ML20059H909
| ML20059H909 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/01/1993 |
| From: | Storz L CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20059H913 | List: |
| References | |
| 2187, NUDOCS 9311100264 | |
| Download: ML20059H909 (14) | |
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C.NT.M_
.' 300 Mod: son Avenue Louts F. Storr s
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- Toleda OH 43652-0001 '
Vice President-Nuclear '
419-249-2300
- Davis-Besse h{
_-Docket. Number 50-346 E
License Number NPF-3 b
Serial.Nunber 2187 November 1, 1993
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h United States Nuclear Regulatory Ccmmission Document Contiol Desk Vashington, DC 20555
Subject:
Revision 18 to the Davis-Besse Unit 1 Updated Safety Analysis Report (USAR)
Gentlemen:
The Toledo Edison Company is submitting, pursuant to 10 CFR 50.71, one (1) original plus ter. (10) copies of Revision 18 to the Updated
. Safety Analysis Report (USAR).
Updated Safety Analysis Report Revision 18 reflects facility changes.im-1 plemented between January 23, 1992 and May 1, 1993. This USAR revision
.1 includes facility changes that occurred during the Eighth Refueling Outage which concluded on May 1, 1993. Revision 18.to the-USAR also updates the-
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Fire' Hazards Analysis Report (FHAR) which is incorporated by reference-into the USAR Section 9.5.1, Fire Protection Systems. This t.pdate trans-mits Revision 14 to the FHAR vhich reflects. changes implemented between May-1, 1992 and May 1, 1993. A summary of the major changes made in the revisions can be found in Attachment 1.
This submittal-also reports changes to the' Davis-Besse Quality Assurance Program in accordance with 10 Cld 50.54(a). provides a brief summary of the changes made in this revision.
Information contained in these revisions to N bSAR and the FHAR is accurate to May 1, 1993.
Please insert the Revision material, dated November 1993, into the USAR and FHAR per the attached Listing of Effec-tive Pages.
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Operating Componies.
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9311100264 931101
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- Modo Edaon PDR ADOCK 05000346 K
T Docket Number 50-346 License Number NPF-3 Serial Number 2187 Page 2 If you have any questions, regarding this matter, please contact Villiam T. O'Connor, Manager - Regulatory Affairs, at (419) 249-2366.
Very truly yours,
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J. B. Hopkins, NRC Senior Project Manager J. B. Martin, Regional Administrator, NRC Region III S. Stasek, DB-1 NRC Senior Resident Inspector Utility Radiological Safety Board 1
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Docket Number 50-346 License Number NPF-3 Serial Number 2187 Enclosure l
SUBMITTAL OF REVISION 18 TO i
THE DAVIS-BESSE UPDATED SAFETY ANALYSIS REPORT (USAR) i FOR DAVIS-BESSE NUCLEAR POVER STATION UNIT NO. 1 Enclosed are the original and 10 copies of Revision 18 to the Davis-Besse Nuclear Power Station, Unit No. 1. Updated Safety Analysis Report.
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By:
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- 1. F. Storz,' T ee Pr si8gnt - Nuclear Sworn and subscribed before me this 1st day of November, 1993.
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s1Ad No'Tary Pp6fic, State of Ohio EVELYNL Dress emeuc.Swsogg
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Docket Number 50-346 License Number NPF-3 Serial Number 2187 Page 1
SUMMARY
OF USAR REVISION 18 MAJOR CHANGES Section 1 Added a new Section to list the Functional Drawings contained in the USAR.
Ei minated reference to some electrical drawings that had in-i formation and level of detail that is not needed in the USAR.
Section 2 Updated the description of the Sodium Hypochlorite system to I
reflect the installation of a new storage tank.
Section 3 Section 3.6, Protection Against Dynamic and Environmental Effects Associated Vith Postulated Rupture of Piping, was changed to reflect repairs to the Continuous Vent Line nozzle and removal of whip restraint R-16.
