ML20195E790

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Forwards marked-up NRC plant-specific List to Document Implementation of Generic Items Per 860430 Request. Nondetailed Response Covers Only Items W/Incomplete Status
ML20195E790
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 06/02/1986
From: Mcdonald R
ALABAMA POWER CO.
To: Rubenstein L
Office of Nuclear Reactor Regulation
References
TASK-***, TASK-TM NUDOCS 8606090227
Download: ML20195E790 (13)
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Text

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-A Mailing Address AIIbima Power Company 600 North 18th Street Post Office Box 2641 Birmingham, Alabama 35291 Telephone 205 783-6090 R. P. Mcdonald Senior Vice President Flintridge Building g ghgg)g g g June 2, 1986 ,,,.y,, c 3, ,

Docket Nos. 50-348 50-364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. L. S. Rubenstein Gentlemen:

1 Joseph M. Farley Nuclear Plant - Units 1 and 2 Implementation of Generic Items By NRC letter of April 30, 1986, information was requested from Alabama

Power Company to assist the NRC in improving "its documentation on the status of power reactor licensees' implementation of approved regulatory improvements." The subject letter also stated that the NRC did not intend for utilities to expend substantial resources in responding to the NRC request. The plant-specific list, provided by the subject letter, has been marked up and is attached.

The scope of the status provided by Alabama Power Company only includes i those items for which the "Lic Act Complete" column does not show a complete status. These items are addressed utilizing the following codes:

1. letter to NRC completing action on (date)
2. letter projected to be transmitted to NRC by (date)
3. closure provided by NRC letter of (date) 4 implementing activity projected to be completed by (date)
5. implementation schedule projected to be provided by (date)

Additional clarifications have been provided by appropriate footnotes.

Alabama Power Company has generated the attached status in accordance with the intent of the NRC request. A substantial effort would be required'to provide a detailed status. Status and action tracking schemes used to

, assure completion of required action items were not intended to allow

! reconstruction of historical data long after the completion and closure of f

an issue. Comitments related to generic issues are tracked until implementation and then removed from the tracking system. In order to provide a more detailed status, each generic NRC item would have to be p correlated to a specific utility licensing issue. The file for each issue f i

0(g 8606090227 860602--

PDR ADOCK 0b000348 t PI)R _ ,

o Mr. L. S. Rubenstein June 2, 1986 U. S. Nuclea.r Regulatory Commission Page 2 would then have to be identified and reviewed to determine the latest commitment. Then, a determination would have to be made of the specific design change number, procedure revision number, etc. implementing the commitment. The responsible site groups would then be required research commitment dates for each action item and from that determine the completion of the final action item. It should be noted that many of these issues have been included in various ISE inspections and that others have been closed by NRR correspondence.

Alabama Power Company is confident that past comitments associated with these issues have been fulfilled. No changes are made to safety related portions of the plant without the completion of detailed evaluations.

Alabama Power Company feels that the current I&E inspection process, in combination with evaluations performed prior to changes associated with safety-related systems, provides the imolementation status and continuing compliance.

If you have any questions, please advise.

Respectfully submitted, ALABAMA POWER COMPANY

) +l J R. P. Mcdonald RPM / JAR:kpc-T.S.1 Attachment cc: Mr. L. B. Long Dr. J. N. Grace Mr. E. A. Reeves Mr. W. H. Bradford

,I IRACKING SYSTEM PAGE NO.s 15Y R-1208731-001 REGULAT0RY INF0RHA1 ION ,

IMPLEMENTATION 03/31/86 FACILITY 4

FACILITY: FARLEY 1 LICENSED P0HER: 2652 MHT PROJECT MANAGER: E. REEVES PLANT LOCATION: 18 MI SE OF DOTNAN, ALA 0829 MHE BRANCH CHIEF

  • L. RUBENSTEIN DESIGN PollLRs . VACANT

! DOCKET NUMBER: 050-00348 NSSS VENDOR: HEST LIC. ASSISTANT:

ARCH / ENGINEER SSI lIE INSPECTOR

  • H. BRADFORD LIC ACT LICENSEE COMPLETE STATUS DATE MPA B TITLE

{ TAC NO.

