ML17347B097
| ML17347B097 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 04/14/1989 |
| From: | Murley T Office of Nuclear Reactor Regulation |
| To: | Conway W FLORIDA POWER & LIGHT CO. |
| References | |
| TASK-***, TASK-TM NUDOCS 8904240292 | |
| Download: ML17347B097 (25) | |
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UNITED STATES t NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555
, April 14, 1989 Docket Nos. 50-250 and 50-251 Mr. W. F.
Conway Senior Vice President-Nuclear Nuclear Energy Department Florida Power and Light Company Post Office Box 14000 Juno Beach, Florida 33408-0420 Gentlemen:
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 TMI 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 coments 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.
890P240292 05000250 PDR ADOCK 'o PDC P
Nr.
W. F.
Conway > April 14, 1989 Your prompt attention to this matter within the requested time frame is appreciated.
Sincerely,
Enclosure:
As stated cc w/enclosure:
See next page
/s/
Thomas E. Nurley, Director Office of Nuclear Reactor Regulation DISTRIBUTION NRC 8 Local-PDRs PDII-2 Reading TMurley/JSniezek JPartlow SVarga GLainas HBerkow DNiller GEdison OGC (info only)
EJordan BGrimes ACRS(10)
BWilson E.&'N:PDII-2 GEdison:bd 04/p/$ 89 D: DII-2 HBerkow 04/g /89 D: NRR TMurley 04//+89
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Mr. W. F.
Conway
'lorida Power and Light Company Turkey Point Plant CC:
Harold F. Reis, Esquire Newman and Holtzinger, P.C.
1615 L Street, N.W.
Washington, DC 20036 Mr. Jack Shreve Office of the Public Counsel Room 4, Holland Building Tallahassee, Florida 32304 John T. Butler, Esquire
- Steel, Hector and Davis 4000 Southeast Financial Center Miami, Florida 33131-2398 Mr. J.
- Odom, Vice President Turkey Point Nuclear Plant Florida Power and Light Company P.O.
Box 029100 Miami, Florida 33102 County Manager of Metropolitan Dade County ill NW 1st Street, 29th Floor Miami, Florida 33128 Resident Inspector U.S. Nuclear Regulatory Commission Turkey Point Nuclear Generating Station Post Offi ce Box 57-1185 Miami, Flori da 33257-1185 Mr. Ja cob Da ni e 1 Nash Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Blvd.
Tallahassee, Flori da 32399-0700 Intergovernmental Coordination and Review Office of Planning
& Budget Executive Off i ce of the Governor The Capitol Building Tallahassee, Florida 32301 Administrator Department of Environmental Regulati on Power Plant Siting Section State of Florida 2600 Blair Stone Road Ta 1 1 ahassee, Florida 32301 Regional Administrator, Region II U.S. Nuclear Regulatory Commission Suite 2900 101 Marietta Street Atlanta, Georgia 30323 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304 Plant Manager Turkey Point Nuclear Plant Florida Power and Light Company P.O.
Box 029100 Miami, Florida 33102
GUIDELINES FOR UPDATING TMI STATUS 1.
The enclosure prov'ides a complete listing of all TMI requ1rements from HUREG-0737 and HUREG-0737 Supplement 1.
Regulatory Gu1de I.g7 requirements, although addressed in Supplement I to XUREG-0737, are excluded since they did not originate from the TMI Action Plan.
This listing consists of a matrix of items applicable to both operat1ng reactors and operating license applicants (NTOLS) as of November,
- 1980, as shown in HUREG-0737 Enclosure I and 2, respectively.
All items which are not listed identically 1n Enclosure I and 2 are marked w1th asterisks to indicate differences between operating reactor and HTOL requirements.
Whenever these d1fferences occur, enter data in accordance w1th the appropr1ate t1tle, regardless of the TMI Action Plan item number listed.
Your HRC Project Manager has indicated which issues are shown as un1mplemented in the NRC tracking system.
Please review the entire 11sting for each 11censed reactor unit.
Where an 1tem was not applicable for your facility, mark N/A in the 1mplementation status column.
2.
Where an item was appl1cable to your facility but no changes were necessary, mark NC in the 1mplementation status column.
3.
Where an item was appl1cable to your facility and changes are complete mark C in the implementation status column. If the date is readily ava1lable (month and year) we request you prov1de it, however, C is sufficient.
4.
Where an item was applicable to your facility and is not fully 1mplemented, provide your projected implementat1on date (month and year) and a short note 1dentify1ng the outstand1ng item (e.g.
- hardware, procedures, training, technical specificat1ons).
l
7 ORETC~ p'a/W7 MULTI-PLANT ISSUE NUMBER ACTION NO.
ISSUE TITLE LICENSEE IMPLEMENTATION STATUS I.A.1.1.1
- I.A.1.1.2 "I.A.1.1.3 AI.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.Z.1.3 I.A.2. 1.4 I.A.2.1.5 I.A.2.3 I.A.3.1.1 I.A.3.1.2 I.A.3. 1.3.A I.A.3.1.3.8 AI.B.1.2 I.C.1.1 I.C.1.2.A I.C.1.2.8 I.C.1.3.A I.C. 1.3.8 I.C.2 I.C.3 I.C.4 I.C.5 I.C.6 AI.C.7.1
- I.C.7.2 "I.C.8 I.O. 1 (See I.D.2.1 F001 F002 F002 F003 F004 F004 F005 FOOS F006 F007 F008 & F071)
F009 SHIFT TECHNICAL ADVISOR - ON DUTY.
SHIFT TECHNICAL ADVISOR - TECH SPECS.
SHIFT TECHNICAL ADVISOR - TRAINED PER LL CAT 8.
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 ANO QUAL. -
SRO EXPER.
IMMEDIATE UPGRADING OF RO & SRO TRAINING ANO QUAL. - SRO'S BE RO'S 1YR.
IMMEDIATE UPGRADIHG OF RO & SRO TRAINING AND QUAL. - 3 MO. TRAINING.