The high energy line breaks for Main Steam to Auxiliary Feed-vater Pump Turbines, Main Feedvater line breaks and Steam Generator Blovdown line breaks were re-analyzed and.re-written.
The re-write of the above sections included eliminating the-l i
description of the equipment in each of the affected rooms and l
the addition of drawings that depict break locations, mitiga-ting equipment, posulated single failure, available backup equipment, room temperature, pressure and room boundaries.
Table 3.6-2, Portulated Break Point Stresses, was removed since the break points were redundant to that found in the CoAR Figures and current stress values are found in the appropriate stress analysis.
USAR Section 3.8, Design of Seismic Class I and Class II Struc-tures, was revised to state that the actual yield. strength documented by Certified Hill Test Reports have been used to establish design allovables for various structural steel members.
Revised Section 3.8 to reflect the revised:blovout pressure for the Auxiliary Building Rooms 303 and 314 blevout panels and lower annulus pressure following a main feedvater line break.
The containment pressure vessel allovable external design pressure was re-evaluated using the 1986 ASME B&PV Code.
Section 3.9.2.11.6, Letdown Coolers, was revised to reflect modifications performed during the Eighth Refueling Outage that replaced both Letdown Coolers with equivalent replacement coolers.
Docket Number 50-346 j
License Number NPF-3 Serial Number 2187 Page 2 Revised Section 3D.l.23, Criterion 27.. Combined Reactivity control Systems capability, stating that 50 percent of the control rods reactivity worth is also taken credit for along vith the minimum boron concentration in the BWST in maintaining i
the reactor suberitical.
j Revised Section 3.9 to state that the description of fuel.
design is historical. The most current information is con-l tained in the reload report (Appendix 4B) and approved B&V Fuel j
Company topical reports.
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-i Updated Section 3.9.3.5, Control Rod Assembly, to reflect the new extended life control rods are being utilized beginning in-l Cycle 9.
.i' Section 4 Updated Appendix 4B, Reload Report to reflect Cycle 9.
j Revised Section 4.1, 4.2, and 4.3 pertaining the fuel, nuclear, i
and thermal-hydraulic design, to state that the most current information is contained in the latest reload report and ap-l proved B&W Fuel Company topical reports.
l Revised the section on control rod assemblies to reflect the new extended life control rods are being utilized beginning in i
Cycle 9.
Section 5 Added information to Appendix SA pertaining to the Reactor l
Coolant Pump Motor Flywheel replacement.
Revised Section 5.3, Thermal-Hydraulic System Design, to re-flect the current DNB ratio used at Davis-Besse.
J Corrected the design heat load data for the Pressurizer Quench
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Tank. Heat Exchanger.
i Revised the Steam Generator description to show that repairs to.
f leaking tubes may be accomplished by sleeving, as approved in j
License Amendment 171.
i Section 6 Revised Section 6.2.1.3.3.d to reflect the preferred opera-tional method of mitigating a potential critical crack of an auxiliary feedvater line in the containment annulus.
j Revised Section 6.2.1.3.2, Containment Pressure Transient i
Analysis Break Spectrum, to reflect the revised blovout pres-sure for the Auxiliary Building Rooms 303 and 314 blowout i
panels and lower annulus pressure following a main feedvater line break. The containment pressure vessel allovable external design pressure was re-evalua'ad using the 1986 ASME B&PV Code, 1
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Docket Number 50-346 License Number NPF-3 Serial Number 2187 I
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Revised Section 6.2.3.2, Emergency Ventilation' System Design, to revise the annulus pressure response following'a LOCA to-take credit for additional flow based on Emergency Ventilation j
System fan curves.
Section 6.2.5, Combustible Gas Control in Containment Vessel, was revised to reflect that the aluminum reactor vessel core cover is now stored in containment. Re-analyses have been performed to allow greater hydrogen generation inside con-tainment. This decreases time between the accident and initi-ation of the Hydrogen Control System.
