ML17342A480
| ML17342A480 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 04/21/1986 |
| From: | Mcdonald D Office of Nuclear Reactor Regulation |
| To: | Woody C FLORIDA POWER & LIGHT CO. |
| References | |
| NUDOCS 8604250069 | |
| Download: ML17342A480 (30) | |
Text
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April 21, 1986 Docket.,Nos.
50-250 and 50-251 1
Mr. C. 0.
Woody, Group Vice President Nuclear Ener'gy Department Florida Power and Light Company Post Office Box 14000 Juno Beach, Florida 33408
Dear Mr. Woody:
Subject:
Implementation of Generic Items DISTRIBUTION C~
NRC PDR Local PDR PADP2 Rdg T. Novak OELD E. Jordan B. Grimes J. Partlow D. McDonald D. Miller ACRS (10)
Tech Branch Gray File The Comptroller General in a Report to the Congress dated September 19, 1984, stated "NRC needs better management controls to ensure implementation of generic issue solutions."
To correct this situation, the Nuclear Regulatory Commission is working on a long-term program which will improve its documentation on the status of power reactor licensees'mplementation of approved regulatory improvements.
To assist me in developing this information for the Turkey Point Plant Units 3 and 4, please review the enclosed plant-specific list, add omitted significant actions to the list, and provide the date that all aspects of each identified requirement were completed/implemented or are expected to be completed.
For each requirement that has been completed, enter "completed" under the Status column and the date the item was completed.
For requirements that have not been completed/implemented, provide the projected date and enter "projected" under the Status column.
I do not expect or want a major effort made to obtain precise dates.
- Rather, I will accept readily-known or best-estimate dates for actions that have been completely implemented.
For example, the year only would be acceptable for completions prior to 1984; the month as well as year is needed for requirements completed after that time.
For projected completions/implementations in 1986, use month and year.
Use year only for projections thereafter.
Please provide a response in the form of a marked up listing by May 31, 1986.
To the extent that you cannot mark up the list for all items by this date, please give priority to those items resulting from TMI and submit remaining items at a later date.
In the future, NRR will need estimated dates prior to issuance of the safety evaluation so that the estimated schedule may be included in the evaluation.
8604850069 86048>
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Mr. C. 0.
Woody The reporting and/or recordkeeping requirements contained in this letter affect fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely,
Enclosure:
As stated cc,) w/ou t f encl osure:
See next p'age '
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Daniel G. McDonald, Project Manager PWR Project Directorate ¹2 Division of PWR Licensing-A Office of Nuclear Reactor Regulation 1S ct 4
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Woody Florida 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 Norman A. Coll, Esquire
- Steel, Hector and Davis 4000 Southeast Financial Center Miami, Florida 33131-2398 Mr. C.
M. Wethy, Yice Pres ident Turkey Point Nuclear Plant Florida Power and Light Company P.O.
Box 029100 Miami, Florida 33102 Mr. M. R. Stierheim County Manager of Metropolitan Dade County Miami, Florida 33130 Resident Inspector U.S. Nuclear Regulatory Commission Turkey Point Nuclear Generating Station Post Office Box 57-1185 Miami, Florida 33257-1185 Mr. Allan Schubert, Manager Public Health Physicist Department of Health and Rehabilitative Services 1323 Winewood Blvd.
Tallahassee, Florida 32301 Intergovernmental Coordination and Review Office of Planning 5 Budget Executive Office of the Governor The Capitol Building Tallahassee, Florida 32301 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Regional Administrator, Region II U.S. Nuclear Regulatory Commission Suite 2900 101 Marietta Street Atlanta, Georgia 30323 Martin K. Hodder, Esquire 1131 NE, 86th Street Miami, Florida 33138 Joette Lorion 7269 SW, 54 Avenue Miami, Flori da 33143 Mr. Chris J. Baker, Plant Manager Turkey Point Nuclear Plant Florida Power and Light Company P.O.
Box 029100 Miami, Florida 33102 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304
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1208731-001 REGULATORY INFORMATION TRACKING SYSTEM FACI L I TY IMP L EMENTATI ON PAGE NO '0>
03/31/86 CILITYc TURKEY POINT 3 ANT LOCATION: 25 MI S OF MIAMI> FLA CKET NUMBER:
050-00250 CH/ENGINEERc BECH INSPECTORc T.
