ML20210R859

Requests Review of Encl plant-specific List,Adding Omitted Significant Actions & Providing Dates That All Aspects of Requirement Completed/Implemented or Expected to Be Complete,In Support of Program to Improve Documentation

ML20210R859
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/02/1986
From:	Vissing G Office of Nuclear Reactor Regulation
To:	Campbell G ARKANSAS POWER & LIGHT CO.
References
TASK-***, TASK-TM NUDOCS 8605200019
Download: ML20210R859 (18)

Text

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May 2,1986 3%$Oh i

Docket No.

DISTRIBUTION SScott W*!P"'

FG2" Mr. Gene Campbell L POR JPartlow Vice President, Nuclear PBD#6 Rdg Ringram Operations FMiraglia GVissing Arkansas Power and Light Company OELD Gray File P. O. Box 551 ACRS-10 HSmith Little Rock, Arkansas 72203

Dear Mr. Campbell:

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' implementation of approved regulatory improvements.

To assist me in developing this information for Arkansas Nuclear One, Unit 1, 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-kncwn 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.

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.

This request is covered by OMB Clearance Number 3150-0011, which expires September 30, 1986.

Sincerely,

• gRtGINAL SG'iG BY:"

Guy S. Vissing, Project Manager PWR Project Directorate #6 Division of PWR Licensing-B

Enclosure:

As Stated cc w/ enclosure: See next page PBI)-6 PBD-F8-6 Gyjs[/86 ing;cf CMcC cken J54 z 5'/f-5///86 Sr 78fi 8605200019 860502 l

PDR ADOCK 05000313 l

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Mr. J. M. Griffin Arkansas Power & Light Company Arkansas Nuclear One, Unit 1 l

cc:

l Mr. J. Ted Enos Manager, Licensing Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkansas 72203 Mr. James M. Levine l

General Manager Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 Mr. Nicholas S. Reynolds Bishop. Liberman, Cook, Purcell & Reynolds 1200 Seventeenth Street, N.W.

Washington, D.C.

20036 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 2090 Russellville, Arkansas 72801 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director l

for Operations I

I 611 Ryan Plaza Drive, Suite 1000 I

Arlington, Texas 76011 Mr. Frank Wilson, Director Division of Environmental Health Protection Department of Health Arkansas Department of Health 4815 West Markham Street Little Rock, Arkansas 72201 Honorable William Abernathy l

County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801

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FACILITY: ARKANSAS 1

'LANT LOCATION: 6 MI HHH OF RUSSELLVILLE, AR LICENSED P0HER: 2568 MHT PROJECT MANAGER: G. VISSING DOCKET NUMBER:

050-00313 DESIGN POWER:

0850 MWE BRANCH CHIEF:

J. STOLZ LRCH/ ENGINEER:

BECH NSSS VENDOR:

B&H LIC. ASSISTANT:

R. INGRAM

[E INSPECTOR:

H. JOHNSON LIC ACT LICENSEE TAC NO.

MPA 8 TITLE COMPLETE STATUS palg M07521 A-01 10 CFR 50.55 A(G) - ISI 04/18/83C M08105 A-02 APPENDIX I - ALARA 09/30/84C M06942 A-03 SECURITY REVIENS-MODIFIED AMENDMENT PLANS 02/23/79C M11480 A-04 APPENDIX J - CONTAINMENT LEAK TESTING 12/02/81C M06161 A-08 ECCS EVALUATION-GENERIC PER 50.46 COMPLIANCE 10/12/79C M11379 A-09 PRESSURE VESSEL BELTLINE MATERIAL C'P.VEILLANCE 05/19/80C M10539 A-10 CONTINGENCY PLANNING 11/01/80C M10537 A-11 GUARD TRAINING PLANS 02/23/82C M10542 A-12 VITAL AREA ANALYSIS 04/12/82C M11236 A-14 10CFR 50.55 ACG) - INSERVICE TESTING 07/30/84C 08458 A-15 QUALITY ASSURANCE REQUEST REGARDING DIESEL GENARAT 04/03/80C 46810 A-16 QUALIFICATIONS OF EXAMINATION, INSPECTION, TESTING 12/15/81C 51069 A-17 INSTRUMENTATION TO FOLLOH THE COURSE OF AN ACCIDEN 05/30/86 5696 A-18 TECM SPECS AFFECTED BY 50.72 AND 50.73 (GL 83-43) 06/28/86 9068 A-20 10 CFR 50.62 OPERATING REACTOR REVIENS 07/13/85C 59939 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE 12/30/86

%06211 B-02 FIRE PROTECTION 08/22/78C 08371 B-03 PWR MODERATOR DILUTION 08/14/81C

[06806 B-04 REACTOR VESSEL OVERPRESSURE PROTECTION 05/05/83C

$08347 B-08 PHR HPSI-LPSI FLOH RESISTANCE 03/01/79C i

I

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LIC ACT LICENSEE RC NO.

