ML20210U208

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Forwards Regulatory Info Tracking Sys Facility Implementation,Updating Status of Generic Items,Per 860902 ltr.Plant-specific List Annotated W/Stated Codes
ML20210U208
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 10/03/1986
From: Mcdonald R
ALABAMA POWER CO.
To: Rubenstein L
Office of Nuclear Reactor Regulation
References
NUDOCS 8610090449
Download: ML20210U208 (13)
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Text

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. -# . 'Memng Address Alibima Power Comptny 600 Nodh 18th Street Post Office Box 2641 Birmingham. Alabama 35291 Telephone 205 7816&M R. P. Mcdonald Senior Vico President Flintridge Building AlabamaPower t~e scurrem e ectrc system October 3,1986 Docket Nos. 50-348 50-364 Di rector, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington,-D.C. 20555 Attention: Mr. L. S. Rubenstein Gentlemen:

Joseph M. Farley Nuclear Plant _- Units 1 and 2 '

Implementation of Generic Items By letter dated June 2,1986, Alabama Power Company provided a status on the

. generic issues included in NRC letter dated April 30,1986. ' This status did not include a detailed reconstruction of the historical data nor did it include research by the site implementation group. The status, however, was provided -in accordance with the intent of the April 30, 1986 NRC request.

Based. on subsequent discussions with members of the NRC Staff, Alabama Power Company stated in letter dated September 2,1986 that the June 2,1986 status would be supplemented by late September 1986. The status of each generic item on the enclosed-list has therefore been updated and reviewed with Alabama Power Company's NRC Project Manager and is considered to be reasonably accurate. In reaching this judgement, a detailed review of each

. item was not performed. To do so would require expenditure of significant manpower resources to review archived record files. Although we are confident that such records do exist, we cannot certify without some element of uncertainty the exact status of each generic issue.

The enclosed plant-specific list nevertheless has been annotated utilizing the following codes:

C - Item considered completed (not based on extensive record review)

L - Estimated completion date for iten I - Item Delieved completed prior to requireiaent being issued j KA - Item considered not applicable god i i 8610090449 861003 I (

PER ADOCK 05000348 P PDR m

Mr. L. S. Rubenstein October 3,1986 I U. S. Nuclear Regulatory Commission Page 2 If there are any ques tions, please advise.

Respectfully submitted, ALABAMA POWER CO f.

R. P. Mcdonald RPM / JAR: dst-D-T.S.7 Enclosure cc: Mr. L. B. Long Dr. J. N. Grace Mr. E. A. Reeves Mr. W. H. Bradford

)

TRACKING SYSTEM PAGE NO. 155

(-1208731-001 REGULAT0RY INF0RHATION FACILITY IMPLEMENTATION 03/31/86 ACILITY: FARLEY 1 '

LANT LOCATION: 18 MI SE OF DOTHAN, ALA LICENSED P0HER: 2652 MHT PROJECT MANAGER: E. REEVES DESIGN Poller: 0829 MWE BRANCH CHIEF: L. RUBENSTEIN OCKET NUllBER: 050-00348 HEST LIC. ASSISTANT: . VACANT RCH/ ENGINEER: SSI NSSS VENDUR:

E INSPECTOR: H. BRADFORD LIC ACT LICENSEE LAC NO. MPA 8 TITLE COMPLETE STATUS RAlf l

12/07/79C C 1979 D04631 A-01 10 CFR 50.55 A(G) - ISI 03/01/82C C 1982 08094 A-02 APPENDIX I - ALARA l

02/26/79C C 1979 ,

,07570 0 A-03 SECURITY REVIENS-MODIFIED AMENDMENT PLANS '

l 1

008672 A-09 PRESSURE VESSEL BELTLINE MATERIAL SURVEILLANCE 05/19/80C NA 1 12/10/80C C 1980 l b10471 A-10 CONTINGENCY PLANNING 08/18/81C C 1981 h10470 A-11 GUARD TRAINING PLANS 04/12/82C NA 910472 A-12 VITAL AREA ANALYSIS 04/29/83C C 1983 211277 A-14 10CFR 50.55 A(G) - INSERVICE TESTING QUALIFICATIONS OF EXAMINATION, INSPECTION, TESTING 01/28/82C C 1982 247477 A-16 L 1988 251088 A-17 INSTRUMENTATION TO FOLLOH THE COURSE OF AN ACCIDEN 02/19/85C C 1985 254235 A-18 TECH SPECS AFFECTED BY 50.72 AND 50.73 (GL 83-43)

