Similar Documents at Byron |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20209B7411999-06-30030 June 1999 Proposed Tech Specs Section 3.8.5, DC Sources - Shutdown, Correcting LCO & Braidwood TS Section 3.8, Electrical Power Systems, Deleting Various References to At&T Batteries ML20204H9781999-03-23023 March 1999 Proposed Tech Specs,Revising Sections 3.7.15,3.7.16,4.3.1 & 4.3.3 to Support Installation of New Boral high-density SFP Storage Racks at Byron & Braidwood Stations ML20204H4291999-03-22022 March 1999 Proposed Tech Specs 3.9.3,allowing Use of Gamma-Metrics post-accident Neutron Monitors to Provide Neutron Flux Info During Operational Mode 6 ML20198N2041998-12-29029 December 1998 Revised Tech Specs Change,Page 3/4 3-54,providing Early Implementation of Containment Floor Drain Sump Water Level Instrumentation Requirements ML20198N3471998-12-29029 December 1998 Proposed ITS Tables 3.3.1-1 & 3.3.2-1,revising Twelve Allowable Values ML20198A0811998-12-14014 December 1998 Proposed Rev T to Improved Tech Specs Section 3.4, Reactor Coolant Sys ML20196G6611998-11-30030 November 1998 Proposed Rev to Improved Tech Specs Section 3.1 ML20155J2051998-11-0505 November 1998 Proposed TS Converting to Its,Rev R ML20155J0041998-10-30030 October 1998 Proposed Tech Specs Section 5.6.2, Fuel Storage Drainage, to Identify Sf Pool Level Sufficient to Ensure SRP Acceptance Criteria ML20154S5011998-10-18018 October 1998 Proposed Rev N to Improved TS Section 3.7 ML20154M5281998-10-15015 October 1998 Revisions K,O & P of 961213 ITS Submittal ML20154A8881998-10-0202 October 1998 Proposed Rev L to Improved Tech Specs Section 3.8 Closeout ML20153G4331998-09-25025 September 1998 Revs J & M to Tech Specs Sections 3.6 & 5.0,converting to Improved Tech Specs (Its),Final Closeout Package ML20236W5851998-07-31031 July 1998 Proposed Rev G to Sections 3.1 & 3.2 of Improved Tech Specs ML20237B6391998-07-30030 July 1998 Proposed Rev H to Section 3.5 of Improved Tech Specs ML20237E9971998-07-21021 July 1998 Rev I to Proposed Improved Tss,Section 3.9 Re Final Closeout ML20237B7021998-07-0909 July 1998 Proposed Improved TS (ITS) Section 3.3 Issued as Result of Removing Generic Change Traveler TSTF-135,Rev E from ITS Submittal ML20236H6531998-07-0202 July 1998 Rev F to 961213 Improved TS Submittal,Containing Final Package Closeout for Improved TS Sections 1.0,2.0 & 3.0 ML20248M1491998-06-0101 June 1998 Proposed Tech Specs Bases Page B 3.8-58b,converting to Improved Tech Specs ML20248C5511998-05-29029 May 1998 Proposed Tech Specs Bases Section 3/4.4.4, Relief Valves, Specifically Crediting Automatic Function of PORVs to Provide Mitigation for Inadvertent Operation of ECCS at Power Accident ML20216D9431998-04-0909 April 1998 Modified Proposed TS Pages Re 980324 Request for Amends to Licenses NPF-37 & NPF-66 ML20217E1891998-03-24024 March 1998 Proposed Tech Specs Surveillance Sections & Bases Allowing Util to Defer 10CFR50,App J,Type a Testing of Byron Unit 2 Containment Until Next Refuel Outage in 1999 ML20217B2681998-02-14014 February 1998 Proposed Rev D to ITS ML20198C3181997-12-30030 December 1997 Proposed Tech Specs 3.7.1.3 Re Condensate Storage Tank ML20203M5921997-12-17017 December 1997 Proposed Tech Specs,Rev C Changes Improved TSs 3.0,3.3,3.7, 