IMMEDIATE UPGRADING OF RO & SRO TRAINING ANO QUAL. - MODIFY TRAINING.
IMMEDIATE UPGRADING OF RO & SRO TRAINING AND QUAL. - FACILITY CERTIF ADMINISTRATIONOF 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 & MANAGEMEHT.
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..NC8?4'.ASH..................
SHORT-TERM ACCIO.
& PROCEDURES REV - TRANSIEHTS & ACCOTS.
REANAL GUIDELINES (PROC.
GEN.
PKG.)
SHORT-TERM ACCIO. & PROCEDURES REV. - TRANSIENTS & ACCDRS.
REVISE PROCEDURES (UPGRADED EOP'S) 44~4HJ.CCrC.'..
SHIFT & RELIEF TURNOVER PROCEDURES.
SHIFT-SUPERVISOR RESPONSIBILITY............................ ~,..........................................
CONTROL-ROOM ACCESS.
FEEDBACK OF OPERATING EXPERIENCE.
VERIFY CORRECT PERFORMANCE OF OPERATING ACTIVITIES.
NSSS VENDOR REV.
OF PROC -
LOW POWER TEST PROGRAM.
NSSS VENDOR REV.
OF PROC -
POWER ASCEHSION & EMER.
PROCS.
PILOT MON OF SELECTEO EMERGENCY PROC FOR NTOLS.
CONTROL-ROOM DESIGN REVIEWS (ENTER DATA FOR MPA FOOB & MPA F-071).
PLANT-SAFETY PARAMETER DISPLAY CONSOLE - DESCRIPTION..
l l
l f
MULTI-PLANT ISSUE NUMBER ACTION NO.
ISSUE TITLE LICEHSEE IMPLEHENTATION STATUS I.D.Z.Z 1.0.2.3 "I.G.1.1 AI.G.1.2 "I.G.1.3 11.8. 1. 1 11.8. 1.2 II.B. 1. 3 II.B. 2. 1 "I1.8.2. 2 "11.B.2. 3 "11.8.2.4
- 11.8.3.1 "11.8.3.2 "II.B.3.3
%II.8.3.4 11.8.4.1 "I1.8.4.2. A "11.8.4.2.8 11.0. 1. 1
- II.D.1.2.A
- II.D. 1.2. 8 II.D.1.3 "11.0.3.1 "11.0.3.2 "II.E.1.1.1 (SEE NOTE "Il.f.l.l.2 (SEE NOTE II.E.1.1.3 (SEE NOTE F009 F009 F010 F010 FOll F012 F013 F013 F013 F014 F015 1)
F015 2)
F015 3)
PLANT-SAFETY PARAMETER DISPLAY CONSOLE - INSTALLED.
PLANT-SAFETY PARAMETER DISPLAY CONSOLE - FULLY IMPLEMENTED.
TRAINING DURING LOW-POWER TESTING - PROPOSE TESTS TRAINING DURING LOW-POWER TESTING - SUBMIT ANAL. 8 PROCS.
TRAINING DURING LOW-POWER TESTING - TRAINING 4 RESULTS.
REACTOR-COOLANT SYSTEM VENTS - DESIGN VENTS...
REACTOR-COOLANT SYSTEM VENTS - INSTALL VENTS (LL CAT 8).
REACTOR-COOLANT SYSTEH VENTS - PROCEDURES.
PLANT SHIELDING - REVIEW DESIGNS.
PLANT SHIELDIHG - CORRECTIVE ACTIONS TO ASSURE ACCESS.
PLANT SHIELDING - PLANT MODIFICATIONS (LL CAT 8).
PLANT SHIELDING - EQUIPHENT QUALIFICATION-NOT TRACKED AS A THI ACTION ITEH.
POSTACCIOENT SAMPLING - INTERIM SYSTEM.
POSTACCIOENT SAHPLING - CORRECTIVE ACTIONS.
POSTACCIOENT SAHPLING -
PROCEDURES.
POSTACCIDENT SAMPLING - PLANT MODIFICATIONS (LL CAT 8)
TRAINING FOR MITIGATING CORE OAHAGE - DEVELOP TRAIHING PROGRAM TRAINING FOR MITIGATING CORE DAMAGE - INITIAL.
TRAINING FOR MITIGATING CORE DAMAGE - COMPLETE.
RELIEF 8 SAFETY VALVE TEST REQUIREMENTS - SUBMIT'ROGRAM.
RELIEF 4 SAFETY VALVE TEST REQUIREMENTS - COHPLETE TESTING..................
RELIEF 8 SAFETY VALVE TEST REQUIREMENTS - PLANT SPECIFIC REPORT...leaf%.OAF.MlÃ..
RELIEF 5 SAFETY VAVLE TEST REQUIREMENTS - BLOCK-VALVE TESTING.
VALVE POSITION INDICATION - INSTALL DIRECT INDICATIONS OF VALVE POS.
VALVE POSTION INDICATION - TECH SPECS.
AFS EVALUATION-ANALYSIS.
AFS EVALUATION-SNORT TERH MOOS.
AFS -LONG TERM MODS.
NOTE 1 - THE ITEH LISTED IS FROH NUREG-0737, ENCLOSURE 2 AND IS APPLICABLE TO NTOLS'S ONLY NOTE 2 - THE ITEH LISTED IS FOR ALL PLANTS (OPERATING REACTORS AND NTOL'S)
NOTE 3 - THE ITEH LISTED IS FOR ALL PLANTS (OPERATING REACTORS AND NTOL'S)
HULTI-P LANT ISSUE NUHBER ACTION NO.
ISSUE TITLE LICENSEE IHPLEHENTATION STATUS II.E.1.2.1.A II.E.1.2.1.8 II.E.1.2.2.A
- II.E. l. 2.2. 8
<<II.E. l. 2.2. C
<<II.E. 3. l. 1
<<II.E.3.1.2 II.E.4.1.1
<< II.E.4. l. 2
<<I I.E.4.1. 3 II.E.4.2. 1-4
- II. E.4.2.5. A
<<II.E.4.2.5.8 II.E.4.2.6 II.E.4.2.7
<<II.E.4.2.8
<<II.F.l.l
<<II.F.1.2. A "II. F. 1.2. 8 "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
- II.F.2.3
<<II.F.2.4
<<II.G.1.1
- II.G.1.2 II.K.1 (Oper.