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Revised Section 6.2.5.2.2, Hydrogen Purge System,'to clarify that the Hydrogen Purge System functions in conjunction with the Containment Hydrogen Dilution System, not as a backup.
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Revised Section 6.3.1.3, Reactivity Requirements, stating that 30 percent of the control rods reactivity worth is also taken credit for along with the minimum boron concentration in the BVST in maintaining the reactor suberitical.
Revised Section 6.3.3.1.2, concerning Large Break LOCA analysis -
to reflect the re-analysis supporting the new boron dilution flow path.
Rcvised Table 6.3-5, Relief Valves in ECCS, to reflect the replacement of valve DH 1509.
Section 7 Revised Section 7.7.1.2.7, ICS System Failure Considerations, to add Megavatt Electric as a parameter that is monitored by a Smart Analog Selector Switch.
Revised the description of the Control Rod Drive Control System
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to reflect the replacement of the CRD programmer motors with-solid-state micronrocessor based programmers.
Section 8 Revised Section 8.1.2.1, Main Generation System, to reflect a modification that connected the division one Generator Pro-l tection System output logic to the division two Generator Pro-tection System.
Created a new section to describe the Station Blackout Diesel Generator that was installed to comply with 10 CFR 50.63.
Revised Section 8.3.1.1.4, to reflect the addition of sync-bronism check relays to both Emergency Diesel Generators.
Revised Section 8.3.1.1.12, Motors, to clarify the description of the acceptance criteria used regarding valve operator ter-l' minal voltage.
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I Docket Number 50-346 License Number NPF-3 l
Serial Number 2187
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Section 8.3.1.2.21, Electric Conductors and Table 8.3 4, l
Environmental Requirement for Class 1E Cables, vere revised to r
remove vendor-specific details.
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Revised the listing of locally mounted instruments on the 125V DC essential panels.
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Updated the load listing on the 125 V DC essential panels.and j
the station batteries.
Section 9 Section 9.1.4, Fuel Handling Systems, was revised to reflect f
new B&V analysis which assumes 50 percent control rod vorth post LOCA and concludes that the BVST minimum boron concen-tration of 1800 ppm is sufficient to maintain the core 1 per-cent Ak/k at 70 degrees Fahrenheit.
i Revised Section 9.2.1, Service Vater System, to reflect-the the installation of flow elements and differential pressure j
indicators in the Service Water System.
Revised Section 9.3.3, Equipment and Floor Drains to reflect
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that the Turbine Building drains can be pumped to the onsite settling basins.
l Revised the description of the Makeup and Purification system to indicate that Purification Demineralizer Prefilter is usu-
.i ally bypassed during normal operations.
Revised Table 9.3-5, Steam Generator Feedvater Quality,.to
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reflect that alternate amines that can be used to control
-t oxygen.
In Section 9.5.4, Diesel Generator Fuel Oil Storage and Trans-fer System, clarified the description of the design of the diesel oil system.
Section 9.5.1 Fire Hazards Analysis Report i
Section 2 Updated several calculation references relating to the associated circuit coordination study.
i Section 4 Various small changes were made due to the incorporation of plant modifications. The changes include reflecting l
revised circuit numbers, deleting sub-components, and i
revising the associated notes.
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Docket Number 50-346' License Number NPF-3 Serial Number 2187 Page 5
-Section 8 Incorporated a change relating to theLcompensatory.
measures for inoperable Thermo-Lag barriers where the barrier is still physically intact.
Section 9 Revised to reflect new-organization-tittle changes.
Appendix B-1 Various small changes vere made due to the incorporation of plant modifications. The type of changes include-revised raceway identifications and circuit numbers.;
Appendix B-2 Various small changes were made due to the incorporation of plant modifications. The type of changes include revised raceway identifications and circuit. numbers.
Appendix C-1 Various small changes vere made due to the incorporation of plant modifications.
The type of changes included adding new circuit numbers to reflect revised cable routings.
Appendix C-2 Made various small changes due to the incorporation of' plant modifications. The type of changes included adding new circuit numbers to reflect rev', ed cable routings.
