Application for Amend to License NPF-3,changing Section 6.0, Administrative Controls, to Reflect Position Title Changes & Organization Changes Made by Centerior Energy CorpML20235B959 |
Person / Time |
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Site: |
Davis Besse |
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Issue date: |
06/30/1987 |
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From: |
Shelton D TOLEDO EDISON CO. |
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To: |
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Shared Package |
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ML20235B942 |
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References |
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1395, NUDOCS 8707090256 |
Download: ML20235B959 (8) |
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20216E6051999-09-0707 September 1999 Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation ML20210H0631999-07-28028 July 1999 Application for Amend to License NPF-3,revising TS 3/4.7.5.1, Ultimate Heat Sink, by Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4131999-07-27027 July 1999 Application for Amend to License NPF-3,changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G8831999-07-26026 July 1999 Application for Amend to License NPF-3,revising TSs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5251999-07-26026 July 1999 Application for Amend to License NPF-3,revising Tech Specs for Implementation of 10CFR50,App J,Option B for Type B & C Containment Leakage Rate Testing ML20210G4631999-07-26026 July 1999 Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1, Safety Features Actuation Sys Instrumention & Associated Bases 3/4.3.1 & 3/4.3.2, Reactor Protection Sys & Safety Sys Instrumentation ML20195F9121999-06-10010 June 1999 Application for Amend to License NPF-3,changing TS 3/4.6.4.4 Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20207E7861999-05-21021 May 1999 Application for Amend to License NPF-3,allowing Use of Expanded Spent Fuel Storage Capability ML20205E4961999-03-19019 March 1999 Application for Amend to License NPF-3,requesting Withdrawal of Proposed New Action B to TS 3.6.5.2,previously Submitted in 981027 Application ML20204F1691999-03-0909 March 1999 Application for Amend to License NPF-3,adopting Changes in Frequency & Scope of Volumetric Exams Justified by W TR WCAP-14535A ML20196F3791998-11-30030 November 1998 Supplemental Application for Amend to License NPF-3, Proposing Changes to License Conditions 2.C(6) & 2.E by Transferring Operating Authority for DBNPS from Toed & Centerior Svc Co to Firstenergy Nuclear Operating Co ML20155E3181998-10-28028 October 1998 Application for Amend to License NPF-3,revising Various Sections of TS 6.0, Administrative Controls, Including Relocation of Contents of 6.11 to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155E0701998-10-27027 October 1998 Application for Amend to License NPF-3,revising TSs 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation by Providing Potential Reduction in Spurious Trip Rate to Provide Cost Savings in Excess of $50,000 ML20155D7731998-10-27027 October 1998 Application for Amend to License NPF-3,relocating Existing TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8481998-10-27027 October 1998 Application for Amend to License NPF-3,revising Existing TS SRs 4.8.2.3.2.d,4.8.2.3.2.e,4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20151W2811998-09-0808 September 1998 Application for Amend to License NPF-3,permitting Use of Framatome Cogema Fuels M5 Advanced Alloy Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2851998-09-0808 September 1998 Application for Amend to License NPF-3,revising TS Section 3/4.7.6, Plant Systems - 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Depressurization & Cooling Sys - Containment Spray Sys ML20117K1871996-05-28028 May 1996 Application for Amend to License NPF-3,revising TS 3/4.3.1.1 RPS Instrumentation & TS 3/4.3.2.2 - Anticipatory RTS Instrumentation to Increase Trip Device Test Interval ML20107L3541996-04-18018 April 1996 Application for Amend to License NPF-3,requesting NRC Review & Approval to Use Alternate Electrical Lineup.Station Blackout DG as Standby Emergency Power Source to Supply Loads Normally Supplied by EDG 1,while Being Reworked ML20101M1601996-03-29029 March 1996 Application for Amend to License NPF-3,App A,Re Surveillance Requirements for Charcoal Filter Lab Testing to Revise Testing Methodology Used to Determine Operability of Charcoal Filters in ESF Air Handling Units ML20101C6911996-03-0606 March 1996 Application for Amend to License NPF-3,revising TS 3/4.5.2 to Allow Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI 1-2 Pump Until 10th Refueling Outage, Scheduled to Begin 960408 ML20100E0051996-02-0505 February 1996 LAR 93-0003 to License NPF-3,revising Table 3.3-3 of TS 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation to More Accurately Reflect