ML20206H797

Forwards List Indicating Implementation Status of NRC Regulatory Info Tracking Sys Licensing Action.Approx 230 Manhours Expended in Review Effort

ML20206H797
Person / Time
Site:	Davis Besse
Issue date:	06/17/1986
From:	Williams J TOLEDO EDISON CO.
To:	Stolz J Office of Nuclear Reactor Regulation
References
TASK-***, TASK-TM 1282, NUDOCS 8606260302
Download: ML20206H797 (9)

Text

.

TOLEDO

%ses EDISON JOE WILUAMS, JR Docket No. 50-346  % ,yo m _,y,,

(419)249 2300 I'l"*""'

License No. NPF-3 Serial No. 1282 June 17, 1986 Director of Nuclear Reactor Regulation Attention: John F. Stolz PWR Project Directorate #6 Division of PWR Licensing-B United States Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Stolz:

On May 8, 1986 Toledo Edison received a Nuclear Regulatory Commission (NRC) letter (Log No. 1978) requesting that Toledo Edison review and status the NRC's Regulatory Information Tracking System licensing action listing for the Davis-Besse Nuclear Power Station Unit No. 1. Toledo Edison was requested to review this listing of 145 licensing actions (Multi-Plant Actions), add omitted significant actions to the listing anc provide the date that all aspects of each identified requirement were completed / implemented or projected to be completed.

Subsequently, Toledo Edison provided Mr. A. W. DeAgazio, NRR Project Manager for Davis-Besse, with the preliminary status of 63 licensing actions (excluding implementing aspects). An extension for submitting the status of the balance of the licensing actions was verbally approved by Mr. DeAgazio on June 2, 1986. The basis for this extension was the substantial effort necessary to review specific documentation and identify the date of completion or projected completion for each licensing action. Approximately 230 manhours were expended in this review and status effort.

Enclosed are Toledo Edison's results. Due to the NRC's time constraints concerning this response, the implementing aspects of licensing actions listed as " completed" have not been statused. A full verification effort .

would require 2000 additional manhours. Therefore, for licensing actions  !

listed an " completed", the date of completion listed may exclude full implementation. For licensing actions identified as not completed, tentative projected completion dates have been provided.

k P

DO f I

[

THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652

- . - . - . _ . - . .- . - - . .=- .- _ .

1

..Dockst No. 50-346 License No. NPF-3 Serial No. 1282

! June 17, 1986 Page 2 1,

1 Toledo Edison requests that your office review the enclosed _information to ensure concurrence on the identified status of each of these licensing actions. Should you require additional information, please feel free to contact my office.

Very truly yours,

. n a o<_ Ludl e. J r. %A l JW:DRW:plf ,

i Enclosure j

cc: DB-1 NRC Resident Inspector A. W. DeAgazio, NRR Project Manager

i i

.1 J

l 1

i I

i

.i 1

i l

,___m.__ . . . _ m_ ..-__ , - _ _4 _ _.. . ,_.. . . _ . , _ _ , . , -. .,_. .

. I al P.y. id 7 R-1208731 -001 REGULAT0RY INF0RMATION TRACKINO SYSTEM PAGE NO. 119

+

FACILITY IMPLEMENTATION 04/14/8t FACILITY: DAVIS-BESSE 1 PLANT LOCATION: 21 MI E OF TOLEDO, OH LICENSED PDAER: 2772 MHT PROJECT MANAGER: A. DEAGAZIO DOCKET NUMBER: 050-00346 DESIGN PONER: 0906 MHE BRANCH CHIEF: J. STOLZ ARCH / ENGINEER: BECH NSSS VENDOR: B&H LIC. ASSISTANT: R. INGRAM IE INSPECTOR: H. ROGERS TAC NO. MPA 8 TITLE A7"d N I M11309 C-01 DAVIS BESSE 1 - SECONDARY HATER CHEMISTRY co.,,4/.d_j9gg M07889 B-01 DAVIS BESSE 1 - DIESEL GENERATOR LOCKOUT c,.[1feg, jpg y M49I62 G-01 /