N//S / L 1986 E59092 A-20 10 CFR 50.62 OPERATING REACTOR REVIENS 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE NA E59953 A-21 04/13/79C C 1979 E08671 B-02 FIRE PROTECTION 02/21/79C C 1979 E08379 B-03 PHR MODERATOR DILUTION 07/31/79C C 1979 N04835 B-04 REACTOR VESSEL OVERPRESSURE PROTECTION 02/13/79C C 1979 E08165 B-08 PHR HPSI-LPSI FLOH RESISTANCE 10/03/80C C 1980 E08676 B-14 CEA GUIDE TUBE HEAR 04/01/81C C 1981 R12168 B-16 EMERGENCY PLANNING AND REVISIONS 03/01/82C C 1982 108674 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SHUBBERS

l-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE N3.: 155 FACILITY IMPLEMENTATION 03/31/86 fARLEY 1 (CONTINUATION)

LIC ACT LICENSEE AC NO. MPA 9 TITLE COMPLETE STATUS RAlg 10263 B-20 CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION 08/25/80C C 1980 10326 B-21 LOSS OF 125-V DC BUS VOLTAGE HITH LOSS OF ANNUNCIA 02/28/82C NA 08675 B-22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 03/01/82C C 1982 04836 B-23 DEGRADED GRID VOLTAGE 03/09/81C C 1981 10166 B-24 VENTING AND PURGING CONTAINMENTS HHILE AT FULL P0H 07/16/80C C 1980 42555 B-24 VENTING AND PURGING CONTAINMENTS HHILE AT FULL P0H 03/02/81C C 1981 10225 B-26 INADVERTANT SAFETY INJECTION DURING COOLDOHN 12/28/79C C 1979 49418 B-52 BLOCKED SI SIGNAL DURING C00LD0HN 01/09/84C C, 1984 08656 B-39 PHR PRESSURE - TEMPERATURE LIMIT TECH SPECS 11/13/80C C 1980 48571 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 08/26/83C C 1983

'48014 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 05/05/82C C 1982 11099 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 03/01/82C C 1982 11688 B-42 TMI FOLLOH UP - ALL PLANTS 05/27/81C C 1981 11767 B-43 PHR FEEDHATER LINE CRACKS 02/08/80C C 1980 43134 B-43 PHR FEEDHATER LINE CRACKS 05/25/82C C 1982 30598 B-44 LESSONS LEARNED IMPLEMENTATION 04/03/80C C 1980 30599 B-44 LESSONS LEARNED IMPLEMENTATION 04/05/80C C 1980 30600 B-44 LESSONS LEARNED IMPLEMENTATION 04/03/80C C 1980 30601 B-44 LESSONS LEARNED IMPLEMENTATION 04/03/80C C 1980 30602 B-44 LESSONS LEARNED IMPLEMENTATION 04/03/80C C 1980 330603 B-44 LESSONS LEARNED IMPLEMENTATION 04/03/80C C 1980 R30604 B-44 LESSONS LEARNED IMPLEMENTATION 04/03/80C C 1980 B30605 B-44 LESSONS LEARNED IMPLEMENTATION 04/03/80C C 1980

-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE N3.8 157 FACILITY IMPLEMENTATION 03/31/86 NRLEY 1 (CONTINUATION)

