ML13322A970

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Requests Prompt Review & Reporting of Status of Implementation of TMI Action Plan Items.Printout of All TMI Items,Annotated Where Tracking Sys Indicates Implementation Incomplete,Encl
ML13322A970
Person / Time
Site: San Onofre  
Issue date: 04/14/1989
From: Murley T
Office of Nuclear Reactor Regulation
To: Baskin K
SOUTHERN CALIFORNIA EDISON CO.
References
TASK-***, TASK-TM NUDOCS 8904270142
Download: ML13322A970 (22)
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Text

PSREGL, UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 April 14, 1989 Docket Nos.:

50-206, 50-361 and 50-362 Mr. Kenneth P. Baskin Vice President Southern California Edison Company 2244 Walnut Grove Avenue Post Office Box 800 Rosemedd, California 91770 Mr. Baskin:

The purpose of this letter is to request your prompt review and reporting of the status of implementation of TMI Action Plan Items at your facility. As an enclosure we are providing a printout of all TMI items annotated where our tracking system indicates that implementation is not complete. For the purpose of this request, implementation should be considered complete when, to the best of your knowledge, all actions necessary to satisfactorily meet the requirements of NUREG-0737 and NUREG-0737 Supplement 1 have been completed.

Where you have not fully completed an item as described above, we request that you mark-up the enclosure to reflect your projected implementation date. Add a short note identifying remaining work (e.g., hardware, procedures, training, technical specifications). More explicit instructions are provided as part of the enclosure. We request that this information reach this office by April 18, 1989.

The information we are requesting will be utilized to validate our existing data base so that we can accurately respond to congressional inquiries concerning the status of implementation of THI Action Plan Items. In view of the importance of the information we request your personal attention and certification that the information is correct to the best of your knowledge.

This request is covered by Office of Management and Budget Clearance Number 3150-0011, which expires December 31, 1989. The estimated average burden hours is 40 person hours per owner response, including searching data sources, gathering and analyzing the data, and preparing the required letter. Send 0414 OFol1 8904270142 69 P

PN'J

2 -

April 14, 1989 comments regarding this burden estimate or any other aspect of this collection of information, including suggestions for reducing this burden, to the Records and Reports Management Branch, Division of Information Support Services, Office of Information Resources Management, U.S. Nuclear Regulatory Commission Washington, D.C. 20555; and to the Paperwork Reduction Project (3150-00115, Office of Management and Budget, Washington, D.C. 20503.

Your prompt attention to this matter within the requested time frame is appreciated.

Sincerely, Thomas E. Murley, D' ector Office of Nuclear Rea lation

Enclosure:

As stated cc w/enclosure:

See next page

2 -April 14, 1989 comments regarding this burden estimate or any other aspect of this collection of information, including suggestions for reducing this burden, to the Records and Reports Management Branch, Division of Information Support Services, Office of Information Resources Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555; and to the Paperwork Reduction Project (3150-0011), Office of Management and Budget, Washington, D.C. 20503.

Your prompt attention to this matter within the requested time frame is appreciated.

Sincerely, Oi'ginal signed by ThomasE.Murley Thomas E. Murley, Director Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/enclosure:

See next page DISTRIBUTION Docket File TMurley NRC & Local PDRs JSniezek PD #5 Reading JPartlow GHolahan MVirgilio JLee CTrammell DHickman OGC Eordan BGrimes ACRS (10)

PDV (Gray File)

L D5 D

/PD5 DRSP/D:PD5 TR mmelIr Hi kman GKnighton M

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89 4/\\ /89 4/ /89 4/89

Mr. Kenneth P. Baskin San Onofre Nuclear Generating Southern California Edison Company Station, Unit No. 1 cc Charles R. Kocher, Assistant Mr. Paul Szalinski, Chief General Counsel Radiological Health Branch James beoletto, Esquire State Department of Health Southern California Edison Company Services Post Office Box 800 714 P Street, Office Bldg. #8 Rosemead, California 91770 Sacramento, California 95814 David R. Pigott Orrick, Herrington & Sutcliffe 600 Montgomery Street San Francisco, California 94111 Mr. Robert G. Lacy Manager, Nuclear San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112 Resident Inspector/San Onofre NPS U.S. NRC P. 0. Box 4329 San Clemente, California 92672 Mayor City of San Clemente Sari Clemente, California 92672 Chairman Board of Supervisors County of San Diego 1600 Pacific Highway Room 335 San Diego, California 92101 Director Energy Facilities Siting Division Energy Resources Conservation &

Development Commission 1516 - 9th Street Sacramento, California 95814 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596

Mr. Kenneth P. Baskin San Onofre Nuclear Generating

-Southern California Edison Company Station, Units 2 and 3 cc:

Mr. Gary D. Cotton Mr. Hans Kaspar, Executive Director Senior Vice President Marine Review Committee, Inc.

Engineering and Operations 531 Encinitas Boulevard, Suite 105 San Diego Gas & Electric Company Encinitas, California 92024 101 Ash Street Post Office Box 1831 San Diego, California 92112 Mr. Mark Medford Southern California Edison Company Charles R. Kocher, Esq.

2244 Walnut Grove Avenue James A. Beoletto, Esq.

P. 0. Box 800 Southern California Edison Company Rosemead, California 91770 2244 Walnut Grove Avenue P. 0. Box 800 Mr. Robert G. Lacy Rosemead, California 91770 Manager, Nuclear Department San Diego Gas & Electric Company Orrick, Herrington & Sutcliffe P. 0. Box 1831 ATTN:

David R. Pigott, Esq.

San Diego, California 92112 600 Montgomery Street San Francisco, California 94111 Richard J. Wharton, Esq.

University of Sari Diego School of Alan R. Watts, Esq.

Law Rourke & Woodruff Environmental Law Clinic 701 S. Parker St. No. 7000 San Diego, California 92110 Orange, California 92668-4702 Charles E. McClung, Jr., Esq.

Attorney at Law Mr. S. McClusky 24012 Calle de la Plaza/Suite 330 Bechtel Power Corporation Laguna Hills, California 92653 P. 0. Box 60860, Terminal Annex Los Angeles, California 90060 Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. Charles B. Brinkman 1450 Maria Lane/Suite 210 Combustiun Engineering, Inc.