DAVIS BESSE 1 - REACTOR COOLANT PUMP TRIP n ,,,,,f,f,g' 4 ,,.fffgg M44013 _F-01 DAVIS BESSE - NUREG-0737 I.A.I.1 STA LONG TERM REQUIREMENTS c_', /, hygf M10998 E-01 DAVIS BESSE 1 SPENT FUEL STORAGE MODIFICATION y jg M10985 A-01 DAVIS BESSE 1 - REVISED INSERVICE INSPECTION PROGRAM g,[ 4j,} j99L M10988 B-02 DAVIS BESSE 1- FIRE PROTECTION ufj j9pg M12014 B-02 D 13-1 FIRE PROTECTION - EXTEND DATE FOR MODS g ,gf _j9gg M44081 F-02 DAVIS BESSE - NUREG-0737 I.A.1.3.1, SHIFT MANNING OVERTIME LIMITS m',4g,j[g jg M08141 A-02 DAVIS BESSE 1 - APPENDIX I TECH SPEO IMPLEMENTATION REVIEH g /g jj-j9g M44152 F-03 DAVIS BESSE - NUREG-0737 I.A.2.1.4, UPGRADING OF R0 #

AND SRO TRAINING g g ggg M07677 A-03 DAVIS BESSE 1 SECURITY PLAN REVIEN #

c. ,,/et5.2 /ps/

M08378 B-G{ DAVIS-BESSE-PHR MODERATOR DILUTION ,f,fh jyyrj M44223 F-04 DAVIS BESSE - NUREG-0737 I.C.1.2.A. INADEQUATE CORE COOLING GUIDELINES g /g jg M11555 M11315 D-04 DAVIS BESSE 1 SEAL RING MISSILE PROBLEM g

,j gj jpg B-04 DAVIS BESSE 1 DVERPRESSURE PROTECTION g,,[,f,M jppg "M44293 F-05 DAVIS-BESSE 1 - PROCEDURES GENERATION PACKAGE REVIEH (NUREG 0737 SUPP/1) ~A,,[,.,,fh .g M10984 C-06 DAVIS BESSE 1 - FRACTURE TOUGHNESS & LAMELLAR TEARING OF SG 8 RCP MATERIALS C f / J[jSeyy M47206 F-06 DAVIS-BESSE - FEEDBACK OF OPERATING EXPERIENCE (AP I.C.5) L ,f,fd j9pp M47278 F-07 DAVIS-BESSE - CORRECT PERFORMANCE OF OPERATING ACTIVITIES CAPI.C.6) co,,',,f,/,h /9g2 I e n

NRC Sta ?f acfian w;// 4-d.,,,,,;,,e. p,,, ,.f} co~p4dion dde. .

nt

.I R-1208731-001 Paf 2of 7 REGULAT0RY INF0RHATION TRACKING SYSTEM PAGE NO. 12i.

FACILITY IMPLEMENTATION 04/14/8r DAVIS-BESSE 1 (CONTINUATION)

TAC No. MPA B TITLE gTA TM5 M51154 F-08 DAVIS BESSE 1 - I.D.1.1 - DETAILED CONTROL ROOM DESIGN REVIEH PROGRAM PLAN F-08 P,.,;ec Q ,/9g9 M08164 B-08 DAVIS BESSE 1- PHR HPSI-LPS1 FLOH RESISTANCE-GENERIC e, ,/,f,j j999 M51234 F-09 DAVIS BESSE 1 - I.D.2. SAFETY PARAMETER DISPLAY SYSTEM 7 f, gj jg M11377 A-09 DAVIS BESSE 1 - REACTOR VESSEL BELTLINE MATERIAL

SURVEILLANCE c,,,,, f,f y'f , f977 M10538 A-10 DAVIS BESSE 1 - CONTINGENCY PLAN REVIEH c,,,, Q /pgg M44364 F-10 DAVIS BESSE - NUREG-0737 II.B.I. RCS HIGH POINT VENTS c,,.,f,f,)jpg3 M10986 D-10 DAVIS BESSE 1 - RPV SUPPORTS (ASYMETRIC LOCA LOAD) e, ofmf [g j,,j//pgf M10993 C-10 DAVIS-BESSE 1-CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (NUREG 0612) g_,'f,fj jpg M10104 D-11 DAVIS BESSE 1- ENHANCED FISSION PRODUCT RELEASE FOR HIGH BURNUP LHR FUEL g[,/,/,k jqyrf '

M10535 A-11 DAVIS BESSE 1 - GUARD TRAINING PLAN REVIEH g /,h j9gg M47930 F-11 DAVIS-BESSE - PLANT SHIELDING MODIFICATIONS (II.B.2.2) C,[,/,g, j j9g3 I