LIC ACT LICENSEE

%C NO. MPA 8 TITLE COMPLETE STATUS Ralg 30606 B-44 LESSONS LEARNED IMPLEMENTATION 04/03/80C C 1980 30607 B-44 LESSONS LEARNED IMPLEMENTATION 04/03/80C C 1980 20608 B-44 LESSONS LEARNED IMPLEMENTATION 04/05/80C C 1980 20609 B-44 LESSONS LEARNED IMPLEMENTATION 04/03/80C C 1980 20610 B-44 LESSONS LEARNED IMPLEMENTATION 04/03/80C C 1980 20611 5-44 LESSONS LEARNED IMPLEMENTATION 04/03/80C C 1980 32925 B-45 HASH 1400 EVENT V, " PRIMARY COOLANT SYSTEM PRESSUR 04/20/81C C 1981 92594 B-46 ANALYSIS OF TURBINE DISC CRACKS 08/24/81C C 1981 D2676 B-47 ECCS; CLAD SHELLING AND RUPTURE 09/12/80C C 1980 33006 B-48 ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 03/09/81C C 1981 31868 B-52 REVIEH OF SAFETY ASPECT OF INADVERTENT SAFETY ACTI 12/12/80C C 1980 it6977 B-54 LESSONS CATEGORY A TECH SPEC 10/05/81C C 1981 132095 B-57 DHR CAPABILITY 03/01/82C C 1982 142861 B-59 MASONRY HALL DESIGN 10/25/84C L 1986 142670 B-61 LOSS OF NON CLASS IE 18C P0HER 07/28/82C C 1982 142740 B-62 ESF RESET CONTROL DESIGN DEFICIENCY 12/16/81C C 1981 143885 B-63 INTERIM PROCEDURES FOR SHORT TERM BLACKOUT 12/14/81C C 1981 147172 B-66 NATURAL CIRCULATION C00LDOHN 11/15/83C C 1983 146837 B-69 IEB 80-4 MAINSTEAM LINE BREAK HITH CONTINUED FEEDH 10/21/82C C 1982 149731 B-72 NUREG 0737 TECH SPECS (GENERIC LETTER 82-16) 05/07/84C C 1984 152755 B-76 ITEM 1.1 - POST TRIP REVIEH; PROGRAM DESCRIPTION & 05/21/85C C 1985 152836 B-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION & VENDOR INTER 03/31/86 C 1983 152917 B-78 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 09/10/85C C 1985

'l I-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE HJ.: 158.

FACILITY IMPLEMENTATION 03/31/86 FARLEY 1 (CONTINUATION)

LIC ACT LICENSEE AC NO. TITLE COMPLETE STATUS DATE MPA_1 N52998 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 11/12/85C C 1985 053069 B-80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDO 09/10/85C C 1985 "53122 B-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PROG FOR R 10/24/85C C 1985 53172 B-82 ITEM 4.3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 07/23/84C C 1984 l54531 B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83- 09/12/84C C 1984

.53587 B-85 SALEM ATHS 1.2 DATA CAPABILITY 06/12/85C C 1985 53670 B-86 SALEM ATHS 2.2 S-R COMPONENTS 05/02/86 C 1985 53753 B-87 SALEM ATHS 3.2.1 & 3.2.2 S-R COMPONENTS 12/31/86 C 1986 153836 8-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 11/12/85C C 1985 53909 B-89 SALEM ATHS 4.2.3 & 4.2.4 LIFE COMPONENTS 12/30/86 L 1986

'155354 B-90 SALEM ATHS 4.3 H AND B&W T.S. 03/30/86 L 1987

'54063 B-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 09/10/85C C 1985 W53980 B-93 SALEM ATHS 4.5.2 8 4.5.3 TEST ALTERNATIVES 05/02/87 L 1987 E08057 C-01 PHR SECONDARY HATER CHEMISTRY MONITORING REQUIREME 02/13/79C C 1979 108673 C-06 PUMP SUPPORT-LAMELLAR TEARING 04/17/81C NA I04837 C-07 FUEL HANDLING ACCIDENT INSIDE CONTAINMENT 04/09/80C C 1980 IO7989 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE 07/25/84C C 1984 I43631 C-14 AUXILIARY FEEDHATER SEISMIC QUALIFICATION 11/08/82C C 1982 152226 C-15 CONTROL OF HEAVY LOADS - PHASE II (FOLLOHUP OF MPA 06/28/85C C 1985 M58058 C-16 UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN 01/02/86C C 1986 1107864 D-02 ECCS ZIRC CLAD MODEL ERROR-COMPLIANCE HITH 10 CFR- 05/09/79C C 1979 M11997 D-04 PHR REACTOR VESSEL CAVITY SEAL RING MISSILE PDTENT 01/26/80C C 1980 M08977 D-11 FISSION GAS RELEASE 02/22/80C NA

