ML18054A697

Forwards Details of Document Search,Including Closure Dates Where Readily Available,In Response to 890414 Request for Status of TMI Action Plan Items

ML18054A697
Person / Time
Site:	Palisades
Issue date:	04/18/1989
From:	BERRY K W CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TASK-***, TASK-TM NUDOCS 8904260055
Download: ML18054A697 (7)

Text

. '

• consumers Power POWERINli lllllCHlliAN'S PllOlillESS General Offices: 1945 West Parnall Road, Jackson, Ml 49201 o (517) 788-1636 April 18, 1989 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

• DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -RESPONSE TO REQUEST FOR STATUS OF TMI ACTION. PLAN ITEMS Kenneth W Berry Director Nuclear Licensing NRC letter dated April 14, 1989 requested Consumers Power Company to review the status of implementation of TMI Action Plan Items at our Palisades Plant and return the information by April 18, 1989. Based on the allotted time for verification, the TMI Action Plan Items indicated as closed by the NRC were verified closed by way of a document search. A physical walkdown of plant systems was not conducted.

The enclosure to the April 14, 1989 letter identified six open items, II.D.1.1, II.D.1.2.A, II.D.1.2.B, II.D.1.3, II.F.2.4 and MPA-B083.

Of these six we found items II.D.1.3 and MPA-B083 to still be open. The attached enclosure provides the details of our document search including closure dates where readily available.

Kenneth W Berry Director, Nuclear Licensing CC Administrator, Region III, USNRC NRC Resident Inspector

-Palisades Attachment . 7 MULTI-PLANT ISSURE NUMBER ACTION NO, I.A.1.1.1

• I.A.1.1.2

• I.A.1.1.3

• I.A.1.1.4 I.A.1.2 I.A.1.3.1 I.A.1.3.2 I.A.2.1.1 I.A.2.1.2 I.A.2.1.3 I.A.2.1.4 I.A.2.1.S I.A.2.3 I.A.3.1.1 I.A.3.1.2 I.A.3.1.3.A I.A.3.1.3.B

• I.B.1.2 I.C.1.1 I.C.1.2.A I.C.1.2.B I.C.1,3.A I.C.1.3.B I.C.2 I.C.3 I.C.4 I.c.s I.C.6 *I.C.7,1 *I.C.7.2 *I.C.S FOOl F002 F002 F003 F004 .F004 FOOS FOOS F006 F007 I.D.1 (See FOOS & F071) I.D.2.1 F009 TM! ENCLOSURE A ISSUE TITLE LICENSEE IMPLEMENTATION STATUS DATE SHIFT TECHNICAL ADVISOR -ON DUTY * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• 11/SO SHIFT TECHNICAL ADVISOR -TECH SPECS ******************************* ******************************

• SHIFT TECHNICAL ADVISOR -TRAINED PER LL CAT B .................... , .............................. . SHIFT TECHNICAL ADVISOR -DESCRIBE LONG TERM PROGRAM ********************** ***********************

SHIFT SUPERVISOR RESPONSIBILITIES

• • • • • • • • • • • • • .****************************************************

SHIFT MANNING -LIMIT OVERTIMES

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • , * , *****************************

SHIFT MANNING -MIN SHIFT CREW ***************

*********************************** , ****************

IMMEDIATE UPGRADING OF RO & SRO TRAINING AND QUAL, -SRO EXPER ************************************

IMMEDIATE UPGRADING OF RO & SRO TRAINING AND QUAL. -SRO'S BE RO'S lYR ..........................

