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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20202J0181999-02-0303 February 1999 SER Accepting Changes in Quality Assurance Program,Which Continues to Meet Requirements of App B to 10CFR50 ML20154F8701998-10-0606 October 1998 Safety Evaluation Authorizing Proposed Alternative to Requirements of OMa-1988,Part 10,Section 4.2.2.3 for 21 Category a Reactor Coolant Sys Pressure Isolation Valves ML20153F9871998-09-17017 September 1998 Safety Evaluation Accepting 980225 Proposed Rev 26 to Illinois Power Nuclear Program Qam ML20237E3991998-08-27027 August 1998 SER Accepting Licensee Response to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode, for Clinton Power Station ML20237A1521998-08-0707 August 1998 SER Re Mgt Services Agreement at Clinton Power Station. Approval Under 10CFR50.80 Not Required ML20217H5771998-03-27027 March 1998 Safety Evaluation Concluding That No Significant Safety Hazards Introduced at CPS for Net 32% Ampacity Derating Factor for 1 H & 3 H Conduit Fire Barrier Sys & 1 H Cable Tray Fire Barrier Sys.Requests Response Addressing Issue ML20199F6751998-01-26026 January 1998 Safety Evaluation Accepting 971209 Proposed Change to CPS USAR Which Will Impact Commitments Made in CPS QAP Description ML20141K6321997-05-27027 May 1997 Safety Evaluation Accepting Relief Requests for Inservice Testing Program for Plant ML20135D1191996-12-0404 December 1996 Safety Evaluation of First Ten Year Interval Inservice Inspection Program Plan for Illinois Power Co,Clinton Power Station ML20149L7951996-11-12012 November 1996 Safety Evaluation Related to Licensee 960729 Requests for Relief from Requirements of Section XI of ASME Boiler & Pressure Vessel Code,1980 Edition Through Winter 1981 Addenda ML20116G8771992-10-29029 October 1992 Safety Evaluation Supporting Licensee Method of Coping W/Sbo Except W/Respect to Initial Room Temp Used in Control Room heat-up Calculation ML20059H0671990-08-24024 August 1990 SER Accepting Licensee Response to Generic Ltr 88-01, NRC Position on IGSCC in BWR Austentic Stainless Steel Piping, W/Exception of Licensee Position on Frequency of Leakage Monitoring ML20064A2611990-08-20020 August 1990 Generic SER Re Mark III Containment Hydrogen Control. Hydrogen Injection Rate Strongly Influenced by Background Gas Concentrations ML20246B6311989-08-17017 August 1989 Safety Evaluation Supporting Amend 25 to License NPF-62 ML20245F3471989-08-0404 August 1989 SER Accepting Util 841001,871118 & 880609 Responses to Generic Ltr 83-28,Item 2.1,Parts 1 & 2 Re Evaluation of Reactor Trip Sys Equipment Classification & Vendor Interface,Respectively ML20247B8791989-05-15015 May 1989 Safety Evaluation Concluding That Licensee Combinatory Qualitative Event Analysis Adequately Addresses NRC Concerns Re Loss of Electric Power to nonsafety-related Control Sys ML20246C2301989-05-0303 May 1989 Safety Evaluation Accepting Uitl Response to Generic Ltr 83-28,Item 4.5.2 Re Periodic on-line Testing of Backup Scram Valves & Commitment to Test Backup Scram Valves Independently During Each Refueling Outage ML20244C5671989-04-10010 April 1989 Safety Evaluation Supporting Amend 21 to License NPF-62 ML20247E8831989-03-27027 March 1989 Safety Evaluation Supporting Amend 20 to License NPF-62 ML20206M5561988-11-21021 November 1988 Evaluation Concluding That Basis Provided by Licensee for Justifying Relief Requests for Replacement Parts Sufficient & Relief Requests 5003 & 5044 Acceptable.Licensee Should Certify Compliance W/Commitments When Replacements Complete ML20151N4701988-07-28028 July 1988 Safety Evaluation Supporting Rev to Position Re Nuclear Sys Protection Sys self-test Sys Failure Detection & Indication for Facility ML20147H7651988-03-0101 March 1988 Safety Evaluation Re First ten-year Interval Inservice