12/07/79C

MS4631 A-01 10 CFR 50.55 A(G) - ISI APPENDIX I - ALARA 05/01/82C

,M08094 A-02 02/26/79C M87570 A-03 SECURITY REVIENS-MODIFIED AMENDMENT PLANS 05/19/80C M08572 A-09 PRESSURE VESSEL BELTLINE MATERIAL SURVEILLANCE 12/10/80C lM10471 A-10 CONTINCENCY PLANNING A-11 08/18/81C iM10470 GUARD TRAININh PLANS 04/12/82C

!M10472 A-12 VITAL AREA ANALYSIS A-14 1DCFR 58.55 A(G) - INSERVICE TESTING 04/29/83C

!M11277 A-16 GUALIFICATIONS OF EXAMINATION, INSPECTION, TESilHG 01/28/82C lM47477 4 May 1988 1M51088 A-17 INSTRUMENTATION TO FOLLOW THE COURSE OF AN ACCIDEN 1

A-18 TECH SPECS AFFECTED BY 50.72 AND 58.73 (GL 85-45) 02/19/85C M54235

  • i N//S / 5 A-20 10 CFR 50.62 OPERATING REACTOR REVIEWS lM59092 3 May 1986 IM59953 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE B-02 FIRE PROTECTION 04/13/79C

' M00671 02/21/79C iM08379 B-03 PHR MODERATOR DILUTION 1104835 B-04 REACTOR VESSEL OVERPRESSURE PROTECTION 07/31/79C PHR HPSI-LPSI FLOW RESISTANCE 02/13/79C

,'M08165 5-08 M08176 B-14 CEA GUIDE TURE WEAR 10/03/80C '

R-16 EMERGENCY PLANNING AND REVISIONS 04/01/81C M12148 M08S74

  • B-17 TECM SPEC SURVEILLANCE FOR HYDRAULIC SNUBBLRS 03/01/82C i,

i

!

  • 90 days after NRC issuance of SER on WOG submittal i

1 INF0RMAT ION TRACKING SYSTEM PAGE NO. ',156

t-1208731-001 REGULAT0RY 03/31/86, FACILITY IMPLEMENTATION (CONTINUATION)

.FARLEY 1

! LIC ACT LICENSEE TITLE COMPLETE STATUS DAIX TAC MO. NPA 0 110203 B-20 CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION 08/25/80C 110326 B-21 LOSS OF 125-V DC BUS VOLTAGE WITN LOSS OF ANNUNCI A 02/28/82C ,

I B-22 TECN SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 03/01/82C WE375

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B-23 DEGRADED GRID VOLTAGE 03/09/81C

104836 110166 B-24

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VENTING AND PURGING CONTAINMENTS HNILE AT FULL POW 07/16/80C t

.142556 B-24 VENTING AND PURGING CONTAINMENTS HNILE AT FULL POW 03/02/81C 110225 B-26 INADVERTANT SAFETY INJECTION DURING C00LDOHN 12/28/79C 4

149418 B-32 BLOCKED SI SIGNAL DURING COOLDONN , 01/09/84C

'108656 B-39 PNR PRESSURE - TEMPERATURE LIMIT TECN SPECS 11/13/80C 148571 B-41 FIRE PROTECTION - FINAL TECN SPECS (INCLUDES SER S 08/26/83C 1948014 B-41 FIRE PROTECTION - FINAL TECN SPEdS (INCLUDES SER S 05/05/82C M11099 B-41 FIRE PROTECTION - FINAL TECN SPECS (INCLUDES SER S 03/01/82C t

M11088 B-42 TMI FOLLON UP - ALL PLANTS 05/27/81C iM11767 B-43 PHR FEEDHATER LINE CRACKS 02/08/80C

M43134 B-43 PHR FEEDHATER LINE CRACKS 05/25/82C i

1M30598 B-44 LESSONS LEARNED IMPLEMENTATION 04/03/80C lM30599 B-44 LESSONS LEARNED IMPLEMENTATION 04/05/80C \

i B-44 LESSONS LEARNED IMPLEMENTATION 04/05/80C lM30300 M30001 3-44 LESSONS LEARNED IMPLEMENTATION 04/03/80C

'M30602 B-44 LESSONS LEARNED IMPLEMENTATION 04/05/80C

'M306 u3 B-44 LESSONS LEARNED IMPLEMENTATION 04/03/80C M30004 B-44 LESSONS LEARNED IMPLEMENTATION 04/03/80C 1

.M30605 " B-44 LESSONS LEARNED IMPLEMENTATION 04/05/80C I

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TRACKING SYSTEM PAGE NO. ,157 4-1208731-001 REGULAT0RY INF0RMAT ION FACILITY IMPLEMENTATION 03/31/86 FARLEY 1 (CONTINUATION)

LIC ACT LICENSEE

. TAC NO. MPA 0 TITLE COMPLETE STATUS R&If .