.. IMMEDIATE UPGRADING OF RO & SRO TRAINING AND QUAL. -3 MO. TRAINING *******************************

IMMEDIATE UPGRADING OF RO & SRO TRAINING AND QUAL. -MODIFY TRAINING ******************************

IMMEDIATE UPGRADING OF RO & SRO TRAINING AND QUAL. -FACILITY CERTIF **************** *************

ADMINISTRATION OF TRAINING PROGRAMS ***************************************************************

'REVISE SCOPE & CRITERIA FOR LICENSING EXAMS -INCREASE SCOPE *************************** **********

REVISE SCOPE & CRITERIA FOR LICENSING EXAMS -INCREASE PASSING GRADE,,,,,,,,,,,, ******************

REVISE SCOPE & CRIT. FOR LIC. EXAMS -SIMULATOR PLANTS WITH SIMULATORS

REVISE SCOPE & CRIT. FOR LIC. EXAMS -SIMULATOR

-OTHER PLANTS ************************************

EVALUATION OF ORGANIZATION

& MANAGEMENT

SHORT-TERM ACCIDENT & PROCEDURES REVIEW -SB LOCA *************************************************

SHORT-TERM ACCID. & PROCEDURES REV, -INADEQ. CORE COOL, REANAL. GUIDELINES

SHORT-TERM ACCID. & PROCEDURES REV. -INADEQ. CORE COOL. REVISE PROCEDURES

• • • • • • • • • • • • • • • • • • .*****

SHORT-TERM ACCID. & PROCEDURES REV -TRANSIENTS

& ACCDTS. REANAL GUIDELINES (PROC. GEN. PKG.) .... . SHORT-TERM ACCID. & PROCEDURES REV, -TRANSIENTS

& ACCDRS. REVISE PROCEDURES (UPGRADED EOP' S) .... . c 2/S2 2/Sl H/SO 3/S2 3/S2 11/SO 11/80 11/SO 12/S2 11/SO 11/SO 11/SO 11/SO c c *c 11/SO 5/S4 12/S6 5/S4 12/S6 SHIFT & RELIEF TURNOVER PROCEDURES

**************************

11/SO SHIFT-SUPERVISOR RESPONSIBILITY

11/SO CONTR.OL-ROOM ACCESS ***********************************

o.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

11/80 FEEDBACK OF OPERATING EXPERIENCE,, ************************

,,.,.,,., ******************

,,,..........

3/82 VERIFY CORRECT PERFORMANCE OF OPERATING ACTIVITIES................................................

3/S2 -NSSS VENDOR REV. OF PROC -LOW POWER TEST PROGRAM *************************************************

NSSS VENDOR REV. OF PROC -POWER ASCENSION

& EMER. PROCS ****** , , , ** , * , *********

**** , * , ***********

PILOT MON OF SELECTED EMERGENCY PROC FOR NTOLS ** , ****** , ***************************************.**

CONTROL-ROOM DESIGN REVIEWS (ENTER DATA FOR MPA FOOS & MPA F-071) ****************************.***

PLANT-SAFETY PARAMETER DISPLAY CONSOLE -DESCRIPTION

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • c c c c c '. *

• MULTI-PLANT ISSURE NUMBER ACTION NO. I.D.2.2 I.D.2.3 *I.G.1.1 *I.G.1.2 *I.G.1.3 II.B.1.1 II.B.1.2 II.B.1.3 II.B.2.1 *II.B.2.2

• II.B.2.3

• II.B.2.4

• II.B.3.1

• II.B.3.2

• II.B.3.3

• II.B.3.4 II.B.4.1 *II.B.4.2.A

• II.B.4.2.B II.D.1.1 *II.D.1.2.A

• II.D.1.2.B II.D.1.3 *II.D.3.1

• II.D.3.2 F009 F009 FOlO FOlO F011 F012 F013 F013 F013 F014 *II.E.1.1.1 F015 (SEE NOTE 1) * *II.E.1.1.2 F015 (SEE NOTE 2) II.E.1.1.3 F015 (SEE NOTE 3) ISSUE TITLE LICENSEE IMPLEMENTATION STATUS PLANT-SAFETY PARAMETER DISPLAY CONSOLE -INSTALLED

PLANT-SAFETY PARAMETER DISPLAY CONSOLE -FULLY IMPLEMENTED

TRAINING DURING LOW-POWER TESTING -PROPOSE TESTS ********************************************

• ***** c c c TRAINING DURING LOW-POWER TESTING -SUBMIT ANAL. & PROCS. **.......................................

C TRAINING DURING LOW-POWER TESTING -TRAINING & RESULTS............................................