Design & Actuation Logic of Plant Sequencers & Undervoltage Relays ML20095F5861995-12-12012 December 1995 Application for Amend to License NPF-3,revising TSs Re Containment Sys ML20098C5131995-10-0202 October 1995 Application for Amend to License NPF-3,revising TS Section 5.0,design Features & Adopting Improved STS for B&W Plants Format & Content ML20098C1071995-09-29029 September 1995 Application for Amend to License NPF-3,modifying TS 3.4.3 & Associated Bases for Pressurizer Code Safety Valve Lift Setpoint Tolerances ML20098C3931995-09-29029 September 1995 Application for Amend to License NPF-3,revising Tech Spec 3/4.1.2.8, Reactivity Control Sys - Borated Water Sources - Shutdown, Tech Spec 3/4.1.2.9, Reactivity Control Sys - Operating & TS 3/4.5.1, ECCS - Core Flooding Tanks 1999-09-07
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20216E6051999-09-0707 September 1999 Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation ML20210H0631999-07-28028 July 1999 Application for Amend to License NPF-3,revising TS 3/4.7.5.1, Ultimate Heat Sink, by Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4131999-07-27027 July 1999 Application for Amend to License NPF-3,changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G8831999-07-26026 July 1999 Application for Amend to License NPF-3,revising TSs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5251999-07-26026 July 1999 Application for Amend to License NPF-3,revising Tech Specs for Implementation of 10CFR50,App J,Option B for Type B & C Containment Leakage Rate Testing ML20210G4631999-07-26026 July 1999 Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1, Safety Features Actuation Sys Instrumention & Associated Bases 3/4.3.1 & 3/4.3.2, Reactor Protection Sys & Safety Sys Instrumentation ML20195F9121999-06-10010 June 1999 Application for Amend to License NPF-3,changing TS 3/4.6.4.4 Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20207E7861999-05-21021 May 1999 Application for Amend to License NPF-3,allowing Use of Expanded Spent Fuel Storage Capability ML20205E4961999-03-19019 March 1999 Application for Amend to License NPF-3,requesting Withdrawal of Proposed New Action B to TS 3.6.5.2,previously Submitted in 981027 Application ML20204F1691999-03-0909 March 1999 Application for Amend to License NPF-3,adopting Changes in Frequency & Scope of Volumetric Exams Justified by W TR WCAP-14535A ML20196F3791998-11-30030 November 1998 Supplemental Application for Amend to License NPF-3, Proposing Changes to License Conditions 2.C(6) & 2.E by Transferring Operating Authority for DBNPS from Toed & Centerior Svc Co to Firstenergy Nuclear Operating Co ML20155E3181998-10-28028 October 1998 Application for Amend to License NPF-3,revising Various Sections of TS 6.0, Administrative Controls, Including Relocation of Contents of 6.11 to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155E0701998-10-27027 October 1998 Application for Amend to License NPF-3,revising TSs 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation by Providing Potential Reduction in Spurious Trip Rate to Provide Cost Savings in Excess of $50,000 ML20155D7731998-10-27027 October 1998 Application for Amend to License NPF-3,relocating Existing TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8481998-10-27027 October 1998 Application for Amend to License NPF-3,revising Existing TS SRs 4.8.2.3.2.d,4.8.2.3.2.e,4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20151W2811998-09-0808 September 1998 Application for Amend to License NPF-3,permitting Use of Framatome Cogema Fuels M5 Advanced Alloy Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2851998-09-0808 September 1998 Application for Amend to License NPF-3,revising TS Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20236G6461998-06-29029 June 1998 Application for Amend to License NPF-3,transferring Operating Authority for DBNPS from TE & Centerior Svc Co to New Operating Company Called Firstenergy Nuclear Operating Co.Marked Up License,Safety & Environ Assessments Included ML20236R2301998-06-29029 June 1998 Resubmitted Application for Amend to License NPF-3, Transferring Operating Authority for DBNPS from Teco & Centerior Svc Co to New Operating Company Called Firstenergy Nuclear Operating Co.Safety Assessment & EA Included ML20217P8671998-04-24024 April 1998 Application for Amend to License NPF-3,modifying Existing TS 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases by Relocating Tables of Response Time Limits from TS to Plant USAR Technical Requirements Manual ML20217P8251998-04-24024 April 1998 Application for Amend to License NPF-3,clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20203L0861998-02-26026 February 1998 Application for Amend to License NPF-3 to Revise TS 3/4.4.5 & TS 3/4.4.6.2,incorporating New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2511997-12-23023 December 1997 Application for Amend to License NPF-3.Amend Changes TS Definitions 1.12,TS 3/4.9.5 & New TS 3.0.6 