Walnut Creek, California 94596 12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Resident Inspector, San Onofre NPS c/o U. S. Nuclear Regulatory Commission Mr. Dennis F. Kirsh Post Office Box 4329 U.S. Nuclear Regulatory Commission San Clemente, California 92672 Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Mr. Sherwin Harris Resource Project Manager Public Utilities Department City of Riverside City Hall 3900 Main Street Riverside, California 92522

Southern California Edison Company San Onofre 2/3 (when specified) cc:

California State Library Government Publications Section Library & Courts Building Sacramento, California 95841 ATTN: Ms. Mary Schnell Mayor, City of San Clemente San Clemente, California 92672 Chairman, Board Supervisors San Diego County 1600 Pacific Highway, Room 335 San Diego, California 92101 California Department of Health ATTN: Chief, Environmental Radiation Control Unit Radiolooical Health Section 714 P Street, Room 498 Sacramento, California 95814 Mr. Paul Szalinski, Chief Radiological Health Branch State Department of Health Services 714 P Street, Building #8 Sacramento, California 95814

0 GUIDELINES FOR UPDATING TMI STATUS

1. The enclosure provides a complete listing of all THI requirements from NUREG-0737 and NUREG-0737 Supplement 1. Regulatory Guide 1.97 requirements, although addressed in Supplement 1 to NUREG-0737, are excluded since they did not originate from the TRI Action Plan. This listing consists of a matrix of items applicable to both operating reactors and operating license applicants (NTOLS) as of November, 1980, as shown in NUREG-0737 Enclosure 1 and 2, respectively. All items which are not listed identically in Enclosure 1 and 2 are marked with asterisks to indicate differences between operating reactor and NTOL requirements.

Whenever these differences occur, enter data in accordance with the appropriate title, regardless of the THI Action Plan item number listed.

Your NRC Project Manager has indicated which issues are shown as unimplemented in the NRC tracking system. Please review the entire listing for each licensed reactor unit. Where an item was not applicable for your facility, mark N/A in the implementation status column.

2. Where an item was applicable to your facility but no changes were necessary, mark NC in the implementation status column.
3. Where an item was applicable to your facility and changes are complete mark C in the implementation status column. If the date is readily available (month and year) we request you provide it, however, C is sufficient.
4.

Where an item was applicable to your facility and is not fully implemented, provide your projected implementation date (month and year) and a short note identifying the outstanding item (e.g. hardware, procedures, training, technical specifications).

MULTI-PLANT ISSUL NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS 1A.1.1.1 HIFT TECHNICAL ADVISOR - ON DUTY AA12SHIFT TECHNICAL ADVISOR - TECH SPECS.............................................................................

^l.A..1.3 FOOl SHIFT TECHNICAL ADVISOR -

TRAINED PER LL CAT B A IA.1.

1.4 SHIFT TECHNICAL ADVISOR -

DESCRIBE LONG TERM PROGRAM..........................................................

I.A.1.2 SHIFT SUPERVISOR RESPONSIBILITIES........................................................................

1.A.1.3.1 F002 SHIFT MANNING -

LIMIT OVERTIMES........................................................................

1.A.1.3.2 F002 SHIFT MANNING - MIN SHIFT CREW I.A.2.1.1 IMMEDIATE UPGRADING OF RO & SRO TRAINING AND QUAL. -

SRO EXPER 1.A.2.1.2 IMMEDIATE UPGRADING OF RO & SRO TRAINING AND QUAL. -

SRO'S BE RO'S lYR............................................

I.A.2.1.3 IMMEDIATE UPGRADING OF RO & SRO TRAINING AND QUAL. -

3 MO. TRAINING I.A.2.1.4 F003 IMMEDIATE UPGRADING OF RO & SRO TRAINING AND QUAL. - MODIFY TRAINING 1.A.2.1.5 IMMEDIATE UPGRADING OF RO & SRO TRAINING AND QUAL. -

FACILITY CERTIF l.PA.2.3 ADMINISTRATION OF TRAINING PROGRAMS................................................................................

I.A.3.1.1 REVISE SCOPE & CRITERIA FOR LICENSING EXAMS -

INCREASE SCOPE l.A.3.1.2 REVISE SCOPE & CRITERIA FOR LICENSING EXAMS -

INCREASE PASSING GRADE l.A.3.1.3.A REVISE SCOPE & CRIT. FOR LIC. EXAMS -

SIMULATOR PLANTS WITH SIMULATORS l.A.3.1.3.B REVISE SCOPE & CRIT. FOR LIC. EXAMS -

SIMULATOR -

OTHER PLANTS

  • A.B 31.2 EVALUATION OF ORGANIZATION & MANAGEMENT............................................................................

1A (1.

1 SHORT-TERM ACCIDENT & PROCEDURES REVIEW -

SB LOCA...............................::--?)f

1. 1.2.A F004 SHORT-TERM ACCID. & PROCEDURES REV. -

INADEQ. CORE COOL. REANAL. GUIDELINES........

.C. 1.2.B F004 SHORT-TERM ACCID. & PROCEDURES REV. -

INADEQ. CORE COOL. REVISE PROCEDURES.................

l.C.1.3.A F005 SHORT-TERM ACCID. & PROCEDURES REV -

TRANSIENTS & ACCDTS. REANAL GUIDELINES (PROC. GEN.

I.C.1.3.8 FOOS SHORT-TERM ACCID. & PROCEDURES REV. -

TRANSIENTS & ACCORS. REVISE PROCEDURES (UPGRADED EOP'.......................

I.C.2 SHIFT & RELIEF TURNOVER PROCEDURES.................................................................................

I

.C. 3 SHIFT-SUPERVISOR RESPONSIBILITY....................................................................................

I.C.4 CONTROL-ROOM ACCESS..............................................................................................

1.

C.

F006 FEEDBACK OF OPERATING EXPERIENCE...................................................................................

I.C.6 F007 VERIFY CORRECT PERFORMANCE OF OPERATING ACTIVITIES..................................................................

AlI C. 1.

1 NSSS VENDOR REV. OF PROC -

LOW POWER TEST PROGRAM...................................................................

"AI C.J2 NSSS VENDOR REV. OF PROC -

POWER ASCENSION & EMER. PROCS............................................................

AI8PILOT MON OF SELECTED EMERGENCY PROC FOR NTOLS...................................................................

II.1 (See F008 & F07l)

CONTROL-ROOM DESIGN REVIEWS (ENTER DATA FOR MPA F008 & MPA FO07%,,.~::

11.b F009 PLANT-SAFETY PARAMETER DISPLAY CONSOLE DESCRIPTION 1.C.6 F1-

MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE

(

J LICENSEE IMPLEMENTATION STATUS I.D.2.2 F009 PLANT-SAFETY PARAETER DISPLAY CONSOLE -

INSTALLED.

n 1.0.2.3 F009 PLANT-SAFETY PARAMETER DISPLAY CONSOLE -

FULLY IMPLEMENTED.

  • I.G.1.1 TRAINING DURING LOW-POWER TESTING -

PROPOSE TESTS...............................................................

  • I.G.1.2 TRAINING DURING LOW-POWER TESTING -

SUBMIT ANAL. & PROCS.

  • I.G.1.3 TRAINING DURING LOW-POWER TESTING -

TRAINING & RESULTS 11.8.1.1 REACTOR-COOLANT SYSTEM VENTS -

DESIGN VENTS 11.8.1.2 F010 REACTOR-COOLANT SYSTEM VENTS-INSTALL VENTS (LL CAT B) 11.8.1.3 FO1O REACTOR-COOLANT SYSTEM VENTS -

PROCEDURES II.B.2.1 PLANT SHIELDING -

REVIEW DESIGNS Al I82.2 PLANT SHIELDING -

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

  • 11.8.2.3 Foil PLANT SHIELDING -

PLANT MODIFICATIONS (LL CAT B)

  • 11.8.2.4 PLANT SHIELDING -

EQUIPMENT QUALIFICATION-NOT TRACKED AS A TMI ACTION ITEM..........................................