3.8 & 5.0 as Result of Removing Generic Change Traveler TSTF-115 from Improved TS Submittal ML20203D0361997-12-0909 December 1997 Proposed Tech Specs Pages Correcting Errors Discovered in Current TS W/Regards to Total RCS Volume & Correction to Increase in RCS Volume Associated W/Unit 1 Replacement SGs Accounting for Hot Conditions ML20199A4751997-11-0707 November 1997 Proposed Tech Specs Pages Revising TS Surveillance Sections 4.6.1.1.c,4.6.1.2.a,4.6.1.2.c & Bases to Allow Performance of 10CFR50 App J,Type a Testing ML20217K4461997-10-21021 October 1997 Proposed Tech Specs Re Boron Credit in SFP ML20202F4561997-10-10010 October 1997 Proposed Tech Specs,Deleting Lower Flow Rate Requirement Associated W/Nonaccessible Area Exhaust Filter Plenum & Fuel Handling Bldg Ventilation Sys ML20211D9421997-09-24024 September 1997 Proposed Tech Specs Revising Allowable Time Interval for Performing Turbine Throttle Valve & Turbine Valve SRs Requirements from Monthly to Quarterly ML20216G8541997-09-0808 September 1997 Proposed Tech Specs Change to TS 4.5.2.b & Associated Bases Bringing Byron Unit 1 & Braidwood Unit 1 Requirement in Conformance W/Unit 2 Requirements Approved by NRC in ML20217H6071997-08-0707 August 1997 Proposed Tech Specs Pages,Revising Bases for Proposed Improved TS SR 3.8.6.1 & 3.8.6.3,to Indicate That Correction for Level Is Not Required When Battery Charging Current Is Less than 2 Amps for Gould & Less than 3 Amps for C&D ML20148P7721997-06-30030 June 1997 Proposed Tech Specs,Revising TS 3.9.11,5.6.1.1 & 6.9.10 to Allow Util to Permanently Take Credit for Soluble B in Spent Fuel Storage Pool Water to Maintain Acceptable Margin of Subcriticality ML20141F3081997-06-24024 June 1997 Proposed Tech Specs,Changing TS for ECCS Venting ML20141B7781997-06-17017 June 1997 Proposed Tech Specs Revising TS Sections 3/4.6.1.6,4.6.1.2, 6.8.4 & 6.9.1.11 to Support New Requirements in 10CFR50.55a, Which Requires Utils to Update Existing Containment Vessel Structural Integrity Programs ML20148J3231997-06-0909 June 1997 Proposed TS Reflecting Latest Rev of Waste Gas Decay Tank Rupture Accident Dose Calculation ML20140D0081997-05-31031 May 1997 Proposed Tech Specs,Revising TS Surveillance Requirement Re ECCS Pump Casings & Discharge Piping High Points Outside of Containment ML20141K8991997-05-24024 May 1997 Proposed Tech Specs Revising TS Surveillance Requirement 4.5.2.b to Encompass non-operating ECCS Pumps & Discharge Piping Which Are Provided W/High Point Vent Valves ML20141K3381997-05-23023 May 1997 Proposed Tech Specs Requesting Enforcement Discretion from Compliance W/Ts 4.5.2.b.1 Requirements of Venting of Emergency Core Cooling Sys Pump Casings & Discharge Piping High Points Outside of Containment ML20141K0011997-05-21021 May 1997 Proposed Tech Specs Relocating Reactor Vessel Surveillance Program Capsule Withdrawal Schedules IAW GL 91-01 ML20148B6151997-05-0606 May 1997 Proposed Tech Specs,Revising TS 3/4.7.5, Ultimate Heat Sink & Associated Bases to Support SG Replacement & Incorporate Recent UHS Design Evaluations ML20196G0501997-04-25025 April 1997 Proposed Tech Specs Revising Primary Containment & Reactor Coolant Sys Volume Associated W/Unit 1 Steam Generator Replacement ML20137S5341997-04-0707 April 1997 Proposed Tech Specs 