  09/82            05/83              S(51)
: 56.          Abnormal Transient Operating Guidelines as          09/82            02/83              S(A-45/I.D.1)
Applied to a Steam Generator Overfill Event
: 58.          Inadvertent Containment Flooding                    09/82            08/83              DROP
: 64.          Identification of Protection System Instrument      10/82            02/83              R Sensing Lines
: 65.          Probability of Core-Melt Due to Component Cool-    02/83            07/83              HIGH ing Water System Failures
: 77.          Flooding of Safety Equipment Compartments by        06/83            09/83              HIGH Back-Flow Through Floor Drains
: 79.          Unanalyzed Reactor Vessel Thermal Stress During    06/83            07/83              MEDIUM Natural Convection Cooldown 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
 
O                                                      O    .
O TABLE 6 (CONT.)
GENERIC ISSUES PRIORITIZED AS OF THIRD QUARTER FY-86 Action Item /                                                      Identif.ication Date              Current Issue No. Title                                              Date            Prioritized      Priority FY-84
: 34.          RCS Leak                                            09/82            02/84            OROP
: 35.          Degradation of Internal Appurtenances in LWRs      09/82            02/84            LOW
: 36.          Loss of Service Water                              09/82            02/84            NR
: 43.          Contamination of Instrument Air Lines              09/82            11/83            DROP
: 44.          Failure of Saltwater Cooling System                09/82            10/83            S(43)
: 48.          LCO for Class IE Vital Instrument Buses in          09/82            10/83            NR Operating Reactors
: 49.          Interlocks and 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
: 61.          SRV Line Break Inside the BWR Wetwell Airspace      10/82            11/83            MEDIUM of Mark I and II Containments
: 66.          Steam Generator Requirements                        06/83            11/83            NR
: 68.          Postulated Loss of Auxiliary Feedwater System      06/83            04/84            HIGH Resulting from Turbine-Driven Auxiliary Feedwater Pump Steam Supply Line Rupture
: 69.          Make-up Nozzle Cracking in B&W Plants              06/83            12/83            NR        -
: 70.          PORY and Block Valve Reliability                    06/83            05/84            MEDIUM
: 75.          Generic Implications of ATWS Events at the Salem 06/83              10/83            NR Nuclear Plants
: 80.          Pipe Break Effects on Control Rod Drive Hydrau-    06/83            01/84            LOW lic Lines in the Drywells of BWR Mark I and II
: 82.          Beyond Design Basis Accidents in Spent Fuel        08/83            12/83            MEDIUM Pools
: 90.          Technical Specifications for Anticipatory Trips    02/84            08/84            LOW
: 92.          Fuel Crumbling Durir.g LOCA                        04/83            07/84            LOW B-65          Iodine Spiking                                      09/82            06/84            DROP T6-2                            As of 3rd Quarter FY-86
 
O TABLE 6 (CONT.)
GENERIC ISSUES PRIORITIZED AS OF THIRD QUARTER FY-86 i
Action Item /                                                          Identification Date            Current Issue No.      Title                                                  Date          Prioritized    Priority FY-85                                                                                                                  ,
: 37.          Steam Generator Overfill and Combined Primary          09/82          05/85          S(USI-A47) and Secondary Blowdown
: 54.          Valve Operator-Related Events Occurring                09/82          06/85          S(II.E.6.1)
During 1978, 1979, and 1980
: 55.          Failure of IE Safety-Related Switchgear Circuit        09/82          03/85          DROP Breakers
: 59.          Technical Specification Requirements for Plant          10/82          02/85          RI[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                                                                t
: 83.          Control Room Habitability                              11/83                          NR
: 84.          CE PORVs                                                11/83          02/85          NR
: 85.          Reliability of Vacuum Breakers Connected                11/83          07/85          DROP              I 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.          CR0 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          HICH 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
 
4 TABLE 6 (CONT.)
GENERIC ISSUES PRIORITIZED AS OF THIRD QUARTER FY-86 I
)            Action Item /                                                                              Identification    Date              Current j          Issue No.              Title                                                              Date              Prioritized        Priority FY-85(cont'd)                                                                                                                              ;
l          8-19                  Thermal-Hydraulic Stability                                        02/83            01/85              NR          l' l            B-50                  Post Operating Basis Earthquake Inspection                          02/83            04/85              RI (LOW)
!          B-59                  N-1 Loop Operation in BWRs and PWRs                                02/83            06/85              R HF-01                  Human Factor Program Plan (HFPP twenty four                        08/83            10/84              HIGH subtask elements)
HF- 02                Maintenance and Surveillance program Plan                          04/84            03/85              HIGH (MSPP ten subtasks elements)
!            FY-86                                                                                                                                      t
!              21.                Vibration Qualification of Equipment                                03/83            06/86              DROP i
: 30.                Potential Generator Missiles - Generator Rotor                      09/82            10/85              DROP        l
!                                  Retaining Rings l              74.                Reactor Coolant Activity Limits for Operating                      06/83            05/86              DROP 1                                  Reactors j              97.                PWR Reactor Cavity Uncontrolled Exposure                            09/84            10/85              R 111.                  Stress Corrosion Cracking of Presure Boundary                      01/85            11/85              LI Ferritic Steels in Selected Environments 112.                  Westinghouse RPS Surveillance Frequencies and                      01/85            10/85              RI(R)      ;
Out-of-Service Times 114                    Seismic Induced Relay Chatter                                      03/85            06/86              S(USI-A46) t 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 Ccnstraints                                08/85            01/86              LOW
!            124                    Auxiliary Feedwater System Reliability                              12/85            02/86              NR 125.I.2.a              PORV Reliability - Test' Program                                    11/85            06/86              S(70) 1            125.I.2.b              PORV Reliability - Surveillance                                    11/85            06/86              S(70) 4 125.I.2.c              Auto Block Valve Clostre                                            11/85            06/86              DROP
!            125.I.2.d              Equipment Qualification for Feed-and-Bleed                          11/85            06/86              S(USI-A45) ;
i                                  Environment                                                                                                        l
:            C-4                    Statistical Methods for ECCS Analysis                              02/83            06/86              RI(R)        ,
l            C-5                    Decay Heat Update                                                  02/83            06/86              RI(R) l            C-6                    LOCA Heat Sources                                                  02/83            06/86              RI(R)      ;
l l                                                                                                T6-4                        As of 3rd Quarter FY-86  i
 
TABLE 7                                                      .
GENERIC ISSUES TO BE PRIORITIZED Action Item /                                                                    Identification      Current Issite 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        ,
: 63.        Use of Equipment Not Classified as Essential to Safety in              10/82            12/86        i i                                          BWR Transient Analysis
: 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 l                              73.        Detached Thermal Sleeves                                                06/83            10/86 i                              76.        Instrumentation and Control Power Interactions                          06/83            08/86
!                              78.        Monitoring of Fe.tigue 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 Effective 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        l I                            104.          Reduction of Boron Dilution Requirements                                10/84            03/87 i                            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        t 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 Sr,ubbers        03/85            09/86
!                            115.          Reliability of Westinghouse Solid State Protection System              04/85            07/86
)                            116.          Accident Management                                                    04/85            TBD 1                              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            T80
;                                          Criterion Suggested by the Davis-Besse Incident of June 9, 1985 i
I.
T7-1            As of 3rd Quarter FY-86
 
O                                                O                                                              O        .
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                    07/36 125.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                            11/85                    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                    07/86 125.11.5      Thermal-Hydraulic Effects of Loss and Restoration of Feedwater            11/85                    07/86 on Primary System Components 125.II.6      Reexamine PRA Estimates of Core Damage Risk from Loss of All Feedwater 11/85                        08/86 125.II.7      Reevaluate Provisions to Automatically Isolate Feedwater from Steam      11/85                    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                    07/86 125.11.12    Adequacy of Training Regarding PORV Operation                            11/85                    07/86        1 125.II.13    Operator Job Aids                                                        11/85                    08/86        l 125.11.14    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
 
O                                                      O 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 1E Safety-Related Switchgear Circuit            D              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 Ultincte Heat Sinks                              LI            02/83        08/86 B-31          Dam Failure Model                                                RI            02/83        09/87 B-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)      0,6/83      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 l
T8-1                            As of 3rd Quarter FY-86
 
Table 9 TMI LICENSING ISSUES SCHEDULED FOR RESOLUTION Lead Office /    Current Issue                                                                        Division /    Resolution Number      Title                                                            Branch        Date i
I.A.2.4      NRR Participation in Inspection Training                        NRR/DHFT/      TBD l  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
    .II.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 1
T9-1                        As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM N
Issue Issue Action                        Task Number        h            Level          Office /Div/Br    Manager          TACS No.
3            Safety /    Complete      NRR/DSR0/RSIB      L. Riani        52400 NR Title ----------------      Set Point Drift in Instrumentation.
Work Authorization ---      NRR FY-84 Operating Plan, (Appendix G).
Contract Title -------      None Contractor Name/ FIN --    None Work Scope -----------      Provide technical assistance, as required, to RES for the revision and issuance of Regulatory Guide 1.105, Revision 2.
Affected Documents ---      Revise Reg. Guide 1.105, Rev. 2 (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 tc submit CRGR package for      10/83                -
08/05/83 review.
CRGR review completed and            11/83                -
10/20/83 returned to RES with comments.
ACRS review completed.                -                  -
11/19/83 RES incorporated CRGR comment          -                  -
12/12/83 and returned for approval.
CRGR review                          03/84                -
01/11/84 CRGR meeting                          -                  -
03/12/85 Issue Memorandum to NRR to          08/84                -
05/06/85 establish basis for R.G.
Position.
O l
3-1                As of 3rd Quarter FY-86 a.
 
r l
Generic Issue #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.
l 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.
l i
O l
i l
    ^ Memorandum from H. R. Denton to T. Speis, dated May 19, 1986.
O 3-2                      As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue        Issue        Action                                Task Number      Ty,ge,          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).
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
: 5) Leak Rate Analysis of Westinghouse RCP Contractor Name/ FIN --    1) BNL/A-3751
: 2) BNL/A-3771
: 3) BNL/A-38C6
: 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.
i Task 2 - Evaluate RCP seal cooling for all modes of oper-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 Itr. 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
 
l Generic Issuo #23                                    l l
l 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 Gcide and SRP Section (To Be
;                          Determined)
Status --------------- Work is currently in progress on Tasks 1, 2, and 3 as        J 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        l 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        l ETEC. The AECL contract work has been completed and NUREG/
i 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 assistence contract (FIN A-3751) with BNL, is working on Task 2 (subtask 2.2). The purpore 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 and maintenance induced RCP seal failures or risk.
Subtask 3.1 has been completed and NUREG/CR-4400 has been issued.                                                  ,
1 EIB, under technical assistance contract (FIN A-3806) with  )
BNL is working on Task 2 (subtask 2.3) and Task 3 (subtask 3.2). The purpose cf these subtasks are to          )
evaluate the adequacy of current RCP seal and seal cooling  i system instrumentation to detect RCP seal degradation and    l failures; to evaluate the adequacy of current automatic      '
actions and manual operator responses to prevent RCP seal LOCAs or other unacceptable events and to propose possible instrumentation changes, automatic actions or manual        l l                        operator responses which could improve the current RCP      i l                        seal safety procedures. Subtasks 2.3 and 3.2 have been      l completed and the BNL draft report has been reviewed by      I the staff and is currently being revised by BNL.
l 23-2                  As of 3rd Quarter FY-86 l
l
 
Gtneric Issua #23 l
p  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          i 4/15/86. Additional concerns regarding all types of RCP      l seals were raised as a result of the AECL test program.      !
RES is extending their test program at AECL to further      l 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      l work to the extent possible at this time.
Milestones                                          Original,            Current        Actual GI Action Plan issued For                          04/83                  -
03/31/83 Comment Action Plan Approved by                            10/83                  -
10/26/83 Director, DSI.
Transferred Resolution                                -                  -
06/15/84 Responsibility from DSI to DE Transferred resolution                                -                  -
05/13/85 responsibility from DE Os      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 evaluation of RCP                        12/84                12/85*            -
seal cooling, including determining effect of loss of cooling, evaluating reli-ability of cooling systems, and reviewing RCP seal cooling instrumentation (Task 2)
Issued request for proposal                          -                  -
11/02/83 to BNL for component cooling water PRA.
Complete evaluation of mechani- 01/85                                    -
09/85 cal and maintenance induced fai*Jre mechanisms (Task 3).
Complete feasibility study to                      03/85                10/85*            -
identify most effective fix.
23-3                As of 3rd Quarter FY-86
 
GIneric 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. 30/85*                -              -
Package sent to CRGR.
CRGR review complete.            11/85*                -              -
ACRS review complete.            17e'85*                -              -
EDO approval.                    12/85*                -              -
l Federal Register Notice issued    12/85*                -              -
for public comment.
OMB Clearance.                    04/86*                -              -
i l            Incorporation of comments        04/86*                -              -
!            Package sent to Director, NRR.
1 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 French Reactor RCP seal testing and the additional AECt. test results.
O 23-4                As of 3rd Quarter FY-86
 
A                          GENERIC ISSUE MANAGEMENT CONTROL SYSTEM U
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).
Contract Title -------  Bolting Applications Requirements 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. B2-02, " 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 implementation plan for management consideration.
Affected Documents ---  SRP revision.
Status ---------------  Transfer of lead to DSR0/EIB was effected following the NRR reorganization. Revision of the Technical Resolution plan and program Milestones is being held in abeyance pending 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 for 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, the need to resolve the issue might change. Rather than pre-pare revisions prematurely, we will let USI A-45 set the pace.
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.
29-1                  As of 3rd Quarter FY-86
 
l Generic Issue #29                                j Technical Reolution --
1 Milestones                    Original          Current            Actual Issue contract to BNL              -                -
03/15/83 Draft NUREG/CR report          07/83                -
07/15/83 received from contractor i
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                -
1 l
CRGR review completed          02/84              07/86                -
j      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 CRGR review completed          08/84              32/86                -
EDO 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
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM O Issue Issue Action Number        Type _      Level
                                      ,    Task Office /Div/Br      Manager          TACS No.
i 36            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 -------      None Contractor Name/ FIN --    None Work Scope -----------      Revise SRP Sections 9.2.1 and 9.2.2 to incorporate concerns of interaction between safety and nonsafety-related portions  l 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.
DSI 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 ent; ACRS of Intent    02/85                -
05/13/86 to Publish.
Issue FR Notice for SRP Change      03/85                -
06/86*
O ^ 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
 
GENERIC ISSUS MANAGEMENT CONTROL SYSTEM Issue            Issue        Action                                                Task Number            Type          Level                      Office /Div/Br          Manaaer          TACS No, t
48                Safety /    Active-L1                    NRR/DSR0/EIB            D. Thatcher      55223 NR Title ----------------          LC0 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 Work Scope -----------        Review LLNL TER containing the technical finding to the above i
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 thar; its Class 1E DC bus and associated inverter.
Affected Documents ---        Plant Technical Specifications Status ---------------        RRAB has completed its review of the LLNL report and deter-mined additional work is required to complete this study.
RRAB has requested plant specific information to perform a new analysis on this issue.
Problem / Resolution ---      RRAB concluded that tiie original analysis was inadequate.
Technical Resolution -
Milestones                                            Original                Current        Actual Generic Issue 48 assigned to                            -                        -
10/15/83 DL by Director, NRR Generic issue lead responsibility                        -                        -
03/01/84 transfer from DL to DSI Request to RRAB for technical                        10/84                      -
05/01/84 assistance to review PRA done
        \        by LLNL 48-1                    As of 3rd Quarter FY-86
 
Generic Issue #48                                  !
                                                                                              )
Milestones                          Oriainal            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 l
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.
Work Scope -----------      Prepare generic letter to all licensees requesting electrical interconnection design information. Prepare contract proposrI 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.
N                                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 1E 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 Status ---------------      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 l
l
 
G:neric Issue #49 Milestor.as                        Original            Current          Actual Request CRGR review and comment    12/85*
CRGR review complete              01/86*                -                -
Generic information request to DL 02/86*                  -                -
Generic 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                -                -
l      Contract proposal evaluated        09/86                -
and accepted i
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 foi review CRGR Package to NRR Director        02/88                -                -
Review Package to CRGR              03/88                -                -
CRGR review complete                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
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM b
  \  Issue        Issue        Action                              Task Number      Type        Level          Office /Div/Br      Manager        TACS No.
51          Safety /    Active-L1      NRR/DSR0/EIB        C. Hickey      53338 Medium Title ----------------    Proposed Requirements for Improving Reliability of Open Cycle Service Water Systems Work Authorization ---    Memorandum to R. J. Mattson from H. R. Denton dated June 3.
1983.
NRR FY-84 Operating Plan, (Appendix G).
Contract Title -------    Improving Reliability of Open-Cycle Water Systems.
Contractor Name/ FIN --  PNL/B-2977.
Work 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.
Affacted Documents ---    To Be Determined Status ---------------    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 S0W 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 B2463 and are complete.
Based upon the results of this research which deals with biofouling, DSR0 will adapt, where possible, methods for surveillance and control of biofouling to fouling by mud, silt and corrosion products.
t The contractor is operating under an FY85 carryover budget of
                                $65K that will run out in May 1986. DSRO has withdrawn tach-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-l                              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 l
final contractor report is scheduled for April 30, 1987.
Coordination of this project with RES is documented in a Memorandum from R. Mattson to F. Arsenault, dated 01/23/84.
51-1                As of 3rd Quarter FY-86
 
Gensric Issue #51 Problem / Resolution ---    Due to budget contraints, RES was not be able to provide all the technical ass'istance originally planned. In particular, could not fund Task V of FIN B2463; Task V called for preparation 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 B2463 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, DSI.
Revised work plan approved and          -                    -
10/03/84        I issued                                                                                  l 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 l
l
 
Generic 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 Comment OMB 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                    -
EDO Approval                    09/88              08/88                    -
Federal Register Notice        09/88              08/88                    -
of Issuance of SRP O
i    ** If required l
51-3              As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue              Issue    Action                              Task Number          h          Level            Office /Div/Cr      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 Due to Postulated SRV Discharge Failure Contractor Name/ FIN --    BNL/A-3793 Work Scope -----------      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 DSI.                11/83                -
11/03/83 Task Action Plan approved by            01/84                -
01/11/84 Director, DSI.
Complete review of BNL-NUREG-          03/85                -
12/14/84 31940 BNL Draft keport                        02/86                -
02/25/86 Review BNL Repcrt                      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
      .                                              61-1                As of 3rd Quarter FY-86
 
Generic Issua #61 Milestones                        Oriainal            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 complete. 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 comment.
OMB Clearance (if'needed).        10/86                N/A        ,
Incoporate public comments.        11/86                N/A              -
Final issuance of NUREG.          03/87                N/A              -
Issue Generic Letter to all        03/87                N/A              -
operating BWR plants with l      Mark I and Mark II containments.
l
* Closecut memo submitted to NRR Director for approval on June 30, 1986.
l l
O 1
61-2                As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue                Issue    Action                                      Task Number                Type      Level            Office /Div/Br            Manager        TACS No.
65                    Safety / Scheduled          NRR/USR0/EIB              J. Jackson    49716 High      with GI 23 Title      ----------------    Component Cooling Water System Failures Work Authorization ---          Memorandum to R. J. Mattson from H. R. Denton dated September 8, 1983.
NRR FY-84 Operating Plan (Appendix G).
Contract Title -------          Reactor Coolant Pump Seal Integrity Centractor 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 determined. The reliability of existing and proposed seal cooling systems will be assessed to determine if additional licensing requirements are required. This work comprises Task 2 of Generic Issue 23, " Reactor Coolaat Pump Seal Failures."
Interruption of seal cooling may lead to RCP seal failure and subsequent loss of primary coolant to containment, i.e., a p
r~'s                                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 snould take, if any, to ensure increased reliability of the component cooling water system relative to its RCP seal cooling function. Test data will be reviewed to determine the time to failure of reals without seal cooling and the leak rate resulting from this type of failure. A probabilistic risk assessment will be performed l                                      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 SRP Section 9.2.2 (To Be Determined)
Revise and issue SRP Section 9.3.4 (To Be Determined)
Issue New Regulatory Guide and SRP Section (To Be Determined)
Status ---------------          A revised 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
 