F016 F017 F018 F019 F019 F020 F020 F021 F022 F023 F024 F025 F026 F026 Reactors Only)
AFS INITIATION& FLOW-CONTROL GRADE AFS INITIATION& FLOW - SAFETY GRADE AFS INITIATION& FLOW -
FLOW INDICATION CONTROL GRADE AFS INITIATION& FLOW - LL CAT A TECH SPECS.
AFS INITIATION& FLOW - SAFETY GRADE EMERGENCY POWER FOR PRESSURIZER HEATERS - UPGRADE POWER SUPPLY.
EHERGENCY POWER FOR PRESSURIZER HEATERS - TECH SPECS.
DEDICATED HYDROGEN PENETRATIONS - DESIGN.
DEDICATED HYDROGEN PENETRATIONS - REVIEW & REVISE H2 CONTROL PROC.
DEDICATED HYDROGEN PENETRATION - INSTALL CONTAINHENT ISOLATION DEPENDABILITY-IHP.
DIVERSE ISOLATION.
CONTAINHENT ISOLAT. DEPENDABILITY - CNTHT PRESS.
SETPT.
SEECIFIY PRESS.
CONTAINHENT ISOLATION DEPENDABILITY - CNTHT PRESSURE SETPT.
HODS.
CONTAINMENT ISOLATION DEPENDABILITY - CNTHT PURGE VALVES.
CONTAINMENT ISOLATION DEPENDABILITY - RADIATION SIGNAL ON PURGE VALVES.
CONTAINMENT ISOLATION OEPENOABLITY - TECH SPECS.
ACCIDENT - HONITORING -
PROCEDURES.
ACCIDENT - HONITORING - NOBLE GAS HONITOR.
ACCIDENT - HONITORING - IODINE/PARTICULATE SAMPLING.
ACCIDENT - HONITORING - CONTAINMENT HIGH-RANGE MONITOR.
ACCIDENT - HONITORING - CONTAINMENT PRESSURE.
ACCIDENT - HONITORING - CONTAINMENT WATER LEVEL ACCIDENT - HONITORING - CONTAINHENT HYDROGEN.
INSTRUMENTATION FOR DETECT.
OF INADEQUATE CORE COOLING -
PROCEDURES.
INSTRUMENTATION FOR DETECT.
OF INADEQUATE CORE COOLING -
SUBCOOL HETER.
INSTRUHENTATION FOR DETECT.
OF INADEQUATE CORE COOLING - OESC.
OTHER.
INSTRUHENTATION FOR DETECT.
OF INADEQUATE CORE CLING INSTLL ADD'L INSTRUHENTATION.
POWER SUPP.
FOR PRESSURIZER
- RELIEF, BLOCK VALVES & LEVEL IND. - UPGRADE.
POWER SUPP.
FOR PRESSURIZER RELIEF, BLOCK VALVES & LEVEL IND. - TECH SP.
IE BULLETINS 05, 79-06, 79-08.
t
ISSUE NUMBER MULTI-PLANT ACTION NO.
ISSUE TITLE LICENSEE IMPLEMEHTATION STATUS "II.K.1.5
- II.K.l. 10 "II K.l.20
- II.K.l. 21
- II.K.l. 22 "II. K.l. 23 "II.K.2.2
- II.K.2.8 II.K.2. 9 II.K.2. 10
- II. K. 2. 11 II. K.2. 13 II.K.2.14 II.K.2.15 II-K.2.16 II.K.2. 17 II.K.2. 19
- II.K.2.20 "II. K. 3. l. A "II. K.3. 1. 8 II.K.3.2 II.K.3. 3 II.K.3.5. A II.K.3.5. 8 II.K.3. 7 II.K.3. 9 II.K.3.10 II.K.3.11 II.K.3. 12. A II. K. 3. 12. 8 II.K.3. 13. A II.K.3. 13. 8 F027 F028 F029 F030 F031 F032 F033 F035 F036 F037 F038 F039 F039 F040 F041 F042 F043 F043 IE BULLETINS - REVIEW ESF VALVES.
IE BULLETINS - OPERABILITY STATUS.
IE BULLETINS -
PROMPT MANUAL REACTOR TRIP.
IE BULLETINS - AUTO SG ANTICIPATORY REACTOR TRIP.
IE BULLETINS - AUX. HEAT REM SYSTEM, PROC.
IE BULLETINS - RV LEVEL, PROCEDURES.
ORDERS ON BtW PLANTS - PROCEDURES TO CONTROL AFW IHO OF ICS.
ORDERS OH BEW PLANTS - UPGRADE AFW SYSTEM.
ORDERS ON 8&W PLANTS -
ORDERS ON MW PLANTS - SAFETY-GRADE TRIP..
ORDERS ON ELW PLANTS - OPERATOR TRAINING.
ORDERS OH MW PLANTS - THERMAL MECHANICAL REPORT (CE 4 W PLANTS ALSO).
ORDERS OH 86W PLANTS - LIFT FRE(UENCY OF PORV'S 8, SV's.
ORDERS OH IRW PLANTS - EFFECTS OF SLUG FLOW.
ORDERS OH IHlW PLANTS - RCP SEAL DAMAGE ORDERS ON 84W PLANTS - VOIDIHG IN RCS (CE 4 W PLAHTS ALSO).
BENCHMARK ANALYSIS OF SEqUEHTIAL AFW FLOW TO ONCE THROUGH STH GENERATOR.
ORDERS ON EN PLANTS - SYSTEM RESPONSE TO SB LOCA.
880 TASK FORCE - AUTOMATIC PORV ISOLATION DESIGH.
FINAL RECOMMENDATIOHS, $$ TASK FORCE - AUTO PORV ISO TEST/INSTALL.