3/4.8.2 Re D.C. Sources ML20137P0081997-03-24024 March 1997 Proposed Tech Specs Removing Values of cycle-specific Core Operating Limits from TS & Relocating Values to Operating Limits Rept ML20137C6381997-03-14014 March 1997 Proposed Tech Specs,Reducing Allowable Unit 1 RCS Dose Equivalent I-131 from 0.35 Uci/Gram to 0.20 Uci/Gram for Remainder of Cycle 8 ML20137C7991997-03-14014 March 1997 Proposed Tech Specs Deleting 12 License Conditions from Unit 1 Operating License & Two License Conditions from Unit 2 Operating License ML20135E6851997-02-28028 February 1997 Proposed Tech Specs,Replacing Original W D4 SG at Byron & Braidwood W/B&W International SGs ML20136G1461997-02-24024 February 1997 Proposed Tech Specs,Reflecting Conversion to Improved TS to Be Consistent w/NUREG-1431 ML20138N6841997-02-24024 February 1997 Proposed Tech Specs Changing TS from Current TS to Improved TS Consistent w/NUREG-1431,Rev 1, STS - W Plants, Dtd Apr 1995 ML20134N8481997-02-18018 February 1997 Proposed Tech Specs Table 2.2-1 & Table 3.3-4 Re Sys Instrumentation Trip Setpoints,Ts 3.4.1.2 Re Reactor Coolant Sys & TS 4.4.1.2.1 Re Surveillance Requirements 1999-06-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20209B7411999-06-30030 June 1999 Proposed Tech Specs Section 3.8.5, DC Sources - Shutdown, Correcting LCO & Braidwood TS Section 3.8, Electrical Power Systems, Deleting Various References to At&T Batteries ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20204H9781999-03-23023 March 1999 Proposed Tech Specs,Revising Sections 3.7.15,3.7.16,4.3.1 & 4.3.3 to Support Installation of New Boral high-density SFP Storage Racks at Byron & Braidwood Stations ML20204H4291999-03-22022 March 1999 Proposed Tech Specs 3.9.3,allowing Use of Gamma-Metrics post-accident Neutron Monitors to Provide Neutron Flux Info During Operational Mode 6 ML20202G9361999-01-30030 January 1999 Rev 1.4 to Chapter 10, Radioactive Effluent Treatment & Monitoring, Rev 1.6 to Chapter 11, Radiological Environ Program & Rev 1.6 to Chapter 12, Radioactive Effluent Technical Standards (Rets), for Odcm,Byron Annex ML20198N3471998-12-29029 December 1998 Proposed ITS Tables 3.3.1-1 & 3.3.2-1,revising Twelve Allowable Values ML20198N2041998-12-29029 December 1998 Revised Tech Specs Change,Page 3/4 3-54,providing Early Implementation of Containment Floor Drain Sump Water Level Instrumentation Requirements ML20198A0811998-12-14014 December 1998 Proposed Rev T to Improved Tech Specs Section 3.4, Reactor Coolant Sys ML20196G6611998-11-30030 November 1998 Proposed Rev to Improved Tech Specs Section 3.1 ML20155J2051998-11-0505 November 1998 Proposed TS Converting to Its,Rev R ML20155J0041998-10-30030 October 1998 Proposed Tech Specs Section 5.6.2, Fuel Storage Drainage, to Identify Sf Pool Level Sufficient to Ensure SRP Acceptance Criteria ML20154S5011998-10-18018 October 1998 Proposed Rev N to Improved TS Section 3.7 ML20154M5281998-10-15015 October 1998 Revisions K,O & P of 961213 ITS Submittal ML20154A8881998-10-0202 October 1998 Proposed Rev L to Improved Tech Specs Section 3.8 Closeout ML20153G4331998-09-25025 September 1998 Revs J & M to Tech Specs Sections 3.6 & 5.0,converting to Improved Tech Specs (Its),Final Closeout Package ML20236W5851998-07-31031 July 1998 Proposed