  • 11.8.3.1 POSTACCIDENT SAMPLING -

INTERIM SYSTEM

  • II.B.3.2 POSTACCIDENT SAMPLING -

CORRECTIVE ACTIONS

  • 11.8.3.3 POSTACCIDENT SAMPLING -

PROCEDURES.................................................................................

  • 11.B.3.4 F012 POSTACCIDENT SAMPLING -

PLANT MODIFICATIONS (LL CAT B) 11.8.4.1 F013 TRAINING FOR MITIGATING CORE DAMAGE -

DEVELOP TRAINING PROGRAM....................................................

  • 11.B.4.2.A F013 TRAINING FOR MITIGATING CORE DAMAGE -

INITIAL All.B.4.2.B F013 TRAINING FOR MITIGATING CORE DAMAGE -

COMPLETE..

11.0.1.1RELIEF

& SAFETY VALVE TEST REQUIREMENTS -

SUBMIT PROGRAM..

^ll.D.1.2.Ah I*

  • 11.0.1.2.A RELIEF & SAFETY VALVE TEST REQUIREMENTS -

COMPLETE TESTING 014._Ac___

0

  • 118 F014 RELIEF & SAFETY VALVE TEST REQUIREMENTS -

PLANT SPECIFIC REPORT.

11.0.1.3 RELIEF & SAFETY VAVLE TEST REQUIREMENTS -

BLOCK-VALVE TESTING

  • j I..3.1 VALVE POSITION INDICATION -

INSTALL DIRECT INDICATIONS OF VALVE POS.................................................

  • 1103.2 VALVE POSTION INDICATION -

TECH SPECS..............................................................................

^II.E.1.1.1 F015 AFS EVALUATION-ANALYSIS (SEE NOTE 1)

  • II.E.1.1.2 F015 AFS EVALUATION-SHORT TERM NODS (SEE NOTE 2)

IE. 1.T1.3 F015 AFS -LONG TERM NODS...........................-

OR................................................................

(SEE NOTE 3)

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 NTOLS)

NOTE 3 -

THE ITEM LISTED IS FOR ALL PLANTS (OPERATING REACTORS AND NTOLLS)

MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS II.E. 1.2. 1.A AES INITIATION & FLOW-CONTROL GRADE I1.E.1.2.1.B F016 AFS INITIATION & FLOW -

SAFETY GRADE II.E.1.2.2.A AFS INITIATION & FLOW -

FLOW INDICATION CONTROL GRADE

.E.1.2.2.B AFS INITIATION & FLOW -

LL CAT A TECH SPECS A'II.El.2.2.C F017 AFS INITIATION & FLOW -

SAFETY GRADE...............................................................................

AII.E.3.1.1 EMERGENCY POWER FOR PRESSURIZER HEATERS -

UPGRADE POWER SUPPLY

^II.E.3.1.2 EMERGENCY POWER FOR PRESSURIZER HEATERS -

TECH SPECS II.E.4.1.1 DEDICATED HYDROGEN PENETRATIONS -

DESIGN

REVIEW & REVISE H2 CONTROL PROC l11.E.4.1.3 F018 DEDICATED HYDROGEN PENETRATION -

INSTALL II.E.4.2.1-4 CONTAINMENT ISOLATION DEPENDABILITY -

IMP. DIVERSE ISOLATION 1.E.4.2.5.A CONTAINMENT ISOLAT. DEPENDABILITY -

CNTMT PRESS. SETPT. SEECIFIY PRESS

  • 11.E.4.2.5.B CONTAINMENT ISOLATION DEPENDABILITY -

CNTMT PRESSURE SETPT. ODS II.E.4.2.6 F019 CONTAINMENT ISOLATION DEPENDABILITY -

CNTMT PURGE VALVES 1I.E.4.2.7 F019 CONTAINMENT ISOLATION DEPENDABILITY -

RADIATION SIGNAL ON PURGE VALVES 11.E.4.2.8 CONTAINMENT ISOLATION DEPENDABLITY -

TECH SPECS 1II.F.1.1 F020 ACCIDENT -

MONITORING -

PROCEDURES

^II.F.1.2.A F020 ACCIDENT -

MONITORING -

NOBLE GAS MONITOR

  • II.F.1.2.B F021 ACCIDENT -

MONITORING -

IODINE/PARTICULATE SAMPLING

  • II.F.1.2.C F022 ACCIDENT -

MONITORING -

CONTAINMENT HIGH-RANGE MONITOR II.F.1.2.0 F023 ACCIDENT -

MONITORING -

CONTAINMENT PRESSURE

^ll.F.1.2.E F024 ACCIDENT -

MONITORING -

CONTAINMENT WATER LEVEL

  • II.F.1.2.F F025 ACCIDENT -

MONITORING -

CONTAINMENT HYDROGEN

  • 11.F.2.1 INSTRUMENTATION FOR DETECT. OF INADEQUATE CORE COOLING -

PROCEDURES..................................................

  • 11F22 INSTRUMENTATION FOR DETECT. OF INADEQUATE CORE COOLING -

SUBCOOL METER......

AII.F.2.3 F026 INSTRUMENTATION FOR DETECT. OF INADEQUATECORE COOLING -

DESC. OTHER 1F2[06INSTRUMENTATION FOR DETECT. OF INADEQUATE CORE CLING INSTLL ADD-L INSTRUMENTATIO. R ll.F.2.4 FO26 O

IGN1.1 POWER SUPP. FOR PRESSURIZER RELIEF, BLOCK VALVES & LEVEL IND. -

UPGRADE...........................................

  • 11..1.2 POWER SUPP. FOR PRESSURIZER RELIEF, BLOCK VALVES & LEVEL IND. -

TECH................................................

IA.K.1 (Oper. Reactors Only) IE BULLETNS 79-05 79-06, 79-08.AFE.............................................

MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS

  • 11.K.1.5

'IE BULLETINS -

REVIEW ESF VALVES

  • 11.K.1.20 IE BULLETINS -

PROMPT MANUAL REACTOR TRIP.

  • I1.K.1.22 IE BULLETINS - AUX. HEAT REM SYSTEM, PROC
  • 11.K.1.23 IE BULLETINS -

RV LEVEL, PROCEDURES.

  • 11.K.2.2 ORDERS ON B&W PLANTS - PROCEDURES TO CONTROL AFW IND OF ICS
  • 11.K.2.8 ORDERS ON B&W PLANTS - UPGRADE AFW SYSTEM II.K.2.9 F027 ORDERS ON B&W PLANTS -

FEMA ON ICS.......

