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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212F5641999-09-23023 September 1999 SER Concluding That All of ampacity-related Concerns Have Been Resolved & Licensee Provided Adequate Technical Basis to Assure That All of Thermo-Lag Fire Barrier Encl Cables Operating within Acceptable Ampacity Limits ML20196K4981999-07-0101 July 1999 Safety Evaluation Authorizing PRR-E12-01,PRR-E21-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01.Concludes That Alternatives Proposed by EOI Acceptable ML20202J0181999-02-0303 February 1999 SER Accepting Changes in Quality Assurance Program,Which Continues to Meet Requirements of App B to 10CFR50 ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program 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 ML20217Q6701998-05-0606 May 1998 SER Approving Proposed Postponement of Beginning Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) at Grand Gulf for Circumferential Shell Welds for Two Operating Cycles ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) ML20217P0381998-04-0606 April 1998 Safety Evaluation Supporting Amend 135 to License NPF-29 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 ML20216J4211998-03-18018 March 1998 SER Approving Alternative to Insp of Reactor Pressure Vessel Circumferential Welds for Grand Gulf Nuclear Station ML20199F6751998-01-26026 January 1998 Safety Evaluation Accepting 971209 Proposed Change to CPS USAR Which Will Impact Commitments Made in CPS QAP Description ML20199H3711997-11-19019 November 1997 SER Accepting Approving Request Relief from Requirements of Section XI, Rule for Inservice Insp of NPP Components, of ASME for Current or New 10-year Inservice Insp Interval IAW 50.55(a)(3)(i) of 10CFR50 ML20199F3431997-11-18018 November 1997 SER Accepting Rev 15 of Operational Quality Assurance Manual for Grand Gulf Nuclear Station,Unit 1 ML20216E9921997-09-0404 September 1997 Safety Evaluation Accepting 970623 Request for Relief Re Authorization for Use of ASME Code Case N-416-1 & N-532,ISI Program for Listed Plants ML20141K6321997-05-27027 May 1997 Safety Evaluation Accepting Relief Requests for Inservice Testing Program for Plant ML20134C5671997-01-30030 January 1997 SER Denying Request for Exemption from 10CFR50.55a Entergy Operating,Inc Et Al,Grand Gulf Nuclear Station,Unit 1 ML20149M4221996-12-12012 December 1996 Safety Evaluation Supporting Update Insvc Insp Programs to 1992 & Portions of 1993 ASME Boiler & Pressure Vessel Code, Sect XI for Licenses DPR-51,NPF-6,NPF-38,NPF-29 & NPF-47. Technical Ltr Rept Encl ML20138B5681996-12-11011 December 1996 Safety Evaluation Re Emergency Plan Change 28.001-95 to Entergy Operations,Inc,Grand Gulf Nuclear Station ML20135D1191996-12-0404 December 1996 Safety Evaluation of First Ten Year Interval Inservice Inspection Program Plan for Illinois Power Co,Clinton Power Station ML20134K5321996-11-18018 November 1996 Safety Evaluation Supporting Request for Relief Re 10CFR50.55a Inservice Testing of Main Steam Safety/Relief Valves for License NPF-29 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 ML20129D0441996-10-22022 October 1996 Safety Evaluation Supporting Request for Relief I-00014 ML20129B8751996-10-18018 October 1996 Safety Evaluation Accepting First 10-year Interval ISI Program Plan Addl Request for Relief ML20128H2491996-10-0707 October 1996 Safety Evaluation Authorizing Licensee Proposed Alternative to Use ASME Code Case N-508-1 for Rotation of Serviced Snubbers & Pressure Relief Valves for Sole Purpose of Testing in Lieu of ASME Requirements ML20107F5611996-04-17017 April 1996 Safety Evaluation Providing Guidance on Submitting plant- Specific Info W/Respect to IST Program Alternatives Request ML20128N1381993-02-17017 February 1993 Safety Evaluation Accepting Proposal to Raise Design Ground Water Level from 109 Ft Above Msl to 114.5 Ft Above Msl 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 ML20058B4411990-10-25025 October 1990 Safety Evaluation Granting 900709 Request for Relief from Requirements for Leakage Testing of RCS in ASME Code,Section XI ML20062A1941990-10-16016 October 1990 Safety Evaluation Granting Relief Request from Inservice Insp Requirements ML20059N4971990-10-0101 October 1990 Safety Evaluation Accepting Util Response to Generic Ltr 88-01,w/listed Exceptions 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 ML20058N3941990-08-0606 August 1990 Generic SER Re Mark III Containment Hydrogen Control, Concluding That HGN-112-NP, Generic Hydrogen Control Info for BWR-6 Mark III Containments Provides Acceptable Basis for Technical Resolution of Degraded Core Hydrogen Issue ML20055G5271990-07-18018 July 1990 Safety Evaluation Re Facility Procedures Generation Package. Util Needs to Revise Package to Address Programmatic Improvements Identified ML20055G0341990-07-16016 July 1990 Safety Evaluation Re Boraflex Gaps in Spent Fuel Racks. Storage Racks Can Safely Accomodate Max Reactivity of Unit 1 Cycle 1 Through Cycle 4 Fuel.Storage Rack Surveillance Program Acceptable for long-term Storage of Spent Fuel ML20055F9081990-07-16016 July 1990 Safety Evaluation Accepting Criticality Analysis for Cycle 5 Fuel in Spent Fuel Storage Racks ML20246D8021989-08-21021 August 1989 Safety Evaluation Granting 880524 Requests for Relief from Certain Requirements of ASME Code,Section XI 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 