-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NJ.: 159 FACILITY IMPLEMENTATION 03/31/86 ARLEY 1 (CONTINUATION)

LIC ACT LICENSEE AC NO. MPA 8 TITLE COMPLETE STATUS MIf 112266 D-15 HIGH ENERGY LINE BREAK & CONSEQUENTIAL SYSTEM FAIL 01/31/84C NA I43005 D-17 DEFINITION OF DPERABLE 03/01/82C C 1982 155857 D-19 DIESEL GENERATOR RELIABILITY TECH SPECS (GL 84-15) 09/04/85C C 1985 144018 F-01 I.A.1.1 SHIFT TECHNICAL ADVISOR 02/16/82C C 1982 144088 F-02 I.A.1.3 SHIFT MANNING 06/30/83C C 1982 144159 F-03 I.A.2.1 UPGRADING OF RO AND SRO TRAINING 02/01/82C C 1981 144230 F-04 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC 06/03/83C C 1983 144300 F-05 I.C.1.2/3.B PROCEDURES GENERATION PACKAGES (NUREG 03/30/86 L 1987 147213 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE 03/24/82C C 1982 147285 F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI 03/24/82C C 1982 951158 F-08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEN PROGRA 10/15/84C C 1984 1

151238 F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM 06/12/85C L 1988 1

444371 F-10 II.B.1 RCS HIGH POINT VENTS 11/07/83C C 1983 47936 F-11 II.B.2 PLANT SHIELDING 12/15/83C C 1983 p44439 F-12 II.B.3 POST ACCIDENT SAMPLING 10/11/84C C 1984 F-13 II.B.4 TRAINING FOR MITIGATING CORE DAMAGE 02/01/82C C 1983 h44509 F-14 II . D.1 RV AND SV TRAINING 07/31/86 C 1984 h44579 b44635 F-15 II.E.1.1 AFH SYSTEM EVALUATION 07/04/81C C 1981 44677 F-16 II .E.1.2.1 AFH SYSTEM INITI ATION 08/07/81C C 1983 F-17 II.E.1.2.2 AFH SYSTEM FLOH INDICATION 08/07/81C C 1983 h44714 F-18 II.E.4.1 DEDICATED HYDROGEN PENETRATION 10/30/81C C 1981 f44777 44848 F-19 II.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY 06/30/81C C 1983 b F-20 I I . F .1.1 NOBLE GAS MONITOR 10/29/81C C 1981 A44919

N1208731-001 REGULATDRY INF0RMATION TRACKING SYSTEM PAGE ND.: 160; FACILITY IMPLEMENTATION 03/31/86

'ARLEY 1 (CONTINUATION)

LIC ACT LICENSEE AC NO. MPA 0 , TITLE COMPLETE STATUS DATI 44990 F-21 II.F.1.2 IODINE / PARTICULATE SAMPLING 10/29/81C C 1981 45061 F-22 II.F.1.3 CONTAINMENT HIGH RANGE MONITOR 12/28/81C C 1981 47597 F-23 II . F.1.4 CONTAINMENT PRESSURE INSTRUMENT 07/30/82C C 1982 47668 F-24 II.F.1.5 CONTAINMENT HATER LEVEL INSTRUMENT 07/30/82C C 1982 47739 F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR 07/30/82C C 1982 45132 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 06/30/87 L 1988 46886 F-30 II.K.2.13 THERMAL-MECHANICAL REPORT 06/18/84C NA 47797 F-33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS 01/10/84C C 1984 (45232 F-36 II.K.3.1 AUTO PORV ISOLATION 09/12/83C C 1983 5278 F-37 II.K.3.2 REPORT ON PORV FAILURES 09/23/83C C 1983

