ML20197G898

Requests Review of & Additions to Encl plant-specific List to Assist NRC in Developing long-term Program to Improve Documentation on Status of Power Reactor Licensee Implementation of Approved Regulatory Improvements

ML20197G898
Person / Time
Site:	Davis Besse
Issue date:	05/02/1986
From:	De Agazio A Office of Nuclear Reactor Regulation
To:	Williams J TOLEDO EDISON CO.
References
TASK-***, TASK-TM NUDOCS 8605160515
Download: ML20197G898 (9)

Text

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' *!- May 2,1986 ObO s

Docket No. 50-346 DISTllB11Il0N WPaulson 16Tcket File) BGrimes L t'U K JPartlow Mr. Joe Williams, Jr. L FDR RIngram Senior Vice President, Nuclear PBD#6 Rug Gray File Toledo Edison Company 0 ELD HSmith Edison Plaza - Stop 712 ACRS-10 SScott 300 Madison Avenue FMiraglia GDick Toledo, Ohio 43652 Edordan GEdison

Dear Mr. Williams:

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 Davis-Besse Unit No.1, please review the enclosed plant-specific list, add omitted significant actions to the list, ard 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 iten 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-known or best-estimate dates for actions thc t 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 estinated 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,

% M .* ? U t" A* Tert 3be Agazio, Project Manager PWR Project Directorate #6 Division of PWR Licensing-B

Enclosure:

As stated cc w/ enclosure: See next age l l

PBD-6 [/ PBD-6 i ~ PBD- I  :

ADe Ag M 0;cf CMcCr ken JSt 'i 5/j/86 5/j//86 5 86x i 8605160515 860502 PDR ADOCK 05000346

l Mr. J. Williams Davis-Besse Nuclear Power Station Toledo Edison Company Unit No. I cc:

Donald H. Hauser, Esq. Ohio Department of Health The Cleveland Electric ATTN: Radiological Health Illuminating Company Program Director P. O. Box 5000 P. 0. Box 118 Cleveland, Ohio 44101 Columbus, Ohio 43216 Mr. Robert F. Peters Attorney General Manager, Nuclear Licensing Department of Attorney Toledo Edison Company General Edison Plaza 30 East Broad Street 300 Madison Avenue Columbus, Ohio 43215 Toledo, Ohio 43652 Mr. James W. Harris, Director Gerald Charnoff, Esq. (Addressee Only)

Shaw, Pittman, Potts Division of Power Generation and Trowbridge Ohio Department of Industrial Relations 1800 M Street, N.W. 2323 West 5th Avenue Washington, D.C. 20036 P. O. Box 825 Columbus, Ohio 43216 Mr. Paul M. Smart, President Mr. Harold Kohn, Staff Scientist Toledo Edison Company Power Siting Commission 300 Madison Avenue 361 East Broad Street Toledo, Ohio 43652 Columbus, Ohio 43216 Mr. Robert B. Borsum President, Board of Babcock & Wilcox County Commissioners of Nuclear Power Generation Ottawa County

• Div'sion Port Clinton, Ohio 43452 Suite 200, 7910 Woodmont Avenue Bethesda, Maryland 2081t.

Resident Inspector U.S. Nuclear Regulatory Commission 5503 N. State Route 2 Oak Harbor, Ohio 43449 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 0