PEEBLES LICENSED POWER>
2200 MWT DESIGN POWER:
0693 MWE NSSS VENDORS WEST PROJECT MANAGERc D.
MCDONALD BRANCH CHIEF:
L. RUBENSTEIN LIC. ASSISTANT:
VACANT 8326 A-01 10 CFR 50.55 A(G) ISI 8127 A-02 APPENDIX I - ALARA 7412 A-03 SECURITY REVIEWS-MODIFIED AMENDMENT PLANS 8779 A-04 APPENDIX J CONTAINMENT LEAK TESTING 8790 A-06 RESPIRATORY PROTECTION SYSTEM 1373 A-09 PRESSURE VESSEL BELTLINE MATERIAL SURVEILLANCE 0392 A-1 0 CONTINGENCY PLANNING 0396 A-11 GUARD TRAINING PLANS 0394 A-12 VITAL AREA ANALYSIS LIC ACT
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04/26/83C 04/23/84C 02/27/79C 11/04/81C 02/15/79C 02/27/80C 11/28/80C 09/04/81C 04/12/82C LICENSEE
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~DA 7084 A-16 QUALIFICATIONS OF EXAMINATIONs INSPECTIONs TESTING 11/02/81C 1363 A-17 INSTRUMENTATION TO FOLLOW THE COURSE OF AN ACCIDEN 01/31/86 5752 A-18 TECH SPECS AFFECTED BY 50.72 AND 50.73 (GL 83-43) 01/31/86 671 7 B"04 B-.07 REACTOR VESSEL OVERPRESSURE PROTECTION STEAM GENERATOR FEEDWATER FLOW INSTABILITY 7965 B-11 FLOOD OF EQUIPMENT IMPORTANT TO SAFETY 0404 B-13 FUEL ROD BOW 9153 A-20 10 CFR 50.62 OPERATING REACTOR REVIEWS 9992 A-21 10 CFR 50.61'RESSURIZED THERMAL SHOCK RULE 6614 B-02 FIRE PROTECTION 8405 B-03 PWR MODERATOR DILUTION 07/31/87 01/30/87 03/21/79C 02/21/79C 03/14/80C 02/04/80C 09/04/79C 01/31/80C 0
208731-001 KEY POINT 3 REGULATORY INFORMATION TRACKING SYSTEM FACI L ITY IMP L EMENTATION (CONTINUATION)
PAGE NO.!
506 03/31/86
~0 796 B-14 152 B-16 CEA GUIDE TUBE HEAR EMfRGENCY PLANNING AND REVISIONS 786 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS 276 B-20 CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION LIC ACT
~CONP T
07/07/80C 04/01/81 C 05/14/81C 01/28/81C LICENSEE
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~DA 340 B-21 LOSS OF 125-V DC BUS VOLTAGE HITH LOSS OF ANNUNCIA 02/28/82C 784 B-22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 10/14/83C 057 B-23 DEGRADED GRID VOLTAGE 08/14/84C 564 B-24 VENTING AND PURGING CONTAINMENTS NHILE AT FULL POH 03/30/83C 202 B-24 VENTING AND PURGING CONTAINMENTS HHILE AT FULL POH 12/08/80C 237 B-26 INADVERTANT SAFETY INJECTION DURING COOLDOHN 126 B-30 STEAM GENERATOR REPLACEMENT PROGRAM 437 B-32 BLOCKED SI SIGNAL DURING COOLDONN 415 B-32 BLOCKED SI SIGNAL DURING COOLDONN 686 B-39 PHR PRESSURE TEMPERATURE LIMIT TECH SPECS 12/28/79C 01/29/79C 04/01/82C 04/13/84C 01/29/81C 552 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S
03/27/84C 081 B-41 FIRE PROTECTION FINAL TECH SPECS (INCLUDES SER S
04/26/81C 849 B-41 FIRE PROTECTION FINAL TECH SPECS (INCLUDES SER S
04/16/84C 807 B-41 FIRE PROTECTION FINAL TECH SPECS (INCLUDES SER S
05/10/82C
'24 B-42 TMI FOLLOH UP ALL PLANTS 716'-42 TMI FOLLOH UP ALL PLANTS 780 B-43 PNR FEEDHATER lINE CRACKS 156 B-43 PHR FEEDWATER LINE CRACKS 390 B-44 LESSONS LEARNED IMPLEMENTATION 07/07/80C 04/01/81 C 02/22/80C 05/25/82C 04/07/80C
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PAGE NO.>
507 03/31/85
~AC NO
~ljt M30391 M30392 LESSONS LEARNED IMPLEMENTATION LESSONS LEARNED IMPLEMENTATION N30384 B-44 LESSONS LEARNED IMPLEMENTATION 830385 B-44 LESSONS LEARNED IMPLEMENTATION N30386 B-44 LESSONS LEARNED IMPLEMENTATION 830387 B-44 LESSONS LEARNED IMPLEMENTATION 830388 B-44 LESSONS LEARNED IMPLEMENTATION 130389 B-44 LESSONS LEARNED IMPLEMENTATION M30393 B-44.