M10541 A-12 DAVIS BESSE 1 - VITAL AREA ANALYSIS MM M44432 F-12 DAVIS BESSE - NUREG-0737 II.B.3.2, POST ACCIDENT SAMPLING MODIFICATIONS Pp. ;eefe/1-/ /9A(

M44502 F-13 DAVIS BESSE - NUREG-0737 II.B.4.1, TRAINING FOR MITIGATING CORE phy/99pg co ,,, , /, fe M11313 B-13 DAVIS BESSE 1 FUEL ROD BON rm[,/,N /9fA M11322 B-14 DAVIS BESSE 1 -1 CEA GUIDE TUBE WEAR Ca /,de2 /92/

M43665 C-14 DAVIS BESSE 1 - SEISMIC QUALIFICATION OF THE AUXILIARY FEEDHATER SYSTEM r , /c-[ /f82.

M44572 F-14 /

DAVIS BESSE 1 - RV AND SV TESTING Co ,,, /cleh he /ja5~

M11316 A-14 DAVIS BESSE 1 - INSERVICE TESTING PROGRAM Ca,,,,r

/, dea

-t N/ou i

/9ff "M12322 D-15 DAVIS BESSE 1 - HELB AND CONSEQUENTIAL SYSTEM FAILURE DAVIS BESSE 1 u M44669 F-15 DAVIS BESSE - NUREG-0737 II.E.1.1, AFH SYSTEM EVALUATION /*,,,,,/m/dg y/jijff M12615 A-15 DAVIS BESSE 1 - QUALITY ASSURANCE REQUIREMENTS REGARDING DIESEL GENERATOR FUEL OIL /% ,/,-h /pg2 /

M52221 C-15 DAVIS BESSE 1 - CONTROL OF HEAVY LOADS - PHASE II (FOLLOWUP OF MPABC-10) /*, ,[/

h/g

. i Hfw./ds,- clahisiny arf /d<. /.c.<nsiay ac6on is nec<.ssey 'dy *^* M Yo Sci AN/*- r N " } -

i 6

bef'/

R-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO. 12 FACILITY IMPLEMENTATION 04/14/8 DAVIS-BESSE 1 (CONTINUATION)

TAC NO. MPA 8 TITLE 8747#5 M42964 F-16 DAVIS-BESSE - NUREG-0757, II.E.1.2.1, AFH SYSTEM SAFETY GRADE INITIATION (',,,/,f /pf,/fgf

/ '(/

M58055 C-16 DAVIS BESSE 1 - UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERNING STEAM GENERATORS (GL 85-02)(,,,,g f / L ,,,jpfg

/ /

M43038 D-17 DAVIS BESSE 1 - TECHNICAL SPECIFICATI0tlS DEFINING OPERABILITY FOR SAFETY SYSTEMS jgjgjjg M11312 B-17 DAVIS BESSE 1 - HYDRAULIC SNUBBERS 4 ,,[/ g [ jff g M44751 F-17 DAVIS BESSE - NUREG-0737 II.E.1.2.2, AFil SAFETY GRADE FLOH INDICATION / j g g M51084 A-17 DAVIS BESSE 1 - INSTRUMENTATION TO FOLLOH THE COURSE OF AN ACCIDENT (RG 1.97) p , g 'g ' M '

M51735 D-18 DAVIS BESSIE 1 - NUREG-0630 CLADDING MODELS FOR LOCA ANALYSIS c,,,,,, /f[jpg z M44770 F-18 DAVIS BESSE - NUREG-0737 II.E.4.1.2, DEDICATED HYDROGEN PENETRATIONS c ,,/,f[gjpg M55704 A-18 DAVIS BESSE 1 - TECH. SPECS. AFFECTED BY 50.72 AND 50.73 (GL 83-43) ,/,M h,,/jpg