'45341 F-38 II.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 03/26/82C C 1982 45395 F-39 II.K.3.5 AUTO TRIP OF RCPS 02/22/83C C 1985 5444 F-40 II.K.3.9 PID CONTROLLER 01/06/82C C 1982 5474 F-41 II.K.3.10 ANTICIPATORY TRIP MODIFICATIONS 01/06/82C C 1982 45504 F-42 II.K.3.12 ANTICIPATORY TRIP DN TURBINE TRIP 01/06/82C C 1982 45627 F-47 II.K.3.17 ECCS OUTAGES 08/10/83C C 1983 48417 F-53 II.K.3.25 P0HER ON PUMP SEALS 07/21/82C C 1982 45824 F-57 II.K.3.30 SB LOCA METHODS 05/23/85C C 1985 48163 F-58 II.K.3.31 COMPLIANCE HITH 10 CFR 50.46 12/31/86 NA 45943 F-63 III.A.1.2 TECHNICAL SUPPORT CENTER 09/30/87 C 1982 46014 F-64 III.A.1.2 OPERATIONAL SUPPORT CENTER 09/30/87 C 1982 46086 F-65 III.A.1.2 EMERGENCY OPERATIONS FACILITY 09/30/87- C 1982 (46158 F-66 III.A.1.2 NUCLEAR DATA LINK 07/30/82C NA

t -12087 31 -0 01 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO 161 FACILITY IMPLEMENTATION 03/31/86 ARLEY 1 (CONTINUATION)

LIC ACT LICENSEE

'AC NO. MPA 5 TITLE COMPLETE STATUS Half F-67 III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 05/24/83C C 1983 146230 146302 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE 09/30/87 C 1982 146573 F-69 III.D.3.3 IMPLANT RADIATION MONITORING 03/26/82C C 1982 142444 F-70 III.D.3.4 CONTROL ROOM HABITABILITY 03/31/83C C 1983 F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEH (FDLLOHUP TO 01/30/87 L 1990 156121 149688 G-01 REACTOR COOLANT PUMP TRIP (D660 - II.K.3.5) 06/30/86 NA L__ . .

1-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO.: 162 FACILITY IMPLEMENTATION 03/31/86

'ACILITY: FARLEY 2 LANT LOCATION: 28 MI SE OF DOTHAN, ALA LICENSED P0HER: 2652 MHT PROJECT MANAGER: E. REEVES OCKET NUMBER: 050-00364 DESIGN PO!!ER: 0829 MNE BRANCH CHIEF: L. RUBENSTEIN RCH/ ENGINEER: SSI NSSS VENDOR: HEST LIC ASSISTANT: . VACANT E INSPECTOR: H. BRADFORD LIC ACT LICENSEE JAC NO, MPA 8 TITLE COMPLETE STATUS DAlf 51033 A-01 10 CFR 50.55 A(G) - ISI 09/22/83C C 1983 47478 A-16 QUALIFICATIONS OF EXAMINATION, INSPECTION, TESTING 01/28/82C C 1982 51089 A-17 INSTRUMENTATION TO FOLLON THE COURSE OF AN ACCIDEN L 1987 54236 A-18 TECH SPECS AFFECTED BY 50.72 AND 50.73 (GL 83-43) 02/19/85C C 1985 59093 A-20 10 CFR 50.62 OPERATING REACTOR REVIENS N//S / L 1986 9954 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE NA 49419 B-52 BLOCKED SI SIGNAL DURING C00LD0HN 01/09/84C C 1984 48572 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 08/26/83C C 1983 4R015 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 05/04/82C C 1982 48016 B-46 ANALYSIS OF TURBINE DISC CRACKS 05/23/85C C 1985 43966 B-59 MASONRY HALL DESIGN 03/01/83C C 1983 43952 B-63 INTERIM PROCEDURES FOR SHORT TERM BLACKOUT 12/14/81C C 1981 47173 B-66 NATURAL CIRCULATION C00LDOHN 11/14/83C C 1983 46838 B-69 IEB 80-4 MAINSTEAM LINE BREAK HITH CONTINUED FEEDH 10/21/82C C 1982 49732 B-72 NUREG 0737 TECH SPECS (GENERIC LETTER 82-16) 05/07/84C C 1984 52756 B-76 ITEM 1.1 - POST TRIP REVIEH; PROGRAM DESCRIPTION & 05/21/85C- C 1985 W52837 B-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION 8 VENDOR INTER 03/31/86 C 1983 252918 5-78 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 09/10/85C C 1985 152999 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 11/12/85C C 1985 253070 B-80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDO 09/10/85C C 1985 4