>130606 B-44 LESSONS LEARNED IMPLEMENTATION 04/05/80C M30507 B-44 LESSONS LEARNED IMPLEMENTATION 04/05/80C M30508 B-44 LESSONS LEARNED IMPLEMENTATION ,

. 04/05/80C 04/03/80C

'M30109 B-44 LESSONS LEARNED IMPLEMENIATION

' 04/03/80C H30610 B-44 LESSONS LEARNED IMPLEMENTATION -

'M30611 5-44 LESSONS LEARNED IMPLEMENTATION 04/05/80C M12925 - B-45 HASN 1400 EVENT V, " PRIMARY COOLANT SYSTEM PRESSUR C4/20/81C 4

M12594 B-46 ANALYSIS OF TURBINE DISC CRACKS 08/24/41C -

M12676 B-47 ECCS; CLAD SHELLING AND RUPTURE 09/12/80C B-48 ADEQUACY OF STATION ELECTRIC _ DISTRIBUTION VOLTAGE 03/09/81C

'M13006 - , .-

-M11868 B-52 REVIEH OF SAFETY ASPECT OF INADVERTENT SAFETY,ACTI 12/12/80C ,

M46977 B-54 LESSONS CA1EGORY A TECN SPEC 10/05/81C B-57 UHR CAPARILITY' 03/01/82C
M42493 ,

M42851 B-59 MASONRY' HALL DESICN 10/25/84C ,

M42670 B-61 ' LOSS OF NON CLASS IE 18C P0HER 07/28/82C

'N42740 B-62 ESF RESET CONTROL DESIGH DEFICIENCY 12/16/81C

M43885 B-63 INTERIM PROCEDURES FOR SHORT TERM BLACKDUT 12/14/81C" lM47172 B-66 NATURAL CIRCULATION C00LDOHN 11/15/83C ,

jM41837 B-69 IER 50-4 MAINSTEAM LINE BREAK HITH CONTINUED FEEDH 10/21/82C MUREG 0737 TECN SPECS (GE$ERI'C LETTER 82-16) 05/07/84C

!M49731 3-12 ._

M52755 B-76 ' ITEM 1.I - POST TRIP REVIEH; PROGRAM DESCRIPTION & 05/21/85C B-77. " ITEM 2.1 - EQUIPMENT CLASSIFICATION & VENDOR INTER 03/31/86 1 1983 IMS2835 IM52917 B-78 ' ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PR' CEDU O 09/10/85C a

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INF0RMAT ion TRACKING SYSTEM PAGE NO.* 158 R-1208731-001 REGULAT0RY FACILITY IMPLEMENTATION 03/31/86 F ARL EY 1 (CONTINUATION)

LIC ACT LICENSEE TAC NO. MPA 0 TITLE COMPL ET E STATUS B&IE

'M52998 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 11/12/85C M55039 B-80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY 'VENDO G9/10/85C M53122 3-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PRQ,G FOR R 10/24/85C M53172 B-82 ITEM 4.3 - AUTOMATIC ACTUATION OF SNUNT TRIP ATTAC 07/23/84C H54531 B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83- 09/12/84C M53587 B-85 SALEM ATHS 1.2 DATA CAPABILITY 06/12/85C ,

B-86 SALEM ATHS 2.2 S-R COMPONENTS 05/02/86 1 April 1985 M53670 12/31/86 3.2.1 1 February 1934 H53753 B-87 SALEM ATHS 3.2.1 4 3.2.2 S-R COMPONENTS M53836 B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 11/12/85C SALEM ATHS 4.2.3 & 4.2.4 LIFE COMPONENTS 12/30/86 4 September 1986

,M53909 B-89 03/30/86 1 December 1985 iM55354 3-90 SALEM ATHS 4.3 H AND 58W T.S.