MPA 6 TITLE COMPLETE STATUS Ralg 12197-B-10 BURNABLE POISON ROD FAILURE - B&W 01/01/70C 11406 B-12 STEAM GENERATOR TUBE INSPECTION 04/10/79C 58453 B-13 FUEL ROD B0H 03/17/78C 08450 B-14 CEA GUIDE TUBE HEAR 07/24/81C 10844 B-14 CEA GUIDE TUBE HEAR 07/24/81C 12199 B-16 EMERGENCY PLANNING AND REVISIONS 04/01/81C D9034 B-16 EMERGENCY PLANNING AND REVISIONS 10/07/78C 11267 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS 10/15/84C 10316 B-20 CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION 01/30/81C 10378 B-21 LOSS OF 125-V DC BUS VOLTAGE HITN LOSS OF ANNUNCIA 02/28/82C 11266 B-22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 10/15/84C l

B0006 B-23 DEGRADED GRID VOLTAGE 01/01/70C 8457 B-23 DEGRADED GRID VOLTAGE 12/17/79C 0212 B-24 VENTING AND PURGING CONTAINMENTS HNILE AT FULL PON 08/14/80C 2595 B-24 VENTING AND PURGING CONTAINMENTS WHILE AT FULL POW 05/15/81C 0253 B-26 INADVERTANT SAFETY INJECTION DURIFG C00LDOHN 09/14/79C

)0529 B-35 DRIFICE ROD ASSEMBLY INTEGRITY - B8H 05/23/79C f7087 B-38 -TENDON SURVEILLANCE - BECHTEL CONTAINMENTS 05/25/82C 38701 B-39 PHR PRESSURE - TEMPERATURE LIMIT TECH SPECS 11/13/80C

)1241 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 02/03/81C 33689 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 04/29/81C 33691 B-41 FIRE PROTECTION - FINAL TECN SPECS (INCLUDES SER S 05/10/82C 33554 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 02/01/83C

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, Si FACILITY IMPLEMENTATION 03/31/86-LRKANSAS 1 (CONTINUATION)

LIC ACT LICENSEE FAC NO.

MPA 9 TITLE COMPLETE STATUS DAIE 111727 B-42 TMI FOLLOH UP - ALL PLANTS 12/19/80C 111728 B-42 TMI FOLLOW UP - ALL PLANTS 01/30/81C 111826 B-42 TMI FOLLOW UP - ALL PLANTS 02/05/81C 111795 B-43 PHR FEEDHATER LINE CRACKS 01/12/81C 112450 B-44 LESSONS LEARNED IMPLEMENTATION 05/11/80C 130015 B-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C 130016 B-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C 133017 B-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C 130018 B-44 LESSONS LEARNED IMPLEMENTATION 05/26/80C 130019 B-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C 130020 B-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C 130021 B-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C 130022 B-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C 130023 B-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C 130024 B-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C 130025 B-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C 130026 B-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C 130027 B-44 LESSONS LEARNED IMPLEMENTATION 03/26/80C 130028 B-44 LESSONS LEARNED IMPLEMENTATION 05/26/80C (12877 B-45 HASH 1400 EVENT V, " PRIMARY COOLANT SYSTEM 'RESSUR 04/20/81C 112578 B-46 ANALYSIS OF TURBINE DISC CRACKS 08/20/81C 142129 B-46 ANALYSIS OF TURBINE DISC CRACKS-05/20/80C 112730 B-47 ECCS; CLAD SHELLING AND RUPTURE 09/09/80C

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$ KANSAS 1 (CONTINUATION)

LIC ACT LICENSEE

'AC NO.

MPA 8 TITLE COMPLETE STATUS DAlg l92790 B-48 ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 05/27/83C l

2253 B-52 REVIEN OF SAFETY ASPECT OF INADVERTENT SAFETY ACTI 10/21/80C

%2120 B-57 DHR CAPABILITY 05/20/81C h2901 B-59 MASONRY HALL DESIGN 08/02/82C

- I 22514 B-60 ENVIRONMENTAL QUALIFICATION 12/03/84C l

f2650 B-61 LOSS OF NON CLASS IE ISC PONER 07/28/82C

,2720 5-62 ESF RESET-CONTROL DESIGN DEFICIENCY 06/17/81C 43548 B-63 INTERIM PROCEDURES FDR SHORT TERM BLACKOUT 12/11/81C b3886 B-63 INTERIM PROCEDURES FOR SHORT TERM BLACK 0UT 12/11/81C I

G3265 B-64 B8C INDUCED FLUX ERRDRS 04/11/82C l

27181 B-66 NATURAL CIRCULATION C00LDONN 07/11/85C 6824 B-69 IEB 80-4 MAINSTEAM LINE BREAK HITH CONTINUED FEEDH 10/08/82C 6597 B-70 FATIGUE TRANSIENT LIMIT TS 05/25/82C g

h2735 B-76 ITEM 1.1 - POST TRIP REVIEN; PROGRAM DESCRIPTION &

08/06/85C

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22816 B-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION & VENDOR INTER 10/30/86