5Ã TASK FORCE - REPORT OH PORV FAILURES.
ES TASK FORCE - REPORTING SV 4 RV FAILURES AHD CHALLEHGES.
$$ TASK FORCE - AUTO TRIP OF RCP'S PROPOSED MODIFICATIONS.
IHS TASK FORCE - AUTO TRIP OF RCP'S MODIFICATIONS.
5$ TASK FORCE - EVALUATION OF PORV OPENING PROBABILITIES.
SM TASK FORCE - PID CONTROLLER MODIFICATION.
840 TASK FORCE -
PROPOSED ANTICIPATORY TRIP MODIFICATIONS.
QO TASK FORCE - JUSTIFY USE OF CERTAIN PORV.
888 TASK FORCE - ANTICIPATORY TRIP OH TURBINE TRIP PROPOSED NODS.
$$ TASK FORCE - ANTICIPATORY TRIP ON TURBINE TRIP INSTALL NODS.
SLO TASK FORCE - HPCI 4 RCIC SYSTEM INITIATION LEVELS ANALYSIS.
888 TASK FORCE - HPCI 4 RCIC IHITIATIOH LEVELS MODIFICATION.
ISSUE NUMBER MULTI-PLANT ACTION NO.
ISSUE TITLE LICENSEE IHPLEHENTATION STATUS "II. K.3. 14 II. K. 3. 15 II. K. 3. 16A II. K. 3. 16. 8 I I.K.3. 17 II. K. 3. 18. A II.K.3. 18. 8 II. K. 3. 18. C "II.K.3.19
- II.K.3. 20 II.K.3.21.A II. K.3.21.8 II. K.3. 22. A II.K.3. 22. 8 II.K.3.24 II.K.3.25.A II.K.3.25. 8 II.K.3.27 II.K.3. 28
- II. K.3. 29 II.K.3.30.A II. K. 3. 30. 8 II.K.3.30.C II.K.3.31
- ll.K.3.40 AII. K. 3. 43 II. K.3.44 II.K.3.45 II.K.3.46
- II.K.3. 57 III.A.1. 1 F044 F045 F046 F046 F047 F048 F048 F048 F049 F050 F050 F051 F051 F052 F053 F054 F055 F056 F057 F058 F059 F060 F061 F062 8&0 TASK F 8&0 TASK F 8&O TASK F B&0 TASK F B&O TASK F 8&0 TASK F 8&0 TASK F B&0 TASK F 8&O TASK F 8&0 TASK F 8&0 TASK F 8&0 TASK F 8&0 TASK F 8&0 TASK 8&0 TASK F B&0 TASK 8&0 TASK F 8&0 TASK 8&0 TASK F 8&O TASK 8&O TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK
RESPONSE
IDENTIFY EHERGENCY ORCE -
ISO CONDENSER ISOLATION ON HIGH RAO.
ORCE - HOOIFY HPCI & RCIC BRK DETECTION CIRCUITRY ORCE - CHALLENGE & FAILURE OF RELIEF VALVES STUDY ORCE CHALLENGE & FAILURE OF RELIEF VALVES MODIFICATIONS.
ORCE -
ECC SYSTEH OUTAGES.
ORCE - ADS ACTUATION STUDY.
ORCE - ADS ACTUATION PRQPOSEO HQDIFICATIONS.
ORCE - AOS ACTUATION HODIFICATIONS.
ORCE - INTERLOCK RECIRCULATORY PUMP HOOIFICATIONS.
ORCE -
LOSS OF SVC WATER AT BRP ORCE - RESTART OF CSS & LPCI LQGIC DESIGN.
ORCE -
RESTART OF CSS
& LPCI LOGIC DESIGN HQDIFICATIONS.
ORCE RCIC SUCTION VERIFICATIQN PROCEDURES.
FORCE - RCIC SUCTION HODIFICATION.
ORCF. - SPACE COOLING FOR NPCIIRCI LOSS QF AC POWER.
FORCE -
POWER ON PUMP SEALS PROPOSEO HOOIFICATIONS.
ORCE -
POWER ON PUMP SEALS HODIFICATIONS.
FORCE -
COMHON REFERENCE LEVEL FOR BWRS.
ORCE - QUALIFICATION OF ADS ACCUMULATORS.
FORCE -
PERFORMANCE OF ISOLATION CONDENSERS.
FORCE - SCHEDULE FOR OUTLINE OF SB LOCA HQDEL FORCE - SB LOCA HOOEL, JUSTIFICATION.
FORCE - SB LOCA METHODS NEW ANALYSES.
FORCE - COMPLIANCE WITH CFR 50.46.
FORCE -
RCP SEAL DAMAGE - COVEREO BY II.K.2.16 AND II.K.3.25.
FORCE - EFFECTS OF SLUG FLOW - COVEREO BY II.K.2.15.
FORCE - EVALUATE TRANSIENT WITH SINGLE FAILURE FORCE ANALYSES TO SUPPORT.
TO LIST OF CONCERNS FROH ACRS CONSULTANT.
WATER SOURCES PRIOR TO MANUAL ACTIVATION OF ADS.
PREPAREDNESS, SHORT TERH.
MULTI-PLANT ISSUE NUMBER ACTION NO.
ISSUE TITLE LICENSEE IHPLEMENTATION STATUS III.A.1.2. 1 III.A.1.2.2 (SEE F063, III.A.1.2.3 (SEE F063, III.A.2.1 III.A.2.2 "III.D.l. 1.1
- III.D.l.l.2 III.D.3.3.1 III.D.3.3.2 III.D.3.4.1 "III.D.3.4.2 AIII.D.3.4.3 HPA-F008 MPA-F063 HPA-F064 MPA-F065 HPA-F071 HPA-8072 HPA-8083 67.4. 1
- F064, F065)
- F064, F065)
F067 F068 F069 F070 F070 F008 F063 F064 F065 F071 8072 8083 G001 UPGRADE EHERGENCY SUPPORT FACILITIES - INTERIH TSC OSC 6 EOF.