C DATE REACTOR-COOLANT SYSTEM VENTS -DESIGN VENTS .*...**....*...***..********...*****....*....*.*..**.*.

11/80 REACTOR-COOLANT SYSTEM VENTS -INSTALL VENTS (LL CAT B) ............................................

11/83 REACTOR-COOLANT SYSTEM VENTS -PROCEDURES..........................................................

11/83 PLANT SHIELDING

-REVIEW DESIGNS ******************************************************************

11/80 PLANT SHIELDING

-CORRECTIVE ACTIONS TO ASSURE ACCESS.............................................

C PLANT SHIELDING

-PLANT MODIFICATIONS (LL CAT B)..................................................

4/83 PLANT SHIELDING

-EQUIPMENT QUALIFICATION-NOT TRACKED AS A TM! ACTION ITEM.......................

3/83 POSTACCIDENT SAMPLING -INTERIM SYSTEM ************************************************************

10/81 POSTACCIDENT SAMPLING -CORRECTIVE ACTIONS *************************************.

• *************

• ***** c POSTACCIDENT SAMPLING -PROCEDURES

• * * * * *. * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• C POSTACCIDENT SAMPLING -PLANT MODIFICATIONS (LL CAT B)............................................

2/85 TRAINING FOR MITIGATING CORE DAMAGE -DEVELOP TRAINING PROGRAM ************************************

12/82 TRAINING FOR MITIGATING CORE DAMAGE -INITIAL.....................................................

12/82 TRAINING FOR MITIGATING CORE DAMAGE _ -COMPLETE ** * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• 12 / 8 2 'RELIEF & SAFETY VALVE TEST REQUIREMENTS

-SUBMIT PROGRAM ******************************************

RELIEF & SAFETY VALVE TEST REQUIREMENTS

-COMPLETE TESTING ****************************************

c c RELIEF & SAFETY VALVE TEST REQUIREMENTS**

PLANT SPECIFIC REPORT...................................

C RELIEF & SAFETY VAVLE TEST REQUIREMENTS

-BLOCK-VALVE TESTING.....................................

O** VALVE POSITION INDICATION

-INSTALL DIRECT INDICATIONS OF VALVE POS **********

11/20 VAL VE POST ION INDICATION

-TECH SPECS *************************************************************

AFS EVALUATION-ANALYSIS

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • .*****

c NA AFS EVALUATION-SHORT TERM MODS ***** , *** ,, **** , ** ,,, ***** *.*.........................................

8/84 AFS -LONG TERM MODS * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• 8 / 84 NOTE 1 -THE ITEM LISTED IS FROM NUREG-0737, ENCLOSURE 2 AND IS APPLICABLE TO NTOLS'S ONLY NOTE 2 -THE ITEM LISTED IS FOR ALL PLANTS (OPERATING REACTORS AND NTOL'S) NOTE 3 -.THE ITEM LISTED IS FOR ALL PLANTS (OPERATING REACTORS AND NTOL'S) ** 0 -Block valves to be installed 1990 refueling outage. TM! ENCLOSURE A *

• MULTI-PLANT ISSURE NUMBER ACTION NO. II.E.1.2.1.A II.E.1.2.1.B F016 II.E.1.2.2.A

• II.E.1.2.2.B

• II.E.1.2.2.C F017 *II.E.3.1.1

• II.E.3.1.

2 II.E.4.1.1

• II.E.4.1.

2 *II.E.4.1.3 F018 II.E.4.2.1-4

• II.E.4.2.5.A

• II.E.4.2.5.B II.E.4.2.6 F019 II.E.4.2.7 F019 *II.E.4.2.8

• II.F.1.1

• II.F.1.2.A

• II.F.1.2.B

• II. F .1. 2.C *II.F .1.2.D *II.F .1. 2.E *II.F.1.2.F

• II.F.2.1

• II.F.2.2 F020 F020 F021 F022 F023 F024 F025 *II.F.2.3 F026 *II.F.2.4 F026 *II.G.1.1

• II.G.l. 2 II.K.1 (Oper. Reactors Only) TMI ENCLOSURE A ISSUE TITLE LICENSEE IMPLEMENTATION STATUS DATE AFS INITIATION

& FLOW-CONTROL GRADE *******************************************

• * * * * * * * * * * * * * * * * * *

• 11/80 AFS INITIATION

& FLOW -SAFETY GRADE **************************************************************

12/82 AFS INITIATION

& FLOW -FLOW INDICATION CONTROL GRADE *********************************************

11/80 AFS INITIATION

& FLOW -LL CAT 0 A TECH SPECS. * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• NA AFS INITIATION