Insp Program.Grants Relief from ASME Code Section XI Requirements for Requests 4002,4001 & 4003 & Denies Requests 5001 & 5002. Program Acceptable & in Compliance w/10CFR50.55a(g) ML20214F5641987-05-18018 May 1987 Safety Evaluation Supporting Util Compliance W/Atws Rule 10CFR50.62, Requirements for Reduction of Risk from ATWS Events for Light-Water-Cooled Nuclear Power Plants ML20137L7111986-01-22022 January 1986 Technical Evaluation Re HVAC Duct Work & Support Sys.Overall Structural Design of HVAC Sys Adequate & Provides Sufficient Margin of Safety to Failure Under Normal & DBA Conditions ML20138H1261985-10-18018 October 1985 Supplemental Safety Evaluation Accepting Use of Rev 2 to NCIG-01, Visual Weld Acceptance Criteria for Structural Welding at Nuclear Power Plants. Criteria Appropriate & Meet Requirements of GDC 1 to App a to 10CFR50 1999-02-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARU-603277, Monthly Operating Rept for Sept 1999 for Clinton Power Station,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Clinton Power Station,Unit 1.With ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers U-603267, Monthly Operating Rept for Aug 1999 for Clinton Power Station,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Clinton Power Station,Unit 1.With U-603245, Monthly Operating Rept for Jul 1999 for CPS Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for Jul 1999 for CPS Unit 1.With ML20211C9621999-07-26026 July 1999 ISI Summary Rept U-603232, Special Rept:On 990531 Lpms Was Declared Inoperable Due to Receipt of High Vibration & Loose Parts Alarm Which Did Not Clear.Lpms Was Restored to Operable Status on 990707 After Alignment & Tension on Recorder Tape Drive Was Adjusted1999-07-0909 July 1999 Special Rept:On 990531 Lpms Was Declared Inoperable Due to Receipt of High Vibration & Loose Parts Alarm Which Did Not Clear.Lpms Was Restored to Operable Status on 990707 After Alignment & Tension on Recorder Tape Drive Was Adjusted U-603233, Monthly Operating Rept for June 1999 for Clinton Power Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Clinton Power Station,Unit 1.With U-603222, Monthly Operating Rept for May 1999 for Clinton Power Station.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Clinton Power Station.With ML20210K8391999-05-11011 May 1999 British Energy Annual Rept & Accounts 1998-99 ML20206H1231999-05-0505 May 1999 Illinois Power Co CPS Main CR Simulator Certification Rept U-603210, Monthly Operating Rept for Apr 1999 for Cps,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Cps,Unit 1.With U-603204, Final Part 21 Rept 21-99-003 Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier Trentec for Westinghouse Breaker 1AP05EH.Issue Determined Not Reportable Per 10CFR211999-04-30030 April 1999 Final Part 21 Rept 21-99-003 Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier Trentec for Westinghouse Breaker 1AP05EH.Issue Determined Not Reportable Per 10CFR21 U-603192, Monthly Operating Rept for Mar 1999 for Clinton Power Station,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Clinton Power Station,Unit 1.With U-603182, Part 21 Rept Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier, Trentec.Condition Rept 1-99-01-136 Was Initiated to Track Investigation & Resolution of Issue1999-03-12012 March 1999 Part 21 Rept Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier, Trentec.Condition Rept 1-99-01-136 Was Initiated to Track Investigation & Resolution of Issue U-603176, Monthly Operating Rept for Feb 1999 for Clinton Power Station,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Clinton Power Station,Unit 1.With ML20207F2031999-02-10010 February 1999 Rev 1 to CPS COLR for Reload 6 Cycle 7 ML20202J0181999-02-0303 February 1999 SER Accepting Changes in Quality Assurance Program,Which Continues to Meet