ML20247G7041989-07-21021 July 1989 SER Accepting Licensee Commitment to Install ex-core Neutron Flux Monitoring Instrumentation Meeting Requirements of Reg Guide 1.97,Rev 2,prior to Restart Following Fourth Refueling Outage 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 ML20245A8251989-04-17017 April 1989 SER Re Proposed Changes to Administrative Controls Section of Tech Specs Concerning Min Shift Crew Composition,Unit Staff Qualifications,Training,Plant Safety Review Committee & Safety Review Committee Composition.Changes Unacceptable ML20244D5291989-04-14014 April 1989 Safety Evaluation Supporting Util Actions in Response to Generic Ltr 83-28,Position 4.5.2, Testing of Reactor Trip Sys. Justification for Not Testing Reactor Mode Switch or Backup Scram Valves Provided ML20244C5671989-04-10010 April 1989 Safety Evaluation Supporting Amend 21 to License NPF-62 ML20248J9001989-04-0505 April 1989 Safety Evaluation Accepting Licensee Statements Confirming That Vendor Interface Program Exists W/Nsss Vendor for Components Required for Performance of Reactor Trip Function ML20247E8831989-03-27027 March 1989 Safety Evaluation Supporting Amend 20 to License NPF-62 1999-09-23
[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 ML20217F9921999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20212F5641999-09-23023 September 1999 SER Concluding That All of ampacity-related Concerns Have Been Resolved & Licensee Provided Adequate Technical Basis to Assure That All of Thermo-Lag Fire Barrier Encl Cables Operating within Acceptable Ampacity Limits 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 ML20211Q3171999-09-0909 September 1999 Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20216E4881999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Grand Gulf Nuclear Station.With 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 ML20211A6921999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20211C9621999-07-26026 July 1999 ISI Summary Rept ML20209J1961999-07-12012 July 1999 Special Rept 99-001:on 990528,smoke Detectors Failed to Alarm During Performance of Routine Channel Functional Testing.Applicable TRM Interim Compensatory Measure of Establishing Roving Hourly Fire Patrol Was Implemented 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 ML20196K4981999-07-0101 July 1999 Safety Evaluation Authorizing PRR-E12-01,PRR-E21-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01.Concludes That Alternatives Proposed by EOI Acceptable ML20209G0691999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Grand Gulf Nuclear Station,Unit 1.With 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 ML20196A1161999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Grand Gulf Nuclear 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 ML20206Q4831999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Grand Gulf Nuclear Station Unit 1.With ML20206J1201999-04-30030 April 1999 Redacted ME-98-001-00, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators 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 ML20205P8771999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Grand Gulf Nuclear Station,Unit 1.With 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 ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207K5141999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Grand Gulf Nuclear Station,Unit 1.With 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 ML20206T7991999-01-31031 January 1999 Iodine Revolatizitation in Grand Gulf Loca ML20206D7721998-12-31031 December 1998 South Mississippi Electric Power Association 1998 Annual Rept ML20207A8301998-12-31031 December 1998 1998 Annual Operating Rept for Ggns,Unit 1 ML20206R9501998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Grand Gulf Nuclear Station,Unit 1.With 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 ML20198E2481998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Grand Gulf Nuclear 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 ML20195F4121998-11-13013 November 1998 Rev 16 to GGNS-TOP-1A, Operational QA Manual (Oqam) ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program ML20195C2791998-11-0505 November 1998 BWR Feedwater Nozzle Inservice Insp Summary Rept for GGNS, NUREG-0619-00006 ML20195F4801998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Grand Gulf Nuclear Station,Unit 1.With 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 ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual 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 1999-09-09
[Table view] |
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.'n UNITED STATES
! "k NUCLEAR REGULATORY COMMISSION
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49 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 25 TO FACILITY OPERATING LICENSE NO. NPF-62 CLINTON POWER STATION, UNIT N0. 1 ILLIN0IS POWER COMPANY, ET AL.
DOCKET NO. 50-461
1.0 INTRODUCTION
By letter dated May 18, 1988, the Illinois Power Company (IP), et al. (the licensees) requested an amendnent to facility Operating License No. NPF-62 for the Clinton Power Station, Unit 1. The proposed amendment would revise Technical Specification Table 3.3.2-1 to add a note providing additional information regarding the channel configuration for the Main Steam Line (MSL)
Turbine Building Temperature - High trip channels. These channels provide for automatic isolation of the main steam lines.