SYSTCM PAGE'HO. 163-

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a1208731-001 /R E G U L A T 0 R Y SI N F OeR M A T I O N. TRACKING kMPLEMENTATION

~

FACILITY 03/31/86 j ,

' I RRLEY 2 (CONTINUATION) -

j LIC ACT LICENSEE RC NO. MPA 9 TITLE COMPLETE STATUS Balg 53123 B-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PROG FOR R 12/24/85C C 1985 53173 B-82 ITEM 4.3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 07/23/84C C 1984 54532 B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83- 09/12/84C C 1984 53588 B-85 SALEM ATHS 1.2 DATA CAPABILITY 06/12/85C C 1985 53671 B-86 SALEM ATHS 2.2 S-R COMPONENTS 05/02/86 C 1985 53754 B-87 SALEM ATHS 3.2.1 & 3.2.2 S-R COMPONENTS 12/31/86 C 1986 53837 B-88 SALEM ATHS 3.2.3 T.S. S-R COMPUNENTS 11/12/85C C 1985 53910 B-89 SALEM ATHS 4.2.3 & 4.2.4 LIFE COMPONENTS 12/30/86 L 1987 55355 B-90 SALEM ATHS 4.3 H AND B&W T.S. 03/30/86 L 1987 54024 B-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 09/10/85C C 1985 53981 B-93 SALEM ATHS 4.5.2 & 4.5.3 TEST ALTERNATIVES 05/15/87 L 1987 B43965 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE 07/25/84C C 1984 047192 C-14 AUXILIARY FEEDHATER SEISMIC QUALIFICATION 11/08/82C C 1982 B52227 C-15 CONTROL OF HEAVY LOADS - PHASE II (FDLLOHUP OF MPA 06/28/85C C 1985 058059 C-16 UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN 01/02/86C C 1986 "46589 D-15 HIGH ENERGY LINE BREAK & CONSEQUENTIAL SYSTEM FAIL 08/31/81C NA 55858 D-19 DIESEL GENERATOR RELIABILITY TECH SPECS (GL 84-15) 09/04/85C C 1985 44019 F-01 I.A.1.1 SHIFT TECHNICAL ADVISOR 02/16/82C C 1982 44089 F-02 I.A.I.3 SHIFT MANNING 06/30/83C C 1982 44160 F-03 I.A.2.1 UPGRADING OF RO AND SRO TRAINING 09/30/80C C 1981 44231 F-04 I.C.1.2/3.A EMERGENCY OPERATIhG PROCEDURES GENERIC 06/03/83C C 1983 4430s F-05 I.C.1.2/3.B PROCEDURES GENERATION PACKAGES (NUREG 03/30/86 C 1983 47214 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE 03/24/82C C 1982

INF0RMATION TRACKING SYSTEM PAGE NO. 160

  • 1208731-001 REGULAT0RY FACILITY IMPLEMENTATION 03/31/86 ARLEY 2 (CONTINUATION)