ML20197J5861997-12-23023 December 1997 Application for Amend to License NPF-3,revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217R2801997-08-26026 August 1997 Application for Amend to License NPF-3,clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2831997-08-26026 August 1997 Application for Amend to License NPF-3,modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5931997-07-29029 July 1997 Suppl 950929 to Application for Amend to License NPF-3, Change TS 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating & Associated Bases 3/4.4.2 & 3/4.4.3 ML20141F1051997-06-24024 June 1997 Application for Amend to License NPF-3,deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138A3201997-04-18018 April 1997 Application for Amend to License NPF-3,requesting Conversion to 24-month Fuel Cycle ML20138C3131997-04-18018 April 1997 Application for Amend to License NPF-3,requesting Rev to TS 3/4.7.6 to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20137M1061997-03-31031 March 1997 Application for Amend to License NPF-57,revising TS to Improve Consistency Between TS & Plant Configuration, Operation & Testing & Complete Required CA to Resolve TS Discrepancies Identified in CA Program ML20138M1251997-02-14014 February 1997 Application for Amend to License NPF-3,requesting Delay of Heat Removal Sys Valve Pit Surveillance Requirements ML20134D7461997-01-30030 January 1997 Application for Amend to License NPF-3,revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134B0561997-01-20020 January 1997 Application for Amend to License NPF-3,involving TS 3/4.5.3 Re ECCS Subsystems ML20132C7771996-12-13013 December 1996 Application for Amend to License NPF-3,authorizing Transfers of Control ML20132B6871996-12-11011 December 1996 Application for Amend to License NPF-3,revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle ML20134F1851996-10-28028 October 1996 Application for Amend to License NPF-3,requesting Revisions to 3/4.8.1.1,3/4.8.1.2,3/4.8.2.3,3/4.8.2.4 & 3/4.8 Re Electrical Power Systems ML20117P5301996-09-17017 September 1996 Application for Amend to License NPF-3,supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8441996-09-12012 September 1996 Application for Amend to License NPF-3,revising Reactivity Control Systems & Emergency Core Cooling Systems ML20117M1971996-09-0404 September 1996 Application for Amend to License NPF-3,App A,Modifying TS 6.2.3 by Removing Specific Overtime Limits & Working H from TS Consistent W/Nrc Recent Determination,On Generic Basis, That Limits Need Not Be Specified ML20116K2601996-08-0707 August 1996 Application for Amend to License NPF-3,changing Tech Specs 1.0, Definitions, Bases 3/4.0, Applicability & 3/4.6.2.1, Containment Sys - Depressurization & Cooling Sys - Containment Spray Sys ML20117K1871996-05-28028 May 1996 Application for Amend to License NPF-3,revising TS 3/4.3.1.1 RPS Instrumentation & TS 3/4.3.2.2 - Anticipatory RTS Instrumentation to Increase Trip Device Test Interval ML20107L3541996-04-18018 April 1996 Application for Amend to License NPF-3,requesting NRC Review & Approval to Use Alternate Electrical Lineup.Station Blackout DG as Standby Emergency Power Source to Supply Loads Normally Supplied by EDG 1,while Being Reworked ML20101M1601996-03-29029 March 1996 Application for Amend to License NPF-3,App A,Re Surveillance Requirements for Charcoal Filter Lab Testing to Revise Testing Methodology Used to Determine Operability of Charcoal Filters in ESF Air Handling Units ML20101C6911996-03-0606 March 1996 Application for Amend to License NPF-3,revising TS 3/4.5.2 to Allow Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI 1-2 Pump Until 10th Refueling Outage, Scheduled to Begin 960408 ML20100E0051996-02-0505 February 1996 LAR 93-0003 to License NPF-3,revising Table 3.3-3 of TS 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation to More Accurately Reflect Design & Actuation Logic of Plant Sequencers & Undervoltage Relays ML20095F5861995-12-12012 December 1995 Application for Amend to License NPF-3,revising TSs Re Containment Sys ML20098C5131995-10-0202 October 1995 Application for Amend to License NPF-3,revising TS Section 5.0,design Features & Adopting Improved STS for B&W Plants Format & Content ML20098C1071995-09-29029 September 1995 Application for Amend to License NPF-3,modifying TS 3.4.3 & Associated Bases for Pressurizer Code Safety Valve Lift Setpoint Tolerances ML20098C3931995-09-29029 September 1995 Application for Amend to License NPF-3,revising Tech Spec 3/4.1.2.8, Reactivity Control Sys - Borated Water Sources - Shutdown, Tech Spec 3/4.1.2.9, Reactivity Control Sys - Operating & TS 3/4.5.1, ECCS - Core Flooding Tanks 1999-09-07
[Table view] |
Text
, 1
. l Docket'No. 50-346 License No. NPF-3 i Serial No. 1395 ]
APPLICATION FOR AMENDMENT TO 1
FACILITY OPERATING LICENSE NO. NPF-3 q
)
FOR DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. I l
Enclosed are requested changes to the Davis-Besse Nuclear Power Station.