Gen:ric Issua #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 inccrporate GI-65 tasks and was issued.
Issued Request for Proposal to RNL            --          --
11/02/83 for component cooling water PRA.
For milestone necessary to Resolve and complete this issue refer to Milestone for Generic Issue No. 23, Task 2 9
9 65-2              As of 3rd Quarter Fi-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue                  Issue      Action                              Task Number                h          Level            Office /Div/Br    Manager          TACS No.
66                    Safety /    Active-L1        NRR/ORAS/BWR        E. Murphy      TBP NR Title ----------------            Steam Generator Requirements (Integrated Program for Resolution of USIs A-3, A-4 and A-5 Regarding Steam Generator Tube Integrity).
Work Authorization ---            Memorandum to D. G. Eisenhut from H. R. Denton dated November 16 1983 NRR FY ' dperating 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 individuc1 utilities. The staff will identify areas where the utility program appear to fall short of the staff recommendations in Generic Letter 85-02 and will continue to encourage utilities j                                              to implement the staff's programs.
!          Problem / Resolution ---          None Technical Resolution -
Milestonet                                    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
 
G:neric Issue #66 Milestones                          Oriainal    Current        Actual Revised Cornission Paper on        07/84          -
09/07/84 proposed USI resolution (SECY 84-13A)
Comission Meeting                  02/84          -
09/10/84 (a) Issue SECY 84-13B                -            -
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 coment on NUREG-0844 (For Coment)
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        05/36              -
determination by staff of USI resolution NUREG-0844 Issue plant-specific letters      TBD              -              -
describing staff assessment of response to Generic Letter 85-02 O
66-2        As of 3rd Quarter FY-86 i
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM I*ssue'                        Issue    Action                              Task
          'I  Number                        lype      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 Crom 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 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 onISeptember 16, 1985.
Problem / Resolution ---                Issuance of contract to ORNL suspended pending discussions with RES on the incorporation of this program into ongoing PNL/RES program on steam generators. Delays in this generic issue have resulted because of RES stated needs for additional funding, possibly from NRR, to accelerate work to meet a schedule acceptable to NRR.
Technical Resolution -
Milestones                              Original        Current            Actual Generic Issue Assigned                      -                -
03/28/85 Preliminary discussions of                  -                -
04/10/85 work plan with ORNL ORNL provides preliminary                  -                -
06/28/85 outline of work plan
(                            Request for proposal submitted            09/85              -
08/20/85 j                            to ORNL l
Contract Incorporated in                  09/85              -
09/85 i
FIN Plan 67-1              As of 3rd Quarter FY-86 l -          .  - _ _ _ -
 
G:neric Issue #67.7        -
Milestones                          Original          Current        Actual Proposal Evaluated                  09/85              -
09/85 and Accepted Issue Contract                        TBD*              -                  -
to ORNL ORNL Issues Report                    TBD*              -                  -
on Recommendations for Improved Code Provisions and Action Plan ORNL Issues Report                    TBD*              -                  -
Recommending ASME Code Endorsement and/or recommendations for Regulatory Guide Er.dorsement with Exceptions Issue close-out memorandum            TBD*              -                  -
from Director NRR recommending Code Endorsernent or Endorsement with Exceptions i
e l
l t
* EIB is currently in the process of integrating this issue, and some other issues 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.
O 67-2              As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
  ; O    Issue Issue Action Number        Type _          Level Task Office /Div/Br                      Manager        TACS No.
68            Safety /        Active-L1      NRR/DSR0/RSIB                      S. Diab          55225 High Title ----------------          Loss of AFWS Oue to AFW Steam HELB Work Authorization ---        Memorandum to R.'J. Mattson from H. R. Denton dated April 24, 1984 Contract Tit'e -------        None Contractor Name/ FIN --        None Work 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 i
Issued reptioritization memo for comments                        -                                          -
05/85
.              OSI comments received                    -                                          -
05/11/85 Incorporated comments DSI comments                                -                                          -
06/85 Issue draft risk evaluation            05/85                                        -          -
l              Issue closeout memo based on results                            03/85                              06/86*              -
Issue TAP - Approval by Director, DSRO                        05/85                                  N/A          -
j Technical Resolution                  01/86                                  N/A          -
* Final close-out memorandum has not been issued by DSI.                    If reevaluation of schedule shows that close-out is not (easible by June 1986, then the remaining milestone mates l
will be revised to reflect a new resolution date.
68-1                                As of 3rd Quarter FY-86
 
Genaric Issue #68 Milestones                            Oriainal      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                12/86          N/A                                                    -
Review Package to CRGR                01/87          N/A                                                    -
CRGR review and ED0 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 EDO apprcval completed                          09/87          N/A                                                    -
Federal Register Notice of Issuance of SRP                  10/87          N/A                                                    -
O 68-2          As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue                  Issue    Action                                Task Number                Tyge_      Level              Office /Div/Br    Manaaer                TACS No.
70                    Safety /  Active-L1          NRR/DSR0/EIB      R. Kirkwood            55226 Medium Title ----------------          PORV and Block Valve Reliability Work Authorization ---          Memorandum to R. Mattson from H. R. Denton dated May 14, 1984.
Contract Title -------          Estimation of Risk Reduction from Improved PORV (GI-70)
Contractor Name/ FIN            BNL/A-3807 Work Scope -----------          Identify fundamental safety requirements of the PORVs and bloct 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 money that could be spent on PORV/ block valve improvements. Potential improve-ments with the maximum amount of money that could be spent will be identified in the 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 ir.to SRP or regulatory guide Status ---------------          Task action plan was issued on April 30, 1985. A report to the Commission on the status of staff work was issued on February 18, 1986. Recently available information with respect to radiation levels, anticipated funding, and schedule 4
changes indicate that data from disassembly of the PORV from THI-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 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 TMI-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 final version will be issued as a NUREG/CR report. Comments were also furnished on BNL draft report, " Estimation of Risk Reduction from Imnroved PORV Reliability in PWRs," dated September 1985. Upon resolution of staff comments and com-pletion of the remaining issues associated with this task, a 70-1              As of 3rd Quarter FY-86
 
f Generic Issue #70 final version of the report will be issued as a NUREG/CR repo 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 Director,          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, DSI 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 valves Report to the ;ommission 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
 
Gen:ric Issu) #70 I
l 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 coments.
Other division coments            04/86            01/87                .  -
incorporated.
CRGR Package to NRR Director      05/86            02/87                    -
for Review OMB Clearance obtained con        06/86            03/87                    -
currently if applicable Review Package to CRGR            06/86            03/87                    -
CRGR review and EDO approval      07/86            04/87                    -
completed Federal Register Notice of        08/86            05/87                    -
Issuance of SRP for Public Coment Division review of public        09/86            06/87                    -
N  coments completed Coments 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 l
O 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/QAB        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 (Operations)" to contain more detailed guidance for operational QA programs. The staff will consider backfitting this Reg. Guide revision. The work scope of the TMI Items I.B.1.1(6) and I.B.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, the 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 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 ccaments 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 O
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 completion. Pending issuance of the final guide licensee requests for the QA Branch licensing staff will review FSAR Chapter 17 revisions committing to ANS-3.2-1982 on a case-by-case basis.
Problem / Resolution ---  See Status above.
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 l
Public comments on 3rd proposed        01/85                -
Deleted Rev. 3 Re-issue draft R.G. 1.33 for          01/86                -
02/86  1 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                  -
l                                            75-2              As of 3rd Quarter FY-86    l
 
Generic Issue #75 Milestones                                      Original                Current        Actual ACRS Review completed                          12/85                  04/87                      -
EDO Approvkl                                    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                                                                                                        !
4 l
l i
I, i
l l
l l                                                                                ,
;                                                                                              75-3                    As of 3rd Quarter FY-86 l                                                                                      ..
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue              Issue    Action                                  Task Number            Tg_e_
e      Level              Office /Div/Br      Manaaer        TACS No.
77                Safety /  Active-L1          NRR/OSR0/EIB        D. Thatcher      52397 High Title ----------------      Flooding of Safety Equipment Compartments by Back-Flow Through Floor Drains Work Authorization ---      Memorandum to R. J. Mattson from H. R. Denton dated September 8, 1983.
NRR FY-84 Operating Plan, (Appendix G).
Contract Title -------      None Contractor Name/ FIN --      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 i                                                                  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.
Status ---------------      Information to conduct a re-review of previous flooding infor-mation and evaluations for nine selected representative plants is not currently available due to the reluctance of some of the selected utilities to provide the required information.
,                                                                  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 I                                                                  not voluntarily provide the requested information. Considera-tion is now being given to issuing a confirmatory order to j
            .                                                                          77-1                As of 3rd Quarter FY-86
    ., , - - - - ,---y-.ee,e..,-ye_,__                                                                                                4--,
 
Generic Issue #77 these plants to obtain the required information. The addi-tional effort required to obtain the requested information will result in approximately a 15-month delay in the resolu-tion of this issue.
Using FSAR drawings, floor and equipment drainage system draw-ings and previous reviews of flooding of safety equipment com-partments at operating plants, determine the adequacy of the previous reviews for 9 plants. Where necessary, elicit from the licensee additional information regarding the measures taken to orevent flooding of safety-related equipment compartments due to backflow through the drainage systems.
Technical Resolution -    Since the present SRP is indicated as being acceptable, this issue involves a determination that actual features in plants are adequate to assure protection against flooding of safety-related compartments through the floor and equipment drains.
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            Complate - March 1985 the adequacy of existing protection provided against backflow through drains.
: 3.      Determine the need for and efficacy of            Start - May 1985 l              various corrective measures that can be          Complete - August 1985 I              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 OSI                  09/83                  -
09/08/83 TAP Approved by Director, DSI          01/84                  -
01/10/84 Incorporate Division Comments          09/84                  -
09/09/84 l
Revise and Reissue Approval            10/84                  -
10/31/84 Work Plan Task 1-Plant Selection.                10/84                  -
11/84 0
77-2                As of 3rd Quarter FY-86
 
Generic Issue #77 Milestones                          Originai
* 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.
O        Final CRGR package to Director, NRR.
06/86              09/87*            -
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 l
Issue                                                Action (G
j l
Number Issue Type                    Level                                    Office /Div/Br Task 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 teen 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|date=October 15, 1984|text=letter dated October 15, 1984}}. This request has been transmitted to the B&W Owners Group (BWOG) by {{letter dated|date=March 27, 1986|text=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
 
Gensric Issu2 #79 Milestones                        Original            Current                                      Actual Preliminary technical evaluation  07/86              09/86                                          -
for staff review Final technical evaluation        08/86              10/86                                          -
completed Close-out memorandum issued
* 09/86              10/86                                          -
O fit is anticipated that vendor analysis will demonstrate acceptability of current designs. The milestone schedule is based on this assumption. No changes in regulatory requirements will be needed providing this assumption proves valid.
However, if new regulatory requirements are needed the Schedule will have to be expanded by 12 months.
O 79-2              As of 3rd Quarter FY-86
 
i GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue            Issue            Action                                          Task Number            h                Level                      Office /Div/Br      Manager          TACS No 82                Safety /        Active-L1                  NRR/DSR0/RSIB      E. Throm        53347 Medium Title ----------------            Beyond Design Bases Accidents in Spent Fuel Pools Work Authorization ---            Memorandum to R. J. Mattson from H. R. Denton dated December 7, 1983 t
NRR FY-84 Operating Plan, (Appendix G).
Contract Title -------            Study of Beyond Design Bases Accidents in Spent Fuel Pools (Generic Issue 82) i Contractor Name/ FIN --            BNL/A-3786 Work Scope -----------            Nork 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 consecuences and likelihood of severe spent fuel pool accident will be assessed. Should the risk from such an acci-i                                            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 temper.sture 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 tnat 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.                                                l l
Affected Documents ---            SRP Sections 9.1.2, 9.1.3 and 15.7.4.
Regulatory Guide 1.25. STS Status ---------------            Milstones for this generic issue were revised in May 1984, based upon the results of preliminary work by RES. Assessing the probability of pool failure due to earthquake.
82-1              .As of 3rd Quarter FY-86 l                                                    ..
 
G:nr.ric Issue #82 Problem / Resolution ---  Delays encountered due to need for broad-scale structural
  ,                          analysis, consideration of refueling cavity wate" 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 I
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/DSRO on 04/01/86.
Technical Resolution -
Milestones                            Original            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.
I Task Action Plan approved by          02/84                -
02/02/84 l
Director, DSI.
Receive RES Contractors'              04/84                -
05/21/84 l        assessment.
RES Contractors' assessment          05/84                -
05/05/84 sent to DL, DST, DE and OSI:
CPB and DSI:ASB for review and comment.
Complete PID for inclusion of        04/84                -
06/84 l
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 0
82-2                As of 3rd Quarter FY-86
 
Generic Issue #82 i
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 conse-
,                    quences of loss of pool integrity for the most vulnerable design.
Prepare 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 l
Task 4 - Preliminary                09/86            09/86                              -
Risk Profile Task 5 - Evaluate                  09/86            09/86                              -
Alternatives Authorize Fragility                10/96            10/86                              -
Studies Task 6 - Fragility                  05/87            05/87                              -
Studies Task 7 - Value/ Impact              06/87            06/87                              -
Evaluation Draft Regulatory Analysis          07/87            07/87                              -
Evaluate future Schedule            08/87            08/87                              -
lO j                                                        82-3              As of 3rd Quarter FY-86
    - . . - _ _ . . .-.---_l_-..---.----_.--                                --. -.- - ---_., - ...- - .-
 
l 1
GENERIC ISSUE MANAGENENT CONTROL SYSTEM Issue              Issue    Action                                                                      Task                                    !
Number            Tyge__    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 6.4, 9.4.1, 12.3, 6.5.1, 2.3, 2.2.1-2.2.3, 18, 9.5.1; RGs 1.78, 1.95, 1.29, 1.52, 1.101, 1.140; 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.
Status ---------------      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 1
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.
Problem / Resolution ---    The original TAP for GI 83 contained a number of subtasks for
;                                          implementation of the recommendations in the June 1984 Control Room Habitability Report. Work on implementation of these recommendations has been halted due to management concerns over (1) lack of resources to perform independeat 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 i                                          new plant orders, and (3) implementation recommendations that might be interpreted as backfitting without proper backfit
]                                          analysis.
i The implementation of the recommendations in the June 1984 l                                          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 4
  .~,-~- .-._  .,-_,.,_.,._,__mr        ,    - . ..- _ -__,,.- - - -._ _ _- . _ _,_ ,_., , _ ____ ._ _ __                          _
 
G0neric Issuo #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 completi*on 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 generic studies O
83-2                  As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
      \
Issue                    Issue        Action                              Task Number                    Type          Level          Office /Div/Br      Manager        TACS No.
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 stork 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.
I          Technical Resolution -                  To be provided.
Milestones                            Original            Current        Actual Schedule to be developed following the completion of USI A-45 work.
l l
l 84-1              As of 3rd Quarter FY-86 1
  . . _ . ~__,__ ..,_._ ---_.    --
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
    \
Issue                        Issue                                          Action                                            Task Number                      h                                              Level              Office /Div/Br                Manager                            TACS No.
86                          Safety /                                        Active-L1          NRR/ DBL /EB                  W. Hazelton                        07419                              )
NR Title ----------------                                                      Long Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping Work Authorization ---                                                      Memorandum to R. H. Vollmer from H. R. Denton dated October 3, 1984 Contract Title -------                                                      None Contractor Name/ FIN --                                                      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) Pursue 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 t                                                                                        changes desired by the staff have been made.
A 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.
Technical Resolution -
Milestones                                                                  Original                      Current                            Actual SECY 84-301, NUREG-1061                                                      07/84                          -
07/30/84 to Commission Publish NUREG-1061, Vol. I                                                  09/84                          -
09/20/84 End of Comment Period                                                        11/84                          -
11/7/84 Complete preparation of Draft                                                01/85                          -
09/85 NUREG-0313, Rev. 2 86-1                          As of 3rd Quarter FY-86 m_ -..- . - _ . . _ _ - . _        _ . . _ _ _ _ , _ . . . , _ _ _ _ . , , _ , _ _                  __.                      ...,__,m              # . _ _ , _ , . _ . , . _ . . . _ _ _ , _ _ _ _ _ , . _ _
 
G:neric Issue #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 coment.
Draft NUREG-0313, Rev. 2,          02/86                            09/86                                  -
revised to reflect public coments.
Comission Paper on staff            03/86                            10/86                                  -
implementation plan and staff position (NUREG-0313, Rev. 2) reviewed and endorsed by CRGR.
Comission 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 O
86-2                            As of 3rd Quarter FY-86
 
i                                GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue            Issue            Action                                    Task Number          Type _            Level          Office /Div/Br            Manaaer      TACS No.
87            Safety /High          Active-L1      NRR/DSR0/RSIB            H. Woods    60058 Title ---------------              Failure of HPCI Steam Line Without Isolation Work ----------------              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, i                                        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 j                                          Issue II.E.6.1.
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 87-1            As of 3rd Quarter FY-86
 
GENER{CISSUEMANAGEMENTCONTROLSYSTEM Issue          Issue          Action                                Task 4 ( Number          Type          Level                Office /Div/Br  Manager        TACS No 91              Safety /      Active-L1            NRR/ORAS/8WR    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 i
Contract Title -------        Assessment of Diesel Generator Operability / Reliability Contractor Name/ FIN --        PNL/B-2952, B-2963 Work Scope -----------        Resolve concerns relating to the reliability / operability of TDI diesel engines for nuclear services Affected Documents ---        Staff will issue generic SER identifying an acceotable technical resolution 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 Delaval Inc. Emergency Diesel Generators," December 1985.
O                                (2) PNL-5336, " Review of Design Review and Quality Revalidation Report for the Transamerica Delaval Diesel Generators at Shoreham Nuclear Power Station Unit 1," October 1985.
;                                  (3) PNL-5444, " Review of Design Review and Quality Revalidation
;  ,                                      Report for the Transamerica Delaval Diesel Generators at 4
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.
j    Problem / Resolution ---      None 1
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 Office /Div/Br Number      Type          Level                                        Manaaer              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-fled 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, i
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-i                                              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 Issuo #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-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    ,
1 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.
O 93-2              As of 3rd Quarter FY-86
 
G:neric Issue #93 Milestones                            Oriainal      Current          Actual Generic or plant-specific            04/86        09/86                -
.i                preventive maintenance measures, surveillance requirements and
!                corrective actions including l                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-l                  ments for PWRs in this regard
:                  for public comments                    ,
i                  Public comments incorporated.        02/87        06/87            -
OMB clearance, if needed Final CRGR package to Director,      03/87        07/87                -
                                                                                  '~
NRR
!                Review package to CRGR                04/87        07/87 CRGR review and EDO approval          05/87        08/87                -
completed.
Issue regulatory requirements        06/87        09/87                -
;                for PWRs (generic letter if required).
l i
l j                                                        93-3          As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue            Issue        Action                                                    Task
_N_ umber
_                  h            Level            Office /Div/Br                          Manager                TACS No.
94                Safety /    Active-L1        NRR/DSR0/RSIB                            E. Throm              59465 High Title ----------------          Additional Low Temperature Overpressure Protection For                                                      ,
Light Water Reactors i
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 i
Status ---------------          The TAP and RFP have been drafted.
Problem / Resolution ---        T/A funds deleted from budget. Work scope, resources, schedule need to be reassessed.
l                                      Technical Resolution -
Milestones                            Original                                  Current                Actual i
j                                                Generic Issue #94 assigned                  -                                      -
7/23/85 i                                                to RSB/DSI/NRR
'l 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                      -
i                                                analyses for Generic Issue #99 Draft report completed                04/86                                      TBD                      -
CRGR package prepared                  05/86                                      T80                      -
i l
l                                                                                                                                                                                    l l                                                                                        94-1                                      As of 3rd Quarter FY-86.
l
 
G:nsric Issue #94 t
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)
O O
94-2      As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
,          Issue                  Issue -      Action                                          Task I    )    Nu'her                Typ_e          Level            Office /Div/Br                Manager                              TACS No.
J
.          99                    Safety /      Active-L1        NRR/DSR0/RSIB                A. Spano                            59653 High Title ----------------              RCS/RHR Suction Line Interlocks on PWRs                                                        j l          Work Authorization ---              Memorandum to R. Bernero from H. Denton dated j                                                August 13, 1985.
Contract Title -------              RHR System Operability and Interlocks Contractor Name/ FIN --              None i
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 i                                                residual heat removal. The autoclosure feature on these                                        !
!                                                valves was designed to provide the double, high pressure l                                                boundary that is needed for the RCS to conform to GDC 14 l                                                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-i                                                out increasing the risk of failure of the RCS boundary.
Technical Resolution--              PRAs will be performed for the following:
l                                                (1) The present autoclosure interlock system.
(2) The present autoclosure system with various i
modifications to the administrative controls.
I                                                (3) Removal of the autoclosure interlocks.
l                                              (4) Installation of RHR pump low-suction trip devices.                                          ,
i                                              (5) A rewiring of the control switches so that                                                  t pressing a single switch closes both of the two in-series motor-operated valves.
(6) Various combinations of the preceding items.
The effects of making these modifications will be compared.
An optimum modification will be selected and a cost-benefit analysis performed.
Affected Documents ---              None i          Status ---------------              (See Milestones)
{          Problem Resolution ---              A contract will be negotiated to provide PRAs for various alternatives to the present autoclosure interlocks between i                                              the RHR and RCS systems. The results of these PRAs will l                                              be used to find the best method for reducing RHR system l                                              failures without increasing the risk due to an intersystem j                                              LOCA. Initiation of work on this issue has been delayed
!                                              due to the transfer of review responsibilities resulting from the NRR reorganization.
4 99-1                        As of 3rd Quarter FY-86 i                                                                                                                                                l 1
L.____-.._                                                                            _ . _ , . _                    . . _ _ _ . , .          .
 