Requirements of App B to 10CFR50 U-603144, Monthly Operating Rept for Dec 1998 for Clinton Power Station,Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Clinton Power Station,Unit 1.With U-603223, Illinova Corp 1998 Annual Rept. with1998-12-31031 December 1998 Illinova Corp 1998 Annual Rept. with U-603115, Part 21 Interim Rept 21-98-021 Re Deficiencies in Matl Dedication Process Used by Goulds Pumps in Supplying SR Parts to Npps.Issue Is Not Reportable Under 10CFR21. Dedication Process Did Not Affect Ability of Components1998-12-0404 December 1998 Part 21 Interim Rept 21-98-021 Re Deficiencies in Matl Dedication Process Used by Goulds Pumps in Supplying SR Parts to Npps.Issue Is Not Reportable Under 10CFR21. Dedication Process Did Not Affect Ability of Components U-603124, Monthly Operating Rept for Nov 1998 for Clinton Power Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Clinton Power Station,Unit 1.With U-603114, Part 21 Rept 21-98-049 Re W Dhp Circuit Breaker Refurbished by Nuclear Logistics,Inc Which Failed to Operate.Caused by Trip Latch out-of-adjustment & Incorrectly Sized Ratchet Lever Assembly Bushing.Breakers Were Returned to Vendor1998-11-25025 November 1998 Part 21 Rept 21-98-049 Re W Dhp Circuit Breaker Refurbished by Nuclear Logistics,Inc Which Failed to Operate.Caused by Trip Latch out-of-adjustment & Incorrectly Sized Ratchet Lever Assembly Bushing.Breakers Were Returned to Vendor U-603103, Monthly Operating Rept for Oct 1998 for Clinton Power Station,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Clinton Power Station,Unit 1.With U-603101, Special Rept:On 980918,discovered That Triaxial Seismic Accelerometers Had Not Been Properly Calibrated.Caused by Inadequate Calibration Procedure.Calibration to Be Performed off-site1998-10-28028 October 1998 Special Rept:On 980918,discovered That Triaxial Seismic Accelerometers Had Not Been Properly Calibrated.Caused by Inadequate Calibration Procedure.Calibration to Be Performed off-site ML20154F8701998-10-0606 October 1998 Safety Evaluation Authorizing Proposed Alternative to Requirements of OMa-1988,Part 10,Section 4.2.2.3 for 21 Category a Reactor Coolant Sys Pressure Isolation Valves U-603091, Monthly Operating Rept for Sept 1998 for Clinton Power Station,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Clinton Power Station,Unit 1.With ML20153F9871998-09-17017 September 1998 Safety Evaluation Accepting 980225 Proposed Rev 26 to Illinois Power Nuclear Program Qam ML20151U1391998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Clinton Power Station,Unit 1 ML20237E3991998-08-27027 August 1998 SER Accepting Licensee Response to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode, for Clinton Power Station ML20237A1521998-08-0707 August 1998 SER Re Mgt Services Agreement at Clinton Power Station. Approval Under 10CFR50.80 Not Required ML20151Y6591998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Clinton Power Station,Unit 1 U-603033, Part 21 Rept 21-98-039 Re Shrinkage of Medium & High Density Silicone Seals Designed & Installed by Bisco Using Dow Corning Sylgard 170 Matl.Caused by Coefficient of Thermal Expansion.Will Inspect & Rework/Repair Suspected Seals1998-07-20020 July 1998 Part 21 Rept 21-98-039 Re Shrinkage of Medium & High Density Silicone Seals Designed & Installed by Bisco Using Dow Corning Sylgard 170 Matl.Caused by Coefficient of Thermal Expansion.Will Inspect & Rework/Repair Suspected Seals U-603041, Monthly Operating Rept for June 1998 for Clinton Power Station,Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Clinton Power Station,Unit 1 ML20151U1501998-06-30030 June 1998 Revised Monthly Operating Rept for June 1998 for Clinton Power Station,Unit 1 U-603023, Monthly Operating Rept for May 1998 for Clinton Power Station,Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Clinton