Unit No. 1, Facility Operating License No. NPF-3. Also included are the Safety Evaluation and Significant Hazards Consideration.
1 The proposed changes (submitted under cover letter Serial No. 1395) j concern Section 6.0, Administrative Controls: 1 Figure 6.2-1, Davis-Besse Nuclear Power Station Offsite/Onsite Organization; ,
Specification 6.5, Review and Audit; l Specification 6.6, Reportable Event Action; and )
Specification 6.7, Safety Limit Violation. ,
By
~
D. C. Shelton, Vice President, Nuclear l Sworn to and subscribed before me this 30th day of June, 1987.
0h/ l - J l \b N'ota'ry Public, State' of Ohio My commission expires /
8707090256 070630 PDR ADOCK 05000346 P PDR
. )
Docket No. 50-346 License No. NPF-3 Serial No. 1395 Attachment 1 1
The following information is provided to' support issuance of the i requested changes to the Davis-Besse Nuclear Power Station, Unit No. 1 {
Operating License No. NPF-3, Appendix A Technical Specifications, Section 6.0.
A. Time required to implement: This change is to be effective immed-lately upon issuance of the License Amendment. !
i B. Reason for change (Facility Change Request No. 87-0114): Revise Technical Specifications a include recent position title changes, and recent organization changes made by Centerior Energy.
l C. Safety Evaluation: See attached Safety Evaluation (Attachment 2). j i
D. Significant Hazards Consideration: See attached Significant Hazards l Consideration (Attachment 3) .
Docket No. 50-346- )
License No. NPF-3 ;
Serial No. 1395 i Attachment 2 Page 1 i SAFETY EVALUATION I
INTRODUCTION' l 1
The purpose of this Safety Evaluation is to review a proposed change to the Davis-Besse Nuclear Power Station, Unit No, 1 Operating License, Appendix A Technical Specifications. The proposed changes involve revising j organization position titles to reflect recent changes, and including organ- j j;ation changes made by Centerior Energy in Section 6.0, Administrative Controls.
SYSTEMS AFFECTED None j REFERENCES Davis-Besse Nuclear Power Station, Unit No. 1 Operating License, Appendix A, Technical Specifications.
FUNCTIONS OF AFFECTED SYSTEMS N/A PROPOSED AMENDMENT REQUEST DISCUSSION The proposed License Amendment Request revises the following sections of the Davis-Besse Nuclear Power Station, Unit No. 1 Operating License.
Appendix A Technical Specifications as shown below.
Figure 6.2-1 (page 6-2) - Revise figure to include the position of Executive Vice President. The Finance and Administration Vice President and the Vice President, Nuclear will report directly to the Executive Vice President, instead of to the President and Chief Operating Officer. The following title j changes are also made: Administration Senior Vice President to Pinance and Administration Vice President; Senior Vice President, Nuclear to Vice Pres- l q
ident, Nuclear; and Performance Engineering Manager to Performance Engineering j Director. These are administrative changes. y j i
6.5.1.2 (page 6-6) - Delete "or Performance Engineering Manager". This l position has been elevated to Performance Engineering Director, which is {
included as an Engineering Director. This~is an administrative _ change, j 6.5.1.6.e (page 6-7) - Change title of Senior Vice President, Nuclear to Vice President, Nuclear. This is an administrative change.
i 4
Docket No. 50-346 q License No. NPF-3 1 Serial No. 1395 ]
Attachment 2 1 Page 2 j I
6.5.1.7.c (page 6-8) - Change title of Senior Vice President, Nuclear to Vice President, Nuclear. This is an administrative change. ;
I l
6.5.1.8 (page 6-8) - Change title of Senior Vice President, Nuclear to Vice President, Nuclear'. This is an administrative change.
i 6.5.2.2 (page 6-9) - Change title of Senior Vice President, Nuclear to )
Vice President, Nuclear. This is an administrative change. !