"/

M55852 D-19 DAVIS BESSE 1 - DIESEL GENERATOR RELIABILITY TECH. SPECS. (GL 84-15) ~/>,. gQ , y M44841 F-19 DAVIS BESSE - NUREG-0737 II.E.4.2, CONTAINMENT ISOLATION DEPENDABILITY ($, /,fhffgg M44912 F-20 DAVIS BESSE - NUREG-0737 II.F.1.1, NOBLE GAS MONITOR (o '

fdgAf fpgf M10989 B-20 DAVIS BESSE 1 - CONTAINMENT LEAKAGE DUE TO SEAL DEGRADATION cm,,,f,f [ & f9gg M59086 A-20 DAVIS BESSE 1 - 10CFR50.62 OPERATING REACTOR REVIENS ,, / 7,, jg M59950 A-21 DAVIS BESSE 1 - 10CFR50.61 PRESSURIZED THERMAL SHOCK RULE REQUIREMENTS, PHASE 1 c ,.,, / 7,, j9g M10991 B-21 DAVIS BESSE 1 - LOSS OF 125 VDC BUS VOLTAGE WITH LOSS OF ANNUNCIATOR SYSTEM g jg g gg M44983 F-21 DAVIS BESSE - NUREG-0737 II.F.1.2, IODINE / PARTICULATE SAMPLING c jg g M45054 F-22 DAVIS BESSE - NUREG-0737 II.F.1.3, CONTAINMENT HIGH RANGE MONITOR Codf,Q' j9pf M11311 B-22 DAVIS BESSE 1 - MECHANICAL SNUBBERS g, ,/jf,j j u fj g "M10018 B-23 DAVIS-BESSE 1- POTENTIAL EQUIPMENT FAILURES ASSOCIATED WITH GRID VOLTAGE c.,,,,' /t/,j'd,,jgg M47591 F-23 DAVIS-BESSE - NUREG 0757 ITEM II F1.4 - CONTAINMENT PRESSURE INSTRUMENT ,j,fjg jg M47Cd2 F-24 DAVIS-BESSE - NUREG 0737 ITEM II F1.5 CONTAINMENT HATER LEVEL MONITOR (* ,,/ f j k f9 g M10210 B-24 DAVIS BESSE 1 - CONTAINMENT PURGE ( % ,, /, d h [ f9 g

, / J

~

% N4c .h w ae2 Don w H d o 4 , ~ sn a. mjee&d com,o/dion c44.

H+ B.p.et%L Comp /dior, DA A> he AA rmned Jy & Z,,-feyabl ,5e u /e p,,e,_sg,

11 Rp 447 R-1208731-001 REGULAT0RY INF0RHATION TRACKING SYSTEM PAGE NO. 12. ;

FACILITY IMPLEMENTATION 04/14/8e DAVIS-BESSE 1 (CONTINUATION)

TAC NO. MPA 9 TITLE ITATLA.N M42597 B-24 DAVIS BESSE 1 - LONG TERM REVIEW CONTAINMENT PURGE AND VENT (B-24) y w.

M47733 F-25 DAVIS-BESSE - NUREG 0737 ITEM II F1.6 CONTAINMENT HYDROGEN MONITOR g,,,,, /,fg j pg z M11310 B-26 DAVIS BESSE -1 INADVERTANT SAFETY INJECTION DURING C00LDOHN g ,jgg M45125 F-26 DAVIS BESSE - NUREC-07 5? n .7 4. ',, IhADEQUATE CORE COOLING INSTRUMENTATION .p, M jg M42793 F-27 DAVIS BESSE 1 - CONFIRMATORY ORDER - ICS RELIABILITY ANALYSIS d, /,_[gf,y jpg4 M45184 F-28 DAVIS BESSE - NUREG-0737 II.K.2.10, SAFETY GRADE ARTS , /d,_,/ /h f.

M45191 F-29 DAVIS BESSE - NUREG-0737 II.K.2.11, OPERATOR TRAINING AND DRILLING 0, ,/, M g ,,j//fjy M45198 F-30 DAVIS BESSE - NUREG-0737 II.K.2.13, THERMAL-MECHANICAL < - <

REPORT ($ _ ,,/ /, j jappf M45205 F-31 DAVIS BESSE - NUREG-0757 II.K.2. % , LIFT FREQUENCY OF PORV'S AND SV'S & /,/h fggj M45212 F-32 DAVIS BESSE - NUREG-0737 II.K.2.16, RCP SEAL DAMAGE c ,,/f,j j9p j M45218 F-33 DAVIS BESSE - NUREG-0737 II.K.2.17, POTENTIAL FOR VOIDING IN RCS c ,/,/) j9pf M45224 F-35 DAVIS BESSE - NUREG-0737 II.K.2.20, SYSTEM RESPONSE TO SB LOCA go,,, /,4 j9pj M45269 F-36 DAVIS BESSE - NUREG-0737 II.K.3.1, AUTO PORV ISOLATION g ,/, g,/ j9py M45315 F-37 DAVIS BESSE - NUREG-0737 II.K.3.2, REPORT ON PORV FAILURES d ,/,[g/g/