Generic Issua #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 8NL Draft BNL work plan                03/86          -
05/86 Final BNL work plan approved      04/86          -
05/86 Issue contract to BNL              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.                                                        I Regulatory requirements            09/86      09/86                  -
development Prepare initial phase of            09/86      09/86                  -
Regulatory Analysis (Statement of Problem, Proposed t.icensee Actions and Alternatives).
Final report from BNL              02/87      04/87                  -
Final report prepared, CRGR        04/87      06/87                  -
package approved by Director, DSRO, 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                  -
O 99-2            As of 3rd Quarter FY-86
 
                                  -                                    .          -        _--          . _ _ - - = _ - - -              .  - _ - _ .                -.                      _  _- -.
4 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
'                                                                  Issue            Issue          Action                                              Task Number        h                Level                      Office /Div/Br          Manaaer                                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 i
Work Scope -----------          Perform a detailed survey of all BWR plants to determine types of water level instrumentation. Compile failure j                                                                                                  data of instrument piping leaks / break and instrument
  .                                                                                                failures for all BWR plants from LERs. Perform simplified l                                                                                                  risk analyses postulating instrument piping leaks, single failure in instruments and feed water control system l                                                                                                  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 l                                                                            -
,                                                                  Status --------------'-        INEL proposal for technical assistance on this project was
!                                                                                                  accepted on 11/29/85 and work began en March 1, 1986.
:                                                                  Problem / Resolution ---        INEL is in the process of evaluating plant-specific dr.ta.
1                                                                                                  The contractor's report will not be completed until March 1987, i
Technical Resolbtion -
Milestones                                            Original                Current                                Actual l                                                                        Generic Issue 101 assigned to                                -                  -
05/06/85 i                                                                        RSB/DSI/NRR Preliminary Discussion of our                                -                  -
05/24/85 work plan with INEL i
INEL will provide preliminary                        06/85                      -
06/11/85 1
cost estimate of work plan
  ;                                                                      Develop work plan and contract                        06/85                      -
07/26/85 j                                                                        proposal 1
Draft work plant to Director,                          06/85                      -
08/01/85 i                                                                        DSI i
)                                                                        Incorporate Comments to work                          09/85                      -
10/15/85 j                                                                        plan l                                                                                                        .                      101-1                  As of 3rd Quarter FY-86 4
                                                                                                      , , , _ ,              _____,._w-,                  _,,.----,---,,,-,,,,,n-,..,-.-,-.-,-
 
GCneric 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                        08/86      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)
O 101-2    As of 3rd Quarter FY-86
 
i'                                                                                                                                                  i GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
,                      Issue          Issue        Action                              Task Number          h            Level            Office /Div/Br    Manager                              TACS No.
103            Safety /  Active-L1-          NRR/DSR0/EIB      L. Heller                            TBP NR
;i 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.                                      ,
4 Develop recoerendations regarding backfit application of                                      *
;                                                  the most recent PMP determinations. Obtain necessary j                                                  review and approvals, then publish Revision 3 of SRP
,                                                    Sections 2.4.2 and 2.4.3.
l 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 -
Milestones                                Original          Current                              Actual Identification of Potential                  -                -
05/08/84
)                            Generic Requirement Concerning Design for PMP/ Memorandum V. Stello to H. R. Denton i
i                            Prepare draft revisions of                  -                -
07/85 j                            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 l
Divisions i                            DST comments on CRGR package                -                -
09/13/85 I
i 103-1    ,        As of 3rd Quarter FY-86 i
 
G:n:ric Issu] #103 Milestones                          Original  Current          Actual Revised CRGR package based on            -        -
10/85 coments                                -
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 coment.
CRGR package revised incorpo        04/86    02/87              -
rating public coment 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 l
l l
l l
O 103-2    As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue                                              Issue      Action O
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.
t Contractor Name/ FIN -- BNL/A-3829a Work 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 Status ---------------                                          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 t
PRA and an analysis of 3 PWRs, in addition to 3 BWRs.
The schedule has been extended to recognize the time that y ,j l                                                                                  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 j                                              Generic Issue 105 assigned to                              -                  -
06/11/85 RSB/DSI/NRR Preliminary Discussion of our                              -                  -
06/17/85 work plan with BNL
!                                              8NLs preliminary cost estimate                        09/85                    -
08/85 of work plan Develop work plan and contract                        09/85                    -
08/85 l                                              proposal i
Draft work plan to Directors,                        09/85                    -
08/21/85 OSI, DE, DL, DHFS, and AE00 l
Incorporate Comments into                            10/85                    -
10/85 work plan l
i 105-1                    As of 3rd Quarter FY-86 l
i
{
 
f                                                      Generic Issue #105 Milestones                                      ,
                                                                'Jriginal  Current        Actual Final work plan approved by                                  10/85      -
11/18/85 Director, DSI and forwarded to DST Issue contract to BNL                                        10/85      -
12/02/85 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 Lei.ter to Licensees or SRP Changes, etc.)
O 105-2    As of 3rd Quarter FY-86
 
l GENERIC ISSUE MANAGEMENT CONTROL SYSTEM O            Issue Number Issue Tyge_
Action Level              Office /Div/Br Task Manager            TACS No.
119.1            Regulatory Active-L1                          RES/DET/MSEB        J. A. O'Brien      None 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 i
  ,              Work Scope -----------                      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 section has been prepared by RES and approved by NRR.
!                Problem / Resolution ---                    Work on SRP Section 3.9.3 was suspended.            Revising SRP Section i
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 tn revise GOC-2 be initiated in parallel.
Milestones                                              Original            Current            Actual Revise GOC-4
!                      EDO Approval to Begin Rulemaking                              -                -
12/84 i                      Federal Register Notice of                                    -                -
07/85                ,
;                      Proposed Limited Scope Rule l
Federal Register Notice of                              04/86                07/86                  -
Proposed Broad Scepe Rule i
Federal Register Notice of Final Limited Scope Rule                                04/86                  -
04/86 Federal Register Notice of                              02/87                02/87                  -
1                      Final Broad Scope Rule l
    \
119-1                As of 3rd Quarter FY-86 I. _____ _ _ _. _ _ - _ _.__ __. _ _.      . _ _ _ . , _ . _
 
Gen:ric Issue #119.1 Milestones                            Original              Current          Actual Revise SRP 3.6.2 Piping Review Comittee final                      -            -
05/85 report containing recomendations 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              -
corplete Coments resolved, CRGR                07/86                  07/86              -
package to NRR Office Director for review NRR 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            -
E00 approval                          01/87                  01/87            -
Federal Register Notice              01/87                  01/87            -
issued for public coment Public coments resolved,              05/87                  05/87            -
final CRGR package to Division Directors for review l
Division Directors review            06/87                  06/87            -
complete Coments resolved, final CRGR          07/87                  07/87            -
package to NRR Office Director for review l
NRR Office Director review            08/87                  08/87            -
complete package sent to CRGR CRGR review complete, package        10/87                10/87              -
sent to ACRS l
O 119-2                As of 3rd Quarter FY-86
 
t
!                                                                                          Generic Istus #119.1 i
Milestones                                                                      pricinal                      Current        Actual I
;                          ACRS review complete                                                            12/87                        12/87              -
EDO approval                                                                    12/87                        12/87              -
l                          Federal Register Notice of                                                      01/88                        01/88              -
)                            Issuance of SRP 1
\                                                                                                                                                                  l i
t 4
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t                                                                                                                                                                  .
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119-3                        As of 3rd Quarter FY-86 1
 
G3neric Issua #119.1 O
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1 O
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O 119-4                  As of 3rd Quarter FY-86 l
l
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM v                                                                                                          ,
Issue          Issue                Action                              Task Number        h                    Level            Office /Div/Br    Manager          TACS No.
119.2          Regulatory 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 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 experiments to obtain pipe damping values.
I
: 2. Provide basis for pipe damping criteria used in i
4                                      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          Actual 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 l
119-5              As of 3rd Quarter FY-86
 
Genaric Issus #119.2 0
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I O
O 119-6              As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM O'                                                                    .
Issue                      Issue                        Action                                  Task Number                      Tyge_                        Level              Office /Div/Br      Manaaer                      TACS No.
119.3                      Regulatory Active-L1                            RES/DRPES/ESB        A. Murphy                    None Impact /NR Title ----------------                                  Decoupling OBE from SSE Work Authorization ---                                  Memorandum to R. Minogue from H. Denton dated September 10, 1985 j                  Contract Title -------                                  To Be Determined Contractor Name/ FIN --                                  To Be Determined Work Scope -----------                                  To Be Provided Later 4
Affected Documents ---                                  10 CFR 100, Appendix A, a list of other documents to be provided later i
Status ---------------                                  Rulemaking to start in 1988.
Problem / Resolution ---                                None Technical Resolution -
Milestones To be provided later.
1 i
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1 119-7            As of 3rd Quarter FY-86
 
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O 119-8            As of 3rd Quarter FY-86
__]
 
    /'''\                          GENERIC ISSUE MANAGEMENT CONTROL SYSTEM U
Issue          Issue      Action                                Task Number        Tyge_      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 mitigato 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 i
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 Review                        01/86                    -
01/86 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 4
CRGR Review                          09/86                  11/86              -
Commission Paper for Approval        12/86                  02/87            -
  \
119-9                As of 3rd Quarter FY-86
 
l                                            Gen:ric Issue #119.4 Milestones                                            Original _                      Current          Actual i          Generic Letter issued                                04/87                            02/87 Revise Regulatory Guide 1.44 Rescind Regulatory Guide 1.44                        12/87                            10/87                -
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I O
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        ,                                                      119-10                          As of 3rd Quarter FY-86
 
CN                                                                            GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue                            issue                              Action                              Task Number                          h                                  Level            Office /Div/Br      Manager        TACS No.
119.5                            Regulatory Active-L1                                RES/DET/MEBR        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/0-1658 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."
Status ---------------                                              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.
Milestones                                                                  Original            Current        Actual Revise NUREG-0313 4
                                                                                                      ~._
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 Review                                                                01/86                  -
01/86 CRGR Review                                                                  03/86                  -
04/86 Issued for Public Comment                                                  04/86                  -
06/86 l                                                                                                      119-11              As of 3rd Quarter FY-86
 
Generic Issue #119.5 Milestones                          Oriainal      Current        Actual Revision of Draft to Reflect        07/86          09/86            -
Public Coments CRGR Review                        09/86          11/85            -
Comission 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            -
O O
119-12      As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue          Issue        Action                                                        Task Number        Tyge        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 i    Work Scope -----------      Establish a technical position on the need for hydrogen control for LWRs with large, dry containments and make recommendations to the Commission regarding rulemaking.
Affected Documents ---      Possible new amendments to 10 CFR Part 50.44 Status ---------------      At the Commission meeting on December 10, 1984 and in SECY-83-3578, the staff indicated that recommendations for rulemaking related to LWRs with large, dry containments would be provided at the conclusion of ongoing research in mid-1986. Work has been proceeding and staff meetings t
g                            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 2                                Commission during the mid-1986 time period.
Problem / Resolution ---
Technical Resolution -
;          Milestones                                                          Oriainal        Current                  Actual Research Complete                                                  06/86                -                      -
Transmit Recommendations                                            08/86                -                      -
Issue Closecut Memorandum                                          09/86                -                      -
to NRR or Provide Milestone Necessary to Implement Recommendations v
121-1                    As of 3rd Quarter FY-86 i
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
+
Issue        Issue        Action                            Task Number        Tyge          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 A
i Status ---------------      See GI-124
!        Problem / Resolution ---    See GI-124 Technical Resolution -      See GI-124
* Milestones                          Original            Current          Actual i
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122-2          As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue                Issue              Action                                                                    Task Number              TEEe                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 Work Authorization ---                  Memorandum for T. Spets 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
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                        .                                                                                                          122-3      As of 3rd Quarter FY-86
    - . _ - -            , , , _ _ _  ,y_,. --.-.. cv  -
 
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122-4        As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL
* SYbEM Issue        Issue        Action                            Task Number      h            Level          Office /Div/Br    Manager          TACS No.
122.1.c      Safety /    Active-L1      NRR/DSR0/RSIB      S. 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 _
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w 122-5          As of 3rd Quarter FY-86
 
i i
I GENERIC ISSUE MANAGEMENT CONTROL SYSTEM                        I O
V Issue Number Issue M
Action Level          Office /Div/Br Task 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, 1985 Contract Title ------      None Contractor Name/ FIN --    None 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 licensees 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 O                            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),
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) Ft. 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 Status --------------      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              -
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                                                                                  )
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l 124-2      As of 3rd Quarter FY-86 l
 
GENERIC ISSUE MANAGEMENT' CONTROL SYSTEM m
Issue                Issue        Action                            Task Number              Type        Level          Office /Div/Br      Manager          TACS No.
A-3,4,5                USI        Active        NRR/ORAS/BWR        E. Murphy Title ----------------            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 Status ---------------            To be provided Problem / Resolution ---          To be provided Technical Resolution -            To be provided Milestones                          Original            Current        Actual Draft Technical Resolution O.              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 l                  Final Technical Resolution Commissicn Paper Approved by        02/86                -
02/21/86 Director, NRR (Evaluation of Responses to GL 85-02) s A3-1                As of 3rd Quarter FY-86
 
i Generic Issue #A-3,4,5 i
Milestones                      Original      Current        Actual EDO Returned Comission          03/86          -
03/07/86 Paper with Coments Comission Paper to EDO          03/86          -
03/24/86 EDO Approval                    04/86          -
03/24/86 Issue Final Resolution          04/86        07/86              -
(NUREG-0844) l O.
O A3-2          As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM 1
Issue        Issue        Action                                Task Number      M            j.evel          Office /Div/Br        Manaaer        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/8-0789 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 (SAN 080-0884), 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-3533, " 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 Laooratory, July 1984.
(7) NUREG/CR-3922, " Survey and Evaluation of System Interac-tion Events and Sources," Oak 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 will be available in the NRC Public Document Room, 1717 H Street, N.W., Washington, D.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-86
 
l Generic Issua #A-17 l
(10) NUREG/CR-4261, " Assessment of System Interaction Experi-l ence in Nuclear Power Plants," Dak 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.
l Status ---------------        Meeting were held with CRGR in April 1986 and with the ACRS in June 1986 to review the draft of the proposed resolu-l                                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 l                              proposed resolution and in a {{letter dated|date=May 13, 1986|text=May 13, 1986 letter}} to the EDO outlined rather broader concerns.
The staff is in the process of addressing the ACRS letter.
l                                Because of the nature of the ACRS concerns, it is expected l                                that rajor changes will be required to satisfy their l                                concerns, f Problem / Resolution ---      The ACRS {{letter dated|date=May 13, 1986|text=May 13, 1986 letter}} outlined a number of broad concerns. The staff is making some major program changes l                                to attempt to address the ACRS concerns.
Technical Resolution -
Milestones                                Original                    Current          Actual Draft Technical Resolution Issue by DSRO for Staff                    03/30/85                      -
08/14/85 Comment Staff Comments to DSRO                    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*                        -                -
* Schedule being reassessed due to major program changes in response to ACRS.
A17-2                      As of 3rd Quarter FY-86
 
GIneric Issue #A-17 Milestones                          Original            Current        Actual Final Technical Resolution Submit for Staff Review            08/86*                  -              -
Final Package to NRR                09/86*                  -              -
Director Package to CRGR                    10/86*                  -              -
Issue Final Resolution              12/86*                  -              -
* Schedule being reassessed due to major program changes in response to ACRS.
i A17-3                As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SVSTEM                          l l
O l
Issue          Issue      Action                              Task
    , Number        Type,_      Level          Office /Div/Br    Manager          TACS No.
A-29          Safety /  Active-L1        NRR/DSR0/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 time.
Technical Resolution -
Milestones                          Original          Current          Actual TAP issued for comment                -                  -
08/26/83 Final TAP Issued                    01/84                -
01/14/84 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 O
A-29-1                As of 3rd Quarter FY-86
 
Generic Issue #A-29 Milestones                                              Original      Current        Actual Task 1 - Refinement cf Previous                            10/86      10/86              -
Sabotage Models, Data bases and Estimates
* i 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)
O
                                                                                                        ~
* These tasks are work identified by PNL under FIN B-2995 (189a dated May 1986).
Finding as yet uncommitted.
                                                                        .                                    O A-29-2          As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
      \ Issue        Issue      Action                              Task N  Number      Ty2e.      Level            Office /Div/Br      Manager            TACS No.
A-30        Safety /    Active-L1        NRR/DSR0/EIB        D. Thatcher        04587 High                                                                20470 Title ----------------  Adequacy of Safety-Related DC Power Supplies Work Authorization ---  NRR FY-84 Operating Plan (Appendix G)
Contract Title -------  None Contractor Name/ FIN --  None Work Scope -----------  The staff's initial study of the adequacy of DC power supplies was documented in NUREG-0305, " Technical Report on DC Power Supplies in Nuclear Power Plants," (July 1977). This study recommended the performance of a quantitative reliability assessment. This assessment was performed and documented in NUREG-0666, "A Probabilistic Safety Analysis of DC Power Supply Requirements for Nuclear Power Plants," (April 1981). With the aid of a technical assistance contract, the NUREG-0666 recom-mendations were being converted into proposed requirements.
Affected Documents ---  Issue Information Notice (3  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 the A-30 package to CRGR. It was anticipated that this new work would take approximately four months to complete. A revised schedule was approved by the Director, DSI.
As a result of a meeting between INPO, the Director, DSI, and the AD/ CPS on 12/14/83, NRC agreed to review current INPO efforts regarding DC power supply systems to determine the acceptability of this guidance to licensees in lieu of issuing separate A-30 requirements. NRC review resulted in determining l                              that INPO guidance was not sufficient and that the A-30 CRGR package would go forward.
I                                CRGR package sent to Director, NRR on 01/31/84. However, l                                additional modifications were requested. Director, NRR approval obtained on 03/08/84. As a result of this change, all follow-on milestones were changed by one month.
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 l
A30-1              As of 3rd Quarter FY-86
 