I B-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 09/10/85C fM54033 SALEM ATHS 4.5.2 4 4.5.3 TEST ALTERNATIVES 05/02/87 4.5.2 N/A for Alabama Power Company iM53980 i B-95 4.5.3 4 September 1986

M08057 C-01 PHR SECONDARY HATER CHEMISTRY MONITORING REQUIRLME 02/13/79C
M08673 C-06 PUMP SUPPORT-LAMELLAR TEARING 04/17/81C
M04837 C-07 FUEL HANDLING ACCIDENT INSIDE CONTAINMENT 04/09/80C

'M07989 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE 07/25/84C

M43G31 C-14 AUXILIARY FEEDWATER SEISMIC QUALIFICATION 11/08/82C M52226 C-15 CONTROL OF HEAVY LOADS - PHASE II (FOLLOHUP OF MPA 06/28/85C

'. M58 058 C-16 UTILITY RESPONSES TO STAFF RECDPMENDATIONS CONCERN Ol/02/86C lM07864 D-02 ECCS ZIRC CLAD MODEL ERROR-COMPLIANCE WITH 10 CFR- 05/09/79C M11997 D-04 PHR REACTOR VESSEL CAVITY SEAL RING MISSILE POTENT 01/26/80C M08.977 D-11 FISSION GAS RELEASE 02/22/80C 4

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INF0RMAT ION TRACKING SYSTEM PAGE No.: .159' 1-1208751-001 REGULAT0RY l

FACILITY IMPLEMENTATION 03/31/86

ARLEY 1 (CONTINUATION)

LIC ACT LICENSEE f TITLE COMPLETE STATUS B&IX lIAC No. MPA 8 l

!112206 D-15 HIGH ENERGY LINE BREAK 8 CONSEQUENTIAL SYSTEM FAIL 01/31/84C l143005 D-17 DEFINITION OF OPERABLE 03/01/82C 155857 D-19 DIESEL GENERATOR RELIABILITY TECH SPECS, (GL,84-15) 09/04/85C 7

144018 F-01 I.A.1.1 SNIFT TECHNICAL ADVISOR 02/16/82C

!144088 F-02 I.A.1.3 SHIFT MANNING 06/30/83C 144159 F-03 I.A.2.1 UPGRADING OF R0 AND SRO TRAINING 02/01/82C F-04 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC 06/03/83C l144230 F-05 I.C.1.2/3.5 PROCEDURES GENERATION PACKAGES (NUREG 03/30/86 1 July 1983 l144300

147213 F-06 I.C.5 FEEDBACK OF DPERATING EXPERIENCE 03/24/82C

!147285 F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI 05/24/82C F-08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRA 10/15/84C l151158 .

F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM 06/12/85C i151238 144371 F-10 II.B.1 RCS HIGH POINT VENTS 11/07/83C

14793S F-11 II.B.2 PLANT SHIELDING 12/15/83C I144439 F-12 II.B.3 POST ACCIDENT SAMPLING 10/11/84C ,

144509 F-13 II.B.4 TRAINING FOR MITIGATING CORE DAMAGE 02/01/82C F-14 RV AND SV 44WHHH4ErTesting 07/31/86 1 August 1984

144579 II.D.1

> 1446 35 F-15 II.E.1.1 AFH SYSTEM EVALUATION 07/C4/81C F-16 II.E.1.2.1 AFH SYSTEM INITIATION 08/07/81C l144377 144714 F-17 II.E.1.2.2 AFH SYSTEM FLOW INDICATION 08/07/81C 1144777 F-18 II.E.4.1 DEDICATED HYDROGEN PENETRATION 10/30/81C 144848 F-19 II.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY 06/30/81C F-20 II.F.1.1 NOBLE GAS MONITOR 10/29/81C l144919 s.

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REGULAT0RY INF0RMA I ION TRACKING SYSTEM PAGE NO.s ,100 R-1208731-001 IMPLEMENTATION 85/31/86 FACILITY FARLEY 1 (CONTINUATION)

LIC ACT LICENSEE TITLE COMPiETE STATUS Dalf TAC NO. MPA 0 F-21 II.F.1.2 IODINE / PARTICULATE SAMPLING 10/29/81C M44990 F-22 II.F.1.3 CONTAINMENT HIGH RANGE MONITOR 12/28/81C

! M45061 F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT,, 07/30/82C M47597 CONTAINMENT NATER LEVEL INSTRUMENT 07/30/82C M47668 F-24 II.F.1.5 CONTAINMENT HYDROGEN MONITOR 07/30/82C