'2897 B-78 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 07/10/85C

>2978 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 07/10/85C 93059 B-80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDO 12/27/85C 23112 B-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PROG FOR R 12/17/85C B3165 5-82 ITEM 4.3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 05/14/84C i

@4514 B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83-01/31/85C B3567 B-85 SALEM ATHS 1.2 DATA CAPABILITY 01/31/86 23650 B-86 SALEM ATHS 2.2 S-R COMPONENTS 03/15/86

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MPA #

TITLE COMPLETE STATUS DAIE 53733 B-87 SALEM ATHS 3.2.1 & 3.2.2 S-R COMPONENTS 12/17/85C 53816 B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 07/10/85C 53899 B-89 SALEM ATHS 4.2.3 & 4.2.4 LIFE COMPONENTS 12/31/86 55347 B-90 SALEM ATHS 4.3 H AND B8N T.S.

08/30/86 53952 B-91 SALEM ATHS 4.4 B8N TEST PROCEDURES 04/30/86 54043 B-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 01/31/87 53960 B-93 SALEM ATHS 4.5.2 & 4.5.3 TEST ALTERNATIVES 04/30/87 0G038 C-01 PHR SECONDARY HATER CHEMISTRY MONITORING REQUIREME 03/01/83C 07246 C-05 CONVERSION TO STANDARD TECH SPECS 01/21/81C 08447 C-06 PUMP SUPPORT-LAMELLAR-TEARING 04/17/81C l

08461 C-07 FUEL HANDLING ACCIDENT INSIDE CONTAINMENT 11/07/79C 07971 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE 10/11/84C 43632 C-14 AUXILIARY FEEDWATER SEISMIC QUALIFICATION 07/26/84C 43549 C-14 AUXILIARY FEEDHATER SEISMIC QUALIFICATION 04/02/82C 52206 C-15 CONTROL OF HEAVY LOADS - PHASE II (FOLLONUP OF MPA 06/28/85C 58043 C-16 UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN 06/30/86 07863 D-04 PHR REACTOR VESSEL CAVITY SEAL RING MISSILE POTENT 10/30/80C 01908 D-08 DEFICIENCY IN CHEM ADDITION TO CONTAINMENT SPRAYS 01/12/79C 08607 D-08 DEFICIENCY IN CHEM ADDITION TO CONTAINMENT SPRAYS 01/01/70C 37862 D-10 ASYMMETRIC LOCA LOADS 02/14/84C 08455 D-11 FISSION GAS RELEASE 05/23/79C 07476 D-13 B&W SMALL BREAK ERROR 03/01/79C 08445 D-14 REACTOR VESSEL HELD - HIRE DEFICIENCY 02/11/80C

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,8 FACILITY IMPLEMENTATION 03/31/86 3 KANSAS 1 (CONTINUATION)

LIC ACT LICENSEE AC NO.

MPA #

TITLE G_0MPLETE STATUS DAlf 12320 D-15 HIGH ENERGY LINE BREAK & CONSEQUENTIAL SYSTEM FAIL 02/02/84C l43036 D-17 DEFINITION OF OPERABLE 06/06/81C 142151 D-17 DEFINITION OF OPERABLE 06/16/81C

'51731 D-18 NUREG 0630 CLADDING MODELS (B&W PLANTS) 07/19/83C

55836 D-19 DIESEL GENERATOR RELIABILITY TECH SPECS (GL 84-15) 08/06/85C l06235 E-02 FUEL CASK DROP 10/05/78C 18454 E-03 CORE RELOADS REQUIRING PRIOR NRC APPROVAL 05/23/79C 11811 E-03 CORE RELOADS REQUIRING PRIOR NRC APPROVAL 03/09/81C 34000 F-01 I.A.1.1 SHIFT TECHNICAL ADVISOR 02/05/82C S4068 F-02 I.A.1.3 SHIFT MANNING 06/30/83C

$4139 F-03 I.A.2.1 UPGRADING OF RO AND SRO TRAINING 12/01/82C 44210 F-04 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC 06/07/84C 42842 F-05 I.C.1.2/3.B PROCEDURES GENERATION PACKAGES (NUREG 05/30/86 57193 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE 11/21/81C 47265 F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI 11/21/81C 21359 F-08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEH PROGRA 10/10/84C 21219 F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM 07/15/86 44351 F-10 II.B.1 RCS HIGH POINT VENTS 09/13/83C I

47917 F-11 II.B.2 PLANT SHIELDING 05/11/83C 44419 F-12 II.B.3 POST ACCIDENT SAMPLING 08/27/84C l

44489 F-13 II.B.4 TRAINING FOR MITIGATING CORE DAMAGE 12/01/82C 44560 F-14 II. D.1 RV AND SV TRAINING 04/28/86 j

42634 F-15 II.E.1.1 AFH Sib f EM EVALUATION 10/06/83C j

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'AC NO.