Generic Issue #A-30 RRBR of RES, GIB of DST, and PSB. Because of key personnel turnover, RRBR was unable to complete this work as scheduled.
Also, a peer review of the cost / benefit analysis was added to ensure that it was consistent with NRC guidelines. The peer l                                          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 l
when the final revised cost / benefit package is received from RES.
,      Problem / Resolution ---          RRBR has not delivered 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. Package sent to DST and DL.
DST and DL comments incorporated. 05/83                        -
08/12/83 Package sent to Director, clRR.
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 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 l                    completion date A30-2          As of 3rd Quarter FY-86
 
Gen 2ric Issu2 #A-30 Milestones                                      Oriainal            Current          Actual, ACRS review complete                            07/83                  -
NA EDO approval                                    09/83                  -
NA FR Notice issued for public                    09/83                  -
NA comment on proposed SRP Change OMB 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 EDO approval.                                  03/84                  -
NA FR Notice of issuance of SRP                    04/84                  -
NA change.
Second CRGR pkg cost / benefit                    -
12/85***          -
revisions complete (RRBR)
NRR Divisions review complete                    -
TBD***            -
  ,                    Director NRR review complete                      -
TBD***            -
I Second package sent to CRGR                      -
TBO***            -
Issue Information Notice to                      -
TBD***            -
licensees 1                      Second CRGR review complete                      -
TBD***            -
N "By Memorandum for T. Speis 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.
O l
A30-3                As of 3rd Quarter FY-86
 
___ __                    . _ _                            __                        _.          _ ~ . _      _      _ _ _ _ _ _ _ _ _ _ __. _ _ _ .                                    _ _ _ _
i A
.                                                                                                              GENERIC ISSUE MANAGEMENT CONTROL SYSTEM I
Issue                                  Issue                                        Action                                                                Task Number                                Type                                          Level          Office /Div/Br                                        Manaaer        TACS No.
A-40                                  USI                                          Active        NRR/DSR0/EIB                                          K. Shaukat    20334 Title ----------------                                                      Seismic Design Criteria Work Authorization ---                                                        Comission designation of seismic design criteria as a USI.                                                    1 Contract Title -------                                                      Value/ Impact Assessment for Seismic Design Criteria Contractor Name/ FIN --                                                      LLNL/A-0441 Work 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, dRecommend-ed Revisions to Nuclear Regulatory Commission Seismic Design Criteria." This report was prepared by LLNL for the NRC.
i                                                                                                            Reference to technical reports documenting completion of A-40 4
tasks and other pertinent technical work is included in NUREG/CR-1161.      In developing the specific recommendations, the LLNL staff and their team of expert consultants considered i
d11 available and appropriate technical literature in addition i                                                                                                              to the results of USI A-40 tasks. In some cases, recommenda-tions were developed by consensus of expert opinion and stemmed from unpublished 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                                                  i j                                                                                                              already been incorporated into the SRP in a general revision in i
1981.
!                                                                                                              A value/ impact analysis has been completed for the assessment of the safety impact of implementing the SRP changes proposed i                                                                                                              as a result of the technical findings (NUREG/CR-3480). The i                                                                                                              supporting documents required for review by the CRGR have been prepared and include altertiatives 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 l                                                                                                              objectives of this planned SSI workshop are to review the al-ternatives suggested by the staff on SSI and related licensing concerns jointly Dy regulators, practitioners, researchers,
!                                                                                                              utilities and other interested groups, and to discuss sugges-1                                                                                                              tions to improve the licensing criteria on SSI. The outcome of i
f A40-1                                                      As of 3rd Quarter FY-86 4
_ _ . . _ . . . -          __ ,,m,__ . _ . ,      . . . . _ _ _ , , . - - . - - _ _ . . , _ _ _ - _ _ .      .
 
Generic 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 (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.
Affected Documents ---    The following technical reports have been published:
(1) NUREG/CR-1161, " Recommend Revisions to Nuclear Regulatory Commission Seismic Design Criteria," May,1980.                1 (2) NUREG/CR-1717, " Soil-Structure Interaction Methods SIM        !
Code," September 1979.
(3) NUREG/CR-4182, " Verification of Soil-Structure Interaction Methods," May 1985.
l                            (4) NUREG/CR-4329, " Reliability Evaluation of Containments Including Soil-Structure Interaction," December 1985.
l (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.
i l                            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 revise to include the modified SRP requirements with suggested op-tions and acceptance criteria for SSI analysis. A workshop cn 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 l                            published as a NUREG/CR by BNL. The staff is currently l                            working to finalize the CRGR package based on the outcome of l                            the SSI workshop.                                                  '
Problem / Resolution ---  None Technical Resolution -
Milestones                            Original            Current        Actual Draft Technical Resolution Issued by DST for Staff Comment        09/16/83              -
03/16/83 Staff Comments to DST                  10/20/83              -
10/20/83 l
l 9
l                                                A40-2                As of 3rd Quarter FY-86
 
Generic Issun #A-40 0            Milestones                        Original        Current        Actual Ccmpleted 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            -
Issue for Public Comment          11/86            11/86            -
Final Technical Resolution End of Public Comment Period      02/87            07/87            -
Issued by DSR0 for Staff          04/87            04/87            -
s        Comment Staff Comments to DSR0            05/87            05/87            -
Completed Package to Director,    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            -
                                                                                        ~...
1Q l                                                    A40-3            As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue            Issue              Action                            Task Number          M                    Level        Office /Div/Br      Manager        TACS No.
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 power plants.
(2) Estimating the reliability and evaluating the dominant factors affecting the reliability of onsite emergency AC power supplies.
s                                  (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.
(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," Draft, May 1985.
(6) NUREG-1109, " Regulatory Analysis for the Resolution of Unresolved Safety Issue A-44, Station Blackout," Draft, January 1986.
O A44-1                  As of 3rd Quarter FY-86
 
                      ..  ._        ..        .              .    .= -. _ . _ _ _ _        --            ._ _ _ _ .
Generic Issue #A-44 Milestones
* Original                  Current              Actual O        Proposed Dule to Commission            02/85                          -
05/06/85 Evaluation of NUGSB0 Proposal            -                          -
09/04/85 Co.amission 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 DSR0                    -
12/86                  -
Completed Package to Director,        04/86                  01/87                  -
Package to CRGR                        05/36                  03/87                  -
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*            ,
l
* Schedule is being revised to reflect the ED0's proposal for issuing a final rule in 1987.
A44-3                          As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue                          Issue        Action                                                          Task Number                        Ty[Le        Level                Office /Div/Br                              Manager          TACS Nc.
A-45                            USI          Active-L1            NRR/DSR0/RSIB                              A. Marchese      43516 Title ----------------                      Shutdown Decay Heat Removal Requirements 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, i                                                                              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 -
i Milestones                        Original                                    Current                  Actual
.i                                                        Final Value/ Impact                07/85                                          -
08/23/85 i
Report for Quad Cities i
I l                                                          Final Value/ Impact                10/85                                          -
11/15/85 j                                                          Report for Point Beach Draft Value/ Impact                11/85                                          -
12/16/85 Report for Cooper Draft Value/ Impact                11/85                                          -
02/28/85 4                                                          Report for Turkey Point                                                                                                      ,
l                                                        Draft Value/ Impact                  01/86                                    On Hold                        -
Report for Trojan l
l Draft Value/ Impact                  04/86                                        06/86                        -
Report for St. Lucie A45-1                                As of 3rd Quarter FY-86 l
 
D Generic Issue #A-45 Milestones                Original            Current            Actual Draft Value/ Impact        05/86              07/86                -
Report for ANO-1 Contractor Draft Summary  06/86              07/86                -
Report of All Plants DSR0 Oraft Regulatory      08/86              08/86                -
Analysis and Technical Finding Report Issued for Staff Comments Staff Comments to DSR0    09/86              09/86                -
Completed Resolution      10/86              10/86                -
l Dackage to Director, liRR l 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 l
l l
l I
I O
A45-2              As of 3rd Quarter FY-86 l
l
 
l l
l                                                .
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
(                Issue                    Issue              Action                                          Task
;                Number                    Type                Level                  Office /Div/Br          Manager          TACS No.
A-46                        USI                            Active          NRR/OSR0/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 q                                                              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.
Affected 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 Ruggedness of Certain Classes of Equipment in Nuclear Power Plants, SSRAP Report, January 1985.
(6) NUREG-1030, Seismic Qualification of Equipment in Operat-ing Nuclear Pcwer Plants, USI A-46, August 1986.
(7) NUREG-1211, Regulatory Analysis for Proposed Resolution of USI A-46, August 1986.
1                                                                                      A46-1                  As of 3rd Quarter FY-86
 
Generic Issue #A-46 Status --------------    Public comments 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 ACRS 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 hours. 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 DSR0 for Staff            02/15/84              -
03/06/84 Comment Staff Comments 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              05/15/84              -
12/03/84 DSR0 Revised Draft                02/28/85              -
02/28/85 Complete Staff Comments on Revised          03/08/85              -
04/08/85 Oraft to DSRO 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 Comment          06/15/85              -
09/12/85 A46-2                As of 3rd Quarter FY-86
 
G;neric Issue #A-46 Milestones                    Original        Current          Actual Final Technical Resolution Available for staff            05/86            -
06/86 coments Staff coments to DSR0          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 f
O l
l O
A46-3          As of 3rd Quarter FY-86
 
i l                              GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue        Issue      Action                          Task Number      Tyge        Level          Office /Div/Br  Manager            TACS No.
i 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/B-0467, B-0816 j                            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 ar.alysis; (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.
Affected 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 4
Water Reactor," Voi2Nes 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.
A47-1                As of 3rd Quarter FY-86                          ,
i
 
Generic Issue #A-47 (4) NUREG/CR-3991, " Failure Modes and Effects Analysis (FMEA    '
of the ICS/NNI Electric Power Distribution Circuitry at    i 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      l Nuclear Plant," July 1984.                                  l (6) NUREG/CR-4449, "A PWR Hybrid Computer Model for Assessing    l the Safety Implications of Control Systems," March 1986.
(7) NUREG/CR-4265, "An Assessment of Safety Implications of      J Control at the Calvert Cliffs 1 Nuclear Plant," Volume 1,,
April 1986.
(8) NUREG/CR-4387, " Effects of Control System Failure on Tran-sient, Accident and Core-Melt Frequencies at a General Electric Boiling Water Reactor," Dec. ember 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 Pre.ssurized 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 8&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                            Original              Current      Actual Draft Technical Resolution l      Issue by DSP0 for Staff                  09/86              09/86          -
l      Comment l
l      Staff Comments to DSRO                  10/86              10/86          -
Completed Package to Director,          11/86              11/86          -
NRR l
A47-2                As of 3rd Quarter FY-86 l              -
 
Generic Issue #A-47 O'                        Milestones                                      Original                      Current          Actual Packcge 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 Resolution End of Public Comment Period                      05/87                        05/87              -
Issued by DSR0 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              -
O A47-3                          As of 3rd Quarter FY-86
  ..-------n.        - , , - .    ,            . _ . . --, . _ . . -. -              -        - - - -              , , , . _- ,        -- a
 
4 GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue          Issue            Action                              Task Number        M                Level          Office /Div/Br      Manager                        TACS No.
A-48          USI              Active          NRR/DSR0/EIB        C. Ferrell                      43519 Title ---------------      Hydrogen Control Measures and Effects of Hydrogen Burns on Safety Equipment Work Authorization --      Commission Designation of Hydrogen Contrcl 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 Work 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 l                                (fire damage), combustion, and related disciplines.
The evaluation will include the following:
: 1. Scale-up
: a. Evaluate experimental data from various test fa-I                                            cilities (FITS, VEGES, NTS) with respect to the following questions: (1) how typical are the combustion mechanisms in small enclosures as com-l                                            pared with full-size containments? (ii) how well j                                            can they be scaled to full-size containments?                          3
: 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 areas have been properly covered.
l                                3. Detonation I                                      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 Generic Issue #A-48                                                  '
concentrated on deflagration, in view of the difficulty of detonation work and the low probability ascribe:.1 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.
l                              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 eteam-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-I                                    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?
l Affected 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.
O A48-2                            As of 3rd Quarter FY-86
 
I-Generic 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
,                      Camplete Sequoyah Licensing          09/86                -              --
Leview for Hydrogen Control 1                      Complete Grand Gulf Licensing        03/87                -              --
Review for Hydrogen Control                                          .
National Research Council            07/86                07/86          --
Hydrogen Report on Findings Recomendations Issue Generic Sumary Report Issued by DSR0 for Staff Comment      06/87                06/87          --
Staff Comments to DSRO                07/87                07/67          --
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          --
s A48-3              As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM O                    Issue                            Issue                                          Action                                                                                          Task Number                          Type                                            Level                                      Office /Div/Br                                      Manager        TACS No.
A-49                            USI                                            Active-L1                                  NRR/DSR0/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 ISECY-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 circulated in NRR and will be
!                                                                                            circulated in RES soon. Public comments are now included in this package.
Problem / Resolution ---                                      None i                            Technical Resolution -                                        None Milestones                                                                                  Original                                                      Current        Actual
{                                                  Schedule for Final Rulemaking 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 Implementatior                                                                      06/85                                                          -
07/23/85 i
i A49-1                                                          As of 3rd Quarter FY-86 4
 
Generic Issue #A-49 Milestones                          Original    Current        Actual O
Schedule for Regulatory Guide Issue by DST for Staff Comment      02/86          -              -
Staff Comments to DST                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            -
l i
l O
A49-2        As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM 4
Issue          Issue      Action                              Task Number        Type _,    Level            Office /Div/Br      Manager          TACS No.
B-5            Safety /    Active-L1        NRR/DSR0/EIB        L. Heller      07419 Medium Title ----------------    Buckling Behavior of Steel Containments Work Authorization ---    NRR FY-84 Operating Plan, (Appendix G)
Contract Title -------    None Contractor Name/ FIN --    None Work Scope -----------    A containment structure is an asymmetrical shell due to large penetrations. The current staff position allows use of a symmetrical shell model for buckling strength evaluation. To compensate for the uncertainty in this symplifying assumption, i
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.
l
!                                          Affected 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 I                                                                    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 -
Milestones                            Oriainal            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              -
DSRO for processing.
B5-1                As of 3rd Quarter FY-86
 
G:neric Issue #8-5 Milestones                          Oriainal    Curr*ent
* 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.
OM8 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 approval.                      08/86        05/88              -
Federal Register Notice of          09/86        06/88              -
Issuance of SRP O
O 85-2        As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM t
Issue          Issue                      Action                                          Task Number        Type                        Level            Office /Div/Br                Manaaer        TACS No.
B-6            Safety /                    Active-L1        NRR/DSRO/EIB                  J. Page'        20179 High Title ----------------                    Loads, Load Combinations, Stress Limits Work Authorization ---                    NRR FY-84 Operating Plan (Appendix G)
Contract Title -------                    None Cor. tractor 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 i
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 10 12/ year for the large LOCA and 4 x 10 12/ 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.
Preliminary indications are that pipe rupture probabilities in GE reactor coolant loops are substantially greater than in any i                                                  of the PWR vendors.      In addition, a separate CRGR package on a i
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 I
 
Generic Issuo #B-6 for BWRs will be made by RES at the conclusion of the research
                  .        study on GE plants. If this recommendation indicates that decoupling on certain classes of BWRs should be permitted by the SRP, the milestone schedule will have to be revised. The Piping Review Committee recommendations have been categcrized as Generic Issue 119.                                        c The Task Manager is preparing a memorandum recommending that Generic Issue B-6 be subsumed by Generic Issue 119.
Therefore, future tracking of this issue will be under Issue 119 along with other related piping issues.
Technidal 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.
l ACRS subcommittee on leak-before-                                          03/29/83 break and decoupling.
ACRS full Committee meeting          05/83                  -
06/09/83 Piping Review Committee to            02/85                  -
02/85 provide recommendation for decoupling.
l    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.
O B6-2                As of 3rd Quarter FY-86
 
Generic 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          09/86*              09/868            -
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 i
i
* All work on this project has been suspended pending guidance from CRGR.
Schedules indicated above will be revised by RES once work has resumed.
B6-3                As of 3rd Quarter FY-86~
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
(-~s) s_/s Issue Number Issue Type Action Level                          _ Office /Div/Br Task Manager    TACS No.
B-17                    Safety /                                              Active-L1                          NRR/DHFT/HFIB            TBD        TBD Medium Title ----------------                                                          Criteria for Safety Related Operator Actions Work 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 (s.      Technical Resolution -
2 Milestones                                                                                              Original            Current        Actual Milestone being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
I 817-1              As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue        Issue            Action                                Task Number      Type            Level            Office /Div/Br      Manaaer          TACS No.
B-55        Sc/ety/          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 Work 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 l                                        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 (0G) 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 materials that could eliminate excessive setpoint drift 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 several plants during upcoming fuel cycles. The results of this effort will be evaluated by the 0G 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 0G 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-PMo 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.                                              l B55-1                As of 3rd Quarter FY-86 ini  i r
 
G:n:ric Issua #B-55 Problem / Resolution ---  The resolution of this issue is aimed at increasing the reli-ability of these valves to meet the current plent 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 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                            Oricinal          Current        Actual Meeting with BWR Owners                12/83              -
11/83 Setpoint Orift 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 Communication to OG re: NRC              -                -
03/85 comments / concerns.
OG presentation to the staff          10/85              -
10/85 Staff receives Owners' program        10/85              -
10/85 for eliminating set point drift l
l      Owners begin to install new            01/86              -
01/86 l      pilot disks to test in plant i      for one fuel cycle l
l      Issue close-out memorandum            12/85            07/86              -
O B55-2            As of 3rd Quarter FY-86 l
l i
 
l GENERIC ISSUE MANAGEMENT CONTROL SYSTEM                                                          i
                  +
a i
Issue        Issue                Action                                                  Task Number        h                    Level                            Office /Div/Br        Manager            TACS No.          !
8-56          Safety /            Active-L1                          NRR/DSR0/RSIB        A. Rubin            49942 High l                        Title ----------------              Diesel Reliability j
Work Authorization ---              NRR FY-83 Operating Plan (Appendix G).
;                      Contract Title -------            Actions to improve and maintain diesel generator reliability.                                  ,
i                                                                                                                                                        l Contractor Name/ FIN --            BNL/A-3817                                                                                    !
j                      Work Scope -----------            The work scope of B-56 is closely coordinated with the resolu-1 tion of USI A-44, Station Blackout.                        (Both issues are being managed by the same Task Manager). The proposed resolution of i                                                        USI A-44 includes, among other things, a recommendation that i                                                            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 i                                                          contains the following three items: (1) The staff's approach li                                                          for reducing the number of cold fast start surveillance tests; (2) Evaluate licensees submit current diesel generator reli-ability J,ita and programs; and (3) A request that licensees                                  l ll 1
submit a description of their diesel generator reliability program, if any, and example performance technical specifi-
: j.                                                          cations for diesel generator reifability.
j                                                          Responses to the generic letter from all licensees have been                                  ,
i                                                            received and reviewed.                        In addition, the staff met with 4                                                            industry representatives including licensees, DG manufacturers                                .
:                                                          and NSAC to discuss diesel generator testing. Comments have                                    I
{                                                          also been received from ACR$ and EPRI regarding DG testing.
!                                                            Evaluations of the response to the generic letter and other J'                                                          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 j                                                          Power Plant Diesel Generator Reliability," was published in                                    !
April 1986. Standard Technical Specifications and Regulatory                                  '
l                                                          Guide 1.108 (as a long-term effort associated with the final
  !                                                          resolution of USI A-44).                                                                      '
i
!                        Status ---------------            A generic letter 84-15 was sent out to all licensees on July 2, 1984, and responses have been received from all licensees.                                    ,
l l
i i
}-                                                                                                                                                        !
)                        '
856-1                As of 3rd Quarter FY-86 l                                                                                                                                                        :
I.
    -.w.-m-,wv--                                                  wwwer                                  -
                                                                                                          ,,rw~-        ,.- - - - - w.-    , - r- -,--- -
 
Generic Issue #B-56 MPA D-19 has been established to implement Item #1 of the generic letter.
NUREG/CR-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, OSI 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 to              -                -
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 Issued 50.54(f) generic letter        06/84                -
07/02/84 (84-15) to licensees Received public comments              09/84                -
11/01/84 Issued technical assistance          06/85                -            06/20/85 contract to BNL O
B56-2              As of 3rd Quarter FY-86
 