1I.K.2.10 F028 ORDERS ON B&W PLANTS -

SAFETY-GRADE TRIP.......................................................................

  • I1.K.2.11 F029 ORDERS ON B&W PLANTS -

OPERATOR TRAINING..................................................

II.K.2.13 F030 ORDERS ON B&W PLANTS -

THERMAL MECHANICAL REPORT (CE & W PLANTS ALSO)..............................................

II.K.2.14 F031 ORDERS ON B&W PLANTS -

LIFT FREQUENCY OF PORV'S & SV's............................................................

II.K.2.15 ORDERS ON B&W PLANTS -

EFFECTS OF SLUG FLOW.....................................................................

II.K.2.16 F032 ORDERS ON B&W PLANTS -

RCP SEAL DAMAGE.........................................................................

II.K.2.17 F033 ORDERS ON B&W PLANTS - VOIDING IN RCS (CE & W PLANTS ALSO).......................................................

II.K.2.19 BENCHMARK ANALYSIS OF SEQUENTIAL AFW FLOW TO ONCE THROUGH STM GENERATOR...........................................

  • 11.K.2.20 F035 ORDERS ON B&W PLANTS - SYSTEM RESPONSE TO SB LOCA.................................................................
  • II.K.3.1.A F036 B&O TASK FORCE - AUTOMATIC PORV ISOLATION DESIGN..................................................................
  • 11.K.3.1.B FINAL RECOMMENDATIONS, B&O TASK FORCE - AUTO PORV ISO TEST/INSTALL......................................................

H.K.3.2 F037 B&O TASK FORCE - REPORT ON PORV FAILURES................................................................................

II.K.3.3 F038 B&O TASK FORCE - REPORTING SV & RV FAILURES AND CHALLENGES......

II.K.3.5.A F039 B&O TASK FORCE - AUTO TRIP OF RCP'S PROPOSED MODIFICATIONS..

II.K.3.5.B F039 B&O TASK FORCE - AUTO TRIP OF RCP'S MODIFICATIONS..........

II.K.3.7 B&O TASK FORCE -

EVALUATION OF PORV OPENING PROBABILITIES...............

II.K.3.9 F040 B&O TASK FORCE -

PID CONTROLLER MODIFICATION................................

II.K.3.10 F041 B&O TASK FORCE -

PROPOSED ANTICIPATORY TRIP MODIFICATIONS........................................................

II.K.3.11 B&O TASK FORCE - JUSTIFY USE OF CERTAIN PORV....................

II.K.3.12.A B&O TASK FORCE - ANTICIPATORY TRIP ON TURBINE TRIP PROPOSED MODS..................................................

II.K.3.12.B F042 B&O TASK FORCE - ANTICIPATORY TRIP ON TURBINE TRIP INSTALL MODS.

II.K.3.13.A F043 B&D TASK FORCE - HPCI & RCIC SYSTEM INITIATION LEVELS ANALYSIS..

II.K.3.13.B F043 B&O TASK FORCE - HPCI & RCIC INITIATION LEVELS MODIFICATION.............................................................

MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS

  • 11.K.3.14 F044 B&O TASK FORCE -

ISO CONDENSER ISOLATION ON HIGH RAD II.K.3.15 F045 B&O TASK FORCE -

MODIFY HPCI & RCIC BRK DETECTION CIRCUITRY II.K.3.16A F046 B&O TASK FORCE -

CHALLENGE & FAILURE OF RELIEF VALVES STUDY II.K.3.16.B F046 B&O TASK FORCE -

CHALLENGE & FAILURE OF RELIEF VALVES MODIFICATIONS II.K.3.17 F047 B&O TASK FORCE -

ECC SYSTEM OUTAGES.

II.K.3.18.A F048 B&O TASK FORCE -

ADS ACTUATION STUDY.

II.K.3.18.B F048 B&D TASK FORCE -

ADS ACTUATION PROPOSED MODIFICATIONS II.K.3.18.C F048 B&O TASK FORCE -

ADS ACTUATION MODIFICATIONS 11.K.3.19 F049 B&O TASK FORCE -

INTERLOCK RECIRCULATORY PUMP MODIFICATIONS

  • II.K.3.20 B&O TASK FORCE -

LOSS OF SVC WATER AT BRP II.K.3.21.A F050 B&O TASK FORCE -

RESTART OF CSS & LPCI LOGIC DESIGN II.K.3.21.B FOSO B&O TASK FORCE -

RESTART OF CSS & LPCI LOGIC DESIGN MODIFICATIONS II.K.3.22.A F051 B&D TASK FORCE -

RCIC SUCTION VERIFICATION PROCEDURES II.K.3.22.B F051 R&D TASK FORCE -

RCIC SUCTION MODIFICATION II.K.3.24 F052 B&O TASK FORCE -

SPACE COOLING FOR HPCI/RCI LOSS OF AC POWER II.K.3.25.A B&O TASK FORCE -

POWER ON PUMP SEALS PROPOSED MODIFICATIONS II.K.3.25.B F053 B&O TASK FORCE -

POWER ON PUMP SEALS MODIFICATIONS II.K.3.27 F054 B&D TASK FORCE -

COMMON REFERENCE LEVEL FOR BWRS II.K.3.28 F055 B&O TASK FORCE -

QUALIFICATION OF ADS ACCUMULATORS 11.K.3.29 F056 B&O TASK FORCE -

PERFORMANCE OF ISOLATION CONDENSERS II.K.3.30.A B&O TASK FORCE -

SCHEDULE FOR OUTLINE OF SB LOCA MODEL II.K.3.30.B F057 B&O TASK FORCE -

SB LOCA MODEL, JUSTIFICATION II.K.3.30.C B&O TASK FORCE -

SB LOCA METHODS NEW ANALYSES II.K.3.31 F058 B&O TASK FORCE -

COMPLIANCE WITH CFR 50.46

  • 11.K.3.40 R&D TASK FORCE -

RCP SEAL DAMAGE -

COVERED BY II.K.2.16 AND II.K.3.25

  • 11.K.3.43 B&D TASK FORCE -

EFFECTS OF SLUG FLOW -

COVERED BY II.K.2.15........................................................

II.K.3.44 F059 B&D TASK FORCE -

EVALUATE TRANSIENT WITH SINGLE FAILURE II.K.3.45 F060 B&D TASK FORCE -

ANALYSES TO SUPPORT II.K.3.46 FO61 RESPONSE TO LIST OF CONCERNS FROM ACRS CONSULTANT

  • 11.K.3.57 F062 IDENTIFY WATER SOURCES PRIOR TO MANUAL ACTIVATION OF ADS 1II.A. 1.1 EMERGENCY PREPAREDNESS, SHORT TERM.................................................................................

MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS II.A.1.2.1

'UPGRADE EMERGENCY SUPPORT FACILITIES -

INTERIM TSC OSC & EOF.....................................................