LESSONS LEARNED IMPLEMENTATION M30382 B-44 LESSONS LEARNED IMPLEMENTATION M30383 B-44 LESSONS LEARNED IMPLEMENTATION LIC ACT
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04/07/80C 04/07/80C 04/07/80C 04/07/80C 04/07/80C 04/07/80C 04/07/80C 04/07/80C 04/07/80C 04/07/80C 04/07/80C LICENSEE 812940 B-45 HASH 1400 EVENT Vp "PRIMARY COOLANT SYSTEM PRESSUR 04/20/81C 112574 B-46 ANALYSIS OF TURBINE DISC CRACKS 812690 B-47 ECCSp CLAD SWELLING AND RUPTURE 112964 413036 B"49 ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE PHR CONTROL ROD MISALIGNMENT 08/21/81C 09/12/80C 12/17/82C 05/06/81C 411881 B-52 REVIEW OF SAFETY ASPECT OF INADVERTENT SAFETY ACTI 10/21/80C
%2322 B-53 LESSONS LEARNED CATEGORY B (ITEMS) 542712 542784 B-61 B-62 LOSS OF NON CLASS IE I&C POWER ESF RESET CONTROL DESIGN DEFICIENCY
%21 03 B"57 DHR CAPABILITY 442869 B-59 MASONRY HALL DESIGN 142470 B"60 ENVIRONMENTAL QUALIFICATION 10/31/80C 07/30/82C 01/04/85C 10/25/84C 07/28/82C 05/12/82C
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PAGE NO.:
. 508 03/31/86
~CN 0 i 13913
'17154
>6866
>66%0 B-63 B-66 B-69 B-70 INTERIM PROCEDURES FOR SHORT TERN BLACKOUT NATURAL CIRCULATION COOLDOWN
- IEB 80-0 NAINSTEAN LINE BREAK WITH CONTINUED FEEDW FATIGUE TRANSIENT LIMIT TS
)9766 B-72 NUREG 0737 TECH SPECS (GENERIC LETTER 82-16)
LIC ACT CON~P 06/26/82C 07/28/83C 10/20/82C 05/25/82C 08/27/86C LICENSEE B-73 PLANS FOR PREVENTING EXCEEDING PTS SCREENING CRITE 11/17/83C B-76 ITEN 1.1 - POST TRIP REVIEWp PROGRAN DESCRIPTION 06/25/85C B-77 ITEN 2.1 - EQUIPNENT CLASSIFICATION & VENDOR INTER 09/30/86 B-78 ITENS 3.1.1
& 3.1.2
-POST MAINTENANCE TEST PROCEDU 01/15/86 B-79 ITEN 3.1.3 - POST NAINTENANCE TESTING CHANGES TO 11/14/85C B-80 ITEN 0.1 REACTOR TRIP SYSTEM RELIABILITY VENDO 01/15/86 B-81 ITEMS 4.2.1
& 0.2.2
-PREVENTATIVE PAINT PROG FOR R
06/29/85C B-82 ITEN 4.3 AUTONATIC ACTUATION OF SHUNT TRIP ATTAC 12/03/84C B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83-10/17/84C
)9611 i2810 i2891 i2972 i3053 i31 07 i3160 i3202 i%576 i3643 B-85 SALEM ATWS 1.2 DATA CAPABILITY 11/27/85C 01/01/87 12/31/86 11/1 0/85C 11/28/86 02/28/86 11/01/86 00/30/87 i3726 B-86 SALEM ATWS 2.2 S-R COMPONENTS i3809 B-87 SALEM ATWS 3.2.1
& 3.2.2 S-R CONPONENTS B-88 SALEM ATWS 3.2.3 T.S.