Generic Issue #B-56 Milestones                        Original      Current        Actual O    Publish contractor report on licensee response to 50.54(f) 04/86          -
04/86 letter Develop diesel generator            10/86        10/86              -
reliability program Final technical resolution to      11/86        11/86              -
divisions for coment Staff coments 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 coment            06/87        06/87              -
Received public coments            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              -
l I
O 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    i l
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 Wor k Scope -----------                  In general, plants will be classified such that'in each class, similar ECCS outage unavailabilities will have similar impacts on risk. The effect of a given ECCS availability on risk will be determined, for each class of plant, as well as the impacts of any changes in allowable ECCS outage period. Consideration of support system outages must be included. Details of the work scope are contained in the draft action plan.
Affected Documents ---                  Technical Specification changes are possible.
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 j              issued for 00 approval Coordinate Technical Rcsolution                              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 Task II-Apply to a PWR or BWR                                02/85          11/86                                          -
Apply Methodology to a                                        08/85          07/87                                          -
Selection of Plants 4
v B61-1          As of 3rd Quarter FY-86
 
Generic Issuo #B-61 Milestones                            Original        Current          Actual Develoo a Licensing Position Develop an Initial 03/86              08/87              -
Recommendation for Staff Ccmments 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          ' 6/88 0                  -
Ends Division Review of Public              02/87            07/88              -
Comments Completed, and final CRGR package completed NRR Review of CRGR package            04/87            08/68                -
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 O
B61-2            As of 3rd Quarter FY-86
 
GENERIC ISSLE MANAGEMENT CONTROL SYSTEM (Oj V
Issue Number        h Issue      Action Level            Office /Div/Br Task Manager        TACS No.
B-64          Safety /    Active-L1        RES/DET/CHEB      K. Steyer      04765 NR Title ----------------    Decommissioning of Reactors Work Authorization ---    NRR FY-84 Operating Plan, (Appendix G).
Contract Title -------    Decontamination and Decomissioning Review Contractor Name/ FIN --    PNL/8-2342 Work Scope -----------    Develop a general decommissioning policy, prepare the atten-dent changes in regulations, covelop 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.
Status ---------------    Draft final rule changes and other package material are
,  g                                    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 on RES input (see note below).
Technical Resolution -    Published rule changes on decommissioning, issue new regula-tory guides and revision to R.G. 1.86, issue new standard review plan on decommissicning.
Milestones                            Original          Current        Actual CRGR review completed on                -                  -
08/08/84 decommissioning rule (Research)
EDO approval of decommissioning -      -                  -
09/07/84 SECY-84-354 (Research)
Commission Approval of                12/84                -
12/84 SECY-84-354 (Research)
Issuance of draft rule                02/85                -
02/11/85 change for public comment
.                  Format and Content for Decommis-      02/84*              -
06/85 l
sioning Plans (from Research) l l
l                                                        B64-1              As of 3rd Quarter FY-86 l ._    ._ -          .      -                              . ___
 
G:neric Issue #B-64 Milestones                          Original          Current        Actual Issuance of SRP Section**
Issue transfer memo to RES          01/86                -
01/86 SRP revision package to Div.        06/84                -                -
Director for review NRR Director Review completed        07/84                -                -
Review Package to CRGR              08/84                -                -
CRGR review completed                09/84                -                -
EDO approval                        09/84                -                -
Federal Register Notice of          10/84                -                -
Issuance of proposed RG and SRP for Public Comment 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 Revised draft rule incorporating    02/86              11/86              -
public comments ready for RES management review l    Revised draft rules                  08/86              06/87              -
l public comments reviewed and approved by CRGR Final rules noticed in the          01/87              10/87              -
Federal Register
  *0riginal 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.
B64-2              As of 3rd Quarter FY-86
 
I i                                    GENERIC ISSUE MANAGEMENT CONTROL SYSTEM                                                      !
)      Issue              Issue      Action                                            Task j      Number              h            Level                        Office /Div/Br      Manager              TACS No.            i
:    C-8                Safety /  ' Active-L1                    NRR/DSR0/RSIB        L. Riani            5147F i                          High l      Title ----------------          Main Steam Line Leakage Control (BWR) 4 i
Work Authorization ---          NRR FY-84 Operating Plan (Appendix G).
{    Contract Title -------          MSIV Leakage and LCS Failure Contractor Name/ FIN --        PNL/8-2529                                                                                ,
:    Work Scope -----------          Review MSIV leakage and LCS failures with respect to plant                                '
i                                      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 j                                      utilities' efforts to reduce MSIV leakage and LCS failures.
Affected 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).                                  .
Status ---------------          On 06/17/86, the BWR Owners' Group (BWR0G) Committee on MSIV Leakage Control made a presentation to the staff on their l                                      review and recommendations concerning future course of issue
!                                    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 i                                      identify options available to licensees pending final resolu-
:                                      tion of Generic Issue C-8. The issue will then be transferred l                                      from 08L to DSRO. The CRGR package will then be prepared and                              ,
j                                      submitted for approval.                                                                ,
l      Problem / Resolution ---        Updated scheduled will need to be assessed by DSRO once the i                                      NUREG is issued by 08L.
Technical Resolution -          Allow licensees to delete MSLLCS from Tech. Specs and j                                      increase MSLIV leakage limits.                                                            >
l l              Milestones                                          Original            Current            Actual l
Task Action Plan approved by                        10/83                    -
10/31/83          ;
Director, OSI.
3              Develop minimum design criteria                      03/84                                  04/18/84            !
l                for alternative equipment for                                                                                  <
l                LOCA mitigation.
i C8-1                As of 3rd Quarter FY-86                ,
t                                                                                                                                ,
i                                                                                                                                f
!                                                                                                                                I C_____                  _                                                          _                  . _ _ _ . _ _ ,
 
Gen:ric Issue #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 00      -          -
06/01/84 Revised request for Technical          -          -
06/15/84 Assistance to D0 for approval Revised TA request Approved        08/84          -
07/03/84 by 00 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 r6 view of compartment    10/85          -
11/85 contamination 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 Issu3 #C-8 Milestones                        Oriainal                                  Current        Actual Issue transfer memo to DSR0        08/86                                    08/86              -
CRGR package approved by          01/86                                        TBD            -
Director, OSRO. 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 raview complete.              04/86                                        TBD            -
E00 approval.                      05/86                                        T80            -
Federal Register Notice            05/86                                        T80            -
issued for public comment.
OM8 Clearance                      09/86                                        T80            -
Incorporation of comments.        09/86                                        T80            -
Package sent to Director, NRR.
O Director, NRR review complete.
Package sent to CRGR.
10/86                                        T80            -
CRGR review complete.              11/86                                        TBD            -
E00 approval.                      12/86                                        T80            -
Federal Register Notice issued. 12/86                                        TBD            -
)
l
(                                                                                                                I
:                                                                                                                1 I
i                                          C8-3                                      As of 3rd Quarter FY-86 i
 
                .._ , -                  - ..    - _ _ _ - .        - . = _    .. . _ . .--..      _      - ,            - - - . -                _. .- - .. ._-
i l                                                              GENERIC ISSUE MANAGEMENT CONTROL SYSTEM                              ,
4 4
  \                            Issue            Issue            Action                                          Task
!                              Number            Tyge,            level                Office /Div/Br            Manaaer              TACS No.
i                              I.A.2.4          Licensing                              NRR/0HFT j
l                            -Title ----------------            NRR Participation in Inspector Training
(
l                              Work Authorization ---            NUREG-0660 i
i                            contract Title -------            To be provided
;                                                                                                                                                                    i Contractor Name/ FIN --            To be provided 1
!                              Work Scope -----------            To be provided
)                              Affected Documents ---            To be provided i                              Status ---------------            To be provided                                                                                      ;
i l                              Problem / Resolution ---          To be provided
$                              Technical Resolution -            To be provided Milestones                                    Oriainal                  Current            Actual l
4 i
l 1
l l
1 i
i t
i                                                                                                                                                                    ,
!                                                                                                                                                                    l l
1 l
r I                                                                                                                                                                    <
1                                                                                                                                                                    ;
I                                                                                                                                                                    <
!                                                                                IA24-1                            As of 3rd Quarter FY-86 I                                                                                                                                                                    i i
I l'
      --,-- - -, _ -, ~.. ..., _ ,. _ ,n                                                                ..- - , - - - - - -            ,-----n.,.--,.
 
i GENERIC ISSUE MANAGEMENT CONTROL SYSTEM 4                                                                                                                                                                                                                      i Issue Issue Action                                                Task Number                  Type                Level      -
Office /Div/Br                                      Manager                                TACS No.
I.A.2.6(1)              Safety /            Active-L1            NRR/DHFT/MTB                                        J. Persensky                            None High                                                                                                                                                                          i
  ;              Title ----------------                      Revise Regulatory Guide 1.8 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 issues HFPP-1.2.
Affected Documents ---                      Same as above Same as above Status ---------------
  !              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.
t l
i i
i 1
i i
IA26-1                                            As of 3rd Quarter FY-86
    .n  ~- -- -.      ,,      .,--__.-_--..--,...,c-_,,                    _ _ - _ _ , - , . . _ _ , , , , _ _ _ , , - , , .              . . - - - , . . - - - - - , _ _ . . _ . - . _ . - - - - . - . . - - - .
 
1 1
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM                                                                                  l l
l
        /    Issue                  Issue          Action                                                    Task Number                  Type            Level                  Office /Div/Br                  Manager                                        TACS No.
I.A.3.3                Safcty/        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 Ccmmission 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-
  \y                                                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 1
the final fitness for duty rule submitted to the Commission i                                                    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                                                Original                        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 t
Complete ACRS Review                                      05/83                                        -
08/05/83 v
IA33-1                      As of 3rd Quarter FY-86
 
l 1
Generic Issue #I.A.3.3                                  1 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 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.
O IA33-2          As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM l
O                  Issue Number Issue Type Action Level          Office /Div/Br Task 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 Title -------                                              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 1
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.
L 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                                            -
09/85 Experiment Report Issue Close-out memorandum                                            06/86                                      06/86                                      -
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                                                                                    \
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue                  Issue            Action                              Task Number                Type            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 p        Technical Resolution -
Milestones                                        Original            Current          Actual Milestones being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
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IA42-3              As of 3rd Quarter FY-86 i
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue            Issue        Action                                                      Task Number          Tyge_        Level                                    Office /Div/Br    Manager    TACS No.
I.A.4.4          Licensing                                              RES Title ----------------      Feasibility Study of NRC Engineering Computer Work Authorization --<-    NUREG-0650 Contract Title -------      To be provided Contrac' tor Name/ FIN --  To be provided Work Scope -----------      To be provided Affected Documents ---      To be provided l  Status ---------------      To be provided Problem / Resolution ---    To be provided Technical Resolution -      To be provided 1 C Milestones            Original Current                                Actual IA44-1                    As of 3rd Quarter FY-86 l
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GENERIC ISSUE MANAGEMENT CONTROL SYSTEM s
Issue        Issue          Action                              Task Number      Type          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.
1B11-1              As of 3rd Quarter FY-86 l
 
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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/QAB                    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 Work Scope -----------      Regulatory Guide 1.33 - QAVT/QAB will revise and issue a change to the guidelines cantained in this Guide. GI #75 subsumed the issue, and information per taining 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 O Status ---------------      Refer to GI #75 subtask 1 and HF-01 issues HFPP-1.2 and 3.4 for Status.
Problem / Resolution ---    None Technical Resolution -
Milestenes                          Original                      Current          Actual Regulatory Guide 1.8 Refer to HF-01 issues HFPP-1.2          -                            -                -
and 3.4 schedule for issuing a revision to Reg. Guide 1.8.
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.8.1.1 Subtasks 6 and 7, have been subsumed by milestones for Generic Issue No. 75 subtask 1.
IB11-3                        As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM O'    Issue Number Issue Type Action Level          Office /Div/Br Task Manager        TACS No, I.C.9            Safety /                      Active-L1      NRR/DHFT/HFIB      J. Bongarra    43505 Medium Title ----------------                        Long-Term Program for Upgrading of Procedures Work Authorization ---                        TMI Task Action Plan Contract Title -------                        Develop recommended interfaces among plant operating procedures.
Contractor Name/ FIN --                        PNL/B-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.
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.
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GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue        Issue        Action                              Task Number        hee _,        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 necez-sary and further that this new revision should be applied to all plants. Based on the PNL recommendations, DHFS has transfered responsibility for this issue to RES (revise R.G. 1.47). Responsibility for issue transferred back to NRR.
Affected Decuments ---      Revision to R.G. 1.47.
Status ---------------      All technical reports on this issue are complete. The project final report has been published as NUREG/CR-3621.
This final report includes guidelines for improving system status 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 for this supplemental work.
Problem / Resolution ---    Response by RES to NRR dated April 17, 1985 identifies need to coordinate plan to revise R.G. 1.47 and fund work.
The termination of human factors research funding at the end of FY 1985 necessitates that this issue be reassigned to DHFS/NRR.
Technical Resolution -      The technical resolution of this issue will be the develop-i                                  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
 
U Genaric Issue #1.0.3 Milestones                          Original  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 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 i Issued memorandum for providing        -        -
11/25/85 I
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/C5      03/87              -
Develop Regulatory Analysis          03/86      06/87              -
Office Concurrence of CRGR          04/86      09/87              -
Package CRGR, EDO, ACRS Review / Approval    07/86      10/87              -
O ID3-2        As of 3rd Quarter FY-86
 
Generic Issue #I.D.3 Milestones                          Original      Current        Actual
, O. 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            -
l 103-3            As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM G
Issue        Issue        Action                                                        Task Number        Type        Level            Office /Div/Br                                Manager          TACS No.
I.D.4        Safety /    Active-L1        NRR/DHFT/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 EDO concurrence with reclassifying this non-scheduled issue.
                                                                                                                          ~
Problem / Resolution ---  Same as above Technical Resolution -
O'      Milestones                            Original                                      Current          Actual None scheduled.
104-1                                        As of 3rd Quarter FY-86
 
l GENERIC ISSUE MANAGEMENT CONTROL SYSTEM D  8 Issue          Issue        Action                              Task Number        Type        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-f\
\'j 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 Install System at a PWR                  -                  -
09/80 Complete PWR Data Acquisition          06/84                -
01/84 Install System 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
 
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              -                                                                GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue                        Issue                                    Action                                                      Task Number                      Type _                                    Level                                  Office /Div/Br        Manager          TACS No.
I.D.5(5)                    Safety /                              Active-L1                                  NRR/DHFT/HFIB        None            None High Title ----------------                                                Disturbance Analysis Systems Work Authorization ---                                                TMI Task Action Plan Contracc 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 i
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
 
O GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue          Issue      Action                              Task h
G Number        Type        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 equipmeat 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                          Original            Current        Actual Task 1: Develop Frame Work              -                  -
02/83 Review NRC Internal Comments      04/83                -
07/83 on NUREG/CR-2631 (rewrite Scope /189 if necessary) and
;            publish NUREG Task 2: Start Method                10/83                -
10/83 Development (Issue Contract to Sandia) l          Completion of Task 2                09/84                -
05/85 l
l          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 EDO            -
ACA                -
or provide additional mile-p      stones necessary to complete issue based on Commission discussion.
IF1-1              As of 3rd Quarter FY-86 l
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM A)                                    Action (V  Issue Number Issue Type                  Level            Office /Div/Br Task Manager          TACS No.
II.B.5      Safety /              Active-L1        RES/DAE/FSRB          M. Silberberg    None (1&2)        High                                    RES/DAE/CSRB            R. T. Curtis Title ----------------              Research on Phenomena Associated With Core Degradation and Fuel Melting Work Authorization ---              TMI Task Action Plan LRRP, Budget Authorization Documentation Contract Title -------              Multiple contracts Contractor Name/ FIN --            SNL/INEL/BCL/PNL Work Scope -----------              Conduct an extensive experimental and analytical program on the behavior of damaged fuel, hydrogen generation, and control, fuel structure interaction, containment analysis, and fission product release and transport as described in detail in NUREG-0900, 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 p                                        reactor.
k' 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 Term (Final expected July 1986).
(4) NUREG-1150 New Risk Profiles for Five Reference Plant (Draft for Comment September 1986).
Status ---------------              Severe fuel damage in pile research is in progress in ACRR and the Canadian NRU reactors and complete in PBF.
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 SCDAP, HECTR, CORCON, MELPROG, TRAP-MELT, and CONTAIN.
Milestone charts for this work and a more completa descrip-tion of the work appears in NUREG-0900, Rev. 1. Integrated PRA analysis codes such as the Source Term Code Package (STCP) (complete 9/85) and MELCOR (1987) will be used for extensive uncertainty analysis through FY 1988-89.
S IIB 5-1                As of 3rd Quarter FY-86
 
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)
Final Reassessment of the            07/86                07/86              -
Technical Bases for Estimating Source Terms (NUREG-0956)
Severe Accident Risk Rebase-        12/83                09/86              -
lining program draft report (NUREG-1150)
NRC Severe Accident Policy          11/85                  -
07/85 Final Recommendations to the        06/84                11/87-            -
Commission on Severe Accident Requirements for Operating Plans and Plants under Construction Issue close-out memo to EDO          06/88                06/88              -
O IIB 5-2              As of 3rd Quarter FY-86 I
 
  -s                          GENERIC ISSUE MANAGEMENT CONTROL SYSTEM                            1 Issue          Issue      Action                            Task                            '
Number        Tys          Level            Office /Div/Br    Manager              TACS No.
II.B.5(3)    Safety /    Active-L1        RES/DAE/CShB      P. R. Worthington    None Medium 4
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.
Contr6ctor Name/ FIN --    SNL, LANL/A-1246, A-1270, B-82C8, I.-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 de"lagrations, global and local detonations, flame accelera-tion and the transition to detonation. The effect of burning
.!                              on equipment and the efficiency of H2 control 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 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 IIB 5-3          As of 3rd Quarter FY-86
 
e Generic Issue #II.B.5 (3)
Milestones                          Original        Current        Actual Effectiveness of Nonpowered        09/86            -
06/86 Igniters Effect of H, Burns in Aerosols      10/83          10/86              -
Scoping Stu8y Report 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*      .
l      Manual revision l
l      Research information Letter to      07/87          07/87              -
NRR and issue close-out memo l      to EDO 1
1 l
* Not Funded in FY 1987.
l l
l 9
l                                          IIB 5-4        As of 3rd Quarter FY-86 l
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM p t Issue        Issue        Action                                  Task (d  Number      Type        Level              Office /Div/Br      Manager        TACS No.
II.C.4      Safety /    Active-L1          RES/DRA0/RRB        C. E. Johnson  None Medium Title ----------------    Reliability Engineering                                          '
Work Authorization ---    TMI Task Action Plan Contract Title -------    Operational Safety Reliability Contractor Name/ FIN --  BNL/A-3282 Work Scope -----------    Evaluate the effectiveness of reliability program elements and techniques applicable to maintaining LWR safety during the operating life of the plant. Tcsks include:
(1) Survey generic issues and precursors to assess the effectiveness of reliability technology to help resolve current safety issues.
(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 p
g example, performance indicators and alert levels) for trial application to LWRs.
(4) Evaluate the effectiveness of a reliability program through initial trial application to an example safety system at 1 plant.
(5) Publish a technical report (NUREG/CR) that integrates interim results from the above tasks to identify the essential elements of a reliability program, evaluate their effectiveness, and identify attributes of successful reliability programs.
Affected Documents ---    To be determined based on the results of this project.
Status ---------------    The contractor is summarizing results to date in the interim technical report (Task 5), a draft of which will be completed by April 30, 1986.
In response to a memorandum from Mr. Stello 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-tial needs for implementation of reliability assurar.ce in 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.
Technical Resolution -
IIC4-1              As of 3rd Quarter FY-86
 
Gentric Issue #II.C.4 Milestones                          Original      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-0885, 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.
Staff memo to EDO evaluating        06/86        06/86              -
regulatory needs for reliability assurance and outlining plan for implementation.
ACRS Subcommittee review            05/87        05/87              -
Publish final NUREG                  12/87        12/87              -
Issue close-out memo                12/87        12/87              -
to EDO 1
l O
IIC4-2      As of 3rd Quarter FY-86
 