MPA t TITLE COMPLETE STATUS PALE M4707 F-16 II.E.1.2.1 AFH SYSTEM INITIATION 07/28/82C i

M4749 F-17 II.E.1.2.2 AFH SYSTEM FLOH INDICATION 07/23/82C 144757 F-18 II.E.4.1 DEDICATED HYDROGEN PENETRATION 08/14/81C M4828 F-19 II.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY 09/15/82C M4899 F-20 II. F.1.1 NOBLE GAS MONITOR 02/03/82C K4970 F-21 II. F.1. 2 IODINE / PARTICULATE SAMPLING 02/05/82C 145041 F-22 II.F.1.3 CONTAINMENT HIGH RANGE MONITOR 01/12/82C K7578 F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT C6/06/83C N7649 F-24 II.F.1.5 CONTAINMENT HATER LEVEL INSTRUMENT 06/06/83C K7720 F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR 06/06/83C K5112 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 01/30/87 M2791 F-27 II.K.2.9 FMEA ON ICS 02/24/82C K5182 F-28 II.K.2.10 SAFETY GRADE ARTS 11/02/81C M5189 F-29 II.K.2.11 CONTIdUED OPERATOR TRAINING AND DRILIIN 12/09/81C K3425 F-30 II.K.2.13 THERMAL-MECHANICAL REPORT 06/07/84C K5203 F-31 II.K.2.14 LIFT FREQUENCY OF PORVS AND SVS 05/25/82C M2617 F-32 II.K.2.16 RCP SEAL DAMAGE 02/12/82C K2619 F-33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS 12/09/81C K2621 F-35 II.K.2.20 SYSTEM RESPONSE TO SB LOCA 08/17/81C K5267 F-36 II.K.3.1 AUTO PORV ISOLATION 09/15/83C M5313 F-37 II.K.3.2 REPORT ON PORV FAILURES 09/20/83C M5321 F-38 II.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 03/05/82C K5434 F-39 II.K.3.5 AUTO TRIP OF RCPS 02/23/83C

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MPA 8 TITLE COMPLETE STATUS MTf.

145607 F-47 II.K.3.17 ECCS OUTAGES 08/10/83C 148441 F-53 II.K.3.25 PONER ON PUMP SEALS 08/31/82C 145803 F-57 II.K.3.30 SB LOCA METHODS 08/30/85C 148144 F-58 II.K.3.31 COMPLIANCE HITH 10 CFR 50.46 03/31/87 145923 F-63 III.A.1.2 TECHNICAL SUPPORT CENTER 03/30/86 145994 F-64 III.A.1.2 OPERATIONAL SUPPORT CENTER 03/30/86 14G066 F-65 III.A.1.2 EMERGENCY OPERATIONS FACILITY 03/30/86 14G138 F-66 III.A.1.2 NUCLEAR DATA LINK 01/22/82C 146210 F-67 III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 05/11/83C 14G282 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE 03/30/86 146353 F-69 III.D.3.3 IMPLANT RADIATION MONITORING 02/23/82C 142424 F-70 III.D.3.4 CONTROL ROOM HABITABILITY 04/29/82C 156100 F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEH (FOLLOHUP TO 07/20/86 149699 G-01 REACTOR COOLANT PUMP TRIP (D660 - II.K.3.5) 06/30/86

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FACILITY IMPLEMENTATION 04/14/86 FACILITY: ARKANSAS 1 PLANT LOCATION: 6 MI HNH OF RUSSELLVILLE, AR LICENSED POWER: 2568 MHT PROJECT MANAGER: G. VISSING DOCKET NUMBER:

050-00313 DESIGN POWER:

0850 MHE BRANCH CHIEF:

J. STOLZ ARCH / ENGINEER:

BECH NSSS VENDOR:

B8H LIC. ASSISTANT:

R. INGRAM IE INSPECTOR:

H. JOHNSON TAC NO.

MPA 1 TITLE M49699 G-01 ARKANSAS 1 - REACTOR COOLANT PUMP TRIP M06038 C-01 AND 1 - PHR SECONDARY HATER CHEMISTRY MONITORING REQUIREMENTS - GENERIC M07521 A-01 ANO 1 - REVISED ISI M44000 F-01 ANO 1 - NUREG-0737 I. A.1.1 STA LONG TERM REQUIREMENTS M08105 A-02 ANO 1 - APPENDIX I TECH SPEC IMPLEMENTATION REVIEH M06211 B-02 AND-1-- UNIT 1 FIRE PROTECTION M06235 E-02 AND -1 SMALL FUEL CASK DROP M44068 F-02 ANO 1 - NUREG-0737 I.A.1.3.1, SHIFT MANNING OVERTIME LIMITS M44139 F-03 AND 1 - NUREG-0737 I.A.2.1.4, UPGRADING OF R0 AND SRO TRAINING M11811 E-03 ANO 1 - REFUELING FOR CYCLE 5 OPERATION M08454 E-03 ANO-1 THIRD RELOAD 106942 A-03 ANO-1 PHYSICAL SECURITY PROGRAM 101371 B-03 AND I - GENERIC - PHR MODERATOR DILUTION M07863 D-04 AND 1 - REACTOR CAVITY VESSEL SEAL RING PROBLEM 106806 B-04 AND 1 - OVERPRESSURIZATION I11480 A-04 AND 1 - REQUEST FOR EXEMPTION - APP J TESTING OF VALVES OF VALVES M44210 F-04 ANO 1 - NUREG-0737 I.C.1.2.A, INADEQUATE CORE COOLING GUIDELINES M42842 F-05 ARKANSAS 1 - PROCEDURES GENERATION PACKAGE REVIEH (NUREG 0737 SUPP/1)

M07246 C-05 AND-1 STANDARD TECHNICAL SPECIFICATIONS M08447 C-06 ANO-1 S/G SUPPORTS LAMELLAR TEARING & FRACTURE TOUGHNESS

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TAC No.