Appendix C-3 Made various small changes due to the incorporation of plant modifications. The type of changes include chan-ging load descriptions and circuit numbers.
Reformatted the Appendix to reflect the deletion of-several columns of information found in other documents.
This allowed the use of a portrait format instead of a landscaped format.
Appendix D Revised to reflect new organization tittle changes.
Section 10 Updated the description of the Sodium Hypochlorite system to reflect the installation of a new storage tank.
Section 10.4.7, Condensate and Feedvater Systems, was revised to show that the combined drains for the Number 1 and Number 2 feedvater drains can be drained to the condensers.
Section 10.4.7 vas also revised to reflect the ability to use alternate amines for oxygen scavenging.
Section 11 Revised the Miscellaneous Liquid Radvaste description to reflect the replacement of the Vaste Evaporator with the Radvaste Demineralizer system for the processing of liquid radvaste.
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Docket Number 50-346 i
License Number NPF-3 Serial Number 2187 i
Page 6 Revised various parts of Section 11 to reflect compliance with the revised 10 CFR_20 requirements.
i Revised several sections of Section 11 to reflect the removal and replacement of the Radiological Environmental Monitoring
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requirements from the Technical Specification to the Offsite Dose Calculation Manual.
1 Section 12 Revised various sections to reflect the new programs in place to meet the requirements of the revised 10 CFR 20.
Section 13 Removed Sections 13.1 and 13.1.2.1 through 13.1.2.5 as they were a duplication of information contained in Section 17.2.
l Revised Section 13.1.2.6.2, operations Section, to show the i
elimination of the position of Superintendent - Shift Operation.
In Section 13.1.2.3.6, Radiation Protection Section, to eliminate the supervisor's position descriptions.
Revised Section 13.1.2.6.2, to reflect License Amendment l'75, j
tegarding minimum shift crew composition.
Section 15 No major changes.
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Docket Number 50-346.
License Number NPF-3 Serial Number 2187 i
Page 1 i
ATTACHMENT 2 CHANGES.T0 QUALITY ASSURANCE PROGRAM 4
Section 17.2.12.6, pertaining to devices and standards potentially found in j
conditions adverse to quality, was revised to eliminate an in-line reviev performed by the Quality Assurance Department.
Evaluations of measuring and test equipment, that indicated conditions adverse to quality did not' exist, required review and approval by the Quality Assurance Director.
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Analysis of several years of evaluations indicated that there were no sub-sequent conditions adverse to quality and, therefore, this in-line reviev vas no longer required. NRC reviewed and approved this change in a letter' dated May 4, 1993 (Log 1-2840).
'I The organization described under Section 17.2.1, Organization, under vent numerous changes. The following is a description of the changes:
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In July of 1992, Toledo Edison submitted a request to the NRC to eliminate Engineering Assurance's day-to-day quality review of en-l gineering specifications and modifications. This request entailed.
I eliminating the associated activities from the responsibilities of I
the Manager - Engineering Assurance and Services in Section 17.2.1 and removing the description of the activities from Section 17.2.3.5, Design Package Review.
Reviews of Engineering Assurance's assessment results since its formation in 1988 continued to indicate that no significant programmatic or prevalent technical problems existed.
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This in effect confirmed that the formal verification process and inter-discipline reviews inherent in the specification and modifica-i tion development processes were working. This request was revieved by i
'the NRC and approved on October 30, 1992 (Log 1-2751).
B)
In October of 1992, the Quality Assurance organization vent through a i
reorganization. This reorganization consisted of eliminating the l
position of Manager - Quality Systems and reassigning the duties to the Manager - Quality Verification and Manager-Ouality Control. The administrative and programmatic duties and responsibilities of the Manager - Quality Systems were not deleted. These duties were shared by the remaining two Managers. The above change had established lines.
of authority, responsibility, and communication.
