Similar Documents at Perry |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in PNPP to Ceico ML20212A6881999-08-31031 August 1999 Safety Evaluation Supporting Amend 106 to License NPF-58 ML20207G2741999-06-0707 June 1999 Safety Evaluation Concluding That Firstenergy Flaw Evaluation Meets Rules of ASME Code & That IGSCC & Thermal Fatigue Crack Growth Need Not Be Considered in Application ML20206G6451999-05-0303 May 1999 Safety Evaluation Authorizing Requests for Relief IR-032 to IR-035 & IR-037 to IR-040 Re Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp ML20206E2261999-04-29029 April 1999 Safety Evaluation Concluding That Proposed Alternatives Will Result in Acceptable Level of Quality & Safety.Authorizes Use of Code Case N-504 for Weld Overlay Repair of FW Nozzle Weld at PNPP & Use of Table IWB-3514 ML20205P4371999-04-15015 April 1999 Safety Evaluation Concluding That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking or Thermal Binding ML20205G4221999-03-31031 March 1999 Safety Evaluation Accepting Second 10-yr Interval IST Program Releif Requests for Plant,Unit 1 ML20205E0591999-03-26026 March 1999 Safety Evaluation Supporting Amend 105 to License NPF-58 ML20205D6921999-03-26026 March 1999 Safety Evaluation Supporting Amend 104 to License NPF-58 ML20205D3101999-03-26026 March 1999 Safety Evaluation Supporting Amend 103 to License NPF-58 ML20205C3761999-03-26026 March 1999 Safety Evaluation Supporting Request for Proposed Exemption to 10CFR50,app a GDC 19 ML20204C0711999-03-11011 March 1999 Safety Evaluation Supporting Amend 102 to License NPF-58 ML20207F4361999-03-0303 March 1999 Safety Evaluation Supporting Amend 101 to License NPF-58 ML20207L4881999-02-24024 February 1999 Safety Evaluation Supporting Amend 100 to License NPF-58 ML20203F8381999-02-0808 February 1999 Safety Evaluation Supporting Amend 97 to License NPF-58 ML20203A5961999-02-0202 February 1999 Safety Evaluation Accepting Licensee Proposed Revs to Responsibilities of Plant Operations Review Committee as Described in Chapter 17.2 of USAR ML20203A5211999-01-27027 January 1999 Safety Evaluation Accepting Licensee Calculations Showing That Adequate NPSH Will Be Available for HPCS Pumps ML20198R8921999-01-0707 January 1999 SER Accepting Licensee Proposed Amend to TSs to Delete Reference to NRC Policy Re Plant Staff Working Hours & Require Administrative Controls to Limit Working Hours to Be Acceptable ML20198J0031998-12-22022 December 1998 SER Accepting Licensee Response to GL 92-08,ampacity Derating Issues for Perry Nuclear Power Plant,Unit 1 ML20198K9071998-12-21021 December 1998 Safety Evaluation Supporting Amend 96 to License NPF-58 ML20196J4731998-12-0202 December 1998 Safety Evaluation Supporting Amend 95 to License NPF-58 ML20196D2751998-11-23023 November 1998 Safety Evaluation Supporting Amend 94 to License NPF-58 ML20195F6891998-11-0505 November 1998 Safety Evaluation Accepting Proposed Reduction in Commitment in Quality Assurance Program to Remove Radiological Assessor Position ML20153B8221998-09-16016 September 1998 Safety Evaluation Accepting Changes to USAR Section 13.4.3, 17.2.1.3.2.2,17.2.1.3.2.2.3 & App 1A ML20153D0311998-09-15015 September 1998 Safety Evaluation Supporting Amend 93 to License NPF-58 ML20249A1891998-06-11011 June 1998 SER on Moderate Energy Line Pipe Break Criteria for Perry Nuclear Power Plant,Unit 1 & Requests Addl Info to Demonstrate That Plant & FSAR in Compliance W/Staff Position & GDC as Discussed in SER ML20217D2051998-04-20020 April 1998 SER Authorizing Licensee to Use Code Case N-524 Until Such Time as Code Case Included in Future Rev of RG 1.147 ML20216G4711998-03-12012 March 1998 Safety Evaluation Supporting Amend 92 to License NPF-58 ML20216G3901998-03-11011 March 1998 SER on Proposed Merger Between Duquesne Light Co & Allegheny Power Sys,Inc ML20199C0471997-11-0707 November 1997 Safety Evaluation Supporting Amend 91 to License NPF-58 ML20199B2351997-11-0404 November 1997 Safety Evaluation Supporting Amend 90 to License NPF-58 ML20217E2051997-09-24024 September 1997 Safety Evaluation Supporting Amend 89 to License NPF-58 ML20211H6791997-09-18018 September 1997 Safety Evaluation Authorizing Licensees Request for Alternative from Augmented Insp of Reactor Pressure Vessel