& FLOW -SAFETY GRADE **************************************************************

12/82 EMERGENCY POWER FOR PRESSURIZER HEATERS -UPGRADE POWER SUPPLY ************************************

11/80 EMERGENCY POWER FOR PRESSURIZER HEATERS -TECH SPECS **********************************************

11/80 DEDICATED HYDROGEN PENETRATIONS

-DESIGN *************************************

• • * *.* * * * * * * * * * * * * * * * *

• C DEDICATED HYDROGEN PENETRATIONS

-REVIEW & REVISE H2 CONTROL PROC *********************************

DEDICATED HYDROGEN PENETRATION

-INSTALL **********************************************************

CONTAINMENT ISOLATION DEPENDABILITY

-IMP. DIVERSE ISOLATION

CONTAINMENT ISOLAT. DEPENDABILITY

-CNTMT PRESS. SETPT. SEECIFIY PRESS ****************************

CONTAINMENT ISOLATION DEPENDABILITY

-CNTMT PRESSURE SETPT. MODS **********************************

CONTAINMENT ISOLATION DEPENDABILITY

-CNTMT PURGE VALVES ******************************************

CONTAINMENT ISOLATION DEPENDABILITY

-RADIATION SIGNAL ON PURGE VALVES ****************************

CONTAINMENT ISOLATION DEPENDABLITY

-TECH SPECS ***************************************************

ACCIDENT -MONITORING

-PROCEDURES

ACCIDENT -MONITORING

-NOBLE GAS MONITOR *********************************************************

ACCIDENT -MONITORING

-IODINE/PARTICULATE SAMPLING ***********************************************

ACCIDENT -MONITORING

-CONTAINMENT HIGH-RANGE MONITOR ****************

.' ***************************

ACCIDENT -MONITORING

-CONTAINMENT PRESSURE ******************************************************

ACCIDENT -MONITORING

-CONTAINMENT WATER LEVEL ********************************

• ******************

ACCIDENT -MONITORING

-CONTAINMENT HYDROGEN *** * **************************************************

c 12/81 11/80 4/84 4/84 4/84 4/84 c c 10/81 10/81 12/82 8/83 8/83 8/83 INSTRUMENTATION FOR DETECT. OF INADEQUATE CORE COOLING -PROCEDURES

11/80 INSTRUMENTATION FOR DETECT. OF CORE COOLING -SUBCOOL METER............................

C INSTRUMENTATION FOR DETECT. OF INADEQUATE CORE COOLING -DESC. OTHER..............................

C INSTRUMENTATION FOR DETECT. OF INADEQUATE CORE CLING INSTLL ADD'L INSTRUMENTATION.................

C POWER SUPP. FOR PRESSURIZER RELIEF, BLOCK VALVES & LEVEL IND. -UPGRADE ***************************

11/80 POWER SUPP. FOR PRESSURIZER RELIEF,*BLOCK VALVES & LEVEL IND. -TECH SP...........................

C *

• MULTI-PLANT ISSURE NUMBER ACTION NO. IE BULLETINS 05, 79-06, *II.K.1.5

• II.K.1.10

• II.K.1.20

• II.K.1.21

• II.K.1.22

• II.K.1.23

• II.K. 2. 2 *II.K.2.8 II.K.2.9 F027 II.K.2.10 F028 *II.K.2.11 F029 F030 II.K.2.14 F031 II.K.2.15 II.K.2.16 F032 II.K.2.17 F033 II.K.2.19

• II.K.2.20 F035 *II.K.3.1.A F036 *II.K,3.1,B II.K.3,2 F037 II.K.3.3 F038 II.K.3.5.A F039 II.K.3,5,B F039 II.K.3. 7 II.K.3.9 F040 II.K.3.10 F041 II.K.3.11 II.K.3.12.A II.K.3.12.B F042 II.K.3.13.A F043 II.K,3,13.B F043 TMI ENCLOSURE A ISSUE TITLE LICENSEE IMPLEMENTATION STATUS DATE 79-08.........