MPA 0 TITLE N47193 F-06 ARKANSAS 1 - FEEDBACK OF OPERATING EXPERIENCE CAP I.C.5)

N47205 F-07 ARKANSAS 1 - CORRECT PERFORMANCE OF OPERATING ACTIVITIES (API.C.6)

M08461 C-07 ANO-1 FUEL HANDLING ACCIDENT INSIDE CONTAINMENT M06161 A-08 AND-1 ECCS ELECT. SINGLE FAILURE ANALYSIS M08347 B-08 AND-1 HPI & LPI VALVES-FLON SPLIT M01908 D-08 ANO-1 NOAH - BHST DRANDOHN PROBLEMS M08607 D-08 ARKANSAS 1 - REACTOR BUILDING SPRAY SYSTEM M51359 F-08 ARKANSAS 1 - I.D.1.1 - DETAILED CONTROL ROOM DESIGN REVIEN PROGRAM PLAN - F-08 M51219 F-09 ARKANSAS 1 - I.D.2. SAFETY PARAMETER DISPLAY SYSTEM M11379 A-09 ARKANSAS 1-REACTOR VESSEL BELTLINE MATERIAL SURVEILLANCE M12197 B-10 ANO-1 FOLLDHUP ACTIONS RESULTING FROM TMI-2 M10539 A-10 ANO 1 - CONTINGENCY PLAN REVIEN M44351 F-10 ANO 1 - NUREG-0737 II.B.1, RCS HIGH POINT VENTS M07862 D-10 ANO 1 - PRESSURE VESSEL SUPPORT (ASYMMETRICAL LOADS)

N07971 C-10 ARKANSAS 1 -CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (NUREG 0612) 908455 D-11 ANO-1 FISSION GAS RELEASE FROM FUEL PELLETS - HIGH BURNUP 947917 F-11 ARKANSAS 1 - PLANT SHIELDING MODIFICATIONS (II.B.2.2) 910537 A-11 ANO 1 - GUARD TRAINING PLAN REVIEN 910542 A-12 ANO 1 - VITAL AREA ANALYSIS 911406 B-12 ANO 1-CNANGE SCHEDULE OF SG TUBE INSPECTION 944419 F-12 AND I - NUREG-0737 II.B.3.2, POST ACCIDENT SAMPLING MODIFICATIONS.

944489 F-13 ANO 1 - NUREG-0737 II.B.4.1, TRAINING FOR MITIGATING CORE 908453 3-13 ANO-1 FUEL ROD BDH i

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MPA 6 TITLE 107476 D-13 ANO 1-ECCS SMALL BREAK ERROR 108450 B-14 AND-1 CONTROL ROD GUIDE TUBE HEAR 108445 D-14 ANO-1 REACTOR VESSEL A TYPICAL HELD MATERIAL 111235 A-14 AND 1 - REVISED IST - TESTING 143632 C-14 ANO 1 - SEISMIC QUALIFICATION OF THE AUXILIARY FEEDHATER SYSTEM 143549 C-14 ANO 1 - SEISMIC QUALIFICATION OF AUXILIARY FEEDHATER SYSTEMS 144560 F-14 ARKANSAS 1 - RV AND SV TESTING 110844 B-14 ANO 1 - CONTROL ROD GUIDE TUBE HEAR 152206 C-15 ARKANSAS 1 - CONTROL OF HEAVY LOADS - PHASE II (FDLLOHUP OF MPASC-10) 142334 F-15 ARKANSAS 1 - HUREG-0737, II.E.1.1, AFH SYSTEM EVALUATION 112320 D-15 AND 1 - HELB AND CONSEQUENTIAL SYSTEM FAILURE ARKANSAS 1 108458 A-15 ANO-1 QUALITY OF DIESEL FUEL & LUBE DIL 158043 C-16 ARKANSAS 1 - STEAM GENERATOR GENERIC REVIEH CONCERNING STEAM GENERATORS (GL 85-02) 144707 F-16 AND 1 - HUREG-0737 II.E.1.2.1, AFH SAFETY GRADE AUTO INITIATION 146810 A-16 ANO 1 - QUAL. OF INSP., TEST, EXAM, AND AUDIT PERSONNEL 112199 B-16 ANO UPGRADE EMERGENCY PLAN 109034 B-16 REVIEH REVISION TO THE EMERGENCY PLAN FOR AND-1 8 DETERMINE THE ACCEPTABILITY OF THE REVISION 111267 B-17 AND 1 - HYDRAULIC SNUBBERS 143036 D-17 AND 1 - TECHNICAL SPECIFICATIONS DEFINING OPERABILITY SAFETY SYSTEMS 142151 D-17 ANO 1 - T.S DEFINING OPERABILITY OF S.S 144749 F-17 AND 1 - HUREG-0737 II.E.1.2.2, AFH SAFETY GRADE FLON INDICATION 151069 A-17 ARKANSAS 1 - INSTRUMENTATION TO FOLLOH THE COURSE OF AN ACCIDENT (RG 1.97) 151731 D-18 ARKANSAS 1 - HUREG-0630 CLADDING MODELS FOR LOCA ANALYSIS