M45334 F-38 DAVIS BESSE - NUREG-0737 II.K.3.3, REPORT ON RV/SV FAILURES (' /,fo[jppf M10983 B-39 DAVIS BESSE 1 - PHR PRESSURE TEMP LIMITS ~' '

/ ), e rec _de /9fEA M45456 F-39 DAVIS BESSE - NUREG-0737 II.K.3.5, AUTO TRIP OF RCPS /L /,f f gm,.//ffg M11119 B-41 DAVIS BESSE 1 - FIRE PROTECTION SUPPLEMENT SER 8[rud /9A9 M43690 B-41 DAVIS BESSE 1 - MODIFICATION TO MEET APPENDIX R, SECTION III.G.3 (*,, /M/h,gyppf "M11958 B-42 ' #

DAVIS BESSE 1 - TECH SPEC CHANGES REG'D BY ORDER L,/,gh fpgo M11797 B-43 DAVIS BESSE 1- FEEDHATER LINE CRACKS r% ,,/,f / ffjp/

M12453 B-44 DAVIS BESSE 1 - LESSONS LEARNED IMPLEMENTATION & jg M30778 B-44 DAVIS BESSE-2.1.7.B CONTROL GRADE AUX FEED FLOH INDICATION r%(, /,[j /pgr) '

. /--

?"' S U/wy of He beensin c cdion is mee.ss y dg de g c f, a sy.

.>G ci/Sk 6. .sded m _ _ _ _ _ - _ _ _ _ _ _ _ _ _ __

.I Pq e. 5 f 1 R-1208731-001 REGULAT0RY INF0RHATION TRACKING SYSTEM PAGE NO. 12..

FACILITY IMPLEMENTATION 04/14/8f DAVIS-BESSE 1 (CONTINUATION)

TAC NO. MPA 3 TITLE N TA 7"4g M30779 B-44 DAVIS BESSE-2.1.5 A,C DEDICATED H2 CONTROL PENETRATIONS & RECOMBINER PROCEDURE C,,,,,/ g,) /9Ao M30780 B-44 DAVIS BESSE-2.1.1. EMER. POWER SUPPLY PORV/ BLOCK VALVE, PER HEATER & LEVEL g fj fpg M30781 B-44 DAVIS BESSE-2.2.2 A,B,C CONTROL ROOM ACCESS, TSC, OPERATIONAL SUPPORT CENTER coj,pgjjpg M30782 B-44 DAVIS BESSE-2.2.1 A,B,C SHIFT SUPER. RESP., STA, TURNOVER PROCEDURES g f,g,j j9pg M30783 B-44 DAVIS BESSE-2.1.8.C IMPROVED IODINE INST. co[,/g,//9A o M30784 B-44 DAVIS BESSE-2.1.8.B HIGH RANGE RADI ATION MONITORS r,,[,,/,,M/fgp M30785 r . ' .

B-44 DAVIS BESSE-2.1.8.A POST ACCIDENT SAMPLING c.o ,,,,/e f g ,fpA o M30786 B-44 DAVIS BESSE-2.1.6.B SHIELDING REVIEW Com ale d,a/1980 M30787 B-44 DAVIS BESSE-2.1.6.A SYSTEMS INTEGRITY FOR HIGH RADI0 ACTIVITY com 3), M j9po o -

H30788 B-44 DAVIS BESSE-2.1.4 DIVERSE CONTAINMENT ISOL ATION c_ f, f,f jpAD M30789 B-44 DAVIS BESSE-2.1.3.B INST. FOR CORE COOLING (*o[o f,4,) f 9po M30790 B-44 DAVIS BESSE-2.1.3.A DIRECT INDICATION OF VALVE POSITION co[f, f,_[ j9po M30791 B-44 DAVIS BESSE-2.1.2 RELIEF & SAFETY VALVE TESTING i L,l,_4,J /gpn M12890 B-45 DAVIS BESSE 1 - PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVES I

cm,,, , f,_4,f j 9pgn M42050 B-46 DAVIS BESSE 1 - POTENTIAL FOR TURBINE DISC CRACKS p,, ,,, f f,jjpg M42122 B-46 DAVIS BESSE 1 - DECAY HEAT REMOVAL CAPABILITY TECH SPECS i