! M47739 F-25 II.F.1.6

' M45132 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 06/30/87 4 May 1988 F-30 II.K.2.13 THERMAL-MECHANICAL REPORT 06/18/84C M46883 POTENTIAL FOR VOIDING IN RCS Ol/10/84C M47797 F-33 II.K.2.17 F-36 II.K.3.1 AUTO PORV ISOLATION 09/12/83C M45232 REPORT ON PORV FAILURES 09/23/83C M45278 F-37 II.K.3.2 REPORTING SV AND RV FAILURES AND CHALLE 03/26/82C M45541 F-38 II.K.3.3 F-39 II.K.3.5 AUTO TRIP OF RCPS 02/22/83C M45395 F-40 II.K.3.9 PID CONTROLLER 01/06/82C M45444 ,

F-41 II.K.3.10 ANTICIPATORY TRIP MODIFICATIONS 01/06/82C

! M45474

^ M45504 F-42 I I . K . 3.12 ANTICIPATORY TRIP DN TURBINE TRIP 01/06/82C

> M45627 F-47 II.K.3.17 ECCS OUTAGES 08/10/83C POWER ON PUMP SEALS 07/21/82C l M48417 F-53 II.K.3.25 58 LOCA METHODS 05/23/85C

!M45824 F-57 II.K.3.30 .

F-58 II.K.3.31 COMPLIANCE WITH 10 CFR 50.46 12/31/86 2 June 1986 M48163 F-63 III.A.1.2 TECHNICAL SUPPORT CENTER 09/30/87 1 1982*

1"M45943 F-64 OPERATIONAL SUPPORT CENTER 09/30/87- 1 1982 i M43014 III.A.1.2 F-65 III.A.1.2 EMERGENCY OPERATIONS FACILITY 09/30/87 1 1982 M43083 M4G158 F-66 III.A.1.2 NUCLEAR DATA LINK 07/30/82C i.

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  • SPDS data equipment to be installed in accordance with SPDS schedule t

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REOULAT0RY INF0RMATION TRACKING SYSTEM PAGE N2.8 .161 R-1208731-001 FACILITY IMPLEMENTATION 03/31/86

!FARLEY1 (CONTINUATION)

LIC ACT LICENSEE TAC NO. MPA 0 i TITLE COMPLETE STATUS BAIE

'M45230 F-67 III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 05/24/83C METEOROLOGICAL DATA UPGRADE 09/30/87 1 1982 M46502 F-68 III.A.2.2

'M46373 F-69 III.D.3.3 IMPLANT RADIATION MONITORING ,

03/24/82C

M46444 F-70 III.D.3.4 CONTROL ROOM HABITABILITY 03/31/83C F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEH (FOLLOHUP TO 01/30/87 2 December 1986*

}M56121 G-01 REACTOR COOLANT PUMP TRIP (D660 - II.K.3.5) 06/30/86 1 October 1985

'M49688 i

  • Summary Report

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TRACKING SYSTEN PACE NO. .162' R-1208731-001 REGULAT0RY INF0RHAI ION i

IMPLEMENTATION 03/31/86:

FACILITY I

' FACILITY: FARLEY 2 i

LICENSED P0HER: 2652 MHT PROJECT MANAGERS E. REEVES PLANT LOCATION: 28 MI SE OF DOTHAN, ALA 0829 MHE BRANCH CHIEF: L. RUBLHSTEIN

DOCKET NUMBER
050-00364 DESIGN PONER: . VACANT NSSS VENDOR: HEST LIC. ASSISTANT:

! ARCH / ENGINEER: SSI IE INSPECTOR: H. BRADFORD

! LIC ACT LICENSEE 4

COMPL ET E STATUS Ralg

TAC NO. MPA 3 TITLE A-01 10 CFR 50.55 A(G) - ISI 09/22/83C

.M51033 A-16 QUALIFICATIONS OF EXAMINATION, INSPECTION, TESTING 01/28/82C

!M47478 4 November 1987 M51089 A-17 INSTRUMENTATION TO FOLLON THE COURSE OF AN ACCIDEN A-18 TECH SPECS AFFECTED BY 50.72 AND 50.73 (GL 83-45) 02/19/85C

.M54235

  • N//S / 5 M59093 A-20 10 CFR 50.62 OPERATING REACTOR REVIENS 3 May 1986
M59954 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE B-32 BLOCKED SI SIGNAL DURING C00LD0HN 01/09/84C