S-R CONPONENTS B-89 SALEM ATWS 4.2;3
& 0.2.0 LIFE COMPONENTS i3892
'i3947 i5384 B"90 SALEM ATWS 0.3 W AND B&W T.S.
B-92 SALEM ATWS 6.5.1 DIVERSE TRIP FEATURES i%119 i6036 B-93 SALEN ATWS 0.5.2
& 0.5.3 TEST ALTERNATIVES I8255 C-01 PWR SECONDARY WATER CHEMISTRY MONITORING REQUIRENE 10/30/81C
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PAGE NO.>
50'.
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l08651 I03963 l08793 C-03 C-04 C-06 QUALIFICATIONS OF RADIATION PROTECTION MANAGER JILTER TECH SPECS PUMP SUPPORT-LAMELLAR TEARING l08798 C-07 FUEL HANDLING ACCIDENT INSIDE CONTAINMENT LIC ACT
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~DA l08088 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE 11/01/83C l13041 C-13 LOSS OF OFFSITE POWER I43649 C-14 AUXILIARYFEEDWATER SEISMIC QUALIFICATION 05/06/80C 08/25/83C l52281 C-15 CONTROL OF HEAVY LOADS PHASE II (FOLLOWUP OF MPA 06r28r85C I58098 C-16 UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN 01/22/86C l07878 D-02 ECCS ZIRC CLAD MODEL ERROR-COMPLIANCE WITH 10 CFR-09r22r78C I07859 D-03 PRESSURIZER HEATUP RATE ERROR 108782 D-10 ASYMMETRIC LOCA LOADS l10002 D-11 FISSION GAS RELEASE l08800 D-14 REACTOR VESSEL WELD WIRE DEFICIENCY 10/25/78C 02/06/84C 02/22/80C 02/13/79C l12280 D-15 HIGH ENERGY LINE BREAK 8 CONSEQUENTIAL SYSTEM FAIL 02/02/84C I43013 D-17 DEFINITION OF OPERABLE 05/1 2/81 C I55915 D-19 DIESEL GENERATOR RELIABILITYTECH SPECS (GL 84-15) 03/31/86 I44275 l44345 F-04 F-05 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC I.C.1.2/3.B PROCEDURES GENERATION PACKAGES (NUREG I47259 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE I44062 F-01 I.A.1.1 SHIFT TECHNICAL ADVISOR
=I44133 F-02 I.A.1.3 SHIFT MANNING 144204 F-03 I.A.2.1 UPGRADING OF RO AND SRO TRAINING 01/08/82C 06/30/83C 10/25/82C 06/07/84C 11/30/86 10/20/81C
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PAGE NO ~ i. 516 D3/31/86
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Yt7331 151213 F-07 F-08 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI
'I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEN PROGRA 551293 F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM 144413 F-1 0 II.B.1 RCS HIGH POINT VENTS
'I47982 F-11 I I.B. 2 PLANT SHIELDING
'I44483 F-12 II.B.3 POST ACCIDENT SAMPLING 144554 F-13 II.B.4 TRAINING FOR MITIGATING CORE DAMAGE Yt4626 F-14 II.D.1 RV AND SV TRAINING 142324 F-15 II.E.1.1 AFW SYSTEM EVALUATION
%4697 144736 F-16 II.E.1.2.1 AFH SYSTEM INITIATION F-17 II.E.1.2.2 AFH SYSTEM FLON INDICATION 144822 F-18 II.E.4.1 DEDICATED HYDROGEN PENETRATION Yi4893 F-19 II.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY 144964 F-20 II.F.1.1 NOBLE GAS MONITOR 145035 F-21 II.F.1.2 IODINE/PARTICULATE SAMPLING Yi51 06 F-22 I I. F. 1. 3 CONTAINMENT HIGH RANGE MONITOR Yi7643 F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT
'l47714 F-24 II.F.1.5 CONTAINMENT HATER LEVEL INSTRUMENT
%7785 F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR LIC ACT