These responsibili-ties and duties vere under the overall responsibility of the Director
- Quality Assurance and continued to remain under the Quality Assur-ance organization. This change did not alter or negate our commitment to provide and describe the organizations responsible for establish-ment and implementation of the Nuclear Quality Assurance Program.
This change has since been superseded by the major Nuclear Group i
reorganization described in Item D.
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Docket Number 50-346 License Number NPF-3 Serial Number 2187-Page 2 C)
In June of 1993, the position of Senior Vice-President - Nuclear (CSC) was created. This new position reports directly to the Chairman, President and Chief Executive Officer and is responsible for directing the operation of the Davis-Besse Nuclear Power Station and the Perry Nuclear Power Plant. This reassignment of responsibilities did not reduce previously established responsibilities and continues to sat-isfy the criteria of 10 CFR 50 Appendix B and USAR commitment pre-viously accepted by the NRC.
D)
In July of 1993 the Nuclear Group under vent a major reorganization.
This change consisted of modifying the existing five director fune-tional arrangement to four directors with the associated realignment of activities to accommodate this new structure. Reporting to the Vice President - Nuclear are 1) the Plant Manager, responsible for Operations, Maintenance, Radiation Protection and Security; 2) the:
Director - Engineering, responsible for Design Engineering, Plant Engineering (previously Systems and Performance Engineering), and Nuclear Engineering; 3) the Director - Nuclear Services, responsible for Materials Management, Regulatory Affairs (previously Licensing and Emergency Preparedness), Planning and Training; and 4) the Director -
Nuclear Assurance (previously Quality Assurance), responsible for Quality Control, Quality Assessment (previously Ouality Verification) and Quality Services (previously Records Management and Document Control).
The organization change outlined above in Item D identified two Quality Assur-ante Program reductions.
They included 1) the Director - Nuclear Assurance vill be responsible for non-quality assurance related functions of the Quality Services section and adds operational experience assessment activities to the functions performed by the Quality Control Section; and 2) the independent safety engineering function reports to the Manager - Quality Control rather than directly to the Vice President - Nuclear. These two changes were sent to the l
NRC on August 5, 1993 (Serial 2167) and vere approved by the NRC on August 13, i
1993.
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There vere several transfers of responsibilities that vere noted as non-reduc-tions to Quality Assurance Program Description commitments. The following is a.
description of the changes.
In Section 17.2.1.3, Corporate Organization, the following changes were made:
- 1) The new position of Executive Vice President - Operations and l
Engineering was assigned the responsibilities of the deleted posi-t tions of Vice President - Fossil Operations and Executive Vice 6
President - Power Generation.
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Serial Number 2187 Page 3
- 2) A new position of Vice President - Finance and Administration was j
created and assumed the responsibilities of the deleted positions i
of Executive Vice President - Finance and Administration and Senior Vice president Legal, Human and Corporate Affairs.
- 3) The responsibility for the control of: security related activities vas transferred from the Vice President - Finance and Administra-i tion to the Executive Vice President - Operations and Engineering.
This responsibility is assigned to the new position, Director -
l Corporate Services under the new position of Vice President -
Customer Support who is under the jurisdiction of the Executive Vice President - Operations and Engineering.
In Section 17.2.1.4, Toledo Edison Nuclear Group,the following transfer 'af re-sponsibilities occurred:
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- 1) The Manager -- Quality Assessment (previously Quality Verification) assumed the responsibility for independent assessment of engi-neering activities and products. These duties were previously performed by the deleted position of Manager - Engineering i
Assurance and Services.
- 2) The responsibility for the formulation, implementation, and i
periodic assessment of the effectiveness of the fire protection l
piogram was transferred from the deleted position of Manager -
Systems Engineering to the Manager - Operations.
- 3) The Manager - Nuclear Engineering received additional responsibil-ities for coordinating computer related services provided by the Centerior Service Company Information Systems Department. This 3
~ ifted from the position of Manager - Planning and Support.