Rev G to Sections 3.1 & 3.2 of Improved Tech Specs ML20237B6391998-07-30030 July 1998 Proposed Rev H to Section 3.5 of Improved Tech Specs ML20237E9971998-07-21021 July 1998 Rev I to Proposed Improved Tss,Section 3.9 Re Final Closeout ML20237B7021998-07-0909 July 1998 Proposed Improved TS (ITS) Section 3.3 Issued as Result of Removing Generic Change Traveler TSTF-135,Rev E from ITS Submittal ML20236H6531998-07-0202 July 1998 Rev F to 961213 Improved TS Submittal,Containing Final Package Closeout for Improved TS Sections 1.0,2.0 & 3.0 ML20248M1491998-06-0101 June 1998 Proposed Tech Specs Bases Page B 3.8-58b,converting to Improved Tech Specs ML20248K7361998-05-31031 May 1998 Commonwealth Edison Bnps Unit 1 Cycle 9 Startup Rept ML20248C5511998-05-29029 May 1998 Proposed Tech Specs Bases Section 3/4.4.4, Relief Valves, Specifically Crediting Automatic Function of PORVs to Provide Mitigation for Inadvertent Operation of ECCS at Power Accident ML20217Q8521998-05-0101 May 1998 Rev 9 to Bzp 310-2, Nuclear Accident Reporting Sys Form (Primary Responsibility - Station Director). W/Notes & Comments ML20216D9431998-04-0909 April 1998 Modified Proposed TS Pages Re 980324 Request for Amends to Licenses NPF-37 & NPF-66 ML20217E1891998-03-24024 March 1998 Proposed Tech Specs Surveillance Sections & Bases Allowing Util to Defer 10CFR50,App J,Type a Testing of Byron Unit 2 Containment Until Next Refuel Outage in 1999 ML20217B2681998-02-14014 February 1998 Proposed Rev D to ITS ML20199J7581997-12-31031 December 1997 Rev 1 to IST Plan Pumps & Valves Byron Nuclear Generating Station,Units 1 & 2 ML20198C3181997-12-30030 December 1997 Proposed Tech Specs 3.7.1.3 Re Condensate Storage Tank ML20203M5921997-12-17017 December 1997 Proposed Tech Specs,Rev C Changes Improved TSs 3.0,3.3,3.7, 3.8 & 5.0 as Result of Removing Generic Change Traveler TSTF-115 from Improved TS Submittal ML20203D0361997-12-0909 December 1997 Proposed Tech Specs Pages Correcting Errors Discovered in Current TS W/Regards to Total RCS Volume & Correction to Increase in RCS Volume Associated W/Unit 1 Replacement SGs Accounting for Hot Conditions ML20199A4751997-11-0707 November 1997 Proposed Tech Specs Pages Revising TS Surveillance Sections 4.6.1.1.c,4.6.1.2.a,4.6.1.2.c & Bases to Allow Performance of 10CFR50 App J,Type a Testing ML20216H8241997-10-31031 October 1997 Revs to OCDM for Byron Station,Including Rev 1.3 to Chapter 10,rev 1.5 to Chapters 11 & 12 & Rev 1.3 to App F ML20198M2621997-10-31031 October 1997 Revs to Offsite Dose Calculation Manual,Consisting of Rev 1.5 to Chapter 11 & Rev 1.5 to Chapter 12 ML20217K4461997-10-21021 October 1997 Proposed Tech Specs Re Boron Credit in SFP ML20202F4561997-10-10010 October 1997 Proposed Tech Specs,Deleting Lower Flow Rate Requirement Associated W/Nonaccessible Area Exhaust Filter Plenum & Fuel Handling Bldg Ventilation Sys ML20211D9421997-09-24024 September 1997 Proposed Tech Specs Revising Allowable Time Interval for Performing Turbine Throttle Valve & Turbine Valve SRs Requirements from Monthly to Quarterly ML20216G8541997-09-0808 September 1997 Proposed Tech Specs Change to TS 4.5.2.b & Associated Bases Bringing Byron Unit 1 & Braidwood Unit 1 Requirement in Conformance W/Unit 2 Requirements Approved by NRC in ML20217H6071997-08-0707 