• .* * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• 3/80 IE BULLETINS

-REVIEW ESF VALVES. * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• NA IE BULLETINS

-OPERABILITY STATUS ****************************************

........................

NA IE BULLETINS

-PROMPT MANUAL REACTOR TRIP. * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• NA IE BULLETINS

-AUTO SG ANTICIPATORY REACTOR TRIP..................................................

NA IE BULLETINS

-AUX. HEAT REM SYSTEM, PROC. * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• NA IE BULLETINS

-RV LEVEL, PROCEDURES.

• * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• NA ORDERS ON B&W PLANTS -PROCEDURES TO CONTROL AFW IND OF res.......................................

NA ORDERS ON B&W PLANTS -UPGRADE AFW SYSTEM *********************************************

***********

ORDERS ON B&W PLANTS -FEMA ON ICS ************************

***************************************

ORDERS ON B&W PLANTS -SAFETY-GRADE TRIP ..........................

• ..............................

.. ORDERS ON B&W PLANTS -OPERATOR TRAINING ****************

• '* ****************************************

ORDERS ON B&W PLANTS -THERMAL MECHANICAL REPORT (CE & W PLANTS ALSO) *****************************

ORDERS ON B&W PLANTS -LIFT FREQUENCY OF PORV Is & sv Is ********************************************

NA NA NA NA 8/84 . NA ORDERS ON B&W PLANTS -EFFECTS OF SLUG FLOW. * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• NA ORDERS ON B&W PLANTS -RCP SEAL DAMAGE. * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• NA ORDERS ON B&W PLANTS -VOIDING IN RCS (CE & W PLANTS ALSO) ****************************************

10/83 BENCHMARK ANALYSIS OF SEQUENTIAL AFW FLOW TO ONCE THROUGH STM GENERATOR...........................

NA ORDERS ON B&W PLANTS -SYSTEM RESPONSE TO SB LOCA. * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• NA B&O TASK -FORCE -AUTOMATIC PORV ISOLATION DESIGN **************************************************

FINAL RECOMMENDATIONS, B&O TASK FORCE -AUTO PORV ISO TEST/INSTALL

B&O TASK FORCE -REPORT ON PORV FAILURES **********************************************************

B&O TASK FORCE -REPORTING SV & RV FAILURES AND CHALLENGES

B&O TASK FORCE -AUTO TRIP OF RCP'S PROPOSED MODIFICATIONS

B&O TASK FORCE -AUTO TRIP OF RCP 'S MODIFICATIONS

B&O TASK FORCE -EVALUATION OF PORV OPENING PROBABILITIES

NA NA 10/83 6/82 7/83 7/83 NA ' B&O TASK FORCE -PID CONTROLLER MODIFICATION

• • • • • • • • • • • • • • , ***** , * , * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• NA B&O TASK FORCE -PROPOSED ANTICIPATORY TRIP MODIFICATIONS.........................................

NA B&O TASK FORCE -JUSTIFY USE OF CERTAIN PORV. * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• NA B&O TASK FORCE -ANTICIPATORY TRIP ON TURBINE TRIP PROPOSED MODS..................................

NA B&O TASK FORCE -ANTICIPATORY TRIP ON TURBINE TRIP INSTALL MODS...................................

NA B&O TASK FORCE -HPCI & RCIC SYSTEM INITIATION LEVELS ANALYSIS....................................

NA B&O TASK FORCE -HPCI & RCIC INITIATION LEVELS MODIFICATION........................................

