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  
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)
v • d • e


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

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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 8606090227 860602--

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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 R-1208731-001 REGULAT0RY INF0RHA1 ION IRACKING SYSTEM PAGE NO.s 15Y 03/31/86 FACILITY IMPLEMENTATION 4

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

! DOCKET NUMBER: 050-00348 DESIGN PollLRs 0829 MHE BRANCH CHIEF

  • L. RUBENSTEIN NSSS VENDOR:

HEST LIC. ASSISTANT:

. VACANT ARCH / ENGINEER SSI lIE INSPECTOR

  • H. BRADFORD LIC ACT LICENSEE COMPLETE STATUS DATE

{ TAC NO.

MPA B TITLE

MS4631 A-01 10 CFR 50.55 A(G) - ISI 12/07/79C 05/01/82C

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

!M10472 A-12 VITAL AREA ANALYSIS

!M11277 A-14 1DCFR 58.55 A(G) - INSERVICE TESTING 04/29/83C lM47477 A-16 GUALIFICATIONS OF EXAMINATION, INSPECTION, TESilHG 01/28/82C 4

May 1988 1M51088 A-17 INSTRUMENTATION TO FOLLOW THE COURSE OF AN ACCIDEN 1

M54235 A-18 TECH SPECS AFFECTED BY 50.72 AND 58.73 (GL 85-45) 02/19/85C 5

i lM59092 A-20 10 CFR 50.62 OPERATING REACTOR REVIEWS N//S /

3 May 1986 IM59953 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE 04/13/79C

' M00671 B-02 FIRE PROTECTION 02/21/79C iM08379 B-03 PHR MODERATOR DILUTION 1104835 B-04 REACTOR VESSEL OVERPRESSURE PROTECTION 07/31/79C

,'M08165 5-08 PHR HPSI-LPSI FLOW RESISTANCE 02/13/79C M08176 B-14 CEA GUIDE TURE WEAR 10/03/80C

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

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

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

1

t-1208731-001 REGULAT0RY INF0RMAT ION TRACKING SYSTEM PAGE NO. ',156 FACILITY IMPLEMENTATION 03/31/86, (CONTINUATION)

.FARLEY 1 LIC ACT LICENSEE TAC MO.

NPA 0 TITLE COMPLETE STATUS DAIX 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 WE375 B-22 TECN SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 03/01/82C

104836 B-23 DEGRADED GRID VOLTAGE

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03/09/81C 110166 B-24 VENTING AND PURGING CONTAINMENTS HNILE AT FULL POW 07/16/80C

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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

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

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

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4-1208731-001 REGULAT0RY INF0RMAT ION TRACKING SYSTEM PAGE NO.

,157 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

'M30109 B-44 LESSONS LEARNED IMPLEMENIATION 04/03/80C H30610 B-44 LESSONS LEARNED IMPLEMENTATION 04/03/80C

'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

'M13006 B-48 ADEQUACY OF STATION ELECTRIC _ DISTRIBUTION VOLTAGE 03/09/81C

-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
M42493 B-57 UHR CAPARILITY' 03/01/82C 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

!M49731 3-12 MUREG 0737 TECN SPECS (GE$ERI'C LETTER 82-16) 05/07/84C

M52755 B-76

' ITEM 1.I - POST TRIP REVIEH; PROGRAM DESCRIPTION &

05/21/85C IMS2835 B-77.

" ITEM 2.1 - EQUIPMENT CLASSIFICATION & VENDOR INTER 03/31/86 1

1983 IM52917 B-78 ' ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PR' CEDU 09/10/85C O

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R-1208731-001 REGULAT0RY INF0RMAT ion TRACKING SYSTEM PAGE NO.*

158 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 M53670 B-86 SALEM ATHS 2.2 S-R COMPONENTS 05/02/86 1

April 1985 H53753 B-87 SALEM ATHS 3.2.1 4 3.2.2 S-R COMPONENTS 12/31/86 3.2.1 1

February 1934 M53836 B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 11/12/85C

,M53909 B-89 SALEM ATHS 4.2.3 & 4.2.4 LIFE COMPONENTS 12/30/86 4

September 1986 iM55354 3-90 SALEM ATHS 4.3 H AND 58W T.S.

03/30/86 1

December 1985 I

B-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 09/10/85C fM54033 iM53980 i B-95 SALEM ATHS 4.5.2 4 4.5.3 TEST ALTERNATIVES 05/02/87 4.5.2 N/A for Alabama Power Company 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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1-1208751-001 REGULAT0RY INF0RMAT ION TRACKING SYSTEM PAGE No.:

.159' FACILITY IMPLEMENTATION 03/31/86 l

ARLEY 1 (CONTINUATION)

LIC ACT LICENSEE flIAC No.