! M49419 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 08/26/83C

!M43572 4

B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 05/04/82C i M43015 B-46 ANALYSIS OF TURBINE DISC CRACKS 05/23/85C M43016

M43966 B-59 MASONRY HALL DESIGN 03/01/83C M43952 B-63 INTERIM PROCEDURES FOR SHORT TERM BLACKOUT 12/14/81C iM47173 B-66 NATURAL CIRCULATION C00LDOWN 11/14/83C M44838 B-69 IEB 80-4 MAINSTEAM LINE BREAK HITN CONTINUED FEEDH 10/21/82C B-72 NUREG 0737 TECH SPECS (GENERIC LETTER 82-16) 05/07/84C

!M49732 B-76 ITEM 1.1 - POST TRIP REVIEH; PROGRAM DESCRIPTION & 05/21/85C fM52756 1 1983 ITEM 2.1 - EQUIPMENT CLASSIFICATION & VENDOR INTER 03/31/86 i*M52837 B-77 B-78 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 09/10/85C iM52918 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 11/12/85C

- M52999 1

'M53070 B-80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDO 09/10/85C j'

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  • 90 days after NRC issuance of SER on WOG submittal v

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SYSTEM PAGE NO. ,163 3-1208731-001 REGULAT0RY INF0RMAI ION TRACKING IMPLEMENTATION 03/31/86 FACILITY 7ARLEY 2 (CONTINUATION)

LIC ACT LICENSEE COMPL ETE STATUS R&lg TAC NO. MPA 8 TITLE B-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PROG FOR R 12/24/85C 253123 M53173 5-82 ITEM 4.5 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 07/23/84C 5-83 TECH SPECIFICATIONS COVERED BY GENERIC LE,TTERS 83- 09/12/84C M54532 B-85 SALEM ATHS 1.2 DATA CAPABILITY 06/12/85C M53588 B-86 SALEM ATHS 2.2 S-R COMPONENTS 05/02/86 1 April 1985 M53671 12/31/86 3.2.1 1 February 1984 M53750 B-87 SALEM ATHS 3.2.1 & 3.2.2 S-R COMPONENTS 3.2.2 3 March 1986 B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 11/12/85C M53837 12/30/86 4 September 1986 M53910 B-89 SALEM ATHS 4.2.3 & 4.2.4 LIFE COMPONENTS 03/30/86 1 December 1985 M55555 B-90 SALEM ATHS 4.3 H AND B&W T.S.

B-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 09/10/85C M540G4 253981 B-95 SALEM ATHS 4.5.2 & 4.5.3 TEST ALTERNATIVES 05/15/87 4.5.2 N/A for Alabama Power Company 07/25/84C 4.5.3 4 September 1986 I43905 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE M47192 C-14 AUXILIARY FEEDWATER SEISMIC QUALIFICATION 11/08/82C C-15 CONTROL OF HEAVY LOADS - PHASE II (FOLLONUP OF MPA 06/28/85C H53227 M58059 C-16 UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN 01/02/86C Q46589 D-15 HIGH ENERGY ? THE BREAK & CONSEQUENTIAL SYSTEM FAIL 08/31/81C Q55858 D-19 DIESEL GENERATOR RELIABILITY TECH SPECS (GL 84-15) 09/04/85C.

Q44019 F-01 I.A.1.1 SHIFT TECHNICAL ADVISOR 02/16/82C F-02 1.A.1.3 SHIFT MANNING 06/30/83C Q44089 F-03 I.A.2.1 UPGRADING OF R0 AND SRO TRAINING 09/30/80C T44100 M44231 F-04 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC 06/03/83C I.C.1.2/3.5 PROCEDURES GENERATION PACKAGES (NUREG 03/30/86 1 1983 Q44301 F-05 M47214 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE 03/24/82C

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INF0RMATION TRACKING SYSTEM PAGE NO.* 164

R-1208731-001 REGULAT0RY 03/31/86,

! FACILITY IMPLEMENTATION JARLEY 2 (CONTINUATION) s.