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6 FACILITY IMPLEMENTATION 04/14/86 LRKANSAS 1 (CONTINUATION)

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MPA 9 TITLE 144757 F-18 ANO 1 - NUREG-0737 II.E.4.1.2, DEDICATED HYDROGEN PENETRATIONS 155696 A-18 ARKANSAS 1 - TECH. SPECS. AFFECTED BY 50.72 AND 50.73 (GL 83-45) 155833 D-19 ARKANSAS 1 - DIESEL GENERATOR RELIABILITY TECH. SPECS.

(GL 84-15) 144828 F-19 AND 1 - NUREG-0737 II.E.4.2, CONTAINMENT ISOLATION DEPENDABILITY 144899 F-20 ANO 1 - NUREG-0737 II.F.1.1, NOBLE GAS MONITOR 110316 B-20 ANO 1 - CONTAINMENT LEAKAGE DUE TO SEAT DETERIORATION 159068 A-20 ARKANSAS 1 - 10CFR50.62 OPERATING REACTOR REVIENS 159939 A-21 ARKANSAS 1 - 10CFR50.61 PRESSURIZED THERMAL SHOCK RULE REQUIREMENTS, PHASE 1 110378 B-21 AND 1 - LOSS OF 125 DC BUS VOLTAGE HITH LOSS OF ANNUNCIATOR SYSTEM 144970 F-21 AND 1 - HUREG-0737 II.F.1.2, IODINE /

PARTICULATE SAMPLING p35041 F-22 AND 1 - NUREG-0737 II.F.1.3, CONTAINMENT HIGH RANGE MONITOR 511266 B-22 ANO 1 - MECHANICAL SNUBBERS 10006 B-23 ARKANSAS NUCLEAR ONE POTENTIAL EQUIPMENT FAIL-URES ASSOCIATED WITH GRID VOLTAGE g

[08457 B-23 ANO-1 DEGRADED GRID VOLTAGE h37578 F-23 ARKANSAS 1 - NUREG 0737 ITEM II.c1.4 - CONTAINMENT PRESSURE INSTRUMENT

7649 F-24 ARKANSAS 1 - NUREG 0737 ITEM II F1.5 CONTAINMENT HATER LEVEL MONITOR 210212 B-24 ARKANSAS 1 - CONTAINMENT PURGE 032595 B-24 ANO 1 - LONG TERM REVIEN CONTAINMENT PURGE AND VENT (B-24)

$37720 F-25 ARKANSAS 1 - NUREG 0737 ITEM II F1.6 CONTAINMENT HYDROGEN MONITOR

?05112 F-26 ANO 1 - NUREG-0737 II.F.2.3, INADEQUATE CORE COOLING INSTRUMENTATION h10253 S-26 ARKANSAS 1 - INADVERTENT SAFETY INJECTION DURING C00LD0HN (PHR'S) 32791 F-27 ANO 1 - CONFIRMATORY ORDER - ICS RELIABILITY ANALYSIS pS5182 F-28 AND 1 - NUREG-0737 II.K.2.10, SAFETY GRADE ARTS

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MPA 9 TITLE 14S189 F-29 AND 1 - NUREG-0737 II.K.2.11, OPERATOR TRAINING AND DRILLING 143425 F-30 ANO 1 - ITEM II K.2.13 THERMAL-MECH EFFECTS OF HPI ON VESSEL I45203 F-31 ANO 1 - NUREG-0737 II.K.2.14, LIFT FREQUENCY OF PORV'S AND SV'S 142617 F-32 AND 1 - B&W PLANTS - ITEM II K.2.16 - RCP SEAL DAMAGE ON LOSS OF OFFSITE P0HER N2619 F-33 AND 1 - B&W PLANTS - ITEM II K.2.17 POTENTIAL VOIDING DURING ANTICIPATED TRANSIENTS 142621 F-35 AND 1 - B&W PLANTS ITEM II K.2.20 ANALYSIS OF SBLOCA HNICH DEPRESSURIZES TO PORV SET PT 110529 B-35 ANO-1 ORIFICE ROD ASSEMBLY INTEGRITY--B&W I45247 F-36 ANO 1 - NUREG-0737 II.K.3.1, AUTO PORV ISOLATION l