Circumferential Weld in Plant,Unit 1 ML20217B2601997-09-11011 September 1997 Safety Evaluation Supporting Amend 87 to License NPF-58 ML20211A5881997-09-11011 September 1997 Safety Evaluation Supporting Evaluation of First 10-yr Interval ISI Program Plan Requests for Relief PT-004,PT-005 & PT-006 for Plant,Unit 1 ML20217K9061997-08-12012 August 1997 Safety Evaluation Accepting Plant First 10-yr Interval ISI Program Plan Relief Request PT-007 ML20141C0081997-06-19019 June 1997 Safety Evaluation Approving Merger Agreement Between Centerior Energy Corp & Ohio Edison Co Affecting NPF-58 ML20141L9131997-05-27027 May 1997 Safety Evaluation Accepting Relief Requests for First 10-yr Interval Inservice Insp Program Plan for Plant,Unit 1 ML20147H4211997-04-0101 April 1997 Safety Evaluation Accepting Changes to USAR Sections,Which Continue to Satisfy Criteria of App B of 10CFR50 ML20134D1061997-01-27027 January 1997 Safety Evaluation on Revised EALs for Plant.Proposed EALs Changes Are Consistent W/Guidance in NUMARC/NESP-007,with One Exception,& Meets Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20114E4561996-06-18018 June 1996 Safety Evaluation Supporting Amend 85 to License NPF-58 ML20101G8351996-03-22022 March 1996 Safety Evaluation Supporting Amend 84 to License NPF-58 ML20100R1171996-02-27027 February 1996 Safety Evaluation Supporting Amend 81 to License NPF-58 ML20101G0761996-01-20020 January 1996 Corrected SE Supporting Amend 79 to License NPF-58. Inaccuracies in Description of Changes Has Been Corrected ML20100C8031996-01-19019 January 1996 Safety Evaluation Supporting Amend 78 to License NPF-58 ML20095G0201995-12-0808 December 1995 Safety Evaluation Supporting Amend 76 to License NPF-58 ML20095A5401995-11-29029 November 1995 Safety Evaluation Supporting Amend 75 to License NPF-58 ML20092N0611995-09-26026 September 1995 Safety Evaluation Supporting Amend 73 to License NPF-58 ML20092J1451995-09-15015 September 1995 Safety Evaluation Supporting Amend 72 to License NPF-58 ML20086C1551995-06-27027 June 1995 Safety Evaluation Supporting Amend 70 to License NPF-58 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000440/LER-1999-004, :on 990916,loss of Safety Function Resulted in TS 3.0.3 Entry.Caused by Design Deficiency in Control Complex Architectural Walls.Revised Storm Contingencies Instructions.With1999-10-18018 October 1999
- on 990916,loss of Safety Function Resulted in TS 3.0.3 Entry.Caused by Design Deficiency in Control Complex Architectural Walls.Revised Storm Contingencies Instructions.With
ML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & PNPP QA Program ML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in PNPP to Ceico PY-CEI-NRR-2437, Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With 05000440/LER-1999-003-01, :on 990218,post-accident Dose Limits Were Exceeded.Caused by Relief Valve Leakage Outside of Containment.Removed Relief Valve on 990913,by Design Change Package Implemented Under 10CFR50.59.With1999-09-27027 September 1999
- on 990218,post-accident Dose Limits Were Exceeded.Caused by Relief Valve Leakage Outside of Containment.Removed Relief Valve on 990913,by Design Change Package Implemented Under 10CFR50.59.With
PY-CEI-NRR-2429, Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With ML20212A6881999-08-31031 August 1999 Safety Evaluation Supporting Amend 106 to License NPF-58 PY-CEI-NRR-2424, Monthly Operating Rept for July 1999 for Perry Npp.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Perry Npp.With ML20210J3851999-07-28028 July 1999 PNPP - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval PY-CEI-NRR-2416, Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With ML20196A1951999-06-17017 June 1999 Instrument Drift Analysis ML20207G2741999-06-0707 June 1999 Safety Evaluation Concluding That Firstenergy Flaw Evaluation Meets Rules of ASME Code & That IGSCC & Thermal Fatigue Crack Growth Need Not Be Considered in Application PY-CEI-NRR-2409, Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2393, Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored1999-05-12012 May 1999 Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored ML20206G6451999-05-0303 May 1999 Safety Evaluation Authorizing Requests for Relief IR-032 to IR-035 & IR-037 to