(g,/,./,j g,,J/pg M12732 B-47 DAVIS BESSE 1 - ECCS CLAD SWELLING & RUPTURE (;_,[,/,f,.j [ppo M45620 F-47 DAVIS BESSE - NUREG-0737 II.K.3.17. ECC SYSTEM OUTAGES e ,.I ,,/ M / / g 3 M12745 B-48 DAVIS BESSE 1 - ADEQUACY OF STATION ELECTRIC DISTRIBUTION SYSTEMS VOLTAGES c.,,./[- N /9g2 "M45817 F-57 DAVIS BESSE - NUREG-0737 II.K.3.30, SB LOCA OUTLINE no e/ de Aa. / 9B5' M48157 F-58 DAVIS-BESSE -NUREG 0737 II.K.3.31 COMPLIANCE HITH 10 CFR 50.46 p,., , ,gg yg jpg M42903 B-59 DAVIS BESSE 1 - MASONRY HAL DESIGN. RESPONSE TO IE BULLETIN 80-11 (> ,ghjfh jyg M42508 B-60 DAVIS BESSE 1 - ENVIRONMENTAL QUALIFICATIONS OF SAFETY RELATED ELECTRICAL EQUIPMENT (80-CLI-[1) J3., g s y .4 t9k

________'fL_________________.________________________.__.________ __

s il PQ41 R-1208731-001 REGULAT0RY INF0RHATION TRACKING SYSTEM PAGE NO. 12' FACILITY IMPLEMENTATION 04/14/8(

DAVIS-BESSE 1 (CONTINUATION)

TAC NO. MPA 8 TITLE ITATit/

M42665 B-61 DAVIS BESSE 1 - IE BULLETIN 79-27, LOSS OF NON CLASS IE INST & CONTR. POWER. REV. & EVAL. RESPONSES M42735 B-62 DAVIS BESSE 1 - ESF RESET CONTROL DESIGN DEFICIENCY - ISE BULLETIN 80-06 c, /A J /980

/jgj j M43940 B-63 DAVIS-BESSE 1 - STATION BLACKOUT PROCEDURES & TRAINING g /g[jj9gj M45936 F-63 DAVIS BESSE - NUREG-0737 III.A.1.2, TECHNICAL SUPPORT CENTER pj,gj f,,7 M46007 F-64 DAVIS BESSE - NUREG-0737 III.A.1.2, OPERATIONAL SUPPORT CENTER P, $. /.) [9n /

M43266 B-64 DAVIS BESSE 1 - B8H ACCIDENT INDUCED NEUTRON FLUX ERRORS (MULTI-PLANI ITEM B-64)  % ,fff /fg/

M46079 F-65 DAVIS BESSE - NUREG-0737 III.A.1.2, EMERGENCY OPERATIONS FACILITY P,.[,,f) jpp/

M47182 B-66 M46151 DAVIS BESSE 1 NATURAL CIRCULATION COOLDONH (GENERIC LTR 81-21) g, gjgffg F-66 DAVIS-BESSE 1 - III.A.2 NUCLEAR DATA LINK DATA p[,./,$/ j9g,f M46223 F-67 F-68 DAVIS-BESSE - III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE [fg[/9g M46295 DAVIS BESSE - NUREG-0737 III.A.2.2, METEOROLOGICAL DATA UPGRADE g[gfjj9gj M43366 F-69 DAVIS BESSE - NUREG-0737 III.D.3.3, INPLANT RADIATION MONITORING g-2,44/f9A2 M46832 B-69 DAVID BESSE 1 - PHR MSLB W11H CONTINUED FEEDHATER ADDITION co ,4 h /gg M46437 F-70 DAVIS BESSE - NUREG-0737 III.D.3.4, CONTROL ROOM /

HABITABILITY 4,_,/, f,) jpp2 M56116 F-71 DAVIS BESSE 1 - I.D.1.2 DETAILED CONTROL ROOM DESIGN REVIEW

SUMMARY

REPORT - F-71 p,.[f,,/,h y.