III.A.1.2.2 UPGRADE EMERGENCY SUPPORT FACILITIES-DESIGN-INCORP. INTO F063/F064/F065...........................................

(SEE F063, F064, F065)

III.A.1.2.3 UPGRADE EMER SUPPORT FACILITIES - MODS INCORPOR. INTO F063, F064 & F065...

(SEE F063, F064, F065)

III.A.2.1 F067 UPGRADE PREPAREDNESS - UPGRADE EMERGENCY PLANS TO APP.

R 0 III.A.2.2 F068 UPGRADE PREPAREDNESS -

METEOROLOGICAL DATA....

1

  • 1i.0.1.1.1 PRIMARY COOLANT OUTSIDE CONTAINMENT -

LEAK REDUCTION.

  • 111.D.1.1.2 PRIMARY COOLANT OUTSIDE CONTAINMENT - TECH SPECS...................

III.D.3.3.1 INPLANT RAD. MONIT. -

PROVIDE MEANS TO DETER. PRESENCE OF RADIOIODINE..............................................

III.D.3.3.2 F069 INPLANT RADIATION MONIT. -

MODIFICATIONS TO ACCURATELY MEAS. IODI F 111.0.3.4.1 F070 CONTROL ROOM HABITABILITY -

REVIEW.......................................................

AIII.D. 3.4.2 F070 CONTROL ROOM HABITABILITY -

SCHEDULE MODIFICATIONS...... O h.................................

IMPLEMENT MODIFICATIONS................................................

MPA-F008 F008 I.0.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRAM PLA......................

MPA-F063 F063 III.A.1.2 TECHNICAL SUPPORT CENTER.....................

MPA-F064 F064 III.A.1.2 OPERATIONAL SUPPORT CENTER...........................................

MPA-F065 F065 III.A.1.2 EMERGENCY OPERATIONS FACILITY...................

o 74-J.

MPA-FO71 F071 I.D.1.2 DETAILED CONTROL ROOM REVIEW (FOLLOWUP TO F-8)....

MPA-B072 B072 NUREG-0737 TECH SPECS (GENERIC LETTERS 82-16 & 83-02)..................

MPA-B083 B083 TECH SPEC COVERED BY GENERIC LETTERS 83-26 & 83-37 FOR UREG-0737.................................................

67.4.1 G001 REACTOR COOLANT PUMP TRIP (GENERIC LETTER 85-12).......... r.fle.

2 April 14, 1989 and Reports Management Branch, Division of Information Support Services, Office of Information Resources Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555; and to the Paperwork Reduction Project (3150-0011), Office of Management and Budget, Washington, D.C. 20503.

Your prompt attention to this matter within the requested time frame is appreciated.

Sincerely, Original signed by Thomas,

Mi r

Thomas E. Murley, Director Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/enclosure:

See next page DISTRIBUTION Docket File TMurley NRC & Local PDRs JSniezek PD #5 Reading JPartlow GHolahan MVirgilio JLee RSamworth OGC EJordan BGrimes ACRS (10)

PDV (Gray File)

SP/PD5 D

5 RSamworth: rw ton T

4///89 4////89 4T89

Mr. G. C. Sorensen, Manager WPPSS Nuclear Project No. 2 Washington Public Power Supply System (WNP-2) cc:

Nicholas S. Reynolds, Esq.

Regional Administrator, Region V Bishop, Cook, Purcell U.S. Nuclear Regulatory Commission

& Reynolds 1450 Maria Lane, Suite 210 1400 L Street NW Walnut Creek, California 94596 Washington, D.C. 20005-3502 Mr. G. E. Doupe, Esquire Chairman Washington Public Power Supply System Benton County Board of Commissioners P. 0. Box 968 Prosser, Washington 99350 3000 George Washington Way Richland, Washington 99532 Mr. Curtis Eschels, Chairman Mr. Christian Bosted Energy Facility Site Evaluation Council U. S. Nuclear Regulatory Commission Mail Stop PY-11 P. 0. Box 69 Olympia, Washington 98504 Richland, Washington 99352 Mr. Alan G. Hosler, Licensing Manager Washington Public Power Supply System P. 0. Box 968, MD 956B Richland, Washington 99352 Mr. A. Lee Oxsen Assistant Managing Director for Operations Washington Public Power Supply System P. 0. Box 968, MD 1023 Richland, Washington 99352 Mr. Gary D. Bouchey, Director Licensing and Assurance Washington Public Power Supply System P. 0. Box 968, MD 280 Richland, Washington 99352 Mr. C. M. Powers WNP-2 Plant Manager Washington Public Power Supply System P. 0. Box MD 927M RichWand, Washington 99352

GUIDELINES FOR UPDATING IMI STATUS

1. The enclosure provides a complete listing of all THI requirements from NUREG-0737 and NUREG-0737 Supplement 1. Regulatory Guide 1.97 requirements, although addressed in Supplement I to NUREG-0737, are excluded since they did not originate from the ThI Action Plan. This listing consists of a matrix of items applicable to both operating reactors and operating license applicants (ETOLS) as of November, 1980, as shown in NUREG-0737 Enclosure I and 2, respectively. All items which are not listed identically in Enclosure 1 and 2 are marked with asterisks to indicate differences between operating reactor and NTOL requirements.

Whenever these differences occur, enter data in accordance with the appropriate title, regardless of the THI Action Plan item number listed.

Your NRC Project Manager has indicated which issues are shown as

(

=p ented in the NRC tracking system. Please review the entire listing for each licensed reactor unit. Where an item was not applicable for your facility, mark N/A in the implementation status column.

2. Where an item was applicable to your facility but no changes were necessary, mark NC in the implementation status column.
3.

Where an item was applicable to your facility and changes are complete mark C in the implementation status column.

If the date is readily available (month and year) we request you provide it, however, C is sufficient.

4. Where an item was applicable to your facility and is not fully implemented, provide your projected implementation date (month and year) and a short note identifying the outstanding item (e.g. hardware, procedures, training, technical specifications).

MULTI-PLANT ISSUL NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS

.A.1.1.1IFT TECHNICAL ADVISOR -ON DUTY...............................

Al AI.2 SHIFT TECHNICAL ADVISOR -

TECH SPECS..........................................................................

Al A..1.3 Fool SHIFT TECHNICAL ADVISOR - TRAINED PER LL CAT B..................................................................

AA

.1.4 SHIFT TECHNICAL ADVISOR -

DESCRIBE LONG TERM PROGRAM................................................

^.A.1.2 SHIFT SUPERVISOR RESPONSIBILITIES l.A.1.3.1 F002 SHIFT MANNING -

LIMIT OVERTIMES........................................................................

L.A.1.3.2 F002 SHIFT MANNING - MIN SHIFT CREW.....................................................................................

I.A.2.1.1 IMMIEDIATE UPGRADING OF RD &, SRO TRAINING AND QUAL. -

SRO EXPER......................................................

I.A.2. 1.2 IMMIEDIATE UPGRADING OF RD & SRO TRAINING AND QUAL. -

SRO'S BE RD'S lYR..............................................