f 's ( llC L 9731-001 REGULAT0RY INF0RMATION TRACKING $YSTEM PAGE NO. 119 FACILITY IMPLEMENTATION 04/14/86 ITY: DAVIS-BESSE 1 LOCATION: 21 MI E OF TOLEDO, OH LICENSED POWER: 2772 MHT PROJECT MANAGER: A. DEAGAZIO T NUMBER: 050-00346 DESIGN POWER: 0906 MHE BRANCH CHIEF: J. STOLZ ENGINEER: BECH NSSS VENDOR: B&H LIC. ASSISTANT: R. INGRAM iPECTOR: H. ROGERS L MPA 9 TITLE D C-01 DAVIS BESSE ? - SECONDARY HATER CHEMISTRY 0 B-01 DAVIS BESSE 1 - DIESEL GENERATOR LOCK 0UT S G-01 DAVIS BESSE 1 - REACTOR COOLANT PUMP TRIP' 3 F-01 DAVIS BESSE - NUREG-0737 I.A.1.1 STA LONG TERM REQUIREMENTS S E-01 DAVIS BESSE 1 SPENT FUEL STORAGE MODIFICATION 9 A-01 DAVIS BESSE 1 - REVISED INSERVICE INSPECTION PROGRAM 8 B-02 DAVIS BESSE 1- FIRE PROTECTION 4 B-02 D 13-1 FIRE PROTECTION - EXTEND DATE FOR MODS 1 F-02 DAVIS BESSE - HUREG-0737 I.A.1.3.1, SHIFT MANNING OVERTIME LIMITS 1 A-02 DAVIS BESSE 1 - APPENDIX I TECH SPEC IMPLEMENTATION REVIEW 2 F-03 DAVIS BESSE - NUREG-0737 I.A.2.1.4, UPGRADING OF R0 AND SRO TRAINING 7 A-03 DAVIS BESSE 1 SECURITY PLAN REVIEN 8 B-03 DAVIS-BESSE-PHR' MODERATOR DILUTION 3 F-04 DAVIS BESSE - NUREG-0737 I.C.1.2.A, INADEQUATE CORE COOLING GUIDELINES 5 D-04 DAVIS BESSE 1 SEAL RING MISSILE PROBLEM S B-04 DAVIS BES'SE 1 0'VERPRESSURE PROTECTION 3 F-05 DAVIS-BESSE 1 - PROCEDURES GENERATION PACKAGE REVIEN (NUREG 0737 SUPP/1)

C-06 DAVIS BESSE 1 - FRACTURE TOUGHNESS & LAMELLAR TEARING OF SG & RCP MATERIALS F-06 DAVIS-BESSE - FEEDBACK OF OPERATING EXPERIENCE (AP I.C.5)

F-07 DAVIS-BESSE - CORRECT PERFORMANCE OF OPERATING ACTIVITIES (API.C 6)

-1208731-001 REGULAT0RY INF0RHATION TRACKING SYSTEM PAGE NO. 120 FACILITY IHPLEMENTATION 04/14/86 4VIS-BESSE 1 (CONTINUATION)

AC NO. MPA # TITLE 51154 F-08 DAVIS BESSE 1 - I.D.1.1 - DETAILED CONTROL ROOM DESIGN REVIEW PROGRAM PLAN F-08 08164 B-08 DAVIS BESSE 1- PHR HPSI-LPS1 FLOH RESISTANCE-GENERIC 51234 F-09 DAVIS BESSE 1 - I.D.2. SAFETY PARAMETER DISPLAY SYSTEM 11377 A-09 DAVIS BESSE 1 - REACTOR VESSEL BELTLINE MATERIAL SURVEILLANCE 10538 A-10 DAVIS BESSE 1 - CONTINGENCY PLAN REVIEN 44564 F-10 DAVIS BESSE - NUREG-0737 II.B.1, RCS HIGH POINT VENTS 10986 D-10 DAVIS BESSE 1 - RPV SUPPORTS ( ASYMETRIC LOCA LOAD) 10993 C-10 DAVIS-BESSE 1-CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (NUREG 0612) 10104 D-11 DAVIS BESSE 1- ENHANCED FISSION PRODUCT RELEASE FOR HIGH BURNUP LHR FUEL 10535 A-11 DAVIS BESSE 1 - GUARD TRAINING PLAN REVIEW 47930 F-11 DAVIS-BESSE - PLANT SHIELDING MODIFICATIONS (II.B.2.2) 10541 A-12 DAVIS BESSE 1 - VITAL AREA ANALYSIS 44432 F-12 DAVIS BESSE - NUREG-0737 II.B.3.2, POST ACCIDENT SAMPLING MODIFICATIONS b4502 F-13 DAVIS BESSE - NUREG-0737 II.B.4.1, TRAINING FOR MITIGATING CORE 11313 B-13 DAVIS BESSE 1 FUEL ROD B0H 11322 B-14 DAVIS BESSE 1 - 1 CEA GUIDE TUBE HEAR 63665 C-14 DAVIS BESSE 1 - SEISMIC QUALIFICATION OF THE AUXILIARY FEEDHATER SYSTEM b4572 F-14 DAVIS BESSE 1 - RV AND SV TESTING l1316 A-14 DAVIS BESSE 1 - INSERVICE TESTING PROGRAM