6.5.2.9 (page 6-12) - Change title of Senior Vice President, Nuclear to Vice President, Nuclear. This is an administrative change.
6.5.2.10.a (page 6-12) - Change title of Senior Vice President, Nuclear to Vice President, Nuclear. This is an administrative change.
6.5.2.10.b (page 6-12) - Change title of Senior Vice President, Nuclear to Vice President, Nuclear. This is an administrative change. I 6.5.2.10.c (page 6-12) - Change title of Senior Vice President, Nuclear to Vice President, Nuclear. This is an administrative change.
6.6.1.b (page 6-12) - Change title of Senior Vice President, Nuclear to i Vice President, Nuclear. This is an administrative change. j 6.7.1.b (page 6-13) - Change title of Senior Vice President, Nuclear to l I
Vice President, Nuclear. This is an administrative change.
6.7.1.d (page 6-13) - Change title of Senior Vice President, Nuclear to Vice President, Nuclear. This is an administrative change.
DISCUSSION OF UNREVIEWED SAFETY QUESTION The proposed changes involve revising organization position titles, i Therefore, the implementation of these proposed changes would not:
Increase the probability of occurrence of an accident previously evaluated in the USAR because the accident conditions and assumptions are not affected by the proposed Technical Specification changes. The proposed changes do not involve a test or experiment, or a modification to a system. The proposed changes are administrative in nature and do not increase the probability of an accident previously evaluated (10CFR50.59 (a)(2)(1)).
Increase the consequences of an accident previously evaluated in the USAR because the accident conditions and assumptions are not affected by the proposed Technical Specification changes. The proposed changes do not involve a test or experiment, or a modification to a systen. The proposed changes are administrative in nature and do not increase the consequences of an accident previously evaluated (10CFR50.59(a)(2)(1)).
+
s 1:
Docket No. 50-346 License No, NPF-3 !
Serial No. 1395 , i Attachment 2
- Page 3 Increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the USAR because the proposed changes do not involve a test or experiment and no station equipment is being modified. The proposed changes are administrative in nature and dc ;
not increase the probability of occurrence of a malfunction of equipment !
1mportant to safety (10CFR50.59(a)(2)(1)) . l Increase the consequences of a malfunction of equipment important to safety previously evaluated in the USAR because the proposed changes do not involve a test or experiment and no station equipment is being modified. The proposed changes are administrative in nature and do not increase the consequences of a malfunction of equipment important to safety (10CFR50.59(a)(2)(1)) .
l Create the possibility for an accident of a different type than any l evaluated previously in the USAR because the accident conditions and I assumptions are not affected by the proposed Technical Specification changes. The proposed changes do not involve d test or experiment, or a modification to a system and do not affect any plant equipment or oper-ation procedures which could impact the probability of an accident. The proposed changes are administrative in nature and involve-no accident scenario. On matters related to. nuclear safety, all accidents are bounded j by previous analysis and no new accidents are involved (10CFR50.59(a)(2)(ii)).
Create the possibility for a malfunction of a different type than any evaluated previously in the USAR because no station equipment is being modified by the proposed Technical Specification changes. The proposed changes do not involve a test or experiment, or a modification to a system and do not affect any plant equipment or operational procedures which could impact'the probability of a malfunction. The changes are adminis-trative in nature and involve no malfunction scenario (10CFR50.59(a)(2)(11)).
Reduce any margin of safety as defined in the basis for any Technical Specification because the amendment does not affect any operating prac-tices or limits nor any equipment or system important to safety. The proposed changes are administrative in nature and will not reduce the l margin of safety (10CFR50.59(a)(2)(111)). j CONCLUSION ]
l Based on the above, it is concluded that the proposed Technical l Specification changes do not constitute an unreviewed safety question.
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Docket No. 50-346 License No. NPF-3 Serial No. 1395 {
Attachment 3 Page 1 SIGNIFICANT HAZARDS CONSIDERATION INTRODUCTION The purpose of this Significant Hazards Consideration is to review a proposed change to the Davis-Besse Nuclear Power Station, Unit No. 1 Operating License, Appendix A Technical Specifications. The proposed changes involve revising organization position titles to reficct recent changes, and including organization changes made by Centerior Energy in Section 6.0, Administrative Controls.
