ML20076C813
| ML20076C813 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/22/1991 |
| From: | Shelton D CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20076C817 | List: |
| References | |
| 1962, NUDOCS 9107240328 | |
| Download: ML20076C813 (7) | |
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CENTERDOR ENERGY Donald C. Shelton 300 Madson Avenue Vce President Nuclear Toledo. 0H 436520001 Davts Besse (419)249 2300 Docket Number 50-346 License Number NPF-3 Serial Number 1962 July 22, 1991 United States Nuclear Regulatory Commission Document Control Desk Vashington, DC 20555 Subj ec t :
Revision 14 to the Davis-Besse Unit 1 Upda t ed Saf et:, Analysi' Report (USAR)
Gentlemen:
The Toledo Edison Company is submitting, pursuant to 10 CFR 50.71, one (1) original plus ten (10) copies of Revision 14 to the USAR for the Davis-Besse Nuclear Pover Station, Unit 1.
For administrative reasons no changes were made to the USAR under Revision 13.
Updated Safety Analysis Report Revision 14 reflects facility changes implemented between January 22, 1990 and January 22, 1991, and cortects discrepancies which have been discovered in the USAR.
This submittal also reports changes to the Davis-Besse Quali ty Assurance Program in accordance with 10 CFR 50.54(a). provides a brief summary of the changes made in this revision.
Information contained in Revision 14 to the USAR is aceutate to January 22, 1991.
Plea;e insert the Revision material, dated July 1991, into the USAR per the attached Revision 14 Listing of Effective Pages.
Very truly yours,
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P. M. Byron, NRC hegion III, DB-1 Senior Resident Inspector A. B. Davis, Regional Administrator, NRC Region III J. B. Hopkins, NRC/NRR DB-1 Senior Project Manager q o n Utility Radioltgical Safety Board
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Docket Number 50-346-
-License Number NPF-3 Serial Number 1962 Enclosure SUBMITTAL OF REVISION 14 TO THE DAVIS-BESSE UPDATED SAFETY ANALYSIS REPORT (USAR)
FOR DAVIS-BESSE NUCLEAR POVER' STATION UNIT NO. 1 Enclosed are the original and 10 copies of Revision 14 to the Davis-Besse Nuclear Power Station, Unit No. 1, Updated Safety Analysis Report.
Fort D. C. Shelton, Vice President, Nuclear By:
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rs, Director - Technical Services Sworn and subscribed before me this 22nd day of July,1991.
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!L!db Y' tary Public, State of Ohio No JUDITH HIRSCH Notary Public State Of Oh!o My Commession Expres June 30,1992
Docket Number.50-346
_ License Number NPF-3 Serial Number 1962 Page 1 of 5
SUMMARY
OF USAR REVISION 14 MAJOR CHANGES-Section 1 Deleted Piping and Instrument Drawings (P& ids) contained in
' die USAR and replaced them with functional drawings. The functional. drawings are simplified flow diagrams which contain sufficient detallito provide an_ understanding of hov each plant system functions.
P& ids in the following sections have been replaced:
3, 5, 6, 7, 9, 10 and 11.
Revised Section 1.4.1, Identification of Agents and Contractors, to reflect the organizational structure under the Centerior Energy Corporation, in accordance with License Amendment 152.
Section 2 No major-changes.
Section 3 Revised Section 3.6-3 to. accurately reflect the pipe break criteria used to locate and design the pipe whip restraints for the Main Steam, Main Feedvater Decay Heat, Auxiliary Feedvater and Core Flood systemr-Revised Section 3.6.2.6.2, Reactor Coolant System Supports, to correct inconsistencies in the explanation of design load cases and allovable stress values.
The revision now gives details of' load cases and stress allovables used in the design of the reactor vessel and steam generator non-integral component supports.
Revised Section 3.6.2.7.15 to add Auxiliary Feedvater flow control valves 1-1 and 1-2 and associated cabling to the listing of rooms that contain safety-related equipment.
In Section 3.6.2.7.2.13, modified the description of flooding that would occur following a circulating water line break to better describe the sequence of events based on the configuration of the condenser pit.