      ,q                            GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue        Issue        Action                              Task Number      Type          Level            Office /Div/Br    Manager          TACS No.
II.E.4.3    Safety /      Active-L1        NRR/OSR0/RSIB    A. Serkiz        52409 High l
Title ----------------    Containment Design - Integrity Check Work Authorization ---    NRR FY-84 Operating Plan (Appendix G).
Contract Title -------    Feasibility Study of Alternative Containment Test Methods Contractor Name/ FIN --    SNL/A-1802
                                                                                                      ~
Work 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.
p(  %
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 har 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 deobligations, 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
 
4 l
l      Milestones                          Original          Current        Actual Request for Proposal for              -                -
01/12/83 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 l      Integrity (Tasks 1&2) l      Receive Contractor Draft Report      02/15/84          05/84*          05/18/84**
l      on Review of Containment l      Integrity (Task 1&2) 1 1
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 j      Additional Milestones for Resolu-I      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 l      Issue Contract to Evaluate          04/85              -
05/85 i      Feasibility of Alternative l      Containment Test Methods I
(SNL Tasks 1&2)
I i      Interim Report on the feasi-        03/86              -
05/86
,      bility of alternative contain-ment leak tests l      Evaluate costs of alternative      08/86            11/86'            -
containment leak tests i
Complete Evaluation of              08/86            12/86              -
Industry Testing Procedures l      and Alternate Methods
    " 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 Draft Report (regarding Task 2) deferred to 9/84.
  *** Memorandum from R. Bernero to T. Speis, dated 08/08/84, Transmitting Finding that Further Technical Resolution of the Issue is Warranted.
O IIE43-2          As of 3rd Quarter FY-86 l
,                                                                                            I
 
                                                                                  }
l Generic Issue #II.E.4.3 J Milestones                          Oridinal        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              -
O Final CRGR Package to NRR Director 10/87            10/87              -
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              -
Containment Test Methods Feasibility O
IIE43-3          As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM i
Issue                          Issue                                                  Action                                        Task Number                          Type                                                  Level                    Office /Div/Br      Manager                        TACS No.
II.E.6.1                        Safety /                                              Active-L1                NRR/DSR0/EIB        0. Rothberg                    42416 Medium 2
I              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.
l (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.
l 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 suppo,rt are i
less than anticipated, significant assistance is 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.
I An industry multi-NSSS Dwners Group effort has been initi-ated at the request of the EDO, the purpose of which is to i
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 I                                                                                                      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
 
1 I
Genoric Issue #II.E.6.1                              l I
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, j
An attempt is being made to resolve the various problems now being identified with current valve in situ testing methods to determine if design basis results can be          i extrapolated 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 00E Lab          05/84                -
05/84 proposals for pressure isolation valve leak tests and other testing. Provide recommendations to RES for revisions to test scope and selection of testing lab.
DE Project Manager prepares          07/85                -
07/85 work scope for 00E Lab contract (re: study of adequacy of current valve inservice test-ing methods) and issues RFP.
DSR0 contract initiated              10/85                -
03/86 DSR0 contractor completes review      05/85              12/86              -
of comments to be obtained from AE00, INPO, BWR Licensees, valve manufacturers, determine tentative i      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 DOE Lab report on PIV and MOV testing (RES contract) -- check valves            09/85              07/86              -
l gate valves          09/85              02/87              -
l 1      Issuance of Movats report re          09/85                -
01/86 l      in-situ signature tracing tests (RES contract).
O IIE61-2            As of 3rd Quarter FY-86
 
Ginaric Issue #II.E.6.1 Milestones                                                                                          Original Current                            Actual
        \        Completion of review of Movats                                                                      11/85    08/86                                            -
reports by NRR including receipt of comments from AE00.
a Based on IE review of responses                                                                      10/86    10/86                                            -
to IE Bulletin 85-03, formulate
          ~
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 AEOD contracts.
Value/ Impact statement prepared                                                                    04/87    04/87                                            -
NRR Division Directors deview                                                                        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 Public 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                                            -
Issue close out memo to EDO                                                                          05/88    05/88                                            -
I s IIE61-3  As of 3rd Quarter FY-86
_ . _ ,  ____ _ . _ _ _ _ . , . _ . _ _ , . - . . , , ~ . , , , . , . , . _ . . . , ._.- _-. .__. ._          _ _ . _ _ _ - . - _ . . , . _ . . , . , - . - .    . _
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue          Issue '      Action                              Task Type  c-      Level            Office /Div/Br      Manaaer        TACS No.
      ~} Number II.F.5        Safe'cy/      Active-L1        NRR/DSR0/EIB        TBD            96005 Medium Title --------------- Classification of Instrumentation, Control.and Electrical Equipment Work Authorization -- (1) TMI. Task Action Plan (2) Jan. 15, 1982 and Nov. 8, 1982, NRC Form 173, K. R. Goller, DF0 Contract Title ------ Classification of Systems Important to Safety Contractor Name/ FIN - BNL'/A-3249 Work Scope ---------- To develop a methodology for the classification of systems important to safety.
Affected Documents -- Draft Regulatory Guide for the classification of Instrumentation,
                                    , Control and Electrical Systems and Components (ICES /E) Important to Safety.
Status ^------------ Draft report by BNL was submitted in September 1984 and is awaiting
                                ,-  review and comment by NRR.
Problem / Resolution -- IEEE has not yet issued a standard on classification of systems important to safety.      IEEE Std. P-827 has been abandoned in favor of a different approach involving the development of new standard n                                taking into account applicable work done by other technical socie-
    /    '
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 safety has been designated as priority C and has been taken off the list of active RES tasks.
Technical Resolution - The technical resolution of this item may be achieved by the issuance by the IEEE of a suitable standard which may subsequently be endorsed in whole or in part by a regulatory guide, or alternatively by the issuance of a regulatory guide irrespectively of what or when IEEE might issue a standard in this area. At this time we are continuing our participation in the IEEE effort to develop a draft Standard P-1049 under IEE/NREC/SC-6.2, Working Group on System Classification.
Milestones                              Original            Current        Actual Issue Reg. Guide for comment            10/83              On hold *            -
Issue transfer memo to NRR for          02/86                -
12/20/85 close-out.
Issue close-out memo to EDO            05/86              07/86                -
Issue BM Report                        12/84                TBD                  -
Issue IEEE Std.                        1980                TBD                  -
l
* Letter from H. Denton to R. Minogue,.Dec. 31, 1983.
IIFS-1                As of 3rd Quarter FY-86 i
 
h GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue      Issue    Action                                Task d
Number    Type      Level            Office /Div/Br    Manager                TACS No.
II.H.2    Safety /  Active-L1          RES/DAE/FSRB      R. Foulds              None High Title ----------------      Obtain Technical Data on the Conditions Inside the TMI-2        ,
Containment Structure                                          ;
l Work Authorization ---      TMI Task Action Plan LRRP, Budget Authorization Documentation Contract Title -------      None Contractor Name/ FIN --    None Work Scope -----------      NRC is cooperating with DOE and industry on development of plans and guidance for implementation of research and data gathering programs within the TMI-2 containment.
These programs concentrate on retrieving data which characterize the progression of the accident and the resulting radiological source term for this case. The programs address the examination of the reactor inter-nals (especially the reactor core and fuel), the primary system piping and vessel, the dose reduction effort during decontamination, and various mechanical, elec-
  ,                              trical and instrumentation equipment. NRC primarily provides technical expertise in the program formulation and implementation, the programs are generally, carried out with funds from DOE and others.
Affected Documents ---      NUREG-0900 Severe Accident Research Plan (08/84).
Status ---------------      More than one hundred information reports have been issued by EG&G Idaho for DOE as a serics of GEND reports numbered GEND-001, et. seq. (GEND indicated:
I                                General Public Utilities, Electric Power Research i
Institute, Nuclear Regulatory Commission, and Depart-ment of Energy - who are cooperating in a number of
(                                technical working groups to manage the planning.)
Current efforts are concentrated on TMI-2 core exami-nation both on-site and off-site. NRC is conducting.a series of off-site examinations of selected core materials at a national laboratory. A planning basis for work supported by NRC and separately by DOE has been developed including a priority analysis.
Implementation within NRC depends upon availability I
of samples from DOE.
Problem / Resolution ---    Low funding support for operations in the utility's recovery / cleanup program has delayed the availability of data. An industry supported technical advisory group is assisting the utility in the engineering O                            projects required, to speed up the cleanup effort.
Examination of detailed test description and IIH2-1              As of 3rd Quarter FY-86
 
Gensric Issue #II.H.2 information needs by DOE, EPRI, GPU, NRC, technical working group has delineated 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)
Head Removal                          07/83          -
07/84 Plenum Removal                        07/85          -
05/85 Begin Defueling                        10/85          -
12/85 Revise core examination plan          12/85          -
02/86 Core Drilling                          07/86        07/86              -
Complete Defueling.                    06/87        06/87              -
Final Fuel Analysis Report            09/87        10/88        _
Issue close-out memo to ED0            12/87        12/88              -
l.
l 9
IIH2-2          As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue            Issue      Action                              Task Number          Type      Level          Office /Div/Br      Manager          TACS No.
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 requirements of 10 CFR part 50.55(e) and 10 CFR Part 21 to assure that all reportable items are reported promptly and that the informa-tion submitted is complete. A major cbjective will be to eliminate duplicative evaluation and reporting and establish consistency with the NRC safety deficiency reporting require-ments. The reports received as a result of these rule changes will provide increased information on component failures that affect safety so that prompt and effective corrective action can be taken. The information will also be used as input to an augmented role of the NRC's vendor and construction inspec-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 Commission approval, the proposed rule changes will be published in the Federal Register for public comment.
Problem / Resolution ---    Schedule revised to reflect delays in Commission review.
Technical Resolution -
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    l h n -
g -
 
Generic Zssue #11.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 9
l l
O IIJ41-2        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.3.1    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 Wo rk S cop e -----------  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 INPO 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.
: 3. R.G. 8.XX - revise and hold for issue pending success of INP0/ Industry.
: 4.  " Development of a Program to Evaluate Industry Efforts to Achieve Successful ALARA-Integrated Radiation Protec-tion programs," (R. J. Mattson, June 16, 1983).    -
Action Plan / Assessment Method - developed to evaluate INP0/ industry progress and success in implementing ALARA integrated radiation protection programs.
: 5.  " Evaluation of Industry Efforts to Achieve Successful ALARA Integrated Radiation Protection Programs" (April 23, 1985, D. R. Muller to Division Directors) - criteria, worksheets and examples for Regions to evaluate aspects 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 Analysis of Selected Radiological Trends at Power Reactors" (D. R. Muller to DRSS Division Directors, November 19, 1985).
O IIID31-1                As of 3rd Quarter FY-86
 
E Genoric Issuo #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 closecut memorandum to the EDO in May 1986.
l Problem / Resolution ---  None i
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 INP0 Staff for            -                    -
01/26/83 review and comment.
1 i      Staff Recommendation to EDO to          -                    -
02/25/83 transmit proposed Coordination Plan to INPO (Follow-up to INP0 (Wilkinson) {{letter dated|date=August 26, 1983|text=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 INPO Program, including ALARA checklists and evaluation criteria, distribute to IE, RES, and Regions for I      comment.
Revise evaluation criteria based      06/83                  -
06/15/83 on comments.
Complete a topical / functional      06/83                  -                -
comparison of INPO objectives, criteria and guidelines against NRC criteria.
l      Establish ALARA checklist            07/83                  -
06/15/83 parameter, SALP/ inspection findings, etc., tracking system.
Establish schedule of NRC            09/83                  -
07/06/83 accompanied INP0 Appraisals.
O IIID31-2                As of 3rd Quarte- FY-86
                                                                                                )
t
                                                  ._ _                        - - - _ - ---_-_ L
 
Generic Issue #III.D.3.1                                                            l 1
n            Milestones                Original                Current                          Actual Draft criteria for determination                    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 of INP0/ Industry                                                                                      l 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 s          Technical Resolution Complete.                    03/,85                            -
05/19/86
      \
(Issue close-out documentation memo to EDO.)
EDO Approval                                      06/86                              -
N/A r
              "INP0 data viewed by NRC staff, but not officially submitted to NRC by INPO.
)            ** Proposed effort not supported by RES (Document #7 above), but will be evaluated outside of resolution of this issue based on prioritization within the NRR operating plan.            -
            ***NRC staff identified, compiled, and evaluated data and trends from solely NRC sources, duplicating INPO efforts. An additional 2 months were needed to incor-porate this effort. Final documentation was completed in December of 1985.
m IIIO31-3                                  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.                              ;
III.D.3.2(1) Licensing                                        RES Title ----------------                    Amend 10 CFR 20 Work Authorization ---                    NUREG-0660 i
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
                                                                                                                                                                    ~
I
  ,                      ' Milestones                                            Original                      Current        Actual 4
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GENERIC ISSUE MANAGEMENT CONTROL SYSTEM t
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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 d
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IIID32-4              As of 3rd Quarter FY-86 6 - - - - . - - - - - . - - - . _ _ _ _ _ _ _ _ _ _ __
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue                    Issue    Action                                                                                Task Number                    Type    Level                          Office /Div/Br                                        Manager                                                    TACS No.
l                                III.D.3.2(4) Licensing                                          RES Title ----------------            Develop Method for Testing and Certifying Air-Purifying l                                                                  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 Status ---------------            To be provided l                              Problem / Resolution ---          To be provided                                                                                                                                                  .
Technical Resolution -            To be provided Milestones                                                Original                                                Current                                                    Actual I
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IIID32-5                                                      As of 3rd Quarter FY-86 i
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l GENERIC ISSUE MANAGEMENT CONTROL SYSTEM                                                              ,
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III.D.3.5(1) Licensing                                                                    RES j
Title ----------------                                                  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 Status ---------------                                                  To be provided 2
Problem / Resolution ---                                                To be provided Technical Resolution -                                                  To be provided                                                                        _
Milestones                                                                  Original        Current              Actual 7
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l IIIO35-1                As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue        Issue        Action                                                                  Task l
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 t
Affected Documents ---      To be provided Status ---------------      To be provided Problem / Resolution ---    To be provided
:                              Technical Resolution -      To be provided i
I Milestones                                                  Original                          Current            Actual 1
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. _ _ _ , . . _ _ _ _ _ . _ _                                ___.__...._.__ _ _..._____. ._. _ . _ _ _ __..___._____.~_______
 
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O 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 ---      NUREC-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 IVE -3                As of 3rd Quarter FY-86
 
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IVE -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.
d 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 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                          Cricinal          Current              Actual m
IVE -5                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.
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 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        Acteal
    \
IVG2-1                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      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. Der,'on 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.
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gs                                    GENERIC ISSUE MANAGEMENT CONTROL SYSTEM k
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 Humar 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:
I-                                            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 l
qualification of NPP personnel including the opeating shift t                                        Crew.
    \
Efforts related to the law and to close the issue of qualifi-cations include preparation of a policy statement on training and qualifications and fitness for duty in response to $306, i                                            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.
1                Affected Documents ---      Reg. Guide 1.8 Policy Statement Eng. Exp. on Shift NUREG/CR-Engineering Expertise f
l                Status ---------------      SECY-84-106 was submitted to the Commission in l                                            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.
I                                            Regulatory Guide 1.8 may be delayed due to the extent of the Problem / Resolution ---
Q                                        revision following public comment.
b HF01-3                        As of 3rd Quarter FY-86 1
 
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 Aanagers 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 l
10 CFR 55 rule change package (HFPP-3.3 and 3.4).
(
O HF01-4            As of 3rd Quarter FY-86 l
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p                            GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
: d  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 a      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 j                                inspect utility training products and in event-based reviews.
Affected Documents ---    Policy Statement on Training and Qualifications (SECY 85-1)
Status ---------------    Inspection Modules 41400 and 41701 issued and Training Review      l l                                criteria and procedures developed. Three post-accreditation reviews completed.
O Problem / Resolution ---  INPO objection to NRC performing post-accreditation reviews.
,      Technical Resolution -
1
!            Milestoaes                                Original      Current        Actual Milestones being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
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HF01-5        As of 3rd Quarter FY-86
 
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O HF01-6              As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
('%
Issue                  Issue                Action                                                      Task Number                  Type                Level                                        Office /Div/Br Manager          TACS No.
HF-01                  Safety /            Active-L1                                    NRR/0HFT/MTB  J. Persensky      TBP 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 l
Work Scope -----------                      Apply Review Guidance in post-accreditation reviews Affected Documents ---                      Policy Statement on Training and Qualifications (SECY 85-1) l          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.
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HF01-7          As of 3rd Quarter FY-86
 
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                                                          ,                  c-p                                                                GENERIC ISSUE MANAGEMENT CONTROL SYSTEM d            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                                                  7                                        ,
Title ----------------                                Develop a Means to Evaluate Acceptability of NPP Personnel Qualifications Program Work Authorization ---                                Memorandum to H. Thompson from H. Denton dated October 10, 1384,, Human Factors Program Plan (HFPP)
To Be Determined Contract Title -------
Contracter Name/ FIN --                              To Be Determined Work Scope,-----------                                Develop Review Guidance to be used by staff in post-
                                                                                                                                                  \
accreditation reviews.
Affected Documents ---                                PolicySh.atementonTrainingandQualifications(SECY85-1)
Status ---------------                                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 Jur.e 6, 1986.
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HF01-10          As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue          Issue      Action                                Task Number        Type        Level          Office /Div/Br        Manager        TACS No.
HF-01          Safety /    Active-L1      NRR/DHFT/MTB          J. Persensky    TBP Subtask        High
  , HFPP-2.2 Title ----------------    Evaluate INPO Accreditation Program Work Authorization ---    Memorandem to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title -------    None l
Contractor Name/ FIN --    Not Applicable Work Scope -----------    Monitor industry progress in achieving accreditation through observation of INPO team visits, performing post-accreditation reviews and monitoring indicators data.
Affected Documents ---    Policy Statement on Training and Accreditation (SECY 85-1)
Status ---------------    Three post-accreditation reviews completed, 20% of Team visits observed. All Accreditation Board review meetings observed.
Problem / Resolution ---  INP0 objection to 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.
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HF01-11              As of 3rd Quarter FY-86 l                              -    _    .                                    .-            -
 
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HF01-12                    As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue          Issue      Action                              Task Number        Type        Level          Office /Div/Br      Manager        TACS No.
HF-01          Safety /    Active-L1      NRR/0HFT/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 Work Scope -----------    To Be Provided Later Affected Documents ---    To Be Provided Later
                                                                      ~
Status ---------------    On hold until effect of Policy Statement on Training and Qualifications is determined. Issue to be closed-out.
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.
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n                          GENERIC ISSUE MANAGEMENT CONTROL SYSTEM U 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 /0-1315 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                              .
Problem / Resolution ---  None d Technical Resolution -
Milestones                          Vriginal,          Current        Actual Draft Catalogue for panel            01/86              03/86              -
review Final Draft for NRC review          03/86              06/86              -
Issue NUREG-1123                    06/86              09/86              -
Issue Close-out Memorandwn          07/86              10/86              -
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GENERIC ISSUE MANAGEMENT CONTROL SYSTEM Issue          Issue      Action                              Task Number        Type        Dvel            Office /Div/Br    Manager        TACS No.
HF-01          Safety /    Active-L1        NRR/DHFT/0LB      B. Boger        M40428 Subtask        High HFPP-3.2 Title ----------------    Develop Licensing Examination Handbook (NUREG-1121)
Work Authorization ---    Memorandum to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title -------    Development of NRC Operator Licensing Examinations Specifications Contractor Name/ FIN --    Professional Examination Services /D1315 Work 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
[
Problen/ Resolution ---    None Technical Resolution -
Milestones                            Original          Current        Actual Pilot Test begun                      10/85                  -
09/85 Pilot Test complete                  03/86                -                -
Contractor recommendations            07/86              07/86              -
Final Pilot Test complete            09/86              09/86              -
Revise NUREG-1021                    11/86              11/86              -
Issue Close-out Memorandum            12/86              12/86              -
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GENERIC ISSUE MANAGEMENT CONTROL SYSTEM b
V  Issue          Issue          Action                                    Task Number        Type _          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 Title ----------------        Develop Criteria for NPP Simult. tors 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 Work Scope -----------        This item is addressed by activities currently underway in response to Section 306 PL 97-425, and by FIN 0-1317. Speci-fically, proposed changes to 10 CFR Part 55, recommended changes to Regulatory Guide 1.149, " Nuclear Power Plant Simulator Facilities for use in Operator. License Exanina-tions," and results expected from a technical assistance con-f                                  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 methocology 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 l          Office Review                              12/85                      -              -
l CRGR Review                                12/85                    02/86              -
O HF01-19                  As of 3rd Quarter FY-86
                  .    ._- = _ - . _ - .        -                  _ _ _ _ .          . .
 