SYSTEMS AFFECTED None REFERENCES Davis-Besse Nuclear Power Station, Unit No. 1 Operating License, Appendix A, Technical Specifications.
FUNCTIONS OF AFFECTED SYSTEMS N/A PROPOSED AMENDMENT REQUEST DISCUSSION The proposed License Amendment Request revises the following sections of the Davis-Besse Nuclear Power Station, Unit No. 1 Operating License, Appendix A Technical Specifications as shown below.-
Figure 6.2-1 (page 6-2) - Revise figure to include the position of Executive Vice President. The Finance and Administration Vice President and the Vice President, Nuclear will report directly to the Executive Vice Preside.nt inst ead of to the President and Chief Operating Officer. The following title chanaes are also made: Administration Senior Vice President to Finance and Administration Vice President; Senior Vice President, Nuclear to Vice President, Nuclear; and Performance Engineering Manager to Performance Engineering Director. These are administrative changes.
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6.5.1.2 (page 6-6) - Delete "or Performance Engineering Manager". This !
position has been elevated to Performance Engineering Director, which j is included as an Engineering Director. This is an adminior.rative change. ,
l 6.5.1.6.e (page 6-7) - Change title of Senior Vice President, Nuclear to ~ j Vice President, Nuclear. This is an administrative change. j i
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Docket No. 50-346 License No. NPF-3
~ Serial No. 1395 Attachment 3 Page 2 6.5.1.7.c (page 6-8) Change title of Senior Vice President, Nuclear to Vice President, Nuclear. This is an administrative change.
6.5.1.8 (page 6-8) - Change title of Senior Vice President, huclear to Vice President, Nuclear. This is an administrative change.
6.5.2.2 (page 6-9) - Change title of Senior Vice President, Nuclear to Vice President, Nuclear. This is an administrative' change.
6.5.2.9 (page 6-12) - Change title of Senior Vice President, Nuclear to Vice President, Nuclear. This is an administrative change.
6.5.2.10.a (page 6-12) - Change title of Senior Vice President, Nuclear to Vice President,-Nuclear. This is an administrative change.
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1 6.5.2.10.b (page 6-12) - Change title of Senior Vice President, Nuclear l to Vice President, Nuclear. This is an administrative change.
6.5.2.10.c (page 6-12) - Change title of Senior Vice President, Nuclear to Vice President, Nuclear. This is an administrative change.
6.6.1.b (page 6-12) - Change title of Senior Vice President,-Nuclear to Vice President, Nuclear. This is an administrative change. 1 6.7.1.b (page 6-13) - Change title of Senior Vice President, Nuclear to Vice President, Nuclear. This is an administrative change.
6.7.1.d (page 6-13) - Change title of Senior Vice President, Nuclear to Vice Presidenc, Nuclear. Thia is an administrative change. I SIGNIFICANT HAZARDS CONSIDERATION The proposed change does not involve a significant hazards consideration because che operation of the Davis-Besse Nuclear Power Station, Unit No. 1, in accordance with this change would not:
Involve a significant increase in the probability or consequences of an accident previously evaluated because the accident conditions and assumptions are not affected by the proposed Technical Specification changes. The proposed changes do not involve a test or experiment, or a modification to a system. The proposed changes are administrative in nature and do not increase the probability or consequences of an accident previously evaluated (10CFR50.92(c)(1)) .
Create the possibility of a new or different kind of accident from any accident previously evaluated because the accident conditions and assumptions are not affected by the proposed Technical Specification changes. The proposed changes do not involv. 3 test or experiment, or a modification to a system and do not affect any plant equipment or opera-A
4 Docket No. 50-346 License No. NPF-3 Serial No. 1395 Attachment 3 Page 3 ,
i tion procedures which could impact the probability of an accident. The )
proposed changes are administrative in nature and involve no accident I scenario. On matters related to nuclear safety, all accidents are bounded by previous analysis and no new accidents are involved (10CFR50.92 (c) (2))'. j Involve a significant reduction in a margin of safety because the amend- :
ment does not affect any operating practices or limits nor any equipment !
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or system important to safety. The proposed changes are administrative in nature and will not reduce the margin of safety (10CFR50.92(c)(3)).
CONCLUSION l
Based on the above, it is concluded that the proposed Technical Specifi- )
cation charges do not constitute a Significant Hazardo Consideration. '
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