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10/20/81C 01/1 6/84C 03/04/85C 09/02/83C 06/30/83C 11/08/83C 10/25/82C 09/30/86 11/04/82C 09/15/82C 09/15/82C 03/25/82C 11/12/82C 09/30/81C 09/30/81C 02/08/82C 05/02/83C 05/02/83C 05/02/83C LICENSEE
~SA~U 145t76 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 01/26/85C 146910 F-30 II.K.2.13 THERMAL-MECHANICALREPORT 547824 F-33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS Y45254 F-36 II.K.3.1 AUTO PORV ISOLATION 06/06/84C 01/06/84C 09/16/83C
R-1208731-001 TURKEY POINT 3 REGULATORY INFORMATION TRACKING SYSTEM FACIL ITY IMPS ENENTATI ON (CONTINUATION)
PAGE NO.t 51 03/31/8 IK 8o HEM M45300 M45386 iM45417 M45466 F-37 F-38 II.K.3.2 REPORT ON PORV FAILURES "KI.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE F-39 II.K.3.5 AUTO TRIP OF RCPS F-40 II.K.3.9 PID CONTROLLER M45496 F-41 II.K.3.10 ANTICIPATORY TRIP MODIFICATIONS M45526 F-42 II.K.3.12 ANTICIPATORY TRIP ON TURBINE TRIP M45673 F-47 II.K.3.17 ECCS OUTAGES M48437 F-53 II.K.3.25 POHER ON PUMP SEALS M45869 F-57 II.K.3.30 SB LOCA METHODS M48210 F-58 II.K.3.31 COMPLIANCE HITH 10 CFR 50.46 IM45988 F-63 III.A.1. 2 TECHNICAL SUPPORT CENTER M46060 F-64 III.A.1.2 OPERATIONAL SUPPORT CENTER M46347 F-68 III.A'.2.2 METEOROLOGICAL DATA UPGRADE M46418 F-69 III.D.3.3 IMPLANT RADIATION MONITORING M46487 F-70 III.D.3.4 CONTROL ROOM HABITABILITY M46132 F"65 III.A.1.2 EMERGENCY OPERATIONS FACILITY M46204 F-66 III.A.1.2 NUCLEAR DATA LINK M46276 F-67 III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE LIC ACT gONPIg~
09/16/83C 06/24/82C 02/22/83C 08/20/81C 08/20/81C 08/20/81C 08/26/83C 06/24/82C 05/29/85C 12/31/86 06/30/86 06/30/86 06/30/86 07/30/82C 05/13/83C 06/30/86 02/09/82C 11/25/83C LICENSEE
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- M56177 F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEH (FOLLONUP TO 05/21/85C M49678 G-01 REACTOR COOLANT PUMP TRIP (D660 II.K.3.5) 04/20/86
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1208731-001 CILITY: TURKEY POINT 4 REGULATORY INFORMATION TRACKING SYSTEM FACILITY IMP L EMENTATION PAGE NO.~
512 03/31/86 ANT LOCATION: 25 MI S OF MIAMIi FLA CKET NUMBER:
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NEST LIC ACT
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MCDONALD BRANCH CHIEF:
L. RUBENSTEIN LIC. "ASSISTANT>
VACANT LICENSEE
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~AT 8287 A-01 10 CFR 50.55 A(G) ISI 8128 A-02 APPENDIX I - ALARA 8795 A-03 SECURITY REVIEHS-MODIFIED AMENDMENT PLANS 8780 A-06 APPENDIX J CONTAINMENT LEAK TESTING 8791 A"06 RESPIRATORY PROTECTION SYSTEM 1372 A-09 PRESSURE VESSEL BELTLINE MATERIAL SURVEILLANCE r
0393 A-10 CONTINGENCY PLANNING 0397 A-11 GUARD TRAINING PLANS 0395 A-12 VITAL AREA ANALYSIS 04/26/83C 0I/23/8 4 C 02/27/79C 11/00/81C 02/15/79C 02/27/80C 11/28/80C 09/06/81C 04/12/82C 7085 A 16 QUALIFICATIONS OF EXAMINATIONi INSPECTIONi TESTING 11/02/81C 1364 A-17 INSTRUMENTATION TO FOLLOH THE COURSE OF AN ACCIDEN 01/31/86 5753 A-18 TECH'PECS AFFECTED BY 50.72 AND 50.73 (GL 83-43) 01/31/86 915%
A-20 10 CFR 50.62 OPERATING REACTOR REVIEWS 9993 A-21 10 CFR 50.61>
PRESSURIZED THERMAL SHOCK RULE 8788 B-02 'IRE PROTECTION 8006 B-03 PHR MODERATOR DILUTION 8789.