UPGRADE EHERGENCY SUPPORT FACILITIES-DESIGN-INCORP.
INTO F063/F064/F065.
UPGRADE EHER SUPPORT FACILITIES - HODS INCORPOR.
INTO F063, F064 4 F065.
UPGRADE PREPAREDNESS - UPGRADE EHERGENCY PLANS TO APP.
E.
UPGRADE PREPAREDNESS - HETEOROLOGICAL DATA.
PRIHARY COOLANT OUTSIDE CONTAINHENT - LEAK REDUCTION....
PRIHARY COOLANT OUTSIDE CONTAINHENT - TECH SPECS.
INPLANT RAD. HONIT. - PROVIDE HEANS TQ DETER.
PRESENCE OF RADIOIODINE IMPLANT RADIATION HONIT. - HODIFICATIONS TO ACCURATELY HEAS.
IODINE CONTROL ROOH HABITABILITY-REVIEW..
CONTROL ROOH HABITABILITY-SCHEDULE HODIFICATIONS.
CONTROL ROOH HABITABILITY-IHPLEMENT HODIFICATIONS.
I.D.l. 1 DETAILED CONTROL ROOH DESIGN REVIEW PROGRAH PLAN.
III.A.1.2 TECHNICAL SUPPORT CENTER.
III.A.1.2 OPERATIONAL SUPPORT CENTER.
III.A.1.2 EHERGENCY OPERATIONS FACILITY.
I.D. 1.2 DETAILED CONTROL ROOH REVIEW (FOLLOWUP TO F-8).
NUREG-0737 TECH SPECS (GENERIC LETTERS 82-16 6 83-02)
TECH SPEC COVERED BY GENERIC LETTERS 83-26 4 83-37 FOR NUREG-0737.
REACTOR COOLANT PUMP TRIP (GENERIC LETTER 85-12)..
GUIOELINES FOR UPOATING TNI STATUS 1.
The enclosure provides a complete listing of all TNI requirements from NUREG-0737 and NUREG-0737 Supplement I.
Regulatory Guide I.g7 requirements, although addressed in Supplement I to NUREG-0737, are excluded s1nce they did not orig1nate from the THI Action Plan.
This 11st1ng consists of a matrix of items applicable to both operating reactors and operating license applicants (NTOLS) as of Kovember,
- 1980, as shown in HUREG-0737 Enclosure I and 2, respect1vely.
All items which are not 11sted identically in Enclosure I and 2 are marked w1th asterisks to ind1cate differences between operat1ng reactor and HTOL requirements.
Nhenever these differences occur, enter data in accordance with the appropriate title, regardless of the THI Action Plan item nurber listed.
Your HRC Project Nanager has indicated wh1ch 1ssues are shown as unimplemented 1n the NRC tracking system.
Please rev1ew the entire list1ng for each licensed reactor unit.
Mhere an item was not appl1cable for your fac111ty, mark N/A in the implementation status column.
2.
Mhere an 1tem was applicable to your facility but no changes were necessary, mark HC in the 1mplementat1on status column.
3.
Hhere an item was applicable to your facility and changes are complete mark C 1n the implementation status column. If the date is readily ava11able (sooth and year) we request you provide 1t, however, C is suff1c1ent.
4.
Where an 1tem was applicable to your facility and is not fully imp1emented, provide your projected implementation date (month and year) and a short note 1dentify1ng the outstanding item (e.g.
- hardware, procedures, training, technical specificat1ons).
7 ~W~ey R~~~ r MULTI-PLANT ISSUE NUMBER ACTION NO.
ISSUE TITLE LICENSEE IMPLEMENTATION STATUS I.A.1.1. 1
<<I.A. l.l. 2
- I.A.l.l. 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. 1.5 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.1.2.8 I.C.1.3.A I.C.1.3.8 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.B I.D. 1 (See I.D.2.1 FOOl F002 F002 F003 F004 F004 F005 F005 F006 F007 FOOD & F071)
F009 SHIFT TECHNICAL ADVISOR - ON DUTY 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 ANO 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 ACCIO.
PROCEDURES REV. -
INADEQ.
CORE COOL.
REANAL. GUIDELINES.
SHORT-TERM ACCID. & PROCEDURES REV. -
INADEQ.
CORE COOL.
REVISE PROCEDURES...i>iamb Ct~
SHORT-TERM ACCID. & PROCEDURES REV - TRANSIENTS & ACCOTS.
REANAL GUIDELINES (PROC.
GEN. PKG.).
SHORT"TERM ACCID. & PROCEDURES REV. - TRANSIENTS & ACCORS.
REVISE PROCEDURES (UPGRADED EOP'S)./<&tdRCFC...
SHIFT & RELIEF TURNOVER PROCEDURES.
SHIFT-SUPERVISOR RESPONSIBILITY.
CONTROL-ROOM ACCESS.....
FEEDBACK OF OPERATING EXPERIENCE.
VERIFY CORRECT PERFORMANCE OF OPERATING ACTIVITIES.
NSSS VENDOR REV.
OF PROC -
LOM POWER TEST PROGRAM.
NSSS VENDOR REV.
OF PROC -
POWER ASCENSION & EMER.
PROCS.
PILOT MON OF SELECTEO EMERGENCY PROC FOR NTOLS.
CONTROL-ROOM DESIGN REVIEWS (ENTER DATA FOR MPA FOOD & MPA F-071).
PLANT-SAFETY PARAMETER DISPLAY CONSOLE - DESCRIPTION.
MULTI-PLANT ISSUE NUMBER ACTION NO.