2322 D-15 DAVIS BESSE 1 - HELB AND CONSEQUENTIAL SYSTEM FAILURE DAVIS BESSE 1 i4669 F-15 DAVIS BESSE - NUREG-0737 II.E.1.1, AFH SYSTEM EVALUATION 2615 A-15 DAVIS BESSE 1 - QUALITY ASSURANCE REQUIREMENTS REGARDING DIESEL GENERATOR FUEL OIL i2221 C-15 DAVIS BESSE 1 - CONTROL OF HEAVY LOADS - PHASE II (FOLLOHUP OF MPASC-10)

1

-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE No.: 121 IMPLEMENTATION FACILITY 04/14/86 AVIS-BESSE 1 (CONTINUATION)

AC NO. MPA t TITLE

.42964 F-16 DAVIS-BESSE - NUREG-0737, II . E.1. 2.1, A FH SYSTEM SAFETY GRADE INITIATION

.58055 C-16 DAVIS BESSE 1 - UTILITY RESPGNSES TO STAFF RECOMMENDATIONS CONCERNING STEAM GENERATORS (GL 85-02) i43038 D-17 DAVIS BESSE 1 - TECHNICAL SPECIFICATIONS DEFINING OPERABILITY FOR SAFETY SYSTEMS i11312 B-17 DAVIS BESSE 1 - HYDRAULIC SNUBBERS i44751 F-17 DAVIS BESSE - NUREG-0737 II.E.1.2.2, AFH SAFETY GRADE FLOH INDICATION iS1084 A-17 DAVIS BESSE 1 - INSTRUMENTATION TO FOLLON THE COURSE OF AN ACCIDENT (RG 1.97) iS1735 D-18 DAVIS BESSIE 1 - NUREG-0630 CLADDING MODELS FOR LOCA ANALYSIS

.44170 F-18 DAVIS BESSE - NUREG-0737 II.E.4.1.2, DEDICATED HYDROGEN PENETRATIONS

_55704 A-18 DAVIS BESSE 1 - TECH. SPECS. AFFECTED BY 50.72 AND 50.73 (GL 83-43)

=55852 D-19 DAVIS BESSE 1 - DIESEL GENERATOR RELIABILITY TECH. SPECS. (GL 84-15) i44841 F-19 DAVIS BESSE - NUREG-0737 II.E.4.2, CONTAINMENT ISOLATION DEPENDABILITY

.44912 F-20 DAVIS BESSE - HUREG-0737 II.F.1.1, NOBLE GAS MONITOR

_10989 B-20 DAVIS BESSE 1 - CONTAINMENT LEAKAGE DUE TO SEAL DEGRADATION

_59086 A-20 DAVIS BESSE 1 - 10CFR50.62 OPERATING REACTOR REVIENS

_59950 A-21 DAVI: BESSE 1 - 10CFR50.61 PRESSURIZED THERMAL SHOCK RULE REQUIREMENTS, PHASE 1

-10991 B-21 DAVIS BESSE 1 - LOSS OF 125 VDC BUS VOLTAGE HITH LOSS OF ANNUNCIATOR SYSTEM

!44933 F-21 DAVIS BESSE - NUREG-0737 II.F.1.2, IODINE / PARTICULATE SAMPLING

.45054 F-22 DAVIS BESSE - NUREG-0737 II.F.1.3, CONTAINMENT HIGH RANGE MONITOR 111311 B-22 DAVIS BESSE 1 - MECHANICAL SNUBBERS 110018 B-23 DAVIS-BESSE 1- POTENTIAL EQUIPMENT FAILURES ASSOCIATED HITH GRID VOLTAGE 147591 F-23 DAVIS-BESSE - NUREG 0737 ITEM II F1.4 - CONTAINMENT PRESSURE INSTRUMENT 147662 F-24 DAVIS-BESSE - NUREG 0737 ITEM II F1.5 CONTAINMENT HATER LEVEL MONITOR 110210 B-24 DAVIS BESSE 1 - CONTAINMENT PURGE