IR-040 Re Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp PY-CEI-NRR-2399, Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With ML20206E2261999-04-29029 April 1999 Safety Evaluation Concluding That Proposed Alternatives Will Result in Acceptable Level of Quality & Safety.Authorizes Use of Code Case N-504 for Weld Overlay Repair of FW Nozzle Weld at PNPP & Use of Table IWB-3514 05000440/LER-1999-002-01, :on 990327,RHR a Pump Failed to Start & LCO 3.0.3 Was Entered Due to TS Bases Misinterpretation.Caused by Failed Optical Isolator That Provided Signal to Pump Start Permissive Circuitry.Subject Circuitry Was Replaced1999-04-26026 April 1999
- on 990327,RHR a Pump Failed to Start & LCO 3.0.3 Was Entered Due to TS Bases Misinterpretation.Caused by Failed Optical Isolator That Provided Signal to Pump Start Permissive Circuitry.Subject Circuitry Was Replaced
ML20206D7911999-04-23023 April 1999 Rev 6 to PDB-F0001, COLR for Pnpp Unit 1 Cycle 8,Reload 7 05000440/LER-1999-001-01, :on 990317,discovered That Control Complex Bldg Architectural Walls Were Not Included in Tornado Dp Loading Design.Caused by Failure to Consider Tornado Dp Loads. Compensatory Measures Were Implemented.With1999-04-16016 April 1999
- on 990317,discovered That Control Complex Bldg Architectural Walls Were Not Included in Tornado Dp Loading Design.Caused by Failure to Consider Tornado Dp Loads. Compensatory Measures Were Implemented.With
ML20205P4371999-04-15015 April 1999 Safety Evaluation Concluding That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking or Thermal Binding ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected PY-CEI-NRR-2389, Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With ML20205G4221999-03-31031 March 1999 Safety Evaluation Accepting Second 10-yr Interval IST Program Releif Requests for Plant,Unit 1 ML20206D8461999-03-31031 March 1999 Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7 Cycle 8 ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205E0591999-03-26026 March 1999 Safety Evaluation Supporting Amend 105 to License NPF-58 ML20205D3101999-03-26026 March 1999 Safety Evaluation Supporting Amend 103 to License NPF-58 ML20205D6921999-03-26026 March 1999 Safety Evaluation Supporting Amend 104 to License NPF-58 ML20205C3761999-03-26026 March 1999 Safety Evaluation Supporting Request for Proposed Exemption to 10CFR50,app a GDC 19 ML20204C0711999-03-11011 March 1999 Safety Evaluation Supporting Amend 102 to License NPF-58 ML20207F4361999-03-0303 March 1999 Safety Evaluation Supporting Amend 101 to License NPF-58 PY-CEI-NRR-2369, Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 9902271999-03-0303 March 1999 Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 990227 PY-CEI-NRR-2372, Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With ML20207L4881999-02-24024 February 1999 Safety Evaluation Supporting Amend 100 to License NPF-58 ML20203F8381999-02-0808 February 1999 Safety Evaluation Supporting Amend 97 to License NPF-58 ML20203A5961999-02-0202 February 1999 Safety Evaluation Accepting Licensee Proposed Revs to Responsibilities of Plant Operations Review Committee as Described in Chapter 17.2 of USAR ML20203A5211999-01-27027 January 1999 Safety Evaluation Accepting Licensee Calculations Showing That Adequate NPSH Will Be Available for HPCS Pumps ML20198R8921999-01-0707 January 1999 SER Accepting Licensee Proposed Amend to TSs to Delete Reference to NRC Policy Re Plant Staff Working Hours & Require Administrative Controls to Limit Working Hours to Be Acceptable ML20206B0101998-12-31031 December 1998 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 PY-CEI-NRR-2356, Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With ML20198J0031998-12-22022 December 1998 SER Accepting Licensee Response to GL 92-08,ampacity Derating Issues for Perry Nuclear Power Plant,Unit 1 ML20198K9071998-12-21021 December 1998 Safety Evaluation Supporting Amend 96 to License NPF-58 ML20196J4731998-12-0202 December 1998 Safety Evaluation Supporting Amend 95 to License NPF-58 PY-CEI-NRR-2346, Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With ML20196D2751998-11-23023 November 1998 Safety Evaluation Supporting Amend 94 to License NPF-58 ML20195F6891998-11-0505 November 1998 Safety Evaluation Accepting Proposed Reduction in Commitment in Quality Assurance Program to Remove Radiological Assessor Position 05000440/LER-1998-003, :on 981001,missed TS SR on H Igniters Was Noted.Caused by Personnel Error.Missed Surveillance Was Performed on Day of Discovery of Item & Function of H Igniters Were Verified.With1998-11-0202 November 1998