Power Station,Unit 1 U-603014, Special Rept:On 980512,lightning Struck Primary Meteorological Monitoring Instrumentation Tower Damaging 60- Meter Wind Speed & Associated Transmuter Circuit Card. Surveillance Testing Performed1998-05-28028 May 1998 Special Rept:On 980512,lightning Struck Primary Meteorological Monitoring Instrumentation Tower Damaging 60- Meter Wind Speed & Associated Transmuter Circuit Card. Surveillance Testing Performed ML20236E7991998-05-26026 May 1998 Final Part 21 Rept Re W Dhp Circuit Breaker Auxillary Switch Operating Assembly Anomalies.Caused by Loss of Breaker Safety Function.Dhp Circuit Will Be Inspected ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted U-603004, Part 21 Rept Re 980107 Determination That Itt Barton Model 580A Series Differential Pressure Indicating Switches Operating Forces Too Low.Manufacturing Sys Allowed Switches to Be Mixed.Evaluation Concludes Issue Not Reportable1998-05-15015 May 1998 Part 21 Rept Re 980107 Determination That Itt Barton Model 580A Series Differential Pressure Indicating Switches Operating Forces Too Low.Manufacturing Sys Allowed Switches to Be Mixed.Evaluation Concludes Issue Not Reportable ML20216A9601998-05-0808 May 1998 Part 21 Rept Re Failure of 12 Volt DC Inverter Power Supply. Caused by Inadequately Sized Output Transistor Pair Combined W/Degraded Capacitors.Licensee Plans to Replace All Output Transistors & Degraded Capacitors U-602995, Part 21 Interim Rept 21-98-021 Re Deficiencies in Matl Dedication Process Used by Goulds Pumps During Use of Portable Metal Analyzer.Util Identified Discrepancies Which Are Acceptable W/Some Exception of Some Replacement Parts1998-05-0505 May 1998 Part 21 Interim Rept 21-98-021 Re Deficiencies in Matl Dedication Process Used by Goulds Pumps During Use of Portable Metal Analyzer.Util Identified Discrepancies Which Are Acceptable W/Some Exception of Some Replacement Parts U-603006, Monthly Operating Rept for Apr 1998 for Clinton Power Station,Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Clinton Power Station,Unit 1 U-602994, Part 21 Rept Re Final Rept 21-98-008,on 980113,reliance Electric Motors Supplied by Rockwell International for Hydrogen Recombiner Cooling Fans Do Not Have nameplate- Specified High Temperature Bearings.Fan Motors Acceptable1998-04-29029 April 1998 Part 21 Rept Re Final Rept 21-98-008,on 980113,reliance Electric Motors Supplied by Rockwell International for Hydrogen Recombiner Cooling Fans Do Not Have nameplate- Specified High Temperature Bearings.Fan Motors Acceptable ML20216B1351998-04-21021 April 1998 Rev 0 to Illinois Power Co Clinton Power Station SVC Design Rept U-602979, Final Part 21 Rept 21-97-059 Re Discrepancies Found During Receipt Insp of Three Refurbished safety-related W Dhp Circuit Breakers.Util Completed Evaluation,Per 10CFR21 & Concludes That Condition Is Not Reportable1998-04-0707 April 1998 Final Part 21 Rept 21-97-059 Re Discrepancies Found During Receipt Insp of Three Refurbished safety-related W Dhp Circuit Breakers.Util Completed Evaluation,Per 10CFR21 & Concludes That Condition Is Not Reportable U-602976, Monthly Operating Rept for Mar 1998 for Clinton Power Station1998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Clinton Power Station ML20217H5771998-03-27027 March 1998 Safety Evaluation Concluding That No Significant Safety Hazards Introduced at CPS for Net 32% Ampacity Derating Factor for 1 H & 3 H Conduit Fire Barrier Sys & 1 H Cable Tray Fire Barrier Sys.Requests Response Addressing Issue U-602968, Interim Part 21 Rept 21-97-055 Re Westinghouse Dhp Circuit Breaker Auxiliary Switch Operating Assembly Anomalies. Initially Reported on 980116.Util Currently Evaluating Suppliers Response to Questions Re Issue1998-03-24024 March 1998 Interim Part 21 Rept 21-97-055 Re