-1208731-001 REGULAT0RY INF0RHATION TRACKING SYSTEH PAGE NO. 122 FACILITY IMPLEMENTATION 04/14/86 AVIS-BESSE 1 (CONTINUATION)

AC NO. MPA 8 TITLE 42597 B-24 DAVIS BESSE 1 - LONG TERM REVIEH CONTAINMENT PURGE AND VENT (B-24) 47733 F-25 DAVIS-BESSE - NUREG 0737 IIEM II F1.6 CONTAINMENT HYDROGEN MONITOR 91316 B-26 DAVIS BESSE -1 INADVERTA'NT SAFETY INJECTION DURING C00LDOHN 45125 F-26 DAVIS BESSE - NUREG-0737 II.F.2.3, IN' ADEQUATE CORE COOLING INSTRUMENTATION 42793 F-27 DAVIS BESSE 1 - CONFIRMATORY ORDER - ICS RELIABILITY ANALYSIS 45184 F-28 DAVIS BESSE - NUREG-0737 II.K.2.10, SAFETY GRADE ARTS 45191 F-29 DAVIS BESSE - HUREG-0737 II.K.2.11, OPERATOR TRAINING AND DRILLING

'5198 F-30 DAVIS BESSE - NUREG-0737 II.K.2.13, THERMAL-MECHANICAL REPORT 5205 F-31 DAVIS BESSE - NUREG-0737 II.K.2.14, LIFT FREQUENCY OF PORV'S AND SV'S 5212 F-32 DAVIS BESSE - NUREG-0737 II.K.2.16, RCP SEAL DAMAGE 45218 F-33 DAVIS BESSE - NUREG-0737 II.K.2.17, POTENTIAL FOR VOIDING IN RCS I

45224 F-35 DAVIS BESSE - NUREG-0737 II.K.2.20, SYSTEM RESPONSE TO SB LOCA l

45269 F-36 DAVIS BESSE - NUREG-0737 II.K.3.1, AUTO PORV ISOLATION 45315 F-37 DAVIS BESSE -'NUREG-0737 II.K.3.2, REPORT ON PORV FAILURES 45334 F-38 DAVIS BESSE - NUREG-0737 II.K.3.3, REPORT ON RV/SV FAILURES 10983 B-39 DAVIS BESSE 1 - PHR PRESSURE TEMP LIMITS 45436 F-39 DAVIS BESSE - NUREG-0737 II.K.3.5, AUTO TRIP OF RCPS 11119 B-41 DAVIS BESSE 1 - FIRE PROTECTION SUPPLEMENT SER 43690 B-41 DAVIS BESSE 1 - MODIFICATION TO MEET APPENDIX R, SECTION III.G.3 11958 B-42 DAVIS BESSE 1 - TECH SPEC CHANGES REG'D BY ORDER 11797 B-43 DAVIS BESSE 1- FEEDHATER LINE CRACKS 12455 B-44 DAVIS BESSE 1 - LESS0dS LEARNED IMPLEMENTATION 30778 ,

B-44 DAVIS BESSE-2,1.7.5 CONTROL GRADE AUX FEED FLOH INDICATION 4

t-1208731-001 REGULAT0RY INF0RMATION TRACKING SY3 TEM PAGE NO. 123 F A,,C I L I T Y IMPLEMENTATION 04/14/86 DAVIS-BESSE 1 (CONTINUATION)

FAC NO. MPA 1 TITLE 30779 B-44 DAVIS BESSEi z,1.5 A,C DEDICATED H2 CONTROL PENETRATIONS & RECOMBINER PROCEDURE 0780 B-44 DAVIS BESSE-2.1.1. EMER. P0HER SUPPLY PORV/ BLOCK VALVE, PER HEATER & LEVEL 0781 B-44 DAVIS BESSE-2.2.2 A,B,-C CONTROL ROOM ACCESS, TSC, OPERATIONAL SUPPORT CENTER 0782 B-44 DAVIS BESSE-2.2.1 A,B,C SHIFT SUPER. RESP., STA, TURNOVER PROCEDURES 0783 B-44 DAVIS BESSE-2.1.8.C IMPROVED IODINE INST.