- on 981001,missed TS SR on H Igniters Was Noted.Caused by Personnel Error.Missed Surveillance Was Performed on Day of Discovery of Item & Function of H Igniters Were Verified.With
PY-CEI-NRR-2335, Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With 1999-09-30
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30E06 4001 p
1 j
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION 1
l RELATED TO AMENDMENT NO. 96 TO FACILITY OPERATING LICENSE NO. NPF-58
)
,9LEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL.
l PERRY NUCLEAR POWER PLANT. UNIT 1 i
I DOCKET NO. 50-440 l
1 1.0.
INTRODUCTION
(
By letter dated June 30,1998, and as supplemented by submittals dated October 27,
)
November 30, and December 3,1998, The Cleveland Electric illuminating Company and the Centerior Service Company requested approval of the transfer of operating authority under Facility Operating License No. NPF-58 for the Perry Nuclear Power Plant, Unit 1 (PNPP), to a new company, FirstEnergy Nuclear Operating Company (FENOC), and issuance of a i
conforming amendment, pursuant to 10 CFR 50.80 and 50.90. By Order Approving Application j
Regarding the Transfer of Operating Authority, issued on December 2,1998, the U.S. Nuclear Regulatory Commission (NRC) consented to the transfer of the license to FENOC, with respect to authority to operate the facility, on the basis of the findings discussed in the Order. The Order
}
allows FENOC to use and operate PNPP and to possess and use related licensed nuclear materials in accordance with the same conditions and authorizations included in the current operating license. The proposed license amendment would make changes to reflect the i
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transfer of operating authority, including removing the Centerior Service Company from the license. In addition, the proposed amendment would delete certain sections of the license that relate solely to historical events that have long since occurred, and that therefore have no
/
l practical effect or purpose.
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j The supplemental information contained clarifying information and did not change the initial no significant hazards consideration determination and did not expand the scope of the original J
application.
j 2.0 EVALUATION For administrative purposes, there is a need to amend the license to reflect the implementation i
of the approved transfer. References to Centerior Service Company are being removed as they
. are no longer applicable. FirstEnergy Nuclear Operating Company is being added to reflect its status as a licensee, plant operator, and as the agent acting for the owners. References to j
" Cleveland Electric illuminating Company" as an operator are being replaced by references to j
' FENOC. Changes to the antitrust license conditions to account for FENOC's existence are also being made. in addition, as mentioned above, several administrative changes, unrelated to the approved transfer, are being made to delete certain sections of the license that relate solely to O M 44o PDR 4
4 E.
e-AIe e-1r v -
7
"~ ' '
o 2
historical events that have long since occurred, and that therefore have no practical effect or purpose. Finally, format changes are being made for clarification. Each change is described below.
2.1 Title The heading is being revised by adding the FirstEnergy Nuclear Operating Company and deleting Centerior Service Company 2.2 Paraaraoh 1 A Centerior Service Company is being deleted and the FirstEnergy Nuclear Operating Company (FENOC) is being added. In addition, the associated footnote is being replaced with the following:
FENOC is authorized to act as agent for Duquesne Light Company, Ohio Edison Company, OES Nuclear, Inc., Pennsylvania Power Company, the Toledo Edison Company, and The Cleveland Electric illuminating Company, and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.