August 1997 Proposed Tech Specs Pages,Revising Bases for Proposed Improved TS SR 3.8.6.1 & 3.8.6.3,to Indicate That Correction for Level Is Not Required When Battery Charging Current Is Less than 2 Amps for Gould & Less than 3 Amps for C&D ML20148P7721997-06-30030 June 1997 Proposed Tech Specs,Revising TS 3.9.11,5.6.1.1 & 6.9.10 to Allow Util to Permanently Take Credit for Soluble B in Spent Fuel Storage Pool Water to Maintain Acceptable Margin of Subcriticality ML20141F3081997-06-24024 June 1997 Proposed Tech Specs,Changing TS for ECCS Venting ML20141B7781997-06-17017 June 1997 Proposed Tech Specs Revising TS Sections 3/4.6.1.6,4.6.1.2, 6.8.4 & 6.9.1.11 to Support New Requirements in 10CFR50.55a, Which Requires Utils to Update Existing Containment Vessel Structural Integrity Programs ML20148J3231997-06-0909 June 1997 Proposed TS Reflecting Latest Rev of Waste Gas Decay Tank Rupture Accident Dose Calculation ML20140D0081997-05-31031 May 1997 Proposed Tech Specs,Revising TS Surveillance Requirement Re ECCS Pump Casings & Discharge Piping High Points Outside of Containment ML20141K8991997-05-24024 May 1997 Proposed Tech Specs Revising TS Surveillance Requirement 4.5.2.b to Encompass non-operating ECCS Pumps & Discharge Piping Which Are Provided W/High Point Vent Valves ML20141K3381997-05-23023 May 1997 Proposed Tech Specs Requesting Enforcement Discretion from Compliance W/Ts 4.5.2.b.1 Requirements of Venting of Emergency Core Cooling Sys Pump Casings & Discharge Piping High Points Outside of Containment ML20141K0011997-05-21021 May 1997 Proposed Tech Specs Relocating Reactor Vessel Surveillance Program Capsule Withdrawal Schedules IAW GL 91-01 ML20148B6151997-05-0606 May 1997 Proposed Tech Specs,Revising TS 3/4.7.5, Ultimate Heat Sink & Associated Bases to Support SG Replacement & Incorporate Recent UHS Design Evaluations ML20196G0501997-04-25025 April 1997 Proposed Tech Specs Revising Primary Containment & Reactor Coolant Sys Volume Associated W/Unit 1 Steam Generator Replacement ML20137S5341997-04-0707 April 1997 Proposed Tech Specs 3/4.8.2 Re D.C. Sources 1999-06-30
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ADMINISTRATIVE CONTROLS l UNIT STAFF (Continued)
- e. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related .
functions; e.g. , licensed Senior Operators, licensed Operators, i health physics personnel, equipment operators, and key maintenance
- personnel, s
The amount of overtime worked by Unit staff members performing safety-related functions shall be limited in accordance with the i aNRC Policy Statement on working hours (Generic Letter No. 82-12).
6.2.3 ONSITE NUCLEAR SAFETY GROUP (ONSG) l FUNCTION 6.2.3.1 The 0NSG serves as an independent safety engineering group and shall function to examine plant operating characteristics, NRC issuances, industry
- advisories, REPORTABLE EVENTS and other sources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving plant safety. The ONSG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, opera-tions activities or other means of improving plant safety to the Manager of Nuclear Safety, and the Station Manager, Byron Station.
COMPOSITION three 6.2.3.2 The ONSG shall be composed of at least fote, dedicated, full-time l engineers located on site.