Westinghouse Dhp Circuit Breaker Auxiliary Switch Operating Assembly Anomalies. Initially Reported on 980116.Util Currently Evaluating Suppliers Response to Questions Re Issue U-602960, Part 21 & Deficiency Rept Re Commerical Grade Dedication Program of Sentry Equipment Corp.Initially Reported on 980217.IP Performed an Addl Assessment at Sentry Facility on 980226.Next Rept Will Be Submitted by 9804111998-03-12012 March 1998 Part 21 & Deficiency Rept Re Commerical Grade Dedication Program of Sentry Equipment Corp.Initially Reported on 980217.IP Performed an Addl Assessment at Sentry Facility on 980226.Next Rept Will Be Submitted by 980411 U-602954, Interim Part 21 rept,21-98-008 Re Identification That Bearings Installed in Hydrogen Recombiner B Cooling Fan Motor 0HG04CB Were Not Same as Bearings Specified on Motor Nameplate.Will Complete Evaluation of Issue by 9805131998-03-0909 March 1998 Interim Part 21 rept,21-98-008 Re Identification That Bearings Installed in Hydrogen Recombiner B Cooling Fan Motor 0HG04CB Were Not Same as Bearings Specified on Motor Nameplate.Will Complete Evaluation of Issue by 980513 1999-09-30
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l' p*"49 y \ UNITED STATE 8 o NUCLEAR REGULATORY COMMISSION
. g o, WASHINGTON, D.C. SomeHoot s...../
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION MANAGEMENT SERVICES AGREEMENT AT CLINTON POWER STATION ILLINOIS POWER COMPANY DOCKET NO. 50-461 l
I. BACKGROUND lilinois Power Company (IP) is the holder of Operating License NPF-62 for the Clinton Power Station. By letter dated January 5,1998, Illinois Power informed the NRC that it was entering into a management services agreement with PECO Energy to provide senior management oversight for the Clinton Power Station. Mr. Walter G. MacFarland IV was named Chief Nuclear Officer for Clinton, reporting directly to the Chief Executive Officer and President of Illinois Power.
There were two subsequent conference calls between Illinois Power and NRC staff members on January 12,1998, and March 24,1998, in which details of the service agreement were discussed. By letter dated January 23,1998, Illinois Power forwarded a copy of the draft services agreement and concluded in the cover letter that neither the management services agreement with PECO Energy nor the resulting specific management changes would, in their opinion, require NRC approval. By letter dated April 1,1996, Illinois Power forwarded a copy of the final management services agreement.
During the March 24,1998, conference call, the staff was informed that Mr. MacFarland had -
resigned his PECO corporate officer position and had been named a Vice President of Illinois Power. He remains a PECO employee, although he is an officer of IP as well.
A Clinton Power Station organization chart forwarded to the NRC Project Manager on February 3,1998, identified positions being staffed with PECO personnel. Of the nine managers reporting directly to the Chief Nuclear Officer, Mr. MacFarland, three are to be PECO personnel: the Station Manager, the Maintenance Manager, and the Manager of Work i
Management. Of the four directors reporting to the Station Manager, only one, the Director of Operations, is to be a PECO employee. Another PECO manager will serve as Supervisor of Operations Services and report to the Director of Operations. Of the six supervisors reporting to the Maintenance Manager, only one, the Supervisor of Electrical Maintenance, is to be a PECO employee. Of the four supervisors reporting to the Manager of Work Management, one will be a PECO employee, the Director of Work Coordination. One additional PECO employee will serve as Director of Design Engineering and report to the IP Manager of the Nuclear Station Engineering Department. A total of nine positions are being filled by PECO personnel.