2.3 Paraaraoh 1.E Replaces the reference to The Cleveland Electric illuminating Company with The FirstEnergy Nuclear Operating Company.
2.4 Paraaraoh 2 Replaces the reference to Centerior Service Company with FirstEnergy Nuclear Operating Company.
2.5 Paraaraoh 2 B(1)
Replaces the reference to The Cleveland Electric illuminating Company (CEICO) with FENOC and deletes the associated footnote.
2.6 Paraaraoh 2.B(2) i CEICO is being added to reflect its status as a non-operating owner, in light of its deletion from Paragraph 2.B(1).
2.7 Paraaraoh 2.B(3)
The reference to CEICO is being replaced with FENOC.
l
.+4..
.A
+s_w e
a i
. 3-2.8 Paraaraoh 2.B(4) i The reference to CEICO is being replaced with FENOC.
i i
2.9 Paraarsoh 2.B(5)
The reference to CEICO is being replaced with FENOC.
2.10 Parsaraoh 2.B(6)
The reference to CEICO is being replaced with FENOC.
2.11 Paraaraoh 2.C(1)
The reference to CEICO is being replaced with FENOC.
2.12 P_aragraoh 2.C(2)
The reference to The Cleveland Electric illuminating Company is being replaced with FENOC.
l 2.13 Paraaraoh 2.C(3)(b)
The paragraph is revised to read as follows:
FENOC shall comply with the antitrust conditions delineated in Appendix C to this license as if named therein. FENOC shall not market or broker power or energy from the Perry Nuclear Power Plant, Unit No.1. The Owners are responsible and accountable for the actions of FENOC to the extent that said actions affect the marketing or brokering of power or energy from the Perry Nuclear Power Plant, Unit No.1, and in any way, contravene the antitrust coaditions contained in the license.
2.15 Paraaraoh 2.C(4)
This license condition, dealing solely with the initial Test Program, which has long been completed, is being deleted.
2.16 Paraaraoh 2.C(5)
This license condition, which deals with submitting the Initial inservice inspection Program, has long been satisfied and is being deleted.
2.17 Paraaraoh 2.Cf6) and 2.C(6)(a)
The references to CEICO are being replaced with FENOC.
t
2.18 Paraaraoh 2.C(7)
This license condition, which deals with the Detailed Control Room Design Review, has long been satisfied and is being deleted. Updated Safety Evaluation Report Appendix 1.B, item 8, provides the history of complying with this requirement.
2.19 Paraaraoh 2.C(8)
This license condition, which deals with the Federal Emergency Management Agency's (FEMA) review of emergency planning procedures, has been satisfied for several years and is being deleted. FEMA's letter of June 17,1994, documented that its review was complete.
2.20 Paraaraoh 2.D The reference to CEICO is being replaced with FENOC.
2.21 Paraaraoh 2.E The reference to CEICO is being replaced with FENOC.
2.22 Earaaraoh 2.F The reference to CEICO is being replaced with FENOC.
2.23 to NPF-58. " Detailed Control Room Desian Review" As described in item 2.18 above, the Detailed Control Room Design Review was completed several years ago; thus, this attachment is being deleted.
2.24 Accendix A Cover Pace The reference to Cleveland Electric illuminating Company is being replaced with a reference to the FirstEnergy Nuclear Operating Company.
2.25 Appendix B Cover Paae The reference to Cleveland Electric lfuminating Company is being replaced with a reference to the FirstEnergy Nuclear Operating Company.
2.26 Summary These changes do no more than conform the license to reflect the approved transfer, and thus are essentially administrative in nature. In consideration of the foregoing, the staff finds the amendment acceptable.
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3 o
3.0 STATE CONSULTATION
in accordance with the Commission's regulations, the Ohio State official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
Pursuant to 10 CFR 51.21 and 51.35, an environmental assessment and finding of no significant impact was published in the Federal Reaister on September 10,1998 (63 FR 48531).
5.0 CONCLUSION
The staff has concluded on the basis of the considerations discussed above that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Douglas V. Pickett Date: December 21, 1998
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