0784 B-44 DAVIS BESSE-2.1.8.B HIGH RANGE RADIATION MONITORS 0785 B-44 DAVIS BESSE-2.1.8.A POST ACCIDENT SAMPLING 0786 B-44 DAVIS BESSE-2.1.6.B SHIELDING REVIEH 0787 B-44 DAVIS BESSE-2.1.6.A SYSTEMS INTEGRITY FOR HIGH RADI0 ACTIVITY 0788 B-44 DAVIS BESSE-2.1.4 DIVERSE CONTAINMENT ISOLATION 0789 B-44 DAVIS BESSE-2.1.3.5 INST. FOR CORE COOLING 0790 B-44 DAVIS BESSE-2.1.3.A DIRECT INDICATION OF VALVE POSITION 10791 B-44 DAVIS BESSE-2.1.2 RELIEF & SAFETY VALVE TESTING 2890 B-45 DAVIS BESSE 1 - PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVES 2050 B-46 DAVIS BESSE 1 - POTENTIAL FOR TURBINE DISC CRACKS 2122 B-46 DAVIS BESSE 1 - DECAY HEAT REMOVAL CAPABILITY TECH SPECS 12732 B-47 DAVIS BESSE 1 - ECCS CLAD SHELLING & RUPTURE

'45620 9 F-47 -DAVIS BESSE - NUREG-0737 II.K.3.17, ECC SYSTEM OUTAGES l

412745 B-48 DAVIS BESSE 1 - ADEQUACY OF STATION ELECTRIC DISTRIBUTION SYSTEMS VOLTAGES l

445817 F-57 DAVIS BESSE - NUREG-0737 II.K.3.30, SB LOCA DUTLINE l

448157 F-58 DAVIS-BESSE -NUREG 0737 II.K.3.31 COMPLIANCE HITH 10 CFR 50.46

2903' B-59 DAVIS BESSE 1 - MASONRY HAL DESIGN. RESPONSE TO IE BULLETIN 80-11 D2508 B-60 DAVIS BESSE 1 - ENVIRONMENTAL QUALIFICATIONS OF SAFETY RELATED ELECTRICAL EQUIPMENT (80-CLI-21)

% 9

R-1208731-001 R E G.U L A T 0 R Y INF0RMATION TRACKING SYSTEM PAGE N0.8 124 FACILITY IMPLEMENTATION 04/14/86' DAVIS-BESSE 1 (CONTINUATION)

TAC NO. MPA 0 TITLE 942605 B-61 DAVIS BESSE 1 - IE BULLETIN 79-27, LOSS OF NON CLASS IE INST & CONTR. P0HER. REV. 8 EVAL. RESPONSES 942735 B-62 DAVIS BESSE 1 - ESF RESET CD,NTROL DESIGN DEFICIENCY - ISE BULLETIN 80-06 443940 B-63 DAVIS-BESSE 1 - STATION BLACKOUT PROCEDURES & TRAINING 945936 F-63 DAVIS BESSE - NUREG-0737 III.A.1.2, TECNNICAL SUPPORT CENTER 446007 F-64 DAVIS BESSE - HUREG-0737 III.A.1.2, OPERATIONAL SUPPORT CENTER 943266 B-64 DAVIS BESSE 1 - B8H ACCIDENT INDUCED NEUTRON FLUX ERRORS (MULTI-PLANT ITEM B-64)