ISSUE TITLE LICENSEE IMPLEMENTATION STATUS I.0.2.2 I.0.2.3 AI.G.1.1 AI.G.1.2
- I.G.1.3 II.8.1. 1 II.B.1.2 II.8.1.3 II.B. 2. 1 "II.B. 2. 2
- II.B.2. 3 "II.B.2.4
- II.8.3.1
- II.8.3. 2
- II.8.3.3
- II.B.3.4 I1.8.4.1 "II.B.4.2.A
- II.8.4.2. 8 II.D. 1. 1
- II.D. 1. 2. A
- II.O.1.2.8 II.D.1.3 "II.O. 3. 1 "II.0.3.2 "II.E.1.1.1 (SEE NOTE "II.E. 1. 1. 2 (SEE NOTE II.E.1.1.3 (SEE NOTE F009 F009 F010 F010 F011 F012 F013 F013 F013 F014 F015 1)
F015 2)
F015 3)
PLANT-SAFETY PARAMETER DISPLAY CONSOLE - IHSTALLED.
PLANT-SAFETY PARAMETER DISPLAY CONSOLE - FULLY IMPLEMENTED.
TRAIHIHG DURING LOW-POWER TESTING -
PROPOSE TESTS.
TRAINING DURING LOW-POWER TESTING - SUBMIT AHAL. 4 PROCS.
TRAIHING DURING LOW-POWER TESTING - TRAINING 8 RESULTS REACTOR-COOLANT SYSTEM VENTS - DESIGN VENTS.
REACTOR-COOLANT SYSTEM VENTS - INSTALL VENTS (LL CAT 8)......
REACTOR-COOLANT SYSTEM VEHTS - PROCEDURES.
PLANT SHIELDING - REVIEW DESIGNS.
PLANT SHIELDING - CORRECTIVE ACTIOHS TO ASSURE ACCESS.
PLANT SHIELDING - PLANT MODIFICATIONS (LL CAT 8).
PLANT SHIELDIHG - EQUIPMENT QUALIFICATION-NOT TRACKED AS A TMI ACTION ITEM.
POSTACCIOENT SAMPLING -
INTERIM SYSTEM.
POSTACCIOENT SAMPLING - CORRECTIVE ACTIONS.
POSTACCIOENT SAMPLIHG -
PROCEDURES.
POSTACCIOENT SAMPLING - PLANT MODIFICATIONS (LL CAT 8).
TRAIHIHG FOR MITIGATING CORE DAMAGE - DEVELOP TRAINING PROGRAM.
TRAIHING FOR MITIGATIHG CORE DAMAGE - INITIAL.
TRAIHIHG FOR MITIGATING CORE DAMAGE - COMPLETE RELIEF 4 SAFETY VALVE TEST REQUIREMENTS - SUBMIT PROGRAM.
RELIEF 4 SAFETY VALVE TEST REQUIREMENTS - COMPLETE TESTING.
RELIEF 4 SAFETY VALVE TEST REQUIREMENTS " PLANT SPECIFIC REPORT...lhf<OWP4P.M.
RELIEF 4 SAFETY VAVLE TEST REQUIREMENTS - BLOCK-VALVE TESTING.
VALVE POSITION INDICATIOH - INSTALL DIRECT INDICATIOHS OF VALVE POS.
VALVE POSTION INDICATION-TECH SPECS.
AFS EVALUATION-ANALYSIS.
AFS EVALUATIOH-SHORT TERM NODS.
AFS -LONG TERM MOOS.
NOTE 1 - 'THE ITEM LISTED IS FROM NUREG-0737, ENCLOSURE 2 AHD IS APPLICABLE TO NTOLS'S OHLY NOTE 2 - THE ITEM LISTED IS FOR ALL PLANTS (OPERATING REACTORS ANO NTOL'S)
NOTE 3 - THE ITEM LISTED IS FOR ALL PLANTS (OPERATING REACTORS AHO NTOL'S)
HULTI-PLANT ISSUE NUMBER ACTION NO.
ISSUE TITLE LICENSEE IHPLEHENTATION STATUS II.E.1.2.1.A II.E.1.2.1.8 II.E. 1.2.2. A "II.E. 1.2.2. 8 "II.E.1.2.2.C
- II.E.3. 1. 1 "II.E.3.1.2 II.E.4.1.1 "II.E.4. l. 2
- II.E.4.1.3 II.E.4.2.1-4
- II.E.4.2.5. A
- II.E.4.2.5. B II.E.4.2.6 II.E.4.2.7
- II. E.4.2. 8
- II.F.l.l "II.F.1.2.A
<<II.F.1.2.B "II. F. 1.2. C "II.F.1.2.0 "II.F.1.2.E
- II.F.1.2.F
- II. F.2. 1
- II.F.2.2
- II.F.2.3 "II.F.2.4
- II.G.l.l "II.G.1.2 II.K.1 (Oper.
F016 F017 F018 F019 F019 F020 F020 F021 F022 F023 F024 F025 F026 F026 Reactors Only)
AFS INITIATION& FLOW-CONTROL GRADE AFS INITIATION& FLOW - SAFETY GRADE AFS INITIATION& FLOW -
FLOW INDICATION CONTROL GRADE AFS INITIATION& FLOW - LL CAT A TECH SPECS.
AFS INITIATION& FLOW - SAFETY GRADE EHERGENCY POWER FOR PRESSURIZER HEATERS - UPGRADE POWER SUPPLY.
EHERGENCY POWER FOR PRESSURIZER HEATERS - TECH SPECS.
DEDICATED HYDROGEN PENETRATIONS - DESIGN.
DEDICATED HYDROGEN PENETRATIONS - REVIEW & REVISE H2 CONTROL PROC.
DEDICATED HYDROGEN PENETRATION - INSTALL CONTAINHENT ISOLATION DEPENDABILITY - IHP.
DIVERSE ISOLATION.
CONTAINHENT ISOLAT. DEPENDABILITY - CNTHT PRESS.
SETPT.
SEECIFIY PRESS.
CONTAINHENT ISOLATION DEPENDABILITY - CNTHT PRESSURE SETPT.
HODS.
CONTAINMENT ISOLATION DEPENDABILITY - CNTHT PURGE VALVES.
CONTAINMENT ISOLATION DEPENDABILITY - RADIATION SIGNAL ON PURGE VALVES.