LIC ACT LICENSEE TITLE COMPLETE STATUS RATE SC NO. MPA 8 CORRECT PERFORMANCE OF OPERATING ACTIVITI 03/24/82C C 1982

  1. 7286 F-07 I.C.6 10/10/84C C 1984 51159 F-08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEH PROGRA SAFETY PARAMETER DISPLAY SYSTEM 06/12/85C L 1987 51239 F-09 I.D.2 RCS HIGN POINT VENTS 11/07/83C C 1983 44372 F-10 II.B.1 F-11 PLANT SHIELDING 12/15/83C C 1983 47937 II.B.2 44440 F-12 II.B.3 POST ACCIDENT SAMPLING 10/11/84C C 1985 TRAINING FOR MITIGATING CORE DAMAGE 05/30/81C C 1981 44510 F-13 II.B.4 44580 F-14 II.D.1 RV AND SV TRAINING 07/31/86 C 1984' 44636 F-15 II.E.1.1 AFH SYSTEM EVALUATION 06/19/81C C 1980 F-16 II.E.1.2.1 AFH SYSTEM INITIATION 08/14/81C C 1982 44678 44715 F-17 II.E.1.2.2 AFH SYSTEM FLOH INDICATION 08/14/81C C 1982 DEDICATED HYDROGEN PENETRATION 09/30/80C C 1981 44778 F-18 II.E.4.1 CONTAINMENT ISOLATION DEPENDABILITY 03/15/81C C 1981 44849 F-19 II.E.4.2 NOBLE GAS MONITOR 10/29/81C C 1981 44920 F-20 II.F.1.1 IODINE / PARTICULATE SAMPLING 05/30/81C C 1981 44991 F-21 II.F.1.2 CONTAINMENT HIGH RANGE MONITOR 12/28/81C C 1981 45062 F-22 II.F.1.3 07/30/ 82C C 1982 47598 F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 01/01/70C C 1982 146492 F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 01/01/70C C 1982 m46493 F-24 II.F.1.5 CONTAINMENT HATER LEVEL INSTRUMENT CONTAINMENT HATER LEVEL INSTRUMENT 07/30/82C C 1982 E47669 F-24 II.F.1.5 CONTAINMENT HYDROGEN MONITOR 07/30/82C C 1982 247740 F-25 II.F.1.6 01/01/70C C 1982 A46494 F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR F-26 INSTRUMENTS FOR DETECTION ON INADEQUATE 06/30/87 L 1987 R45133 II.F.2

( .

~1208731-001

- R E.G U L A T 0 R Y INF0RMATION TRACKINO SYSTEM PAGE NO. 165" FACILITY IMPLEMENTATION 03/31/86-ARLEY 2 (CONTINifATION)

LIC ACT LICENSEE C NO. MPA 8 TITLE COMPLETE STATUS RAJE 46887 F-30 II.K.2.13 THERMAL-MECHANICAL REPORT 06/18/84C C 1984 47798 F-33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS 01/10/84C C 1984 45233 F-36 II.K.3.1 AUTO PORV ISOLATION 09/23/83C C 1983

+5279 F-37 II.K.3.2 REPORT ON PORV FAILURES 09/23/83C C 1984

'45342 F-38 II.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 06/19/81C C 1982 45396 F-39 II.K.3.5 AUTO TRIP OF RCPS 02/22/83C C 1985 45445 F-40 II.K.3.9 PID CONTROLLER 06/19/81C C 1982 45475 F-41 II.K.3.10 ANTICIPATORY TRIP MODIFICATIONS 06/19/81C C 1982 5505 F-42 II.K.3.12 ANTICIPATORY TRIP DN TURBINE TRIP 06/19/81C C 1982 8418 F-53 II.K.3.25 POWER ON PUMP SEALS 07/21/82C C 1982 45825 F-57 II.K.3.30 SB LOCA METHODS 05/00/85C C 1985 48164 F-58 II.K.3.31 COMPLIANCE HITH 10 CFR 50.46 12/31/86 NA 45944 F-63 III.A.1.2 TECHNICAL SUPPORT CENTER 09/30/87 C 1982 46015 F-64 III.A.1.2 OPERATIONAL SUPPORT CENTER 09/30/87 C 1982 46087 F-65 III.A.1.2 EMERGENCY OPERATIONS FACILITY 09/30/87 C 1982 46159 F-66 III.A.I.2 NUCLEAR DATA LINK 07/30/82C NA 46231 F-67 III.A.2.1 EMERGENCY PLAN UPURADE TO MEET RULE 05/24/83C C 1983 46303 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE 09/30/87 C 1982 46574 F-69 III.D.3.3 IMPLANT RADIATION MONITORING 09/30/80C C 1982 46445 F-70 III.D.3.4 CONTROL ROOM HABITABILITY 03/15/81C C 1982 56122 F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEH (FOLLOHUP TO 01/30/87 L 1990 N49689 G-01 REACTOR COOLANT PUMP TRIP (D660 - II.K.3.5) 06/30/86 NA

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