M46079 F-65 DAVIS BESSE - NUREG-0737 III.A.1.2, EMERGENCY OPERATIONS FACILITY 947182 B-66 DAVIS BESSE 1 NATURAL CIRCULATION C00LDOWN (GENERIC LTR 81-21) 946151 F-66 DAVIS-BESSE 1 - III.A.2 NUCLEAR DATA LIhK DATA 943223 F-67 DAVIS-BESSE - III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 946295 F-68 DAVIS BESSE - NUREG-0737 III.A.2.2, METEOROLOGICAL DATA UPGRADE 946366 F-69 DAVIS BESSE - NUREG-0737 III.D.3.3, INPLANT RADIATION MONITORING 946832 B-69 DAVID BESSE 1 - PHR MSLB HITN CONTINUED FEEDWATER ADDITION 946437 F-70 DAVIS BESSE - NUREG-0737 III.D.3.4, CONTROL ROOM NABITABILITY 454116 F-71 DAVIS BESSE 1 - I.D.1.2 DETAILED CONTROL ROOM DESIGN REVIEN

SUMMARY

REPORT - F-71 949730 B-72 DAVIS BESSE 1 "NUREG 0737 TECN SPECS (GENERIC LETTER 82-16 OR 83-02)"

452750 B-76 DAVIS BESSE 1 - ITEM 1.1 - POST TRIP REVIEW PROGRAM DESCRIPTION AND PROCEDURES 452831 B-77 DAVIS BESSE 1 - ITEM 2.1 - EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE - RTS COMPONENTS 452912 B-78 DAVIS dESSE 1 - ITEMS 3.1.1 & 3.1.2 - POST MAINTENANCE TESTING PROCEDURES / VENDOR RECOMMENDATIONS - RTS COMPONE 452993 3-79 DAVIS BESSE 1-ITEM 3.1.3 -POST-MAINT TESTING-CNANGES TO TECN SPECS-RTS COMPONENTS 453067 B-80 DAVIS BESSE 1 - REACTOR TRIP SYSTEM RELIABILITY - VENDOR RELATED MODIFICATIONS 453120' B-81 DAVIS BESSE 1 - ITEMS 4.2.1 & 4.2.2 - PREVENTATIVE MAINT PROGRAM FOR REACTOR TRIP BREAKERS - MAINTENANCE & TRENI 453170 3-82 DAVIS BESSE 1 - ITEM 4.3 - AUTOMATIC ACTUATION OF SNUNT TRIP ATTACNMENT FOR H AND B & N PLANTS

a1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO. 125 FACILITY IMPLEMENTATION 04/14/86 SVIS-BESSE 1 (CONTINUATION)

AC NO. MPA 9 TITLE

$4528 B-83 DAVIS BESSE 1 - TECHNICAL SPECIFICATIONS COVERED BY GENERIC LETTERS 83-36, 83-37 FOR NUREG-0737 53582 B-85 DAVIS BESSE 1 - ITEM 1.2 - POST TRIP REVIEH-DATA AND INFORMATION CAPABILITY 53665 B-86 DAVIS BESSE 1 - ITEM 2.2 - EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE - ALL SR COMPONENTS 53708 B-87 DAVIS BESSE 1 - ITEMS 3.2.1 & 3.2.2 - POST-MAINT TESTING PROCEDURES AND VENDOR RECOMMENDATIONS - ALL SR COMPONEN 53831 B-88 DAVIS BESSE 1 - ITEM 3.2.3 - POST-MAINTENANCE TESTING -CHANGES TO TECH. SPEC. - ALL SR COMPONENTS 53907 B-89 DAVIS BESSE 1 - ITEMS 4.2.3 & 4.2.4-PREVENTATIVE MAINT. PROGRAM FOR RX TRIP BREAKERS-LIFE TESTING & REPLACEMENT 55352 B-90 DAVIS BESSE 1 - ITEM 4.3(TS) - AUTOMATIC ACTUATION OF SHUNT TRIP FOR H AND B&W PLANTS - TECH SPECS 53954 B-91 DAVIS BESSE 1 - ITEM 4.4 - IMPROVEMENTS IN MAINTENANCE AND TEST PROCEDURES FOR B & N PLANTS 54058 B-92 DAVIS BESSE 1 - ITEM 4.5.1 - REACTOR SYSTEM FUNCTIONAL TESTING - DIVERSE TRIP FEATURES 53975 B-93 DAVIS BESSE 1 - ITEMS 4.5.2 & 4.5.3 - REACTOR TRIP SYSTEM FUNCTIONAL TESTING - ALTERNATIVES & TEST INTERVA i

e 1