I.A.2. 1.3 IMMEDIATE UPGRADING OF RD & SRO TRAINING AND QUAL. -

3 MO. TRAINING..................................................

I.A. 2. 1.4 F003 IMMIEDIATE UPGRADING OF RD & SRO TRAINING AND QUAL. -

MODIFY TRAINING................................................

I.A.2.1.5 IMMEDIATE UPGRADING OF RO & SRO TRAINING AND QUAL. -

FACILITY CERTIF................................................

I.A.2.3 ADMINISTRATION OF TRAINING PROGRAMS.............................................................................

^LA.3.1.1 REVISE SCOPE & CRITERIA FOR LICENSING EXAMS -

INCREASE SCOPE L.A. 3.1.2 REVISE SCOPE & CRITERIA FOR LICENSING EXAMS -

INCREASE PASSING GRADE................................................

I.A.3.1.3.A REVISE SCOPE & CRIT. FOR LIC. EXAMS -

SIMULATOR PLANTS WITH SIMULATORS...............................................

I.A. 3.1.3.8 REVISE SCOPE & CRIT. FOR LIC. EXAMS -

SIMULATOR -

OTHER PLANTS......................................................

A I.1.2 EVALUATION OF ORGANIZATION & MANAGEMENT.............................................................................

1..

SHORT-TERM ACCIDENT & PROCEDURES REVIEW -

SB LOCA..................................................................

1. L.2.A F004 SHORT-TERM ACCID. & PROCEDURES REV. -

INADEQ. CORE COOL. REANAL. GUIDELINES..........................................

I.

.2.B F004 SHORT-TERM ACCID. & PROCEDURES REV. -

INADEQ. CORE COOL. REVISE PROCEDURES...........................................

.C.1.3.A F002 SHORT-TERM ACCID. & PROCEDURES REV -

TRANSIENTS & ACCTS. REANAL GUIDELINES (PROC. GEN. PKG.).......................

I.C.1.3.2 F002 SHORT-TERN ACCID. & PROCEDURES REV. -

TRANSIENTS & ACCORS. REVISE PROCEDURES (UPGRADED EOP'S).......................

L.C.2 SHIFT & RELIEF TURNOVER PROCEDURES................................................................................

l.C.3 SHIFT-SUPERVISOR RESPONSIBILITY...................................................................................

L.C.4 CONTROL-ROOM ACCESS...............................................................................................

i.cI.

F006 FEEDBACK OF OPERATING EXPERIENCE...................................................................................

L.C.6 FO07 VERIFY CORRECT PERFORMANCE OF OPERATING ACTIVITIES..............................................................

"AIC

.I N

SSS VENDOR REV. OF PROC -

LOW POWER TEST PROGRAM..................................................................

"AI C.12 NSSS VENDOR REV. OF PROC -

POWER ASCENSION & EHER. PROCS............................................................

Al C8 PILOT MON OF SELECTED EMERGENCY PROC FOR NTOLS.....................................................................

1I. L (See F008 & F0il)

CONTROL-ROOM DESIGN REVIEWS (ENTER DATA FOR MPA FOOB & MPA F-Oil)...................................................

I.D.2.1 F009 PLANT-SAFETY PARAMETER DISPLAY CONSOLE - DESCRIPTION................................................................

1.A.2.1.

MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS I.D.2.2 F009

'PLANT-SAFETY PARAMETER DISPLAY CONSOLE -

INSTALLED.........

1.0.2.3 F009 PLANT-SAFETY PARAMETER DISPLAY CONSOLE -

FULLY IMPLEMENTED........................................................

I.G. 1.1 TRAINING DURING LOW-POWER TESTING -

PROPOSE TESTS..........

  • 1.G.1.2 TRAINING DURING LOW-POWER TESTING -

SUBMIT ANAL. & PROCS...

^I.G.1.3 TRAINING DURING LOW-POWER TESTING - TRAINING & RESULTS.....

II.B.1.1 REACTOR-COOLANT SYSTEM VENTS - DESIGN VENTS.

II.B.1.2 F010 REACTOR-COOLANT SYSTEM VENTS - INSTALL VENTS (LL CAT 8)....

11.8.1.3 F010 REACTOR-COOLANT SYSTEM VENTS - PROCEDURES...

II.B.2.1 PLANT SHIELDING - REVIEW DESIGNS.

  • 11.B.2.2 PLANT SHIELDING - CORRECTIVE ACTIONS TO ASSURE ACCESS......
  • 11.B.2.3 FOl PLANT SHIELDING - PLANT MODIFICATIONS (LL CAT 8)
  • 11.8.2.4 PLANT SHIELDING - EQUIPMENT QUALIFICATION-NOT TRACKED AS A THI ACTION ITEM.......................................d.

A11.B.3.1 POSTACCIDENT SAMPLING -

INTERIM SYSTEM......

  • 11.8.3.2 POSTACCIDENT SAMPLING - CORRECTIVE ACTIONS..
  • 11.B.3.3 POSTACCIDENT SAMPLING - PROCEDURES....
  • 11.8.3.4 F012 POSTACCIDENT SAMPLING - PLANT MODIFICATIONS (LL CAT B)............................................................

11.8.4.1 F013 TRAINING FOR MITIGATING CORE DAMAGE - DEVELOP TRAINING PROGRAM....................................................

  • 11.B.4.2.A F013 TRAINING FOR MITIGATING CORE DAMAGE -

INITIAL....

  • 11.B.4.2.8 F013 TRAINING FOR MITIGATING CORE DAMAGE - COMPLETE..

11.0.1.1 RELIEF & SAFETY VALVE TEST REQUIREMENTS - SUBMIT PROGRAM..........

  • ll..1.2.A RELIEF & SAFETY VALVE TEST REQUIREMENTS -

COMPLETE TESTING........

  • 11.0.1.2.B F014 RELIEF & SAFETY VALVE TEST REQUIREMENTS -

PLANT SPECIFIC REPORT..

11.0.1.3 RELIEF & SAFETY VAVLE TEST REQUIREMENTS - BLOCK-VALVE TESTING..

  • 11.D.3.1 VALVE POSITION INDICATION -

INSTALL DIRECT INDICATIONS OF VALVE POS................................................

  • 11.0.3.2 VALVE POSTION INDICATION - TECH SPECS....
  • II.E.1.1.1 F015 AFS EVALUATION-ANALYSIS............

(SEE NOTE 1)

  • II.E.1.1.2 F015 AFS EVALUATION-SHORT TERN MOOS..........

(SEE NOTE 2)

II.E.1.1.3 F015 AFS -LONG TERM MODS.....................................................................................................

(SEE NOTE 3)

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)

MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS 1l.E.1.2.1.A AFS INITIATION & FLOW-CONTROL GRADE II.E.1.2.1.B F016 AFS INITIATION & FLOW -

SAFETY GRADE 1I.E.1.2.2.A AFS INITIATION & FLOW -

FLOW INDICATION CONTROL GRADE.