145313 F-37 ANO 1 - NUREG-0737 II.K.3.2, REPORT ON PORV FAILURES I45321 F-38 ANO 1 - NUREG-0737 II.K.3.3, REPORT ON RV/SV FAILURES 107087 B-58 ANO-1 TENDON SURVEILLANCE PROBLEMS 108701 B-39 AND 1 - PHR PRESSURE-TEMPERATURE TECH SPECS M5434 F-39 ANO 1 - NUREG-0737 II.K.3.5, AUTO TRIP OF RCPS 111241 B-41 ANO 1 - FIRE PROTECTION - SUPPLEMENTAL SER H3554 B-41 ANO 1 - REASSESSMENT OF SEC. III.G, III.J & III.0 0F APP.R 143689 B-41 ANO 1 - REQUEST FOR EXEMPTION FROM 10 CFR 50 APP R SEC III G8L I43691 B-41 ANO 1 - REQUEST FOR EXEMPTION FROM MEETING SCHDULE OF 50.48 111727 B-42 ANO 1 - HI PRESSURE RPS SET POINT 2300, PORV 2450 111728 B-42 ANO 1 - LCO FOR LOSS OF EMERG. FEEDWATER 111826 B-42 ANO 1 - TECH SPEC FOR ANTICIPATORY REACTOR TRIPS 111795 B-43 AND 1 - FEEDWATER LINE CRACKS 112450 B-44 ANO-1 LESSONS LEARNED IMPLEMENTATION SHORT TERM 130015 B-44 ARKANSAS 1-2.1.7.B CONTROL GRADE AUX FEED FLDH INDICATION

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MPA 1 TITLE 130016 B-44 ARKANSAS 1-2.1.5 A,C DEDICATED H2 CONTROL PENETRATIONS & RECOMBINER PROCEDURE 130017 B-44 ARKANSAS 1-2.1.1. EMER. P0HER SUPPLY PORV/

BLOCK VALVE, PER HEATER & LEVEL 130018 B-44 ARKANSAS 1-2.2.2 A,B,C CONTROL ROOM ACCESS, TSC, OPERATIONAL SUPPORT CENTER 130019 B-44 ARKANSAS 1-2.2.1 A,B,C SHIFT SUPER. RESP.,

STA, TURNOVER PROCEDURES 130020 B-44 ARKANSAS 1-2.1.8 C IMPROVED IODINE INST.

130021 B-44 ARKANSAS 1-2.1.8.5 HIGH RANGE RADIATION MONITORS 130022 B-44 ARKANSAS 1-2.1.8.A POST ACCIDENT SAMPLING 130023 B-44 ARKANSAS 1-2.1.6.B SHIELDING REVIEN 130024 B-44 ARKANSAS 1-2.1.6.A SYSTEMS INTEGRITY FOR HIGH RADI0 ACTIVITY 130025 B-44 ARKANSAS 1-2.1.4 DIVERSE CONTAINMENT ISOLATION 130026 B-44 ARKANSAS 1-2.1.3.B INST. FOR CORE COOLING 130027 B-44 ARKANSAS 1-2.1.3 A DIRECT INDICATION OF VALVE POSITION 130028 B-44 ARKANSAS 1-2.1.2 RELIEF & SAFETY VALVE TESTING 112877 B-45 AND 1 - PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVES ISOLATION VALVES 112578 B-46 AND 1 - ANALYSIS OF TURBINE DISC CRACKS 142129 B-46 AND 1 - DECAY HEAT REMOVAL CAPABILITY TECH SPECS SPECS 112730 B-47 ARKANSAS 1 -ECCS CLAD SHELLING & RUPTURE 145607 F-47 AND 1 - NUREG-0737 II.K.3.17, ECC SYSTEM OUTAGES l

12790 B-48 ANO 1 - ADEQUACY OF ELECT. DIST SYSTEM 112253 B-52 AND 1 - MULTIPLE EQUIPMENT FAILURES l

148441 F-53 AND 1 - NUREG 0737, II.K.3.25 POWER ON PUMP SEALS l

145803 F-57 ANO 1 - NUREG-0737 II.K.3.30, SB LOCA DUTLINE l

142120 B-57 AND 1 - DECAY HEAT REMOVAL CAPABILITY TECH SPECS CAPABILITY TECH SPECS

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MPA 9 TITLE 14S144 F-58 ARKANSAS 1 -HUREG 0737 II.K.3.31 COMPLIANCE HITH 10 CFR 50.46 142901 B-59 ANO 1 - MASONRY HALL DESIGN. RESPONSE TO IE BULLETIN 80-11 942514 B-60 AND 1 - ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT (80-CLI-21) 942650 B-61 AND 1 - IE BULLETIN 79-27, LOSS OF NON CLASS IE INST