LIC ACT LICENSEE 4

IAC NO. MPA 0 TITLE COMPLETE STATUS D&If

M47286 F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI 03/24/82C

!M51159 F-08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEH PROGRA 10/10/84C M51239 F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM . 06/12/85C M44372 F-10 II.B.1 RCS HIGH POINT. VENTS 11/07/83C ,

F-11 II.B.2 PLANT SNIELDING 12/15/83C

]M47957 F-12 II.B.3 POST ACCIDENT SAMPLING 10/11/84C

]M44440 iM44510 F-13 II.B.4 TRAINING FOR MITIGATING CORE DAMAGE 05/30/81C 07/31/86 1 August 1984

!M44580 F-14 II.D.1 RV AND SV TRktMPMGTeStin9

!M44636 F-15 II.E.1.1 AFH SYSTEM EVALUATION 06/19/81C F-16 II.E.1.2.1 AFH SYSTEM INITIATION 08/14/81C lM44G78 F-17 II.E.1.2.2 AFH SYSTEM FLON INDICATION 08/14/81C iM44715 1

iM44778 F-18 II.E.4.1 DEDICATED HYDROGEN PENETRATION 09/30480C t

M44849 F-19 II.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY 03/15 1C IM44920 F-20 II.F.1.1 NOBLE GAS MONITOR 10/29/81C F-21 II.F.1.2 IODINE / PARTICULATE SAMPLING 05/30/ ,1C e M44991 i

. M450G2 F-22 II.F.1.3 CONTAINMENT HIGH RANGE MONITOR 12/28/81C F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 07/30/82C

}M47598

!M40493 F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 01/01/7bC i 01/01/70C F-24 II.F.1.5 CONTAINMENT HATER LEVEL INSTRUMENT jM4G493

M47669 F-24 II.F.1.5 CONTAINMENT HATER LEVEL INSTRUMLNT 07/30/8)C

^

i .

F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR 07/30/83C JM47740 l

lM46494 F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR 01/01/70C i

i 4 November 1987

M45133 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 06/30/83

. v.

I e

- f i

INF0RMA IION TRACKING SYSTEM PAGE NO.8 .105 R-1208731-001 REGULAT0RY FACILITY IMPLEMENTATION 03/31/86

.fARLEY 2 (CONTINUATION)

LIC ACT LICENSEE MPA 0 TITLE COMPLETE STATUS BAIE TAC NO.

M46887 F-30 II.K.2.13 THERMAL-MECHANICAL REPORT 06/18/84C M47798 F-33 II.K.2.17 POTENTIAL ltk VOIDING IN RCS 01/10/84C M45233 F-36 II.K.3.1 AUTO PORV ISOLATION . 09/23/83C .

09/23/83C

'H45279 F-37 II.K.3.2 REPORT ON PORV FAILURES M45342 F-38 II.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 06/19/81C F-39 II.K.3.5 AUTO TRIP OF RCPS 02/22/83C

.M45396 .

M45445 F-40 II.K.3.9 PID CONTROLLER 06/19/81C F-41 II.K.3.10 ANTICIPATORY TRIP MODIFICATIONS 06/19/81C fM05475

'H45505 F-42 II . K . 3.12 ANTICIPATORY TRIP DN TURBINE TRIP 06/19/81C

M48418 F-53 II.K.3.25 PONER ON PUMP SEALS 07/21/82C I M45825 F-57 II.K.3.30 SB LOCA METHOD 3 05/00/85C COMPLIANCE HITH 10 CFR 50.46 12/31/86 2 June 1986

.M48164 F-58 II.K.3.31 09/30/87 1 1982*

M45944 F-63 III.A.1.2 TECHNICAL SUPPORT CENTER 09/30/87 1 1982

.H46015 F-64 III.A.1.2 OPERATIONAL SUPPORT CENTER 09/30/87 1 1982 lM46087 F-65 III.A.1.2 EMERGENCY DPERATIONS FACILITY F-66 III.A.I.2 NUCLEAR DATA LINK 07/30/82C 1M46159 M46231 F-67 III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 05/24/83C 09/30/87 1 1982

M40303 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE M46574 F-69 III.D.3.3 IMPLANT RADIATION MONITORING 09/30/80C F-70 III.D.3.4 CONTROL ROOM HABITABILITY 03/15/81C JM46445 01/30/87 2 December 1986**

M56122 F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEH (FDLLOHUP 10 06/30/86 1 October 1985

.H49689 G-01 REACTOR COOLANT PUMP TRIP (D660 - II.K.3.5)

  • SPDS data equipment to be installed in accordance with SPDS schedule
    • Summary Report v

M

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