11.E.1.2.2.B AFS INITIATION & FLOW -

LL CAT A TECH SPECS.....................................................................

  • 11.E.1.2.2.C F017 AFS INITIATION & FLOW -

SAFETY GRADE......................................................................

  • 11.E.3.1.1 EMERGENCY POWER FOR PRESSURIZER HEATERS UPGRADE POWER SUPPLY AIl.E.3.1.2 EMERGENCY POWER FOR PRESSURIZER HEATERS -

TECH SPECS II.E.4.1.1 DEDICATED HYDROGEN PENETRATIONS -

DESIGN

REVIEW & REVISE H2 CONTROL PROC

INSTALL.

JI.E.4.2.1-4 CONTAINMENT ISOLATION DEPENDABILITY -

IMP. DIVERSE ISOLATION.

  • II.E.4.2.5.A CONTAINMENT ISOLAT. DEPENDABILITY -

CNTMT PRESS. SETPT. SEECIFIY PRESS

  • I1.E.4.2.5.8 CONTAINMENT ISOLATION DEPENDABILITY -

CNTMT PRESSURE SETPT. MODS....................................................

II.E.4.2.6 F019 CONTAINMENT ISOLATION DEPENDABILITY -

CNTMT PURGE VALVES II.E.4.2.7 F019 CONTAINMENT ISOLATION DEPENDABILITY -

RADIATION SIGNAL ON PURGE VALVES..............................................

lIl.E.4.2.8 CONTAINMENT ISOLATION DEPENDABLITY -

TECH SPECS "11.F. 1. 1 F020 ACCIDENT -

MONITORING -

PROCEDURES.................................................................................

AIIF12A F020 ACCIDENT -

MONITORING -

NOBLE GAS MONITOR..........................................................................

  • 1.F..

F021 /AC-0iVtACC IDENT -

MONITORING -

IODINE/PARTICULATE SAMPLING.................................................................

  • 11I.F.1.2.C F0-22 ACCIDENT -

MO0NITORING -

CONTAINMENT HIGH-RANGE MONITOR..............................................................

  • 1I.2.D F023 ACCIDENT - MONITORING -

CONTAINMENT PRESSURE.......................................................................

AIIF12.E F024 ACCIDENT -

MONITORING -

CONTAINMENT WATER LEVEL....................................................................

  • A IF2.F F025 ACCIDENT -

MONITORING -

CONTAINMENT HYDROGEN.......................................................................

  • 1IIF21 INSTRUMENTATION FOR DETECT. OF INADEQUATE CORE COOLING -

PROCEDURES.................................................

  • 11.F22 INSTRUMENTATION FOR DETECT. Of INADEQUATE CORE COOLING -

SUBCOOL METER..............................................

A11lF23 F026 INSTRUMENTATION FOR DETECT, OF INADEQUATE CORE COOLING -

DESC. OTHER................................................

  • 11F24 F026 INSTRUMENTATION FOR DETECT. OF INADEQUATE CORE CLING INSTLL ADD-L INSTRUMENTATION....................................

AuIG.1.1 POWER SUPP. FOR PRESSURIZER RELIEF, BLOCK VALVES & LEVEL IND. -

UPGRADE.............................................

  • 11.G. 1.2 POWER SUPP. FOR PRESSURIZER RELIEF, BLOCK VALVES & LEVEL IND. -

TECH SP.............................................

IL.K.1 (Oper. Reactors Only) IE BULLETINS-79-05, 79-06, 79-08.................................................................................

MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS

  • 1IK.1.5 IE BULLETINS - REVIEW ESF VALVES...............................................................................

All.K.1.10 IE BULLETINS - OPERABILITY STATUS..............................................................................

  • II.K.1.20 IE BULLETINS - PROMPT MANUAL REACTOR TRIP.......................................................................

^II.K.1.21 IE BULLETINS - AUTO SG ANTICIPATORY REACTOR TRIP................................................................

  • 11.K.1.22 IE BULLETINS - AUX. HEAT REM SYSTEM, PROC.......................................................................

All.K.1.23 IE BULLETINS - RV LEVEL, PROCEDURES............................................................................

AII.K.2.2 ORDERS ON B&W PLANTS - PROCEDURES TO CONTROL AFW IND OF ICS......................................................

  • 11K.2.8 ORDERS ON B&W PLANTS - UPGRADE AFW SYSTEM.......................................................................

II.K.2.9 FO27 ORDERS ON B&W PLANTS -

FEMA ON ICS.............................................................................

II.K.2.10 F028 ORDERS ON B&W PLANTS - SAFETY-GRADE TRIP........................................................................

  • 1I.K.2.11 F029 ORDERS ON B&W PLANTS -

OPERATOR TRAINING..............................................................

II.K.2.13 F030 ORDERS ON B&W PLANTS -

THERMAL MECHANICAL REPORT (CE & W PLANTS ALSO)...........................................

II.K.2.14 F031 ORDERS ON B&W PLANTS -

LIFT FREQUENCY OF PORV'S & SV's................................................................

II.K.2.15 ORDERS ON B&W PLANTS -

EFFECTS OF SLUG FLOW............................................................................

II.K.2.16 F032 ORDERS ON B&W PLANTS -

RCP SEAL DAMAGE..................................................................................

II.K.2.17 F033 ORDERS ON B&W PLANTS - VOIDING IN RCS (CE & W PLANTS ALSO)..............................................................

II.K.2.19 BENCHMARK ANALYSIS OF SEQUENTIAL AFW FLOW TO ONCE THROUGH STM GENERATOR.................................................

  • 11.K.2.20 F035 ORDERS ON B&W PLANTS -

SYSTEM RESPONSE TO SB LOCA.......................................................................

  • I.K.3.1.A F036 B&O TASK FORCE - AUTOMATIC PORV ISOLATION DESIGN........................................................................
  • Il.K.3.1.B FINAL RECOMMENDATIONS, B&O TASK FORCE - AUTO PORV ISO TEST/INSTALL......................................................

II.K.3.2 F037 B&O TASK FORCE -

REPORT ON PORV FAILURES................................................................................

II.K.3.3 F038 B&O TASK FORCE -

REPORTING SV & RV FAILURES AND CHALLENGES..............................................................

II.K.3.5.A F039 B&O TASK FORCE - AUTO TRIP OF RCP'S PROPOSED MODIFICATIONS..............................................................

II.K.3.5.B F039 B&O TASK FORCE - AUTO TRIP OF RCP'S MODIFICATIONS.......................................................................

II.K.3.7 B&O TASK FORCE - EVALUATION OF PORV OPENING PROBABILITIES........................................................

II.K.3.9 F040 B&O TASK FORCE - PID CONTROLLER MODIFICATION....................................................................

II.K.3.10 F041 B&O TASK FORCE - PROPOSED ANTICIPATORY TRIP MODIFICATIONS...............................................................