Milestones                    Original  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                  -
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9 HF01-20    As of 3rd Quarter FY-86
 
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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          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 /Pesolution ---          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.
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O HF01-22          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 /      Inactive-L1    NRR/DHFT/0LB        S. Shankman    None Subtask        High HFPP-3.4 Title ----------------        Examination Requirements (Revise 10 CFR 55, RGs 1.149 and 1.8)
Work Authorization ---        Memorandum to H. Thoinpson 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 Work Scope -----------        Provide Support for resolution of Public Comments and develop regulatory analysis.
Affected Documents ---        None Status ---------------        Complete                                                      .
Problem / Resolution ---      None Technical Resolution -
a          Milestones                            Original            Current        Actual Milestones being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
O HF01-23              As of 3rd Quarter FY-86
 
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HF01-24          As of 3rd Quarter FY-86
 
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GENERIC ISSUE MANAGEMENT CONTROL SYSTEM O  Issue              Issue          Action                            Task Number              Type          level            Office /Div/Br  Manager                                  TACS No.
HF-01              Safety /      Active-L1          NRR/DHFT/HFIB    J. Bongarra                              TBP Subtask            High HFPP-4.1 Title ----------------            Inspection Modules for Upgraded Procedures 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 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.
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HF01-25          As of 3rd Quarter FY-86 I
 
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O HF01-26            As of 3rd Quarter FY-86 1
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM O  Issue Number Issue Type Action Level            Office /Div/Br Task Manager                TACS No.
HF-01          Safety /    Active-L1        NRR/DHFT/HFIB      TBP                    48436 Subtask        High HFPP-4.2 Title ----------------    E0P Effectiveness Evaluation Work Authorization ---    Memorandum for H. Thompson from H. Denton dated October 10, 1984, " Human Factors Program Plan" (HFPP)
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.
t    Status ---------------    Two E0P audit completed.
Problem / Resolution ---  Delay in scheduling a third E0P audit may cause schedule to 1                                  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                    -
;O HF01-27            As of 3rd Quarter FY-86
 
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O HF01-28          As of 3rd Quarter FY-86
 
    .  .~.                  .          _
l 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/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 Affected Documents ---      To Be Provided Later Status ---------------      To Be Provided Later
:O
!  Problem / Resolution ---    To Be Provided Later i
Technical Resolution -
Milestones                            Original            Current          Actual DHFS has Issued a memorandum          02/84                  -
03/22/84
,        to RES transferring B-17 l        to their office.
RES issued memorandum trans-            -                    -
04/17/85 ferring B-17 to NRR/DHFS/PSRB Incorporate B-17 into HFPP              -                    -
06/07/85 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
 
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HF01-30            As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM U  Issue        Issue        Action                              Task Number        Type          Level          Office /Div/Br      Manager        TACS No.
HF-01        Safety /      Active-L1      NRR/0HFT/HFIB      TBP            55402 Subtask      High HFPP-4.4 Title ----------------      Guidelines for Upgrading Other Procedures Work Authorization ---      Memorandum for H. Thompson From H. Denton dated October 10, 1984, " Human Factors Program Plan" (HFPP)
Contract Title -------      Develop guidance and regulatory action for ops and AOPs Contractor Name/ FIN --    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 S.ection 13.5.2 Status ---------------      Task 1 (Define Scope of Project and Refine Project Focus),
Task 2 (Review Existing Data Base) have been completed.
s                            Task 3 (Define Current Industry Practices and Problems) and Task 4 (Select and Convene Project Peer Review Group) have been completed with the exception of reviewing sample plant procedures (task 3, subtask h)
Problem / Resolution ---    None Technical Resolution -      NRC will determine the amount of upgrade effort necessary for
                          -    each type of procedure based on a contractor interim report and industry inputs with respect to costs and benefits.
Milestones                            Original            Current        Actual Issued contract to PNL to develop        -                    -
02/01/83 guidelines for upgrading operat-ing procedures.
Define scope of operating                -                    -
01/31/84 procedures Submit a summary letter' report          -                    -
01/31/84 Complete review of data on                -                  -
07/01/84 nuclear power plant operating procedures Submit summary letter report              -                  -
08/15/84 O
HF01-31            As of 3rd Quarter FY-86
 
Milestones                        Original Current        Actual Develop discussion items for        -        -
01/31/84 site visits and submit to NRC Incorporate NRC comments and        -        -
02/15/85    i submit final letter report                                              l Complete site visits              09/84      -
02/01/85    l 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                                                      l Select and contact Peer              -        -
03/30/84 Review Group I
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      -
09/85 urgent NRC action 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 l Issue close-out memorandum        06/86  06/86              -
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HF01-32  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        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.
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HF01-34            As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM fm \
G    Issue        Issue        Action                              Task Number      Type        Level            Office /Div/Br      Manager          TACS No.
HF-01        Safety /    Active-L1        NRR/DHFT/HFIB      R. W. Froelich    40444 Subtask      High 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 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 cooperatino utilities.
An initial step in this process would be the confirmation of the local control station definition that was provided in 4
g                              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 l                                permiI.ted.
Affected Documents ---    The principal one would be NUREG-0700. One primary output of the local control stations review process would be an addendum to NUREG-0700 that would provide guidelines for industry conduct of local control . station design reviews.
;      Status ---------------    Currently going through the ORNL LER data bank retrieval l                              ' system in an attempt to develop a search program that would have a high probability of selecting LERs for further review that were based on local control station problems.
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HF01-35            As of 3rd Quarter FY-86
 
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.
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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/DHFT/HFIB      0. Jones          TBP Subtask        High HFPP-5.2                                                                                  1 Title ----------------      Annunciators Work Authorization ---      Memorandum to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPF)
Contract Title -------      1. HumanFactorsinAnnunciator/AiarmSystems
: 2. Computerized Man-Machine Communication Contractor Name/ FIN --    1. SNL/A-1394
: 2. CECD 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.
  .s  Status ---------------      Experimental evaluation of alarm prioritization ,is awaiting availability of ANO simulator.
Problem / Resolution ---    Availability of ANO simulator to conduct experimental evalua-tion of alarm prioritization plan. Coordination with SNL underway.
Technical Resolution -
Milestones                            Original          Current          Actual Milestones being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
    /
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HF01-38            As of 3rd Quarter FY-86
 
GENERICkSSUEMANAGEMENTCONTROLSYSTEM O 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-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-0835 for the control and display elements in the control rooms.
Affected Documents ---    NUREG-0700 and NUREG-0835 n  Status ---------------    Research began in FY81 with reports being issued annually.
Human Factors Subcommittee 7.0, Power Committee, IEEE, V)
  ,t also is engaged in development of a human factors design standard. Decision to prepare a Rule, Guideline, or only technical reports has not been affirmed.
Problem / Resolution ---  Contract terminated at end of FY-85 Technical Resolution -
Milestones                          Original            Current        Actual Begin criteria development            09/80                  -
12/80 research First report, NUREG/CR-1994,        04/81                    -
04/81 April 1981 Second report, NUREG/CR-2147,        09/81                    -
08/81 September 1981 Third report, NUREG/CR-2828,        06/82                    -
08/82 August 1982 Fourth report, NUREG/CR-2776,        09/82                    -
09/82 September 1982
  'O HF01-39            As of 3rd Quarter FY-86
 
d Milestones                      Original  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/DHFS 06/85        -
07/03/85 DHFS memorandum 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 O
HF01-40    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/0HFT/HFIB      TBP                      TBP Subtask            High HFPP-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 A-6308 Work Scope (2)
Development of Display Design              FY81                  -
FY81 Criteria Started System Design Completed                    09/84                -
09/84 Issue transfer memo to NRR/DHFS            06/85                -
07/03/85 DHFS memorandum provide                    11/85                -
08/08/85 Milestone necessary tc complete issue Work scope for issue I.D.5 (5)              02/86              02/86                      -
will be integrated into HF-01 issue HFPP-5.4 s
HF01-41            As of 3rd Quarter FY-86
 
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HF01-42          As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM V      Issue        Issue        Action                              Task Number        Type          Level            Office /Div/Br    Manager          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/B-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 C                                    position, if required.
Affected Documents ---      NUREG-0800, 10 CFR, NUREG-0731 Status ---------------      The contractor developed report on evaluation of INPO assistance visits to utility corporate and plant facilities has been completed. This information is currently being evaluated with information on PAT, SALP and other independent evaluators of management and organization at nuclear power plants. A staff recommendation on what the NRC positions should be concerning management and organization at operating nuclear power plants is scheduled for July 1985.
Problem / Resolution ---    Close-out issue from 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 INP0          09/83                -
02/84 Review Criteria in Management
:                    and Organization.
O V
HF01-43            As of 3rd Quarter FY-86
 
Milestones                        Original            Current        Actual Establish Technical Basis for a    09/83                -
07/84 Regulatory Position, Make Decision.
Prepare Staff Paper - Recommend-
* 09/84                                  -
ing the NRC Position on M&O at NPPs.
Develop Regulatory Package, If    09/85                *                -
Required.
Issue close-out memorandum to                          TBD              -
EDO.
*Close-out issue based on issuance of commission policy statement.
O O
HF01-44            As of 3ro Quarter FY-86
 
_      _                                      . = - -
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM O          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 i
Title ----------------                              Evaluation Criteria for SALP Reviews Work Authorization ---                              Memorandum to H. Thompson from H. Denton dated October 10, 1984, Human Factors Program Plan (HFPP)
Contract Title -------                              To Be Determined Contractor Name/ FIN --                            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 i
l                Milestones being reassessed in accordance with a memorandum for J. Funches from F. Rowsome dated June 6, 1986.
l HF'01-45        As of 3rd Quarter FY-86
 
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HF01-46            As of 3rd Quarter FY-86
 
GENERIC ISSUE MANAGEMENT CONTROL SYSTEM O Issue Number Issue Type Action Level                                  Office /Div/Br Task Manager                            TACS No.
l 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) 4  Contract Title -------          Human Factors Safety Technology Program, Project M-1 i  Contractor Name/ FIN --          PNL/B-2360 (M1)
Work Scope -----------          This issue will be resolved by accomplishing the following objectives: (1) develop guidelines which describe requi~ red 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 HRR reviewers of operating license applications; (4) train technical reviewers to effectively use workbook and improve
<                                    interview skills; and (5) revise and issue SRP revision.
O 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                                                          Oriainal                                                  Current                            Actual Develop Guidelines for OLs.                                        07/83                                                      11/83                              11/83 i        Develop Workbook for OLs.                                          09/83                                                      11/83                              11/83 Revise and issue a revision to 3
SRP Sections 13.1 l        Complete SRP and NUREGs                                            01/85                                                            -
02/85 draft changes HF01-47                                                    As of 3rd Quarter FY-86
 
Milestones                            Original        Current        Actual Complete V/I Analysis                06/85*              -              -
Complete preparation of              06/86*          06/85*            -
CRGR package Complete NRR review                  08/85*          08/85*            -
Resolve NRR comments and            09/85*          09/85*            -
transmit for NRR Director's review Complete NRR Director's review        11/85*          11/85*            -
Complete CRGR review                  01/86            01/86              -
l Issue draft SRP for public          02/86            02/86              -
l comment Public comment period ends          03/86            03/86              -
Resolve / incorporate public        05/86            05/86              -
comments Complete NRR review                  07/86            07/86              -
i Complete NRR Director reviev          08/86            08/86    ,
Complete CRGR review                  09/86            09/86              -
Issue revised SRP sections          11/86            11/86              -
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* Milestones will be revised after overall schedule has been reevaluated.
O, HF01-48          As of 3rd Quarter FY-86
 
T i        MSPP I-1:BLG
    )
MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 1 Issue                                                                                                            Issue                                                                                                  Action                                Task          TAC Number                                                                                                      , Type _                                                                                                    Level    Office /Dir./Er.          Manager        Number HF-02                                                                                                            Safety /                                                                                              L2        NRR/DHFT/MTB              B.L. Grenier    56465 High                                                                                                                    P.W. McLaughlin N.B. Le J.L. Koontz Subtask: MSPP:I.1
 
==Title:==
Survey of Current Maintenance Practices Work Authorization: MSPP/ Phase I approved for implementation by the EDO on January 11, 1985.
Contract
 
==Title:==
Survey of the Status of Maintenance in the U.S. Nuclear Power Industry
* Contractor Name/ FIN: Pacific Northwest Laboratory (PNL)/ FIN B2984 Work Scope:                                                                                                                                                                                                      This project will include a review and analysis of information needs and sources (e.g., AE00 analyses, INP0 evaluations, PAT inspection reports) and development of a classification scheme for describing the characteristics of current 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 performance 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 perfomance JUN 3 01966 ,
 
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 information 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 comment on March 28.
Task 2 - Review of Salem PM Program The task was completed as of February 20, 1986.
Task 3 - Questionnaire to Regional 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 comments March 27--one day prior to the due date.
Note: Data from the questionnaire were entered into the Statistical Package for Social Sciences (SPSS) Data Base at HARC for preparation of the " census" report and for performing the analyses. A determination needs to be made l whether these these data should be transferred to a dBase III file and I whether the results of analyses will also be entered onto a dBase file for l 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.
O JUN 3 0 1986 1
                                                                                          )
L
 
Task 5 - Site Surveys All trips have been completed and all final reports have been received and distributed. This task is complete.
Task 6 - Final Report The Project report was submitted in draft for NRC coments on March 28 as scheduled. The staff is currently preparing coments.
Technical Resolutions:
Milestones                          Original          Current    Actual Pre-Contract Develop Stater:nt 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 i
Prepare and submit plan for l              analysis of plant operations and maintenance performance data (Task 1)                      not scheduled                  11/15/85 Receive NRC comments on Task 1 analysis plan                not scheduled                  12/3/85 i
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O l                                                                                  JUN a u ud6 i
y---+ -r                        -
 
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 l      a) draft Not schedule        (Not b) final report
! Final report for Task 1 a) draft                    not scheduled          3/28/86 b) final                    not scheduled          4/25/86
                                              ~
i Task 2 - Salem P.M.
l l Gather, review data and assess l lesson learned on Salem Preven-l 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)NRCcomments                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 1
Receive draft questionnaire from                                              l l SRis                                9/20/85              2/14/86            ;
1                                                                              ,
Prepare Quest. Analysis Plan      not scheduled          12/19/85 1
Prepare Quest." Census" report    not scheduled          2/26/86 1                                                                            0' JUN 3 01986
                                  .e
 
O                                                          s 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 up.date 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
  .V            b c
final trip report transmitted to Lic.
not scheduled          11/22/85 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 c) 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) site visit                    not scheduled          9/20/85 i
a) draft trip report      not scheduled          11/11/85 b) 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 c    draft trip report    10/11/85              11/27/85 d    NRC coments          not scheduled          12/16/85 i                  e  final report          11/8/85                1/3/86 f  transmitted to Lic.
P.M.                  not scheduled          1/8/86 JUN 3 01986
 
Milestones                          Original        Current  Actual ANO-2 site visit                    10/25/85                  11/8/85 a    rough draft report        not scheduled              11/19/85 b    NRC input & response      not scheduled              11/22/85 c    draft trip report        11/1/85                    12/12/85 d    NRC coments              not scheduled              12/31/85 e) final report                11/29/85                  1/21/86 f) transmitted to Lic.
P.M.                      not scheduled              2/13/86 Turkey Pt-4 site visit              11/15/85                  12/6/85 a) rough draft report          12/13/85                  12/16/85 b    NRC coments              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 l Task 6 - Final Report l
, Prepare Project Report I
a) outline                      not scheduled              1/9/86 l      b) draft from PNL as            12/27/85                  3/28/86 l
TolT5ws:
Final Report Sections              Original        Current Executive Sumary                      3/28/86                  3/28/86 Section 1 - Introduction              2/21/86                    2/21/86 l Section 2 - Current Plant                          ,
l    Maintenance Practices              3/21/86                    3/21/86
: 1. Methodology
: 2. Organization and Administration
: 3. Facilities and Equipment O
JUN 3 01986 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 l                                        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 l
l i
i JUN 3 01986
  -<n.---.----,_------c,,,,                  , , , _                                  .,,_ _ ,-.- ,-- - - .-- _ -,., --                a,,    _ _                              _ - - _ _ - __
 
MSPP I-2:BLG MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 2 Issue      Issue        Action                            Task            TAC Number    Type        Level      Office /Dir./Br.      Manager        Number HF-02      Safety /    L2          NRR/DHFT/MTB          B. L. Grenier 56467 High                                          P.W. McLaughlin Subtask: MSPP:I.2
 
==Title:==
Maintenance Performance Indicators Work Authorization: MSPP/ Phase I approved for implementation by the ED0 on January 11, 1985.
Contract
 
==Title:==
- Statistical Analysis ,of Maintenance Performance Indicators (82980)
                          - Development of Maintenance Performance Indicators (B2986)
Contractor Name/ FIN:
Pacific  Northwest Pacific Northwest    Laboratory Laboratory    ((PNL)/
PNL)/      FIN 82980 FIN 82986 Work Scope:      Preliminary investigations of plant performance safety indicators have shown that multiple variables may be selected which in combination, indicate the effectiveness of a nuclear utility's maintenance practices. The development of mainte-nance safety indicators will build upon preliminary analyses of variables to derive a set of indicators which may be used to describe industry maintenance performance, compare plant maintenance effectiveness, and assess maintenance trends and patterns. This task will provide further baseline data as reference for industry progress in maintenance program im-I                  provement. Alternative data sources and methods will be evaluated for applicability to maintenance perfonnance assess-ment.
Affected Documents: Report to the EDO, April 1986 l
9 JUN 3 01986
 
v Status:
A survey of non-NRC sources to identify maintenance-related data was completed. The contractor has determined 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 perfonnance data has begun. Work on Tasks 3, 4, and 6 have been delayed in order to concentrate on finalizing 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 O Issuance of Contract and Start of Work 12/10/84                      12/10/84 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 Perfonnance Indicators Complete Task 2 - Evaluation          1/16/85                        1/16/85 of Indicators Prepared by the NRC Maintenance Indicators Task Force Provide NRC Coments to Industry      1/21/85                          1/21/85 (NUMARC)
I Approval of NUMARC Indicators                                        5/29/85 FIN 82986 Issue Request for Proposal and      8/12/85                        8/12/85 l
Start Work JUN 3 01986 I                                                                      .- - ..      .    .. -
 
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) dra f t                    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 maintenance performance across years I      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 9
JUN 3 01986
 
                      ~ .-                          .                      .                          .....            - - - - -                                                  - -          - _ -      .-
                                                                                                                      '                        Milestones (cont'd)                                                                  Original                                                Current            Actual Task 4 - Validate Models (a) Collect, sort and compile available data for 1985                                                  7/11/86 (1) NUREG-0020 Data (outa data)ge                    and availability                                                                                              3/28/86 (2) SALP Scores                                                                                                                          3/28/86 (3) 766 File (violations                                                                                                                  3/28/86 data)
(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 l
(c) Comparative analysis                                                            8/22/86                                                  On hold (d) Prepara report                                                                  8/22/86                                                  On hold l
I                                                                                                                                                                                                                      .
Task 5                      "On-Call Assistance"                                                                                            -
Task Assignment 1 - Prepare Maintenance Data 8ase (MDB)
Sumary 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 1                                                a) Standardize and analyze                                    4/4/86 1985 plant operations and maintenance performance data b) Prepare a report of trends and patterns for 1981-1985:
(1) for 11 measures                              4/11/86 (2)for20 measures                                5/2/86 c) Prepare report (1) draft                                        5/9/86 (2) final                                        5/23/86 O
JUN 3 01986
      ----,---><e
              ,w  --        - - , - - - , . . ,        .-n.,,.--w..w,,.,wn,      -~?,---~ w-e., e, ,- ,        v-,--,.--          -.m,,r----,-,-,-----,,,-m-- - - - - - - - - - - -                    m,--  , - -,,
 