B-04 REACTOR VESSEL OVERPRESSURE PROTECTION 7831 B-07 STEAM GENERATOR FEEDHATER FLOH INSTABILITY 7962 B-11 FLOOD OF EQUIPMENT IMPORTANT TO SAFETY 0405 B-13 FUEL ROD BOW 07/31/87 01/30/87 03/21/79C 02/21/79C 03/14/80C 02/04/80C 09/04/79C 01/31/80C
1208731-001 RKEY POINT 4 REGULATORY INFORNATI F A C I L I T Y I H P L
(CONTINUATION)
ON TRACKING SYSTEM ENENTATI ON PAGE NO.>
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8797 2153 8787 0277 0341 8785 0058 2565 0201 0238 1990 8809 8792 9416 8687 3808 8553 3850 1082 1717.
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,CEA GUIDE TUBE WEAR B-16
&IERGENCY PLANNING AND REVISIONS B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS B-20 CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION B-21 LOSS OF 125-V DC BUS VOLTAGE WITH LOSS OF ANNUNCIA B-22 TECH SPEC SURVEILLANCE REOUIRENENTS FOR MECHANICAL B-23 DEGRADED GRID VOLTAGE B-24 VENTING AND PURGING CONTAINHENTS WHILE AT FULL POW B-24 VENTING AND PURGING CONTAINMENTS WHILE AT FULL POW B-26 INADVERTANT SAFETY INJECTION DURING COOLDOWN B-30 STEAN GENERATOR REPLACEMENT PROGRAN B-30 STEAN GENERATOR REPLACEMENT PROGRAM B-32 BLOCKED SI SIGNAL DURING COOLDOWN B-32 BLOCKED SI SIGNAL DURING COOLDOWN B-39 PWR PRESSURE TEMPERATURE LIHIT TECH SPECS B-41 FIRE PROTECTION FINAL TECH SPECS (INCLUDES SER S
B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S
B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S
B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S
B"42 TNI FOLLOW UP ALL PLANTS B-42 TNI FOLLOW UP ALL PLANTS B-43 PWR FEEDWATER LINE CRACKS B-43 PWR FEEDWATER LINE CRACKS LIC ACT
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208731-001 KEY POINT 4 REGULATORY INFORMATI F A C I L I T Y I M P L
(CONTINUATION)
ON TRACKING SYSTEM EMENTAT I ON PAGE NO.i 514 03/31/86 0
~A~
95 LESSONS LEARNED IMPLEMENTATION LBSSONS LEARNED IMPLEMENTATION 96 B-44
. LESSONS LEARNED IMPLEMENTATION 97 B-44 LESSONS LEARNED IMPLEMENTATION 98 B-44 LESSONS LEARNED IMPLEMENTATION 99 B-44 LESSONS LEARNED IMPLEMENTATION 00 B-44 LESSONS LEARNED IMPLEMENTATION 01 B-44 LESSONS LEARNED IMPLEMENTATION 02 B-44 LESSONS LEARNED IMPLEMENTATION 03 B-44 LESSONS LEARNED IMPLEMENTATION 04 B-44 LESSONS LEARNED IMPLEMENTATION 05 B-44 LESSONS LEARNED IMPLEMENTATION 06 B-44 LESSONS LEARNED IMPLEMENTATION 07 B-44 LESSONS LEARNED IMPLEMENTATION LIC ACT
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04/07/SOC 04/07/SOC 04/07/SOC 04/07/80C 04/07/SOC 04/07/SOC 04/07/SOC 04/07/SOC 04/07/SOC 04/07/80C 04/07/80C 04/07/80C 04/07/SOC 04/07/80C LICENSEE
~~S Dllg 41 B 45 HASH 1 400 EVENT Vp PRIMARY COOLANT SYSTEM PRESSUR 04/20/81 C 75 B-46 ANALYSIS OF TURBINE DISC CRACKS 91 B"47 ECCSJ CLAD SHELLING AND RUPTURE 08/21/81 C 09/12/80C 65 B-48 ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 12/17/82C 37 B-49 PHR CONTROL ROD MISALIGNMENT 05/06/81C 82 23 B-53 LESSONS LEARNED CATEGORY B (ITEMS) 10/31/SOC 07/06/81C 07/30/82C 24 B-54 LESSONS CATEGORY A TECH SPEC 104 B-57 DHR CAPABILITY B-52 REVIEH OF SAFETY ASPECT OF INADVERTENT SAFETY ACTI 10/21/SOC
208731-001 KEY POINT 4 REGULATORY INFORMATION TRACKI NG SYSTEM FACILITY IMPLEMENTATION (CONTINUATION)