2.0 EVALUATION The MSL Turbine Building Temperature sensors are arranged such that five areas are monitored with four temperature sensors in each area. Each of the four temperature sensors in a particular area is associated with a separate division. (The "A" sensor is associated with Division I, the "B" sensor is associated with Division II, the "C" sensor is associated with Division III, and the "D" sensor is associated with Division IV.) Each sensor (thermocouple) provides a signal to a temperature module (trip unit). The relay contacts associated with the temperature modules within a particular division are connected in series. Thus, there are four divisional strings (channels) of l temperature mocules with five temperature modules in each string (channel).
If any temperature racdule is tripped within a channel, then a trip occurs for thbt division. A channel is considered inoperable if one or more temperature modules ond/or sensors within that channel is inoperable. Each channel provides input into each of four two-out-of-four logics. It therefore requires a trip from at least two divisions (i.e., channels) to initiate a nain steem line isolation (MSIV closure).
The ACTIONS and OPERABILITY requirements for the MSL isolation instrumentation of Specification 3.3.2 are structured in accordance with the any-two-from-four sensor logic scheme. Thus, four channels are assumed and each channel is associated with one of four divisions. Since there are 20 sensors associated with the Main Steam Line Turbine Building trip system, the licensee has proposed adding a note to Table 3.3.2-1 to clarify this configuration with the four channel format. The proposed note would read as follows: )
Each channel consists of five temperature modules and their associated sensors. A channel is OPERABLE if and only if five temperature modules and their associateo sensors are OPERABLE.
8908230415 890817 4 PDR ADOCK 05000461 i P PDC
l
- - <. - 4 i
-E-This r.ote is intended to clerify the OPERABILITY requirements for the Main Steam Line Turbine Building Temperature channels, thus, eliminating any confusion regarding compliance with the Limiting Condition for Operation and the associated ACTIONS.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment only involves a change in surveillance requirements for the facility. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents 4 that may be relcased offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Comir.ission has 4
-previously issued a proposed finding that this amendment involves no significant lj hazards consideration and there has been no public comment on such finding, Accordingly, this amendment meets the eligibility criteria for categorical exclusionsetforthin10CFR51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be
-prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
f The proposed change to Technical Specification Table 3.3.2-1 to add a note
-providine additieral information regarding the channel configuration for the
. Main Steam Line (MSL) Turbine Building Temperature - High trip channels is acceptable. . The note is consistent with the design and function of the system and woulc provide clarification for the operations staff. The intent of the I existing Technical Specification would remain unchanged.
The NRC staff has concluced, based on the considerations discussed above, that: 1 (1) there is reasonable assurance that the health arid safet not be endangered by operation in the proposeo manner,such (2) yactivities of the public will will be conducted in complicnce with the Commission's regulations and, (3) the issuance of this amendment will r.ot be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: John B. Hickraan, NRR/PDIII-2 L
l l Dated. August 17, 1989 l
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. s ,9 - .
j 7 August 17, 1989 Docket No. 50-461L DISTRIBUTION Docket tile NRC & Local PDRs
. PDIII-2 r/f MVirgilio Mr. Dale L. Holtzscher LLuther JHickman
- Acting Manager - Licensing and Safety OGC DHagan
'Clinton Power Station '
EJordan TMeek (4)
P. O. Box 678 WJones . JCalvo
, ~ Mail Code'V920 ACRS(10) GPA/PA Clinton, Illinois 61727 OC/LFMB Plant file
Dear Mr. Holtzscher:
SUBJECT:
TECHNICAL SPECIFICATION CHANGE REQUEST TO ADD A NOTE REGARDING THE CHANNEL CONFIGURATION FOR THE MAIN STEAM
., LINE TURBINE BUILDING TEMPERATURE TRIP CHANNELS (TACNO.69550)
RE: Clinton Power Station, Unit No. 1 The Commission has issued the enclosed Amendment No. 25 to Facility Operating License No. NPF-62 for the Clinton Power Station, Unit No. 1. This amendment consists of. changes to the Technical Specifications (TSs) in response to your application dated May 18, 1988.' l l
This amendment revises Technical Specification Table 3.3.2-1 to add a note providing additional information regarding the channel configuration for the MainSteamLine(MSL)TurbineBuildingTemperature-Hightripchannels.
' A copy of our Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/s/ j John B. Hickman, Project Manager Project Directorate III-2 Division of Reactor Projects III, IV, V, and Special Projects Office of liuclear Reactor Regulation
Enclosures:
- 1. Amendment No. 25 to License No. NFF-62
- 2. Safety Evaluation -
.cc w/ enclosures:
See next page NW PDIII-2:LA DIII-2:PM OGCy LLuther:dmjg JHickman [PDlII-2:(
v A)PD PShemanski 7/J //89 7/#8/89 7/31 /89 7/ } /89
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