NA *

• MULTI-PLANT ISSURE NUMBER ACTION NO. *II,K.3.14 F044 II.K.3,15 F045 II.K.3.16A F046 II.K.3.16.B F046 Il,K,3.17 F047 II.K.3.18.A F048 II.K.3.18,B F048 II.K.3.18.C F048 *II.K.3.19 F049 *II.K.3.20 II.K.3.21.A F050 II.K.3.21.B F050 II.K.3.22.A F051 II.K.3,22.B F051 II,K,3,24 FOS2 II.K.3.2S.A II.K.3,2S.B F053 II.K.3.27 F054 II.K.3.28 FOSS *II,K,3,29 FOS6 II.K.3,30.A Il,K,3,30,B FOS7 Il,K,3,30,C II.K.3.31 FOSS *II.K.3.40

• II.K.3,43 II.K.3.44 FOS9 II.K.3,4S F060 II.K.3.46 F061 *II.K.3.57 F062 III.A.1.1 TM! ENCLOSURE A ISSUE TITLE LICENSEE IMPLEMENTATION STATUS DATE B&O TASK FORCE -ISO CONDENSER ISOLATION ON HIGH RAD..............................................

NA B&O TASK FORCE -MODIFY HPCI & RCIC BRK DETECTION CIRCUITRY.......................................

NA B&O TASK FORCE -CHALLENGE

& FAILURE OF RELIEF VALVES STUDY.......................................

NA B&O TASK FORCE -CHALLENGE

& FAILURE OF RELIEF VALVES MODIFICATIONS

NA B&O TASK FORCE -ECC SYSTEM OUTAGES * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * . * * * * * * * .

• NC B&O TASK FORCE -ADS ACTUATION STUDY ************************ , * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• NA B&O TASK FORCE -ADS ACTUATION PROPOSED MODIFICATIONS.............................................

NA B&O TASK FORCE -ADS ACTUATION MODIFICATIONS.

• * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• NA B&O TASK FORCE -INTERLOCK RECIRCULATORY PUMP MODIFICATIONS

B&O TASK FORCE -LOSS OF SVC WATER AT BRP *********************************************************

NA NA B&O TASK FORCE -RESTART OF CSS & LPCI LOGIC DESIGN. * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• NA B&O TASK FORCE -RESTART OF CSS & LPCI LOGIC DESIGN MODIFICATIONS.................................

NA B&O TASK FORCE -RCIC SUCTION VERIFICATION PROCEDURES.............................................

NA B&O TASK FORCE -RCIC SUCTION MODIFICATION

,,,,;,,,,...............................

NA B&O TASK FORCE -SPACE COOLING FOR HPCI/RCI LOSS OF AC POWER.......................................

NA B&O TASK FORCE -POWER ON PUMP SEALS PROPOSED MODIFICATIONS.......................................

NA B&O TASK FORCE -POWER ON PUMP SEALS MODIFICATIONS................................................

NA B&O TASK FORCE -COMMON REFERENCE LEVEL FOR BWRS *** , ****** , ** , , * , * , ********* , ** , , , * , , * , ****** , , , *

• NA B&O TASK FORCE -QUALIFICATION OF ADS ACCUMULATORS

• • * * * * * *

• NA B&O TASK FORCE -PERFORMANCE OF ISOLATION CONDENSERS

• • • , * , , , ******** , , *** , , , * * * * * * * * * * * * * * * * * * * * *

• NA B&O TASK FORCE -SCHEDULE FOR OUTLINE OF SB LOCA MODEL. * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• C B&O TASK FORCE -SB LOCA MODEL, JUSTIFICATION

• • • , * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• C B&O TASK FORCE -SB LOCA METHODS NEW ANALYSES *** *, * * * .. * * * * * * * * * * * * * * * * * * * * * * * * * * * * .. * * .. .. .. * * .. .. C B&O TASK FORCE -COMPLIANCE WITH CFR 50, 46 , .. * * * .. .. * * * * .. .. * * * * * * * .. * * * .. * * * * * * * * .. * * * .. .. .. ..

• *

• NA B&O TASK FORCE -RCP SEAL DAMAGE -COVERED BY II.K,2,16 AND II.K,3.25,,,,,,,,,,,,,,,,,,,,.,, ****** B&O TASK FORCE -EFFECTS OF SLUG FLOW -COVERED BY II.K.2.15

B&O TASK FORCE -EVALUATE TRANSIENT WITH SINGLE FAILURE .......................................... . NA NA NA B&O TASK FORCE -ANALYSES TO SUPPORT..............................................................