PAGE NO.~
515 03/31/86 55M 870 B-59
,MASONRY HALL DESIGN 471 B-60 ENVIRONMENTAL QUALIFICATION 713 B-61:
LOSS OF NON CLASS IE I&C POHER 785 B-62 ESF RESET CONTROL DESIGN DEFICIENCY 914 B-63 INTERIM PROCEDURES FOR SHORT TERM BLACKOUT 155 B-66 NATURAL CIRCULATION COOLDOHN 550 B-67 THERMAL SHOCK 028 B-67 THERMAL SHOCK LIC ACT
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01/04/85C 10/25/84C 07/28/82C 05/12/82C 04/26/82C 07/28/83C 02/09/83C 01/21/82C LICENSEE MQK 2LTK 867 B-69 IEB 80-4 MAINSTEAM LINE BREAK WITH CONTINUED FEEDH 10/20/82C 641 B-70 FATIGUE TRANSIENT LIMIT TS 767 B-72 NUREG 0737 TECH SPECS (GENERIC LETTER 82-16) 05/25/82C 10/01/84C 612 B-73 PLANS FOR PREVENTING EXCEEDING PTS SCREENING CRITE 11/17/83C 811 B-76 ITEM 1.1 POST TRIP REVIEHi PROGRAM DESCRIPTION &
06/25/85C 892 B-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION & VENDOR INTER 09/30/86 973 B-78 ITEMS 3.1.1
& 3.1.2
-POST MAINTENANCE TEST PROCEDU 054 B-79 ITEM 3.1.3 POST MAINTENANCE TESTING CHANGES TO 01/15/86 11/14/85C 0,
108 B-80 ITEM 4.1 REACTOR TRIP SYSTEM RELIABILITY-VENDO 01/15/86 161 B-81 ITEMS 4.2.1
& 4.2.2
-PREVENTATIVE MAINT PROG FOR R
04/29/85C 203 '-82 ITEM 4.3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 12/03/84C 577 B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83-10/17/84C 644 B-85 SALEM ATHS 1.2 DATA CAPABILITY 3727 B-86 SALEM ATHS 2.2 S-R COMPONENTS 3810 B-87 SALEM ATHS 3.2.1
& 3.2.2 S-R COMPONENTS 11/27/85C 01/01/87 12/31/86
1208731-001 RKEY POINT 4 REGULATORY INFORMATION TRACKING SYSTEM FACIL ITY IMP L EMENTATI ON (CONTINUATION)
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3893 3948 B-89
'ALEM ATHS 3.2.3 T.S.
S-R COMPONENTS SALEM ATHS 4.2.3
& 4.2.0 LIFE COMPONENTS 5385 B-90
'%120 56037 08256 08649 08781 08794 08799 08089 13042 43650 52282 58099 407879 B"92 B-93 C-01 C-03 C-04 C"06 C-07 C-10 C-13 C-14 C-15 C-16 D-02 SALEM ATHS 4.3 H AND B&H T.S.
SALEM ATHS 0.5. 1 DIVERSE TRIP FEATURES SALEM ATHS 4.5.2
& 4.5.3 TEST ALTERNATIVES PHR SECONDARY HATER CHEMISTRY MONITORING REQUIREME QUALIFICATIONS OF RADIATION PROTECTION MANAGER FILTER TECH SPECS PUMP SUPPORT-LAMELLAR TEARING FUEL HANDLING ACCIDENT INSIDE CONTAINMENT CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE LOSS OF OFFSITE POHER AUXILIARYFEEDHATER SEISMIC QUALIFICATION CONTROL OF HEAVY LOADS - PHASE II (FOLLOHUP OF MPA UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN ECCS ZIRC CLAD MODEL ERROR-COMPLIANCE WITH 10 CFR-107860 D-03 PRESSURIZER HEATUP RATE ERROR 108783 D-10 ASYMMETRIC LOCA LOADS 410003 508801 112281
%3014 555916 D-11 D-1 5 D-17 D-19 FISSION GAS RELEASE REACTOR VESSEL HELD - HIRE DEFICIENCY HIGH ENERGY LINE BREAK & CONSEQUENTIAL SYSTEM FAIL DEFINITION OF OPERABLE DIESEL GENERATOR RELIABILITYTECH SPECS (GL 86-15)
LIC ACT COM~~
11/1 4/85C 11/28/86 02/28/86 11/01/86 04/30/87 1 0/30/81 C 02/15/79C 03/23/82C 12/10/82C 05/30/79C 11/01/83C 05/06/8 OC 08/25/83C 06/28/85C 01/20/86C 09/22/78C 10/25/78C 02/06/80C
. 02/22/80C 1 1/1 3/7 9C 02/02/8 0 C 05/12/81C 03/31/86 LICENSEE MS]GUS 25IK
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PAGE NO.>
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F-17 II.E.1.2.