M49730 B-72 DAVIS BESSE 1 M52750 "NUREG 0737 TECH SPECS (GENERIC LETTER 82-16 OR 83-02)" A /,4h g/, f9pp B-76 DAVIS BESSE 1 - ITEM 1.1 - POST TRIP REVIEN PROGRAM DESCRIPTION AND PROCEDURES Cob /,42 A[//ffy B-77 M52831 DAVIS BESSE 1 - ITEM 2.1 - EQUIPMENT CL ASSIFICATION AND VENDOR INTERFACE - RTS COMPONENTS ,,./((ppy M52912 B-78 DAVIS BESSE 1 - ITEMS 3.1.1 & 3.1.2 - POST MAINTENANCE TESTING PROCEDURES / VENDOR RECOMMENDATIO S - RTS COMPONI

-M52993 B-79 DAVIS BESSE 1-ITEM 3.1.3 -POST-MAINT TESTING-CHANGES TO TECH SPECS-RTS COMPONENTS j j M53067 B-80 DAVIS BESSE 1 - REACTOR TRIP SYSTEM RELIABILITY - VENDOR RELATED MODIFICATIONS m',g '/gjg MS3120 B-81 DAVIS BESSE 1 - ITEMS 4.2.1 & 4.2.2 - PREVENTATIVE MAINT PROGRAM FOR REACTOR TRIP BREAKERS - KAIN,Ty,NjN g &gTGEN!

M53170 B-82 DAVIS BESSE 1 - ITEM 4.3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTACHMENT FOR H AND B & H PLANTS &f,,/,j pi,fg _

< '(

• NRC M d a.c'6en w/ll N#'"*- /** jex6al com,o febon da7'e -

m ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

il '

Pagl 7*f 7 R-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO. 12!

FACILITY IMPLEMENTATION 04/14/8a DAVIS-BESSE 1 (CONTINUATION)

TAC NO. MPA 9 TITLE $7 A7 gjif M54528 B-83 DAVIS BESSE 1 - TECHNICAL SPECIFICATIONS COVERED BY GENERIC LETTERS 83-36, 83-37 FOR NUREG-0737 M53582 B-85 uAVIs BEssE 1 - ITEM 1.2 - POST TRIP REVIEH-DATA AND Cow ' /saf A r.i//98S INFORMATION CAPABILITY M53665 B-86 doma/e fd'. A/o v /92T DAVIS BESSE 1 - ITEM 2.2 - EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE - ALL SR COMP 0 RENTS '

M53748 B-87 v n . , a t.11987 DAVIS BESSE 1 - ITEMS 3.2.1 & 3.2.2 - POST-MAINT TESTING PROCEDURES AND VENDOR RECunntNUKiluna -

LR CUMPONE!

M53831 B-88 P m e d sd.'ALL /981 DAVIS BESSE 1 - ITEM 3.2.3 - POST-MAINTENANCE TESTING -CHANGES TO TECH. SPEC. - ALL SR COMPONENTS M53907 B-89  % i-sksL /987 DAVIS BESSE 1 - ITEMS 4.2.3 & 4.2.4-PREVENTATIVE MAINT. PROGRAM FOR RX TRIP BREAKERS-LIFE TESTING & REPLACEMENi M55352 B-90 Comn laA. J. A ari/19er DAVIS BESSE 1 - ITEM 4.3(TS) - AUTOMATIC ACTUATION OF SHUNT TRIP FOR H AND B&W PLANTS 4 TECH SPECS ~

M53954 B-91 %Isc.*Ced . ~hna.1996 DAVIS BESSE 1 - ITEM 4.4 - IMPROVEMENTS IN MAINTENANCE AND TEST PROCEDURES FOR 5 & H PLANTS

~

M54058 B-92 DAVIS BESSE 1 - ITEM 4.5.1 - REACTOR SYSTEM FUNCTIONAL

% tee 62'3 % )984 TESTING - DIVERSE TRIP FEATURES -

M53975 B-93 DAVIS BESSE 1 - ITEMS 4.5.2 & 4.5.3 - REACTOR TRIP Mitdd. 7~ m SYSTEM FUNCTIONAL TESTING - ALTERNATIVES & TEST INTERV, u /98 4 Protex1<.A

.i -

% eltBL e

N.

-- - ----- - -