CONTAINMENT ISOLATION OEPENDABLITY - TECH SPECS.
ACCIDENT - HONITORING -
PROCEDURES.
ACCIDENT - HONITORING - NOBLE GAS HONITOR.
ACCIDENT - HONITORING " IODINE/PARTICULATE SAMPLING.
ACCIDENT - MONITORING - CONTAINHENT HIGH-RANGE HONITOR.
ACCIDENT - MONITORING - CONTAINHENT PRESSURE ACCIDENT - HONITORING - CONTAINMENT WATER LEVEL.
ACCIDENT - HONITORING - CONTAINMENT HYDROGEN.
INSTRUHENTATION FOR DETECT.
OF INADEQUATE CORE COOLING - PROCEDURES.
INSTRUMENTATION FOR DETECT.
OF INADEQUATE CORE COOLING - SUBCOOL HETER.
INSTRUMENTATION FOR DETECT.
OF INADEQUATE CORE COOLING - OESC.
OTHER.
INSTRUMENTATION FOR DETECT.
OF INADEQUATE CORE CLING INSTLL ADD'L INSTRUHENTATION.
POWER SUPP.
FOR PRESSURIZER
- RELIEF, BLOCK VALVES & LEVEL IND. - UPGRADE.
POWER SUPP.
FOR PRESSURIZER
- RELIEF, BLOCK VALVES & LEVEL IND. - TECH SP.
IE BULLETINS 05, 79-06, 79-08.
MULTI-PLANT ISSUE NUMBER ACTION HO.
ISSUE TITLE LICENSEE IMPLEMENTATION STATUS
- II.K.l.5
- II. K.l. 10
<<II.K.1. 20
- II. K. l. 21
- II. K.l. 22
- II.K.l. 23
- II. K.2. 2 "II.K.2.8 II.K.2.9 II.K.2. 10 "II.K.2. 11 II. K.2. 13 II.K.2.14 II.K.2.15 II. K.2. 16 II. K.2. 17 II.K.2. 19 "II.K.2. 20 "II.K.3.1.A
- II.K.3. 1.8 II.K.3.2 II.K.3.3 II.K.3.5.A II.K.3.5.8 II.K.3. 7 II.K.3.9 II. K. 3. 10
- 11. K.3. 11 II.K.3. 12. A F027 F028 F029 F030 F031 F032 F033 F035 F036 F037 F038 F039 F039 F040 F041 II.K.3. 12. 8 F042 II.K.3. 13. A F043 II.K.3. 13. 8 F043 IE BULLETINS - REVIEW ESF VALVES.
IE BULLETINS - OPERABILITY STATUS.
IE BULLETINS -
PROMPT MANUAL REACTOR TRIP IE BULLETINS - AUTO SG ANTICIPATORY REACTOR TRIP.
IE BULLETIHS - AUX. HEAT REM SYSTEM, PROC IE BULLETIHS - RV LEVEL, PROCEDURES.
ORDERS ON 8&W PLANTS -
PROCEDURES TO CONTROL AFW IHD OF ICS.
ORDERS ON B&W PLANTS - UPGRADE AFW SYSTEM.
ORDERS ON B&W PLANTS - FEMA OH ICS.
ORDERS OH B&W PLANTS - SAFETY-GRADE TRIP ORDERS ON 8&W PLANTS - OPERATOR TRAINING.
ORDERS ON B&W PLANTS - THERMAL MECHANICAL REPORT (CE & W PLANTS ALSO).
ORDERS ON B&W PLANTS - LIFT FREQUENCY OF POAV'S & SV's.
ORDERS ON B&W PLANTS EFFECTS OF SLUG FLOW.
ORDERS ON 8&W PLANTS -
RCP SEAL DAMAGE.
ORDERS ON 8&W PLANTS - VOIDING IN RCS (CE & W PLANTS ALSO).
BENCHMARK ANALYSIS OF SEQUENTIAL AFW FLO'W TO ONCE THROUGH STM GENERATOR ORDERS OH 8&W PLANTS - SYSTEM RESPONSE TO SB LOCA.
8&0 TASK FORCE - AUTOMATIC PORV ISOLATION DESIGN.
FINAL RECOMMENDATIONS, 8&0 TASK FORCE - AUTO PORV ISO TESTIINSTALL 8&0 TASK FORCE -
REPORT OH PORV FAILURES.
8&O TASK FORCE - REPORTIHG SV & RV FAILURES AHD CHALLENGES.
8&0 TASK FORCE - AUTO TRIP OF RCP'S PROPOSED MODIFICATIONS.
8&0 TASK FORCE - AUTO TRIP OF RCP'S MODIFICATIONS.
8&0 TASK FORCE - EVALUATION OF PORV OPENING PROBABILITIES.
8&0 TASK FORCE - PID CONTROLLER MODIFICATION.
8&0 TASK FORCE -
PROPOSED ANTICIPATORY TRIP MODIFICATIONS.
8&0 TASK FORCE - JUSTIFY USE OF CERTAIN PORV.
8&0 TASK FORCE - ANTICIPATORY TRIP ON TURBINE TRIP PROPOSED NODS.
8&0 TASK FORCE - ANTICIPATORY TRIP ON TURBINE TRIP INSTALL MOOS.
8&0 TASK FORCE " HPCI & RCIC SYSTEM INITIATION LEVELS ANALYSIS.
8&0 TASK FORCE - HPCI & RCIC IHITIATIOH LEVELS MODIFICATION.
~I
~.
~
g
ISSUE NUMBER MULTI-PLANT ACTION NO.