RESPONSIBILITIES 6.2.3.3 The ONSG.shall be responsible for maintaining surveillance of plant activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
RECORDS l 6.2.3.4 Records of activities performed by the ONSG shall be prepared, main-tained, and forwarded each calendar month to the Manager of Nuclear Safsty, and the Station Manager, Byron Station.
6.2.4 SHIFT TECHNICAL ADVISOR The Station Control Room Engineer (SCRE) may serve as the Shif t Technical Advisor (STA) during abnormal operating or accident conditions. During these conditions the SCRE or other on duty STA shall provide technical support to the Shif t Supervisor in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the unit.
- Not responsible for sign-off function.
6-2 AMEND!itNT NO. te-BYRON - UNITS 1 & 2 8803210180 880310 PDR ADOCK 05000454 f5 KrJ6
ATTACHMENT B Following the accident at Three Mile Island Unit 2, the NRC Staff developed the Action plan, NUREG-0660, to provide a comprehensive and integrated plan to improve safety at power reactors. In November, 1980 a set of TMI related actions from NUREG-0660, which were approved for implementation by the Commission, were published in the document NUREG-0737. Included in this NUREG was Item I.B.l.2 - Independent Safety Engineering Group (ISEG). Under the heading of "position", the following requirements for the ISEG were provided:
~
"The principal function of the ISEG is to examine plant operating characteristics, NRC issuances, Licensing Information Service advisories, and other appropriate sources of plant design and operating experience information that may indicate areas for improving plant safety. The ISEG is to perform independent review and audits of plant activities including maintenance, modifications, operational problems, and operational analysis and aid in the establishment of programmatic requirements for plant activities."
"Another function of the ISEG is to maintain surveillance of plant operations and maintenance activities to provide independent verification that these activities are performed correctly and that human errors are reduced as far as practicable. ISEG will then be in a position to advise utility management on the overall quality and safety of operations."
In NUREG-0800 Item II.3.6. , it is further stated that "That group shall be comprised of a minimum of five dedicated, full-time engineers, located onsite, but reporting offsite to a corporate official who holds a high-level, technically oriented position who is not in the nanagement chain for power production. For utilities with multiple sites, it may be possible to perform portions of the independent safety assessment function in a centralized location for all the utility's plants. In such cases, on Onsite Group still is required, but it may be slightly smaller than would be the case if it were performing the entire independent safety asnessment."
The requirement for establishing an ISEG was applied only to applicants for operating licenses. Therefore, LaSalle County Station was the first Edison station to have an ISEG followed closely by Byron and Braidwood. The size of the ISEG at each of these three stations consists of four fall-time engineers. These groups are administered by the Manager of Nuclear Safety who is located in the Company corporate offices. The Manager of Nuclear Safety reports directly to the Chairman and Chief Executive Officer. Three stations, Zion, Dresden and Quad-cities, do not have an ISEG.
Commonwealth Edison's nuclear program is large; there are six, two-unit nuclear stations. The completion of Braidwood Unit 2 marks the end of the construction program in the nuclear division. In June of 1987, there was a major reorganization of the nuclear operations area at the corporate level. Also, a Strategic Plan for Excellence in Nuclear Operations was
1 created to integrate the goals and action plans of all departments within the Nuclear Operations area to achieve excellence. To achieve the goals of the Strategic Plan, the reorganization had to embody stzong central control and direction at the corporate level.
The new organization includes two major station support gicups:
The first is Licensing and plant Support Services ara the second is Training, Fuel and Administrative Services. These the Gioups are each headed by Assistant Vice Presidents who report directly to the Senior Vice President and are independent of plant operations. Ebm+ of the responsibilities and functions of those two groupu neu duplicate the efforts of the ISEG. The new corporate support groups interface with six stations, whereas the ISEG only covers three stations. Thri Licensing and Plant Support Services Group (LPSSG) now has responsibility for performance assessment of the six stations. They monitor station terformance utilizing data trending and assessing work procedures and work practices. Among other things, they assess appropriateness of station programa in meeting regulations, standards and guidelines. In addition, they apprise station and corporate management of performance problems including identification of underlying causes and timely resolution to problems. Ancther function of the LPSSG is the implementation of the Operation Experience Asse8sment Program wnich includes t:2 coordinated development of corrective actionr.
which are uniform across the six stations.