I 9908130132 990807 PDR ADOCK 05000461 l P PDR l
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- 11. ANALYSIS The transfer of licenses is govemed by 10 CFR 50.80, which states that "no license for a production or utilization facility, or any right thereunder, shall be transferred, assigned, or in any manner disposed of, either voluntarily or involuntarily, directly or indirectly, through trar'sier of control of the license to any person, unless the Commission shall give its consent in writing? In
- reviewing license transfers, the Commission must determine whether the proposed tranMree is qualified to be the holder of the license, and whether the license transfer is consistent with applicable provisions of law, regulations, and orders issued by the Commission. ,
l In SECY-g7-304," Response to Staff Requirements Memorandum: SECY-97-144,' Potential Policy 16 sues Raised by Non-Owner Operators," it was noted that various altemative non- 4
- l. owner operator arrangements would be pursued by licensees as utilities evolve under i deregulation. With regard to these new arrangements, the decision on whether consent under 10 CFR 50.80 is necessary depends on the extent to which operating control is being transferred and the degree of autonomy being granted to the operating company.
The service agreement between IP and PECO is similar in certain respects to the Maine Yankee management services agreement with Entergy Nuclear, Inc., signed in early 1997. In its letter of April 1,1998, IP maintained that there was ample regulatory precedent involving l similar arrangements for contract management services to support its conclusion that IP would l in substance remain the licensed operator (as well as owner) of the Clinton facility, maintaining ultimate control over plant operations.
l l During the March 24,1998, conference call with the NRC staff, IP maintained that a new i operating entity was not being created. The service agreement states that PECO management personnel serving at Clinton Station will be treated as employees of IP for operational and functional purposes and will exercise their authority in the IP organization on behalf of, and subject to the direction of, IP senior management. With the Chief Nuclear Officer becoming an officer of IP, the licensee maintains that there is no transfer of authority to PECO.
- . Management personnel from PECO serving at the Clinton station will be receiving technical
!- direction not from senior management back at PECO but from the IP organization. Alllicensed j operators at Clinton will remain solely employees of IP.
During the January 12,1998, conference call with IP, the staff requested confirmation that the management changes proposed under the services agreement would be consistent with the Final Safety Analysis Report licensing bases or that appropriate change requests would be submitted, in its letter of April 1,1998, IP stated that as of that date nine management positions had been filled by PECO employees and none of the management changes required changes to the plant Technical Specifications.
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lli. CONCLUSIONS The determination of whether consent under 10 CFR 50.80 is necessary depends on the extent to which operating controlis being transferred. If a transfer of control under 10 CFR 50.80 is viewed as a transfer of the ultimate authority granted under a license, then it would follow that a licensee who has chosen to hire and use contractors to perform activities under the facility license has not transferred control, as long as the licensee has retained the authority to direct the activities of the contractor, including, for example actions to shut down or start up the reactor, and has the ability to terminate such contract services.
! The staff concludes that notwithstanding the management services agreement between IP and l PECO, IP retains authority and responsibility for the safe operation of the plant and for regulatory compliance. ' In addition, PECO Energy will not be performing activities that would require a license. Approval under 10 CFR 50.00 is therefore not required.
Regardless of whether 10 CFR 50.80 consent is required, a licensee engaging contract service company management personnel must verify that the contract managers meet the requisite qualifications for the positions they are holding, if there is any disparity between the committed / required qualifications for a position and the actual qualifications of the new l
manager (s), then the licensee should pursue the appropriate method to resolve the disparity.
Verification that PECO management personnel meet required educational and experience requirements for the positions they are filling at Clinton will be accomplished via NRC inspection and regulatory programs.
l PrincipalContributor: M. Davis l
I Date: August 7, 1998 l
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