MPA 8 TITLE COMPLETE STATUS B&IX 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 l144230 F-04 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC 06/03/83C l144300 F-05 I.C.1.2/3.5 PROCEDURES GENERATION PACKAGES (NUREG 03/30/86 1

July 1983

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 l151158 F-08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRA 10/15/84C i151238 F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM 06/12/85C 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
144579 F-14 II.D.1 RV AND SV 44WHHH4ErTesting 07/31/86 1

August 1984

> 1446 35 F-15 II.E.1.1 AFH SYSTEM EVALUATION 07/C4/81C l144377 F-16 II.E.1.2.1 AFH SYSTEM INITIATION 08/07/81C 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 l144919 F-20 II.F.1.1 NOBLE GAS MONITOR 10/29/81C s.

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

LIC ACT LICENSEE TAC NO.

MPA 0 TITLE COMPiETE STATUS Dalf M44990 F-21 II.F.1.2 IODINE / PARTICULATE SAMPLING 10/29/81C

! M45061 F-22 II.F.1.3 CONTAINMENT HIGH RANGE MONITOR 12/28/81C M47597 F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT,,

07/30/82C M47668 F-24 II.F.1.5 CONTAINMENT NATER LEVEL INSTRUMENT 07/30/82C

! M47739 F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR 07/30/82C

' M45132 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 06/30/87 4

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

! M45474 F-41 II.K.3.10 ANTICIPATORY TRIP MODIFICATIONS 01/06/82C

^ 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 l M48417 F-53 II.K.3.25 POWER ON PUMP SEALS 07/21/82C

!M45824 F-57 II.K.3.30 58 LOCA METHODS 05/23/85C M48163 F-58 II.K.3.31 COMPLIANCE WITH 10 CFR 50.46 12/31/86 2

June 1986 1"M45943 F-63 III.A.1.2 TECHNICAL SUPPORT CENTER 09/30/87 1

1982*

i M43014 F-64 III.A.1.2 OPERATIONAL SUPPORT CENTER 09/30/87-1 1982 M43083 F-65 III.A.1.2 EMERGENCY OPERATIONS FACILITY 09/30/87 1

1982 M4G158 F-66 III.A.1.2 NUCLEAR DATA LINK 07/30/82C i.

i

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

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R-1208731-001 REOULAT0RY INF0RMATION TRACKING SYSTEM PAGE N2.8.161 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 M46502 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE 09/30/87 1

1982

'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

}M56121 F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEH (FOLLOHUP TO 01/30/87 2

December 1986*

'M49688 G-01 REACTOR COOLANT PUMP TRIP (D660 - II.K.3.5) 06/30/86 1

October 1985 i

  • Summary Report

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

.162' 03/31/86:

i FACILITY IMPLEMENTATION I

' FACILITY: FARLEY 2 PLANT LOCATION: 28 MI SE OF DOTHAN, ALA LICENSED P0HER: 2652 MHT PROJECT MANAGERS E. REEVES i

DOCKET NUMBER

050-00364 DESIGN PONER:

0829 MHE BRANCH CHIEF:

L. RUBLHSTEIN

! ARCH / ENGINEER: SSI NSSS VENDOR:

HEST LIC. ASSISTANT:

. VACANT IE INSPECTOR:

H. BRADFORD LIC ACT LICENSEE 4

COMPL ET E STATUS Ralg

TAC NO.

MPA 3 TITLE

.M51033 A-01 10 CFR 50.55 A(G) - ISI 09/22/83C

!M47478 A-16 QUALIFICATIONS OF EXAMINATION, INSPECTION, TESTING 01/28/82C 4

November 1987 M51089 A-17 INSTRUMENTATION TO FOLLON THE COURSE OF AN ACCIDEN

.M54235 A-18 TECH SPECS AFFECTED BY 50.72 AND 50.73 (GL 83-45) 02/19/85C M59093 A-20 10 CFR 50.62 OPERATING REACTOR REVIENS N//S /

5 3

May 1986

M59954 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE

! M49419 B-32 BLOCKED SI SIGNAL DURING C00LD0HN 01/09/84C

!M43572 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 08/26/83C 4

i M43015 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 05/04/82C M43016 B-46 ANALYSIS OF TURBINE DISC CRACKS 05/23/85C 03/01/83C

M43966 B-59 MASONRY HALL DESIGN 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

!M49732 B-72 NUREG 0737 TECH SPECS (GENERIC LETTER 82-16) 05/07/84C B-76 ITEM 1.1 - POST TRIP REVIEH; PROGRAM DESCRIPTION &

05/21/85C fM52756 i*M52837 B-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION & VENDOR INTER 03/31/86 1

1983 iM52918 B-78 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 09/10/85C

- M52999 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 11/12/85C 1

'M53070 B-80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDO 09/10/85C 1j'

  • 90 days after NRC issuance of SER 4

on WOG submittal v

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l 3-1208731-001 REGULAT0RY INF0RMAI ION TRACKING SYSTEM PAGE NO.

,163 03/31/86 FACILITY IMPLEMENTATION 7ARLEY 2 (CONTINUATION)

LIC ACT LICENSEE TAC NO.