At the station level, the Onsite Regulatory Assurance Department is under the functional control of the Nuclear Licensing Department which is in the LPSSO. This control provides consistency in the review of KRC licensing, inspection and enforcement correspondence. the tracking of commitments and evaluation of NRC policies ar.d regulations and their impact on the operating stations.
Another department that impacts on the functions of ISEG is the '
operational section of the Onsite Quality Assurance Group. Like the Department of Nuclear Safety, the Quality Assurance Department is entirely independent of the Nuclear Operations area. The operational section of the onsite Quality 3.-surance Group at each of the six stations has one to two people licenses the SRO level. With their knowledge of plant systems and the technical s; .fications they .sre able to perform a knowledgeable indeper dent review and assessment of plant operations.
Since the ISEG is part of the technical specifications, the Quality Assurance Department conducts pericdic audits of the ISEG to determine if they are in compliance with the requirements of the applicable section of the technical specifications.
1 g The technical specification required functions of the 1880 are not changed by this proposed amendment. Those review items listed in Technical tipecification 6.2.3.1 will continue to be reviewed by the ISBG, however, the ISBG will make further use of the corporate level independent review work in performing onsite reviews.
Based on the above information, it has been concluded the that ISBG ,
size could be reduced from four to three people without any loss in meeting-the requirements of the technicel specifications. Using t!'e material developed by all ther' o'5er support groups in the Nuclear Operations area as a base, the ISEG -
im form their functions in a more effective manner with a lower investt- manhours, and hence fewer people. The option for i a lower number of pe .el is permitted under NUREG-0800.
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ATTACHMENT C Evaluation of significant Hazards Consideration commonwealth Edison has evaluated this proposed amendment and determined that it involves no significant hazards consideration. According to 10 CPR 50.92(c),'a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the amendment would not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or
- 2) Create the possibility _of a new or different kind of accident from any accident previously evaluated; or
- 3) Involve a significant reduction in a margin of safety.
The purpose of this amendment is to reduce the Onsite Nuclear i ~ Safety Group minimum staffing requirement from four engineers to three engineers. The proposed amendment will have no effect on the consequences of an accident previously evaluated because it will not involve any physical change in the plant or operating procedures. The proposed amendment may have some effect on the probability of an accident previously evaluated since there will be fewer people performing the independent safety assessment function within the Onsite Nuclear Safety Group (ONSG). However, any increase in this probability will not be significant and will be compensated for by the activities of several new corporate level groups (created by recent corporate organization changes) that are independent of the immediate management chain for power production. These groups now perform independent assessments of operating characteristics and safety issues that are often redundant to the technical specification responsibilities of the ONSG, This proposed amendment does not change ONSG areas of review as described in the technical specifications. The ONSG retains responsibility for review of those items listed in Technical specification 6.2.3.1, but will make additional use of the independent review work done by the above noted corporate level groups.
There will be no change in the physical plant or in the way the plant is operated. No new accidents are postulated. As a result, operation of the plant in accordance with the proposed amendment will not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed amendment will not involve any physical change in the margin of safety because there will be no physical change in the plant or change in operation of the plant. There may be some effect on the margin of safety in terms of the amount of review of operating characteristics and safety issues, but this change will not be significant due to the
T independent assessment activities of recently created corporate level groups. These groups now have responsibilities that often overlap the technical specification responsibilities of the ONSG. When performing their onsite reviews, the ONSG will increase their use of corporate level independent review work performed by new departments.
Based on the preceding discussion, Commonwe.:.lti: Edison believes this proposed amendment involves no significant hazards consider.3 tion.
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