& CONTR, PONER. REV. & EVAL. RESPONSES 442720 B-62 AND 1 - ESF RESET CONTROL DESIGN DEFICIENCY - ISE BULLETIN 80-06 143548 B-63 ANO 1 - EMERG PROCEDURES & TRAINING FOR STATION BLACKOUT EVENT 143886 B-63 ARKANSAS UNIT 1 - STATION BLACK 0UT PROCEDURES

& TRAINING 945923 F-63 ANO 1 - NUREG-0737 III.A.1.2, TECHNICAL SUPPORT CENTER 445994 F-64 ANO 1 - NUREG-0737 III.A.1.2, OPERATIONAL SUPPORT CENTER 943265 B-64 ANO 1 - B&W ACCIDENT INDUCED NEUTRON FLUX ERRORS (MULTI-PLANT ITEM B-64) 146066 F-65 AND 1 - NUREG-0737 III.A.1.2, EMERGENCY OPERATIONS FACILITY 647181 B-66 ARKANSAS 1 NATURAL CIRCULATION COOLDDHN (GENERIC LTR 81-21) 446138 F-66 ARKANSAS 1 - III.A.2 NUCLEAR DATA LINK DATA 946210 F-67 ARKANSAS 1 - III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE I46282 F-68 ANO 1 - NUREG-0737 III.A.2.2, METEOROLOGICAL DATA UPGRADE I46824 B-69 ARKANSAS 1 - PHR MSLB HITN CONTINUED FEEDHATER ADDITION 046353 F-69 ANO 1 - NUREG-0737 III.D.3.3, INPLANT RADIATION MONITORING I46424 F-70 ANO 1 - NUREG-0737 III.D.3.4, CONTROL ROOM NABITABILITY I46597 B-70 ARKANSAS 1 - MONITORING OF FATIGUE TRANSIENT LIMITS FOR THE REACTOR COOLANT SYSTEM 156100 F-71 ARKANSAS 1 - I.D.1.2 DETAILED CONTROL ROOM DESIGN REVIEN

SUMMARY

REPORT - F-71 152735 B-76 ARKANSAS 1 - ITEM 1.1 - POST TRIP REVIEN PROGRAM DESCRIPTION AND PROCEDURES 152816 B-77 ARKANSAS 1 - ITEM 2.1 - EQUIPMENT CLASSIFICATION AND VEND 3R INTERFACE - RTS COMPONENTS 152897 B-78 ARKANSAS 1 - ITEMS 3.1.1 & 3.1.2 - POST MAINTENANCE TESTING PROCEDURES / VENDOR RECOMMENDATIONS - RTS COMPONE

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MPA 9 TITLE 152978 B-79 ARKANSAS 1-ITEM 3.1.3 -POST-MAINTENANCE TESTING-CHANGES TO TECH SPECS-RTS COMPONENTS 153059 B-80 ARKANSAS 1 - ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY

- VENDOR RELATED MODIFICATIONS 153112 B-81 ARKANSAS 1 - ITEMS 4.2.1 & 4.2.2 - PREVENTATIVE MAINT PROGRAM FOR REACTOR TRIP BREAKERS - MAINTENANCE & TREND 153165 B-82 ARKANSAS 1 - ITEM 4.3 - AUTDAMTIC ACTUATION OF SHUNT TRIP ATTACHMENT FOR H AND B & H PLANTS 154514 B-83 ARKANSAS 1 - TECHNICAL SPECIFICATIONS COVERED BY GENERIC LETTERS 83-36, 83-37 FOR NUREG-0737 153567 B-85 ARKANSAS 1 - ITEM 1.2 - POST TRIP REVIEH-DATA AND INFORMATION CAPABILITY (53650 B-86 ARKANSAS 1 - ITEM 2.2 - EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE - ALL SR COMPONENTS 153733 B-87 ARKANSAS 1-ITEMS 3.2.1 & 3.2.2 - POST-MAINT TESTING PROCEDURES AND VENDOR RECOMMENDATIONS - ALL SR COMPONEt 453816 B-88 ARKANSAS 1 - ITEM 3.2.3 - POST-MAINTLNANCE TESTING

-CHANGES TO TECH. SPEC. - ALL SR COMPONENTS 153899 B-89 ARKANSAS 1 - ITEMS 4.2.3 & 4.2.4-PREVENTATIVE MAINTENANCE PROGRAM FOR RX TRIP BREAKERS - LIFE TESTING & REPLACEME 155347 B-90 ARKANSAS 1 - ITEM 4.3(TS) - AUTOMATIC ACTUATION OF SHUNT TRIP FOR H AND B&H PLANTS - TECH SPECS 153952 B-91 ARKANSAS 1 - ITEM 4.4 - IMPROVEMENTS IN MAINTENANCE AND TEST PROCEDURES FOR B & N PLANTS E54043 B-92 ARKANSAS 1 - ITEM 4.5.1 - REACTOR SYSTEM FUNCTIONAL TESTING - DIVERSE TRIP FEATURES 153960 B-93 ARKANSAS 1 - ITEMS 4.5.2 & 4.5.3 - REACTOR TRIP SYSTEM FUNCTIONAL TESTING - ALTERNATIVES & TEST INTERVALS l

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