MPA 8 TITLE COMPL ETE STATUS R&lg 253123 B-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PROG FOR R 12/24/85C M53173 5-82 ITEM 4.5 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 07/23/84C M54532 5-83 TECH SPECIFICATIONS COVERED BY GENERIC LE,TTERS 83-09/12/84C M53588 B-85 SALEM ATHS 1.2 DATA CAPABILITY 06/12/85C M53671 B-86 SALEM ATHS 2.2 S-R COMPONENTS 05/02/86 1

April 1985 M53750 B-87 SALEM ATHS 3.2.1 & 3.2.2 S-R COMPONENTS 12/31/86 3.2.1 1

February 1984 3.2.2 3

March 1986 M53837 B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 11/12/85C M53910 B-89 SALEM ATHS 4.2.3 & 4.2.4 LIFE COMPONENTS 12/30/86 4

September 1986 M55555 B-90 SALEM ATHS 4.3 H AND B&W T.S.

03/30/86 1

December 1985 M540G4 B-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 09/10/85C 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 4.5.3 4

September 1986 I43905 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE 07/25/84C M47192 C-14 AUXILIARY FEEDWATER SEISMIC QUALIFICATION 11/08/82C H53227 C-15 CONTROL OF HEAVY LOADS - PHASE II (FOLLONUP OF MPA 06/28/85C 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 Q44089 F-02 1.A.1.3 SHIFT MANNING 06/30/83C T44100 F-03 I.A.2.1 UPGRADING OF R0 AND SRO TRAINING 09/30/80C M44231 F-04 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC 06/03/83C Q44301 F-05 I.C.1.2/3.5 PROCEDURES GENERATION PACKAGES (NUREG 03/30/86 1

1983 M47214 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE 03/24/82C

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164 FACILITY IMPLEMENTATION 03/31/86, JARLEY 2 (CONTINUATION) s.

LIC ACT LICENSEE IAC NO.

MPA 0 TITLE COMPLETE STATUS D&If 4

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

]M47957 F-11 II.B.2 PLANT SNIELDING 12/15/83C

]M44440 F-12 II.B.3 POST ACCIDENT SAMPLING 10/11/84C

!iM44510 F-13 II.B.4 TRAINING FOR MITIGATING CORE DAMAGE 05/30/81C

!M44580 F-14 II.D.1 RV AND SV TRktMPMGTeStin9 07/31/86 1

August 1984

!M44636 F-15 II.E.1.1 AFH SYSTEM EVALUATION 06/19/81C lM44G78 F-16 II.E.1.2.1 AFH SYSTEM INITIATION 08/14/81C iM44715 F-17 II.E.1.2.2 AFH SYSTEM FLON INDICATION 08/14/81C 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 e M44991 F-21 II.F.1.2 IODINE / PARTICULATE SAMPLING 05/30/,1C i

. M450G2 F-22 II.F.1.3 CONTAINMENT HIGH RANGE MONITOR 12/28/81C

}M47598 F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 07/30/82C

!M40493 F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 01/01/7bC i

jM4G493 F-24 II.F.1.5 CONTAINMENT HATER LEVEL INSTRUMENT 01/01/70C

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

^

JM47740 F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR 07/30/83C lM46494 F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR 01/01/70C l

i

M45133 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 06/30/83 4

November 1987 i

v.

I e

f i

R-1208731-001 REGULAT0RY INF0RMA IION TRACKING SYSTEM PAGE NO.8.105 FACILITY IMPLEMENTATION 03/31/86

.fARLEY 2 (CONTINUATION)

LIC ACT LICENSEE TAC NO.

MPA 0 TITLE COMPLETE STATUS BAIE 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 09/23/83C M45233 F-36 II.K.3.1 AUTO PORV ISOLATION

'H45279 F-37 II.K.3.2 REPORT ON PORV FAILURES 09/23/83C M45342 F-38 II.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 06/19/81C

.M45396 F-39 II.K.3.5 AUTO TRIP OF RCPS 02/22/83C M45445 F-40 II.K.3.9 PID CONTROLLER 06/19/81C fM05475 F-41 II.K.3.10 ANTICIPATORY TRIP MODIFICATIONS 06/19/81C

'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

.M48164 F-58 II.K.3.31 COMPLIANCE HITH 10 CFR 50.46 12/31/86 2

June 1986

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 09/30/87 1

1982 1M46159 F-66 III.A.I.2 NUCLEAR DATA LINK 07/30/82C M46231 F-67 III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 05/24/83C

M40303 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE 09/30/87 1

1982 M46574 F-69 III.D.3.3 IMPLANT RADIATION MONITORING 09/30/80C JM46445 F-70 III.D.3.4 CONTROL ROOM HABITABILITY 03/15/81C M56122 F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEH (FDLLOHUP 10 01/30/87 2

December 1986**

.H49689 G-01 REACTOR COOLANT PUMP TRIP (D660 - II.K.3.5) 06/30/86 1

October 1985

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

M

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