NA .RESPONSE TO LIST OF CONCERNS FROM ACRS CONSULTANT.................................................

NA IDENTIFY*WATER SOURCES PRIOR TO MANUAL ACTIVATION OF ADS..........................................

NA EMERGENCY PREPAREDNESS, SHORT TERM, ******************* , , ******************* , *** , ** , * * * * * * * * * * * * * *

• C *

• __J MULTI-PLANT ISSURE NUMBER ACTION NO. III.A.1.2.1 III.A.1.2.2 (SEE F063, F064, F065) III.A.1.2.3 (SEE F063, F064, F065) III.A.2.1 .F067 III.A.2.2 F068 *III.D.1.1.1

• III.D.1.1.2 III.D.3.3.1 III.D.3.3.2 F069 III.D.3.4.1 F070 *III.D.3.4.2 F070 *III.D.3.4.3 MPA-FOOS FOOS MPA-F063 F063 MPA-F064 F064 MPA-F065 F065 MPA-F071 F071 MPA-B072 B072 MPA-B083 B083 67.4.1 GOOl ** ISSUE TITLE LICENSEE IMPLEMENTATION STATUS UPGRADE EMERGENCY SUPPORT FACILITIES

-INTERIM TSC OSC & EOF **************************************

UPGRADE EMERGENCY SUPPORT FACILITIES-DESIGN-INCORP.

INTO F063/F064/F065

UPGRADE EMER SUPPORT FACILITIES

-MODS INCORPOR.

INTO F063, F064 & F065, **************************

UPGRADE PREPAREDNESS

-UPGRADE EMERGENCY PLANS TO APP. E. 10 CFR 50 *********************.*********

UPGRADE PREPAREDNESS

-METEOROLOGICAL DATA *********************** , ******** ,,,., ****.*** , **********

PRIMARY COOLANT OUTSIDE CONTAINMENT

-LEAK REDUCTION

PRIMARY COOLANT OUTSIDE CONTAINMENT

-TECH SPECS **************************************************

INPLANT RAD. MONIT. -PROVIDE MEANS TO DETER. PRESENCE OF RADIOIODINE

INPLANT RADIATION MONIT. -MODIFICATIONS TO ACCURATELY MEAS. IODINE *******************************

CONTROL ROOM HABITABILITY

-REVIEW ****************************************************************

CONTROL ROOM HABITABILITY

-SCHEDULE MODIFICATIONS

• • • • • .*****

_-*************************************

CONTROL ROOM HABITABILITY

-IMPLEMENT MODIFICATIONS

I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRAM PLAN ** ,,., ***********************

,, ** ,, ******* III .A.1. 2 TECHNICAL SUPPORT CENTER **********************************

, ****************************

III .A.1. 2 OPERATIONAL SUPPORT CENTER,,, ****** , ****************************** , * , *******************

III .A.1. 2 EMERGENCY OPERATIONS FACILITY ***********************************************************

I.D.1.2 DETAILED CONTROL ROOM REVIEW (FOLLOWUP TO F-8) **********************************

., *********

NUREG-0737 TECH SPECS (GENERIC LETTERS 82-16 & 83-02) *********************************************

TECH SPEC COVERED BY GENERIC LETTERS 83-26 & 83-37 FOR NUREG-0737

• • • • • • • • • • .***********************

REACTOR COOLANT PUMP TRIP (GENERIC LETTER 85-12) **************************************************

0 -This item is identified as open and consistent with the Consumers Power Company restructured Tech Specs submittal dated 1/24/89 which withdrew and included in the restructured Tech Spec Program Tech Specs for II.B.1, II.F.11, II.F.1.2, II.F.1,3, II.F.1.6, II.F.2 and III.D.3.4.

This restructured Tech Spec program is scheduled for submittal fourth quarter 1990. TMI ENCLOSURE A c c c c c c c c c c c c DATE 10/84 11/84 6/84 11/83 c c O** c ' ( *-* *