II.K.3.11 B&O TASK FORCE - JUSTIFY USE OF CERTAIN PORV............................................................................

II.K.3.12.A B&O TASK FORCE - ANTICIPATORY TRIP ON TURBINE TRIP PROPOSED MODS........................................................

II.K.3.12.8 F042 B&O TASK FORCE - ANTICIPATORY TRIP ON TURBINE TRIP INSTALL NODS.........................................................

II.K.3.13.A F043 B&O TASK FORCE - HPCI & RCIC SYSTEM INITIATION LEVELS ANALYSIS..........................................................

II.K.3.13.B F043 B&O TASK FORCE - HPCI & RCIC INITIATION LEVELS MODIFICATION.............................................................

MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS

  • 11.K.3.14 F044 B&O TASK FORCE -

ISO CONDENSER ISOLATION ON HIGH RAD Il.K.3.15 F045 B&O TASK FORCE -

MODIFY HPCI & RCIC RK DETECTION CIRCUITRY.

II.K.3.16A F046 B&O TASK FORCE -

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

II.K.3.16.B F046 B&O TASK FORCE -

CHALLENGE & FAILURE OF RELIEF VALVES MODIFICATIONS.

II.K.3.17 F047 8W TASK FORCE - EC SYSTEM OUTAGES.........................................................................

II.K.3.18.A F048 B&O TASK FORCE - ADS-ACTUATION STUDY...........................................................................

II.K.3.18.8 F048 B&O TASK FORCE - ADS ACTUATION PROPOSED MODIFICATIONS II.K.3.18.C F048 8W TASK FORCE -

ADS ACTUATION MODIFICATIONS

^ll.K.3.19 F049 B&O TASK FORCE -

INTERLOCK RECIRCULATORY PUMP MODIFICATIONS

  • 11.K.3.20 B&O TASK FORCE -

LOSS OF SVC WATER AT BRP...........................................................................

II.K.3.2.A F050 B&O TASK FORCE -

RESTART OF CSS & LPCI LOGIC DESIGN ll.K.3.21.8 F050 B&O TASK FORCE -

RESTART OF CSS & LPCI LOGIC DESIGN MODIFICATIONS II.K.3.22.A F051 B&O TASK FORCE -

RCIC SUCTION VERIFICATION PROCEDURES II.K.3.22.A F051 B&O TASK FORCE -

RCIC SUCTION MODIFICATION 11.K.3.24 F052 B&O TASK FORCE -

SPACE COOLING FOR HPCI/RCI LOSS OF AC POWER II.K.3.25.A BW TASK FORCE -

POWER ON PUMP SEALS PROPOSED MODIFICATIONS II.K.3.25.8 F053 B&O TASK FORCE -

POWER ON PUMP SEALS MODIFICATIONS II.K.3.27 F054 B&O TASK FORCE -

COMMON REFERENCE LEVEL FOR BWRS I.K.3.28 F055 B&O TASK FORCE -

QUALIFICATION OF ADS ACCUMULATORS

  • 11.K.3.29 F056 B&O TASK FORCE -

PERFORMANCE OF ISOLATION CONDENSERS II.K.3.30.A B&O TASK FORCE -

SCHEDULE FOR OUTLINE OF SB LOCA MODEL II.K.3.30.B F057 B&O TASK FORCE -

SB LOCA MODEL, JUSTIFICATION II.K.3.30.C B&O TASK FORCE -

SB IOCA METHODS NEW ANALYSES II.K.3.31 F058 B&O TASK FORCE -

COMPLIANCE WITH CFR 50.46

  • 11.K.3.40 AD TASK FORCE -

RCP SEAL DAMAGE -

COVERED BY II.K.2.16 AND II.K.3.25

  • 11K.343 B&O TASK FORCE -

EFFECTS OF SLUG FLOW -

COVERED BY II.K.2.15........................................................

II.K.3.44 F059 B&O TASK FORCE -

EVALUATE TRANSIENT WITH SINGLE FAILURE II.K.3.45 F060 B&O TASK FORCE -

ANALYSES TO SUPPORT ll.K.3.46 F061 RESPONSE TO LIST OF CONCERNS FROM ACRS CONSULTANT

  • II.K.3.57 F062 IDENTIFY WATER SOURCES PRIOR TO MANUAL ACTIVATION OF ADS I 11.A. 1.1l EMERGENCY PREPAREDNESS, SHORT TERM.................................................................................

MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS III.A.1.2.1

'UPGRADE EMERGENCY SUPPORT FACILITIES -

INTERIM TSC OSC & EOF........

II.A.1.2.2 UPGRADE EMERGENCY SUPPORT FACILITIES-DESIGN-INCORP. INTO F063/FO64/FO65...........................................

(SEE F063, F064, F065)

III.A.1.2.3 UPGRADE EMER SUPPORT FACILITIES -

MODS INCORPOR. INTO F063, F064 & F065....

(SEE F063, F064, F065) 11I.A.2.1 F067 UPGRADE PREPAREDNESS - UPGRADE EMERGENCY PLANS TO APP. E. 10 CFR 50...............................................

JII.A.2.2 F068 UPGRADE PREPAREDNESS - METEOROLOGICAL DATA......................................................................

  • III.D. 1. 1.1 PRIMARY COOLANT OUTSIDE CONTAINMENT -

LEAK REDUCTION............................................................

  • 11D.1.1.2 PRIMARY COOLANT OUTSIDE CONTAINMENT -

TECH SPECS................................................................

Ill.D.3.3.1 INPLANT RAD. MONIT. - PROVIDE MEANS TO DETER. PRESENCE OF RADIOIODINE.............................................

Ill.D.3.3.2 F069 INPLANT RADIATION MONIT. - MODIFICATIONS TO ACCURATELY MEAS. IODINE...............................................

111.0.3.4.1 F070 CONTROL ROOM HABITABILITY -

REVIEW...............................................................................

Ill.D. 3.4.2 F070 CONTROL ROOM HABITABILITY -

SCHEDULE MODIFICATIONS................................................................

IMPLEMENT MODIFICATIONS.

MPA-F008 FOO I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRAM PLAN....

MPA-F063 F063 III.A.1.2 TECHNICAL SUPPORT CENTER......

MPA-F064 F064 III.A.1.2 OPERATIONAL SUPPORT CENTER...

MPA-F065 F065 III.A.1.2 EMERGENCY OPERATIONS FACILITY................

9>MPA-F071 FO71 /Var d 1.0.1.2 DETAILED CONTROL ROOM REVIEW (FOLLOWUP TO F-8)................................

MPA-B072 B072 NUREG-0737 TECH SPECS (GENERIC LETTERS 82-16 & 83-02).................................

MPA-8083 8083 TECH SPEC COVERED BY GENERIC LETTERS 83-26 & 83-37 FOR NUREG-0737..

67.4.1 GOO REACTOR COOLANT PUMP TRIP (GENERIC LETTER 85-12)

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

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