Milestones                                Original  Current                      Actual Task 8 - MDB Software Enchancements a) Complete user-friendly, nemu-driven software program (1) Submit to NRC              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                7/20/85 O
t O
JUN 3 0 B86
 
    -6 O                MSPP I-3:BLG MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 3 Issue    Issue            Action                                          Task                                  TAC Number    Type              Level              Office /Dir./Br.            Manager                              Number HF-02      Safety /          L1                  NRR/DHFT/MTB                8 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 Information from Programs Related to the Maintenance and Surveillance Program Plan.
Contractor Name/ FIN: Support within Project 2, FIN B2984 Pacific Northwest Laboratory (PNL)
Work Scope:        The Maintenance Section personnel will monitor industry x'                                      progress and experience in developing strategies for improved maintenance. Coordination with INPO will be necessary to monitor the effectiveness of the INP0 plant evaluations, accreditation of training, and good practices in enhancing I                                        maintenance perfonnance in the nuclear industry. Implementa-tion of EPRI guidelines and the results of industry initiatives will be monitored and their impact assessed. In addition, industry activities such as standards development and data reporting will provide input to the NRC development of perfor-mance measurement methods, guidelines, and criteria for maintenance and surveillance.
Affected Documents: Report to the EDO, April 30, 1986
  \
JUN 3 01986 1
 
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 the EDO.
Problem / Resolution: None Technical Resolutions:
Milestones                            Original        Current        Actual Attend NUMARC/EDO Coordination        1/3/85                        1/3/85 Meeting Regarding the MSPP Attend NUMARC-INP0 Coordination        2/26/85                      2/26/85 Meeting in Atlanta Attend EPRI Seminar to Review          3/19-21/85                    3/19-21/85 EPRI Report on " Maintain-ability" Participate in EPRI Workshop on        4/16-17/85                    4/16-17/85 Maintenance Safety Related Equipment Attend ANS Maintenance Panel          6/12/85                      6/12/85 Meeting, Boston Attend 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 diagnostic tools JUN 3 01986
 
                                          -3 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 sumary 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 O
l l
O
                                                                    ,    JUN 3 01986
 
MSPP I-4:BLG MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 4 Issue      Issue      Action                          Task          TAC Number    Type        Level    Office /Dir./Br.      Manager      Number HF-02      Safety /    L1        NRR/DHFT/MTB          B.L. Grenier  40004 High Subtask: MSPP: 1.4
 
==Title:==
Participate in Standards Groups Work Authorization: MSPP/ Phase I approved for implementation by the E00 on January 11, 1985.
Contract
 
==Title:==
None                          ,,
Contractor Name/ FIN: N/A Work Scope:      Maintenance Section personnel participate in development of industry national standards for maintenance by IEEE, ASME, ANS and ANSI groupI. 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 committees 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" 1
JUN 3 01986
 
af Original    Current  Actual
            >=
Attend IEEE 3.3 Standards Ci>m-    2/6-7/85              2/6-7/85 mittee. Meeting to Devise Guidelines for Maintenance
                    " Good Practices" Review and Provide Coments on      4/19/85                4/19/85 IEEE Standards Comittee 3.2 Draft'(#338)" Periodic Surveillance Testing of NPG
                  ; Systems" Attend IEEE Standards Committee    4/30-5/1/85            4/20-5/1/85 Comittee 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 h
Q Comittee Meeting to Devise Guidelines for Maintenance
                      " Good Practices" Attend AS0C Meeting in              9/5/85                9/5/85 Knoxville, TN Attend ANSI /ASME NQA Sub-comittee on Operations Meeting (WG on Maintenance,                                        8 Repairing and Inservice Inspec-tion) to discuss Standard NQA-2 9/11/85                9/11/85 Attend IEEE WG 3.3 Meeting re:
i
                      " Maintenance Management"        10/22-25/85            cancelled
,'                Attend IEEE WG 3.3 Meeting re:
                    ." Maintenance Guidelines"        11/4-8/85              cancelled Attend IEEE WG 3.3 Meeting re:
                      " Goad 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 l v i
JUN 3 01966 i
 
t Milestones                      Original  Current Actual Prepare sumary on IEEE WG 3.3 activities for incorporation in MSPP Phase I repo-t to the EDO                          1/28/86          3/14/86 Incorporate results in MSPP Phase I report to the ED0    4/30/86 O
t I
O JUN 3 0 L986 1
i
 
l MSPP I-5:BLG MAlhiENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 5 Issue        Issue          Action                        Task          TAC Number      Type            Level      Office /Dir./Br. Manager      Number B.L. Grenier  56471 HF-02      Safety /        L1        NRR/DHFT/MTB 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 B2984 O                                            A number of diverse, multidisciplinary programs related to Q                      Work Scope:
maintenance are expected to produce technical data and information that will support the goals and objectives of the Maintenance and Surveillance Program (MSPP). Some of these programs are listed in Table 3.1 of the MSPP and are described in Section 3 of the MSPP. While the scope of these programs encompasses objectives other than maintenance, it is import'nt 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 placed on an "as required" basis. Generally, for each task placed under the contract, the contractor will review and assess interim and final reports, plans, products, or other information (e.g., attending industry meetings) from the standpoints of their relationship (including possible duplica-tion of effort) and possible use in MSPP activities and proposed NRC actions.
Affected Documents: Report to the EDO, April 30, 1986
                      >-                                                                            JUN 3 0 1986
 
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 Proaram Plan (QAPP)
 
==Contact:==
Drew Persinko The Comission paper forwarding the QAPP was approved by the Comission 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 NUREG/CR-4262, " Effects 1/24/86                        2/5/86 of Control System Failures on Transients and Accidents on BWRs" l
(Sept. 85) l 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)
O l                                                                            JUN 3 01986 1
 
A 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 sumary for incorporation 1/28/86                      2/5/86 in the MSPP Phase I report to the EDO Revisions to above sumary            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" O        Prepare sumary for incorporation 1/28/86 in MSPP Phase I report to the EDO 1/29/86 Technical Specifications Imorove-ment Project (TSIP)
 
==Contact:==
John Jankovich Review of TSIP final report          11/15/85                11/30/85 Prepare sumary for incorporation 1/28/86                      1/29/86 in MSPP Phase I report to the EDO Nuclear Plant Aging Research
 
==Contact:==
Tomy Le Review of NUREG/CR-4156: Operating 7/11/85                    7/11/85 Experience and Aging-Seismic Assessment of Electric Motors
      .* a JUN 30 D86
 
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 (MOVATS) to detect degradation, incorrect adjustment and other abnormalities in Motor-Operated Valves 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 l Prepare summary for incorporation 1/28/86                    2/28/86 into MSPP Phase I report to the EDO Effectiveness of Industry ALARA Programs
 
==Contact:==
Jennifer Koontz Review of RES report on              6/30/85                6/30/85 occupational dose reduction and ALARA (NUREG/CR-4254)
O JUN 3 0 1986
 
f
  ^s Milestones (cont'd)                Original  Current        Actual Comment on Comission paper on        11/8/85                  1/10/86 cooperation with INP0 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 sunrnary for incorporation 1/28/86                    1/16/86 in 1/18/86 MSPP Phase I report to the ED0 Eauipment Qualification - R.G. 1.89
 
==Contact:==
Tommy Le Currently, a multi-office (NRR/IE/ Regions) E.Q. inspection team is conducting a series of O          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 Surveillance Section (MSS) is monitoring these activities.
The following inspection reports on the plants listed below will be reviewed for findings                    .
pertinent to the Maintenance and Surveillance Program:
: 1. 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
\s      -
JUN 3 01986
 
l Milestones (cont'd)              Original  Current      Actual
: 7. Brunswick                10/15/85              12/18/85
: 8. Nine Mile Point          11/15/85              2/14/86
: 9. San Onofre              12/15/85  not received
: 10. Sequoyah or Browns Ferry 1/15/85    not received Prepare sumary for incorporation                          3/7/86 in MSPP Phase I report to the ED0 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                11/15/85 In-Plant Reliability Data Base for Nuclear Power Plant Com-ponents: Interim Report -
the Valve Component,"
December 1983.
Review of NUREG/CR-3154 "The      11/29/85              11/15/85 In-Plant Reliability Data Base for Nuclear Power Plant Com-ponents: Interim Report -
the Valve Component,"
December 1983.
Review of ORNL/TM-9066            12/13//85              11/15/85 "In-Plant Reliability Data Base for Nuclear Plant Components: A Feasible Study on Human Error Informatien," March 1984 Review of NUREG/CR-3831 "The'    '12/27/85  ,            11/15/85 In-Plant Reliability Data Base for Nuclear Plant Components: Interim Report - Diesel Generators, Batteries, Chargers and Inverters," January 1985 O
JUN 3 01986
 
i h                                                                                                                          _
Milestones (cont'd)                  Original  Current          Actual 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 summary 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 INP0 Accreditation                                    11 completed Observation Reports                                          as of 2/86 Review of Post-Accreditation                                    3 completed Training Review Reports                                      as of 2/86 Prepare summary for incorporation 1/28/86                        1/16/86 in MSPP Phase I report to the EDO Integration of NDE Reliability                            ,
and Fracture Mechanics Program
 
==Contact:==
Tomy Le Review of semi-annual program        12/13/85  not published progress report (NUREG/CR-4,458 Volume III)
Review of annual program progress 2/7/86                        3/28/86 report (NUREG CP 0058 Volume IV)
O JUN 3 01986
 
Milestones (cont'd)                  Original        Current      Actual Prepare sumary for incorpora-        not scheduled 3/28/86 tion in MSPP Phase I report to the EDO Interfacing Systems LOCA at BWRs - Generic Issue No. 105
 
==Contact:==
Tommy Le Comments on Task Action Plan        9/12/85                        9/12/85 Comments of 50W for contract        9/27/85                        9/27/85 in support of GI 105 Review of Interim Progress            1/17/86        Not received Report Prepare sumary for incorporation 1/28/86                          3/6/86 in MSPP Phase I report to the ED0 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 i
Complete Integration Plan          1/31/86                      2/14/86*
          *The MSS staff has completed its input and IE has document for concurrence.
O I
        ,                                                                            JUN 3 01986
 
e
        )
MAINTENANCE AND SURVEILLANCE PROGRAM PLAN RESOURCE UTILIZATION i
l Phase I - Project 5 "MSPP Integration With Other NRC Related Programs" A.      Staff Resources (in weeks) 6-Month Budget                                    Expenditure                        Percent of to 1/31/86                            Budget (10/1/85-3/31/86) 7.2 psw                                          6.6 psw                                91%
B.      Technical Assistance (in thousands)
Total Funds                      Expenditures                  Percent to 1/21/86                  Expended FIN            Available (FY85+86)
N/A I
I i  J JINi 3 011sb6
 
MSPP I-6:BLG MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 6 Issue      Issue      Action                          Task          TAC Number    Type        Level    Office /Dir./Br.      Manager        Number HF-02      Safety /    L1        NRR/DHFT/MTB          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 Maintenance Programs Contractor Name/ FIN: Pacific Northwest Laboratory (PNL)/ FIN 82550 Work Scope:      The objective of of this project is to assess the degree to which differing Japanese and U.S. approaches to the regulation and practice of nuclear power plant (NPP) maintenance may explain the difference in reactor trips / scrams and safety equipment availability between U.S. and Japanese plants. This project consists of three tasks:    (1) comparing and contrast-ing Japanese and U.S. NPP preventive maintenance programs, (2) assessing Japanese maintenance organizational and management practices, and (3) identification of the difference in Japanese
                  - U.S. NPP operating experience and factors which may account for the differences.
Affected Documents: Report to the EDO, April 30, 1986 1
i l
l O
JUN 3 01986
 
O            Status:    This project is complete. A " draft" summary of the results has been prepared for incorporation into the fiSPP Phase I report to the EDO.
Note: This project was started during development of the MSPP because of the opportunity to exchange information on the subject of maintenance with Japanese at the time.
Problem / Resolution: None                                              ,
Technical Resolutions:
Milestones                                      Original Current  Actual Develop Statement of Work                      2/1/84            2/1/84 Obtain HFRG Approval and Forward to Contractor to Start Work Complete Task 1 - Assess                        4/15/84            5/1/84 Differences in Operating Experience Complete Task 2 - Assess                        4/15/85            5/31/85 I (v'~N 4                  Organization and Management
      ~
Complete Task 3 - Compare / Con-                4/15/85            4/15/85
              +
trast PM programs Appendix B                                      4/30/85            5/31/85 Prepare report of U.S.                          4/15/85            4/30/85 operating experience (additional task)
Printing NUREG/CR 3883                                5/31/85          '
7/6/85 NUREG/CR 3883P                                7/31/85            8/15/85 Prepare summary for incorporation 1/28/86                          1/29/86 in the MSPP Phase I report to the EDO Incorporate results in MSDP                    4/30/86 Phase I report to the EDO O
JUN 3 0 E66
 
MSPP I-7:BLG MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 7 Issue      Issue      Action                        Task          TAC Number    Type        Level      Office /Dir./Br. Manager        Number HF-02      Safety /    L2        NRR/DHFT/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 E00 on January 11, 1985.
Contract
 
==Title:==
Determination of Job-Relevant Maintenance Personnel Qualifications.
Contractor Name/ FIN: To be detemined 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 supervisofy maintenance personnel. The pertinent education and vocational training backgrounds as well as any i                  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-nel.
l The results will provide information about the present level l                  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 detemine format, content, and use of job performance aids as means of improving maintenance personnel performance.,
j Affected Documents: Report to the EDO, April 30, 1986 O
JUN 3 01986 T
 
r3                                                    2 O
Status:    No contractual support will be sought in Phase I. Staff will continue to monitor the INP0 Accreditation Program and industry standards group activities in this area to assess their initiatives.
Problem / Resolution: Given limited resources in view of ongoing industry efforts, no specific staff action is planned in Phase I.
NOTE:        In the earlier version of the MSPP, this task was to have been supported (funodd) by RES but was dropped by PES as a part of thei- discontinuance of su; port to the numan factors areas.
Technical Resolutions:
Milestones                                  Original                Current  Actual Develop Draft Statement of Work              6/30/85                -      6/10/85 Prepare suninary of assessment              1/28/86                          1/16/86 of industry initiatives for incorporation in the MSPP Phase I report to the EDO l
e.
JUN 3 01986
                                      . _ . , .              ~ - - . _ . ..              _ - _ . , - _ -    , .
 
MSPP I-8:BLG MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 8 Issue      Issue      Action                        Task          TAC Number    Type        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 ED0 on January 11, 1985.
Contract
 
==Title:==
Human Factors Aspects of Ultrasonic Testing / Inservice Inspection Tasks Contractor N&me/ FIN: Pacific Northwest Laboratory (PNL)/ FIN 82983 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 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 0
JUN 3 01986
 
b O                                                      )
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      ictual 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
                    - Site Visit to the                                      cancelled (O)      Task EPRI NDE Training Center 11/25/85 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 b second draft                  not scheduled                2/10/86 e 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 O
JUN 3 01986
 
MSPP I-9:BLG MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 9 Iscue          Issue              Action                              Task        TAC Number        Type                Level          Office /Dir./Br. Manager      Number HF-02        Safety /            L1              NRR/DHFT/MTB        B.L. Grenier 57269 High                                          D. Persinko Subtask: MSPP:1.9
 
==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 (AE0D) issued a special study report describing a number of events that resulted from human error in removing equipment from service or restoring equipment following maintenance that involved the wrong unit or wrong train of equipment being rendered unavailable. Although the scope of the study was narrow, AE0D found that 19 out of 27 events identified resulted from human error during maintenance and surveillance testing. AEOD considered such events to be examples of events that could have high safety significance due to potential loss of safety system functions.
As part of the project, the Maintenance Section will identify existing practices that may lead to human errors involving wrong unit / wrong train and to 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 O
JUN 3 01986
 
t                                                                                                                    .
Y Status: The final report has been issued (ref: memo Russell to Denton dated March 13, 1986). The program sumary 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 l
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 80ttom
: 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 Ocoree and                10/25/85                                                    10/25/85 McGuire i
: 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 7.a. Site Visit to Turkey Pt.                  11/22/85                                                    11/22/85 (and Browns Ferry)*
l                      b. Prepare Trip Report                      1/31/86                                                    3/6/86 Issue Draft Report for                          11/15/85                                                    3/3/86 Management Review l
l JUN 3 01986 1
 
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 Resul.ts into  4/30/86 EDO Report
* Browns Ferry cancelled 4
O JUN 3 0 1986
 
A MSPP I-10:BLG fi d                                                                                                          -
MAINTENANCE AND SURVEILLANCE PF6 GRAM PLAN Phase I/ Task 10 Issue      Action                          Task            TAC Issue Number    Type        Level      Office /Dir./Br. Manager          Number HF-02      Safety /    L1        NRR/DHFT/MTB        B.L. Grenier 57270 -
High                                      J.P. Jankovich Subtask: MSPP:1.10
 
==Title:==
Development of an NRC Model Maintenance Program Work Authorization: MSPP/ Phase I approved for implementation by the ED0 on January 11, 1985.-
Contract
 
==Title:==
None Contractor Name/ FIN: N/A s          Werk Scope:      The mainten:r. e redel to be developed will serve as a s
1 conceptual framework to allow a common interpretation for the s>
s role of maintenance between the NRC, the industry, and the standardization groups. The modelling approach will be similar to the instructional systems development used in training by being general for overall acceptance and by providing a common basis to make plant-specific programs comparable. The model will be used to develop the site survey protocol. The modelling approach will include (1) the MSPP definition of maintenance, i.e., preventive, corrective, surveillance, organization, support, etc.; (2) the alignment of safety goals with the goals of the maintenance program; (3) means to compare plant-specific programs with each other for the industry assessment in Phase I of the MSPP.
Affected Documents: Report to the EDO, April 1986 l
l l
JUN 3 019S6
 
r 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 O
O JUN 3 01986
 
l
(^s            MSPP I-11:BLG L)
MAINTENANCE AND SURVEILLANCE PROGRAM PLAN Phase I/ Task 11 Issue      Action                          Task          TAC Issue Number    Type        Level      Office /Dir./Br. Manager        Number HF-02      Safety /    L1        NRR/DHFT/MTB        B.L. Grenier  56466 High                                      J.L. Koontz Subtask: MSPP:1.11
 
==Title:==
Preparation of the MSPP, Phase I Report to the EDO Work Authorization: MSPP/ Phase I approved for implementation by the EDO 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 Scoce:      Phase I of the Maintenance and Surveillanc: Drogram Plan consists of a minimum of 0 projects and will involve ii "s                                interactions with at least 10 other related NRC programs and related industry programs. Results from all c' those projects and programs will produce an enannous amount o: Jata and information that will need to be sumarized 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 l                                  importance in preparing and writing the Phase I Report is the i                                  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 l
O
              -                                                                          JUN 3 01E6
 
Status: The MSS staff is continuing to write the report to the EDO on the R5 F Fhase I results and it is expected to be completed on time.
Problem / Resolution: None Technical Resolutions:
Milestones:                    Original      Current        Actual Prepare 50W to c.btain          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 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 Recomendations O
l l
                                        .                                    JUN 3 0 1986
 
l l
l l
VI. Appendices A. Sumary of Important Activities 80%
Related to the MSPP B. Regulatory Perspectives        95%
7 i                                                    ,
f O
JUN 3 01986
                                                                  /}}

Latest revision as of 19:42, 7 December 2024

Gimcs Third Quarter FY86 Update
ML20204J390
Person / Time
Issue date: 07/31/1986
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20204J358 List:
References
NUDOCS 8608110077
Download: ML20204J390 (300)
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