Removed a statement regarding a jet impingement shield vall Ein Section 3.6.2.7.1.4.
The vall was in the original plant design but due to a modified design it was not_ installed.
Deleted equipment locations and various electrical racevay drawings that were referenced in Table 3.3-1, " Essential-Systems Required for a Safe Shutdown la the Event of a Tornado".
Section 4 Revised the description of the core barrel bolts to reflect the modification that replaced 60 of the 108 velded locking clips with locking cups.
Added a section, 4.3.5.9, under Reactivity Monitoring to describe the ex-core neutron flux detectort.
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Docket Number ~ 50-346-License Number-NPF-3 Serial Number 1962 Page 2 of 5 Raised the Anticipatory Reactor. Trip' System (ARTS) turbine trip arming setpoint from 25% to 45% of full power in accordance with License Amendment 135 -
Section 5 Added.the Steam Generator inspection openirigs to Table 5.1-5,
" Steam Generator Design Data".
Updated Section 5.2.5, Inservice Inspection, to reflect Davir-Besse's commitment to the 1986 revision to ASME Section XI, for the Inservice Inspection progtam.
Changed the Integrated Control System runback rates inom 50-percent to 20 percent per minute.
Section 6 Revised Table 6.3-6, " Single Failure Analysis - Emergency Core Cooling System ", to maintain DH9A and DH9B, isolation valves in the contaliment emergency sump outlet line, closed and the breakers tripped open to resolve an Appendix R concern of a fire induced fault causing DH9A and DH9B to actuate.
Section 7 Section 7.1.2.6, Compliance with IEEE Standard 317 - 1971, was revised to reflect various modifications to the electrical penetrations that added Conax header plates and feedthrough assemblies and/or replaced existing Amphenol feedthroughs with Conax replacements.
Revised Table 7.5-1, "Information Readouts Availabic to Operator for.Honitoring Conditions in Reactor, iteactor Coolant System, Containment Vessel, ECCS and Steam Generator", to revise indicator accuracies to reflect manufacturer's specifications, identify additional post accident monitoring sensors already present;in the table and ccrrecting several indicator ranges, i
Added a description of the Diverse Scram System (DSS):that was installed to comply with 10 CFR 50.62.
Added a section, 7.13.3.11, under Reactivity Monitoring to describe the ex-core. neutron flux detectors.
Revised the Steam end Feedwater Rupture Control System Steam Generator high level trip setpoint to actuate at 225 inches on the start-up range level instrumentation.
Raised the Anticipatory Reactor Trip System (ARTS) turbine trip arming setpoint from 25% to 45% of full power in accordance with-License Amendment 135.
Changed the Integrated control System runback rates from 56 percent to 20 percent per minute.
Docket Number 50-346 License Nuaber NPF-3 1
Serial Number 1962: -
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Page 3lof 5.
ll' Changed feed and bleed permissive in the Integrated Contiol System to allow continuous feed and bleed at full povet levels provided the safety rods are 100 percent withdrawn and control rod g.oup 5 is greater than 25 percent vithdrawn.
I Section 8 In Section 8.3.1.1.4 revised Emergency Diesel Generator air start system description to include the third compressor that was added during the sixth refueling outage.
Added a brief description of the air booster line check valves in the EDG air start system.
Revised Section 8.3.1.1.5 to reflect the installation of grounding resistors in the neutrals of the four class lE.
distribution transformers CEl-1, CEl-2, DF1-1, and DF1-2.
Added a statement to Section 8.3.2.1.6 to reflect the installation of overvoltage relays on the station hat teiles L
that alarm at 150 volts.
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I Section 9 Revised Section 9.1.4.2.2, Fuel !!andling Equipment, to descrioe modification that was performed on-the fuel and control rod masts to make them compatible with the new Mark
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B5 fuel assemblies, Burnable Poison Rods and Orifice Rods.
l Added a atatement to 9.1.4.2.3, Loading and Removing Fuel, regarding the use of Steam Generator nozzle dams if Steam Generator maintenance is performed during refueling.