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- 4) Procurement Engineering responsibilities were transferred from the l
Manager - Design Engineering (who reports to the Director -
l Engineering) to the Manager - Materials Management (who reports to' the Director - Nuclear Services).
This change was also noted in Sections 17.2.4.1, Procurement Document Control, Section 17.2.4.3, Procurement Document Review and Section 17.2.7.2, Source I
Verification.
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- 5) The responsibility for the maintenance of the Fire Hazards Analysis t
Report and fire protection related design documents was transferred from the Systems Engineering to Design Engineering.
- 6) The review of all external information received in support of im-proved performance and reliability and the day-to-day engineering support in the area of plant operations assessment was transferred-f r om the Performance Engineering to the Manager - Quality Control.
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- 7) The respo sibility for evaluation of plant chemistry and radio-chemistry issues vas moved from the deleted position'of Manager -
Engineering Assurance and Services to the new title of Manager.-
Plant Engineering.
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- 8) The responsibilities for emergency preparedness, licensing, safety.
II and environmental compliance are now under the Manager - Regula-tory Affairs.
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- 9) The responsibilities for providing direction for the Nuclear Training Program to support the need of the onsite personnel in accordance with laws, regulations, commitments and. standards was transferred from the Director - Technical Services to the Director l
- Nuclear Service r
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- 10) Engineering support services such as; design process controls and
'j vendor document processing was transferred from the Manager -
l Engineering Assurance and Services to the Manager - Plant Engineering.
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- 11) The review of selected procurement documents, the review and approval of vendor quality assurance programs and procedures, j
performance of vendor audits, and ccatrol of the approved vendor list was transferred from the position of Manager - Quality Control to the Manager - Quality Assessment.
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- 12) The responsibility for the development, maintenance and' control of the Nuclear Quality Assurance Manual was transferred from the j
Manager - Quality Assessment (previously Ouality Verification) to the new position of Manager - Quality Services.
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In addition, the following is a listing of sections that vere revised to reflect
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l title changes-17.2.0, Nuclear Quality Assurance Policy i
17.2.1.3, Corporate Organization j
17.2.1.4, Toledo Edison Nuclear' Group 17.2.2.2, Program Application 17.2.2.3, Program Documentation 17.2.2.5, Program Review 17.2.3.2, Design Process 17 2.4.1, Procurement Document Control 17.?.4.3, Procurement Document. Review 17.2.5.2, Review and Approval (Instruction, Procedures, and Drawings) 17.2.6.3, Distribution and Control 17.2.7.1, Supplier Selection 17.2.7.2, Source Verification 17.2.7.3, Acceptance of Materials and Items 1
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Docket Number 50-346-License Number NPF-3 Serial Number 2187 Page S 17.2.9.4, Noadestructive Examination 17.2.10.2, P):ocedures (Inspection) 17.2.10.3, Personnel Qualificatic.is 17.2.10.4, Supplier Control 17.2.11.3, Procedures (Test Control) 17.2.12.1, Calibration Program 17.2.14.2, Inspection Status 17.2.15.1, Nonconformance Identification 17.2.15.2, Review and Evaluation 17.2.15.3, 10CFR21 Reporting 17.2.15.4, Trending 17.2.16.1, Corrective Action 17.2.16.2, Significant Conditions Adverse to Quality 17.2.17.2, Records Control 17.2.18.1, Audit Requirements 17.2.18.3, Audit Scheduling and Planning 17.2.18.4, Audit Performance 17.2.18.5, Audit Reporting Figure 17.2-1, Organization Chart These changes do not eliminate any duties or responsibilities previously de-scribed in the Quality Assurance Program Description. These changes are changes in reporting relationships only and do not involve changes in func-tions.
As such, these changes do not reduce commitments to the previously ap-proved Quality Assurance Program Description. -These changes do'not alter or negate our commitment to provide and describe the organizations responsible for establishment and implementation of the Nuclear Quality Assurance Program. The above changes continue to satisfy the requirements of 10 CFR 50 Appendix B.