F-18 II.E.4.1 F-19 II.E.4.2 F-20 II.F.1.1 RCS HIGH POINT VENTS PLANT SHIELDING POST ACCIDENT SAMPLING TRAINING FOR MITIGATING CORE DAMAGE RV AND SV TRAINING AFH SYSTEM EVALUATION 1
AFH SYSTEM INITIATION 2 AFH SYSTEM FLOW INDICATION DEDICATED HYDROGEN PENETRATION CONTAINMENT ISOLATION DEPENDABILITY NOBLE GAS MONITOR 036 F-21 II.F.1.2 IODINE/PARTICULATE SAMPLING 1 07" 644 F-22 II.F.1.3 F-23 II.F.1.4 CONTAINMENT HIGH RANGE MONITOR CONTAINMENT PRESSURE INSTRUMENT F-01 I.A.1.1 SHIFT TECHNICAL ADVISOR F-02 I'(A.1.3 SHIFT MANNING F-03
. I.A.2.1 UPGRADING OF RO AND SRO TRAINING F-04 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC F-05 I.C.1.2/3.B PROCEDURES GENERATION PACKAGES (NUREG F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI F-08 I.D.1.1 DETAILED CONTROL ROON DESIGN REVIEH PROGRA F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM LIC ACT COfOP~LE 01/08/82C 06/30/83C 10/25/82C 06/07/84C 11/30/86 10/20/81C 10/20/81C 01/16/84C 03/04/85C 09/02/83C 06/30/83C 11/08/83C 10/25/82C 09/30/86 11/04/82C 09/15/82C 09/15/82C 03/25/82C 11/12/82C 09/30/81C 09/30/81C 02/08/82C 05/02/83C LICENSEE
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~A 05177 F-26 I I. F. 2 INSTRUMENTS FOR DETECTION ON INADEQUATE 01/26/85C 06911 F-30 II.K.2.13 THERMAL"MECHANICALREPORT
%5301 F-37 I I.K.3. 2 REPORT ON PORV FAILURES 47825 F-33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS 45255 F-36 II.K.3.1 AUTO PORV ISOLATION 06/06/80C 01/06/84C 09/16/83C 09/16/83C
%5387 F-38 II.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 06/24/82C 45418 F-39 II.K.3.5 AUTO TRIP OF RCPS 45067 F-F40 II.K.3.9 PID CONTROLLER 45%97 F-41 II.K.3.10 ANTICIPATORY TRIP MODIFICATIONS 45527 F-42 II.K.3.12 ANTICIPATORY TRIP ON TURBINE TRIP 567c4 F-07 II.K.3.17 ECCS OUTAGES 8%38 F-53 II.K.3.25 POWER ON PUMP SEALS 5870 F-57 II.K.3.30 SB LOCA METHODS 8211 F-58 II.K.3.31 COMPLIANCE WITH 10 CFR 50.46 5989 F-63 III.A.1.2 TECHNICAL SUPPORT CENTER 6061 F-66 III.A.1.2 OPERATIONAL SUPPORT CENTER 6368 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE 6419 F-60 III.D.3.3 IMPLANT RADIATION MONITORING 6133 F-65 III.A.1.2 EMERGENCY OPERATIONS FACILITY 6205 F-66 III.A.1.2 NUCLEAR DATA LINK 6277 F-67 III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 02/22/83C 08/20/81C 08/20/81C 08/20/81C 08/26/83C 06/24/82C 05/29/85C 12/31/86 07/31/86 06/30/86 06/30/86 07/30/82C 05/13/83C 06/30/86 02/09/82C
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