ISSUE TITLE LICENSEE IMPLEMENTATION STATUS
- II.K.3.14 II.K.3.15 II.K.3.16A II.K.3.16.8 II.K.3. 17 II.K.3. 18. A II.K.3. 18. 8 II.K.3. 18. C "II.K.3. 19
- II.K.3. 20 II. K.3. 21. A II.K.3.21.8 II. K.3. 22. A II.K.3. 22. 8 II.K.3. 24 II. K.3. 25. A II.K.3.25. 8 II. K.3. 27 II.K.3. 28
<<II.K.3.29 II.K.3.30.A II.K.3.30.8 II.K.3. 30. C II.K.3.31
- II.K.3.40
<<II.K.3.43 II.K.3.44 II.K.3.45 II.K.3. 46
- II.K.3. 57 III.A.1.1 F044 F045 F046 F046 F047 F048 F048 F048 F049 F050 F050 F051 F051 F052 F053 F054 F055 F056 F057 F058 F059 F060 F061 F062 8&0 TASK F B&0 TASK F 8&0 TASK F B&0 TASK F 8&0 TASK F 8&0 TASK F 8&0 TASK F 8&0 TASK F 8&0 TASK F B&0 TASK F 8&0 TASK F 8&0 TASK F 8&0 TASK F 8&0 TASK F 8&0 TASK 8&0 TASK F 8&0 TASK 8&0 TASK B&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK
RESPONSE
IDENTIFY W EMERGENCY ORCE -
ISO CONDENSER ISOLATION OH HIGH RAD.
ORCE - MODIFY MPCI & RCIC BRK DETECTION CIRCUITRY.
ORCE - CHALLENGE & FAILURE OF RELIEF VALVES STUDY.
ORCE - CHALLENGE & FAILURE OF RELIEF VALVES MODIFICATIONS.
ORCE -
ECC SYSTEM OUTAGES.
ORCE - ADS ACTUATION STUDY.
ORCE - ADS ACTUATION PROPOSED MODIFICATIONS.
ORCE - ADS ACTUATION MODIFICATIONS.
ORCE -
INTERLOCK RECIRCULATORY PUMP MODIFICATIONS.
ORCE -
ORCE - RESTART OF CSS & LPCI LOGIC DESIGN.
ORCE - RESTART OF CSS & LPCI LOGIC DESIGN MODIFICATIONS.
ORCE " RCIC SUCTION VERIFICATION PROCEDURES.
ORCE - RCIC SUCTION MODIFICATION.
FORCE - SPACE COOLING FOR HPCI/RCI LOSS OF AC POWER.
ORCE -
POWER ON PUMP SEALS PROPOSED MODIFICATIONS.
FORCE -
POWER ON PUMP SEALS MODIFICATIONS.
FORCE -
COMMON REFERENCE LEVEL FOR BWRS........................
FORCE - QUALIFICATION OF ADS ACCUMULATORS.
FORCE - PERFORMANCE OF ISOLATION CONOENSERS.
FORCE - SCHEDULE FOR OUTLINE OF SB LOCA MODEL.
FORCE - SB LOCA MODEL, JUSTIFICATION.
FORCE -
FORCE - COMPLIANCE WITH CFR 50.46..
FORCE -
RCP SEAL DAMAGE - COVERED BY II.K.2.16 AND II.K.3.25.
FORCE -
EFFECTS OF SLUG FLOW - COVEREO BY II.K.2.15.
FORCE - EVALUATE TRANSIENT WITH SINGLE FAILURE FORCE - ANALYSES TO SUPPORT TO LIST OF CONCERNS FROM ACRS CONSULTANT.
ATER SOURCES PRIOR TO MANUAL ACTIVATIOH OF ADS.
PREPAREDNESS, SHORT TERM.
MULTI-PLANT ISSUE NUMBER ACTION NO.
ISSUE TITLE LICENSEE IHPLEHENTATION STATUS 111.A. l.2. 1 111.A. l.2. 2 (SEE F063, III.A.1.2.3 (SEE F063, III.A.2.1 111.A. 2. 2 "III.D.l. 1. 1 "111.D. l.l.2 111.D.3. 3. 1 111.D. 3. 3. 2 III.D.3.4. I "111.D. 3.4. 2
~ II1.0.3.4. 3 HPA-FOOD HPA-F063 HPA-F064 HPA-F065 MPA-F071 MPA-8072 HPA-8083 67.4.1
- F064, F065)
- F064, F065)
F067 F068 F069 F070 F070 FOOD F063 F064 F065 F071 8072 8083 G001 UPGRADE EHERGENCY SUPPORT FACILITIES - INTERIH TSC OSC E
EOF UPGRADE EHERGENCY SUPPORT FACILITIES-DESIGN-INCORP. INTO F063/F064/F065.
UPGRADE EHER SUPPORT FACILITIES - HODS INCORPOR.
INTO F063, F064 8 F065.
UPGRADE PREPAREDNESS - UPGRADE EHERGENCY PLANS TO APP.
E.
UPGRADE PREPAREDNESS - HETEOROLOGICAL DATA.
PRIHARY COOLANT OUTSIDE CONTAINMENT - LEAK REDUCTION.
PRIHARY COOLANT OUTSIDE CONTAINMENT - TECH SPECS.
INPLANT RAD. HONIT. - PROVIDE MEANS TO DETER.
PRESENCE OF RADIOIODINE.
IMPLANT RADIATION HONIT. - HODIFICATIONS TO ACCURATELY HEAS.
CONTROL ROOH HABITABILITY-REVIEW.
CONTROL ROOH HABITABILITY-SCHEDULE HODIFICATIONS.
CONTROL ROOH HABITABILITY-IHPLEHENT MODIFICATIONS.
I.D.l.l DETAILED CONTROL ROOH DESIGN REVIEW PROGRAH PLAN.
III.A.1.2 TECHNICAL SUPPORT CENTER.
III.A.1.2 OPERATIONAL SUPPORT CENTER.
III.A.1.2 EMERGENCY OPERATIONS FACILITY.
1.0. 1.2 DETAILED CONTROL ROOH REVIEW (FOLLOWUP TO F-B).
NUREG-0737 TECH SPECS (GENERIC LETTERS 82-16 4 83-02)
TECH SPEC COVEREO BY GENERIC LETTERS 83-26 6 83-37 FOR NUREG-0737.
REACTOR COOLANT PUMP TRIP (GENERIC LETTER 85-12)