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Added statements descrjbing_the cross-tie that was installed to the essential component cooling water header to allov for p
alignment of the essential header to the makeup pump 'or cooling during feed and bleed conditions.
l Modified Table 9.4-6,-" Single Failure Analysis-ECCS Room i
Cooling Units", to state that for a certain range of-service vater temperature, operation with only one ECCS room coolet per room-is acceptable.-
Revised Table 9.2-3, " Single Failure Analysis Service Vater System", to remove.the passive mechanical failures.
Revised Section 9.5.4 to reflect the replacement of the p
Emergency Diesel Generator fuel oil storage. tank level
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switches with new measuring probes.
Section 10 In Section 10.3.1.1.1, Main Steam temperature and pressure limits, removed the Safety Features Actuation System signal from the Main Steam Isolation Valves.
Section 11 Revised Section 11.6 to be consistent with Technical Specifications description of the Radiological Environmental Monitoring Program.
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Docket Number 50-346 License Number NPF-3 Serial Number 1962 Page 4 of 5 Corrected the sensitivity value for radiation monitor RE-1822B.
Section 12 No major changes.
Section 13 This Section was revised to teilect organization changes resulting from the Centerior Enctgy Corpotation teorganization.
Section 15 Various changes to reflect accident re-analysis as a iesult of the Cycle 7 core reload.
Increased the allowable response time for the high Ilux/ number of reattor coolant pumps on, trip funetion of the Reactor Protection System from 451 milliseconds to 631 milliseconds. This change is in accordance with License Amendment 148.
The reanalysis conducted for Amendment 148 also used a new value for the trip delay time of 800 milliseconds.
Added statements to section 15,4, Accident Analysis, to reflect re-analysis done in Cycle 6 Reload Repott based on a more conservative source term and three 450 effective full power day cycles.
Lovered the Integrated Control System pr essure setpoints on the turbine bypass system to 935 and 1010 psia to teduce challenges to the Main Steam Salety Valves.
Raised the Anticipatcry Reactor Ttip System (ARTS) tutbine trip arming setpoint from 25% to 45% of full power in accordance with License Amendment 135.
Changed feed and bleed permissive in the Integtated Control System to allow continuous feed and bleed at full pover levels provided the safety rods nre 100 percent withdrawn and control rod group 5 is greater than 25 percent withdrawn.
Incorporated results of re-analysis of main steam line break on one side with a stuck open main steam safety valve on the other side.
Section 16 No major changes.
Section 17 Table 17.2-1, " Applicable URC Regulatory Guides, ANSI Standards, and Industry Codes", was updated to teflect Davis-Besse's commitment to the 1986 revision to ASMR Section XI, for the Inservice Inspection Program.
Docket Number 50-346' License Number NPIA3 i
Serial Number 1962 I
Page 5 of 5 Section 17.2 vas revised to reflect organizational changes resulting=from the Centerior Energy Corpora'.lon reorganization in accordance with License itendment 152.
Notable changes include:
Toledo Edison's Nuclear Group (includlag QA and the Quality Assurance Program) report to :nd is the responsibility of the Vice President - Nuclear, Davis-Besse - Centerior Service Company. The Centerior Service Company (CSC) has ultimate responsitii'lity for the physical construction, operation and maintenance of the Davis-Besse Nuclear Pover Station.
Rostructuring of and using services from other sectors of the Centerior Service Company.
These services includet Procurement 1 Security: Computer related activities: Inspection, analytical and non-destructive
,l-examination; and Medical Services, i
Restructuring of the Nuclear Group in the following ateas
- Industrial Security Section report to the Plant Managet;
- Station modification activities are the responsibility of i
the Manager - DB Maintenance; I
- Materials Management Section reports to the Director -
Planning and Scheduling;
- Reactor and core performance activities are the responsibility of the Manager - Nuclear Engineering; l
- Non-radiological environmental compliance activities and technical support functions for the resolution of plant deficiencies and deviations are the responsibility of the Manager - Nuclesr Licensing.
- Manager - Nuclear Plant Services is responsible for support services such as records management, procedure activities i
and office services.
Revised responsibilities of Manager-Engineering Assurance and Services to include engineering support functions as reviewed and approved in NRC letter dated June 29,1990 (Leg No. 1-2305).
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