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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212J1891999-10-0101 October 1999 Safety Evaluation Supporting Exemption from 10CFR54.17(c)re Schedule to Apply for Renewed Operating Licenses ML20212G2511999-09-22022 September 1999 Safety Evaluation Supporting Amends 180 & 172 to Licenses NPF-35 & NPF-52,respectively ML20211A9791999-08-20020 August 1999 Safety Evaluation Granting Licensee Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section Xi,For Plant,Unit 2 ML20210U8341999-08-13013 August 1999 Safety Evaluation Supporting Amends 179 & 171 to Licenses NPF-35 & NPF-52,respectively ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20206P5201999-05-14014 May 1999 Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20205S5551999-04-21021 April 1999 Safety Evaluation Accepting Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20205N3651999-04-12012 April 1999 Safety Evaluation Accepting IPE of External Events Submittal ML20205N2381999-04-0909 April 1999 Safety Evaluation Supporting Amends 178 & 170 to Licenses NPF-35 & NPF-52,respectively ML20205B3101999-03-26026 March 1999 Safety Evaluation Supporting Amends 176 & 168 to Licenses NPF-35 & NPF-52,respectively ML20206R8381999-01-14014 January 1999 Safety Evaluation Supporting Amends 174 & 166 to Licenses NPF-35 & NPF-52,respectively ML20196J8351998-12-0808 December 1998 Safety Evaluation Granting Relief Request Re Relief Valves in Diesel Generator Fuel Oil Sys ML20196C0251998-11-27027 November 1998 SER Accepting Clarification on Calibration Tolerances on Trip Setpoints for Catawba Nuclear Station ML20196A6881998-11-25025 November 1998 Safety Evaluation Granting Relief Request 98-02 Re Limited Exam for Three Welds ML20238F6181998-08-28028 August 1998 Safety Evaluation Supporting Amends 170 & 162 to Licenses NPF-35 & NPF-52,respectively ML20237E0691998-08-25025 August 1998 Safety Evaluation Supporting Amends 169 & 161 to Licenses NPF-35 & NPF-52,respectively ML20237E1421998-08-25025 August 1998 Safety Evaluation Supporting Amends 168 & 160 to Licenses NPF-35 & NPF-52,respectively ML20236M5951998-07-0909 July 1998 Safety Evaluation Supporting Amends 167 & 159 to Licenses NPF-35 & NPF-52,respectively ML20236K3911998-07-0606 July 1998 Safety Evaluation Accepting Relocation of TS Administrative Control Requirement to Licensee QA Program ML20249B0471998-06-17017 June 1998 Safety Evaluation Supporting Amends 166 & 158 to Licenses NPF-35 & NPF-52,respectively ML20247M0861998-05-21021 May 1998 SER Accepting 1997 Rev to Catawba UFSAR Submitted on 970925. Rev Added Analysis for Postulated Accident Involving Dropping of Sf Pool Weir Gate Onto Sf Assemblies ML20217K6961998-04-27027 April 1998 Safety Evaluation Supporting Amends 165 & 157 to Licenses NPF-35 & NPF-52,respectively ML20217K5731998-04-23023 April 1998 Safety Evaluation Supporting Amends 164 & 156 to Licenses NPF-35 & NPF-52,respectively ML20216E1771998-04-13013 April 1998 Safety Evaluation Accepting Relief Request 98-01 for Catawba Nuclear Station Units 1 & 2 from Requirements of ASME Boiler & PV Code for Second 10-year Interval Program for Inservice Testing of Pumps & Valves ML20217M4211998-04-0303 April 1998 Safety Evaluation Approving Request for Relief 97-04, non-code Repair Valves.Relief Granted Retroactively to Unit 1 & Expired Dec 1997.Relief for Unit 2 Will Expire at End of Cycle 9 Outage or Next Scheduled Outage Exceeding 30 Days ML20197A6331998-03-0202 March 1998 Safety Evaluation Supporting Amends 163 & 155 to Licenses NPF-35 & NPF-52,respectively ML20199A6421998-01-22022 January 1998 Safety Evaluation Accepting Proposed EALs Changes for Plant, Units 1 & 2.Concludes That Changes Consistent W/Guidance in NUMARC/NESP-007,w/variations as Identified & Accepted in Review & Meets Requirements of 10CFR50.47(b)(4) ML20199A5521998-01-22022 January 1998 Safety Evaluation Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves, for Cns,Units 1 & 2 ML20198P9641998-01-15015 January 1998 SE Granting Relief Request 97-03 for Second 10-yr Interval Inservice Insp Program ML20198R9951997-10-30030 October 1997 Safety Evaluation Authorizing Request for Approval of Alternative to Exam Requirement of Reactor Vessel Shell Weld,Per 10CFR50.55a(g)(6)(ii)(A)(5) ML20198J7651997-10-15015 October 1997 Safety Evaluation Accepting 10-yr Interval Insp Program Plan Alternatives for Listed Plants Units ML20211P4521997-10-0909 October 1997 Safety Evaluation Supporting Amend 162 to License NPF-35 ML20211F8801997-09-22022 September 1997 Safety Evaluation Supporting Second ten-year Interval Inservice Inspection Program Plan & Associated Requests for Relief for Catawba Nuclear Station Unit 1 ML20210Q0121997-08-22022 August 1997 Safety Evaluation Supporting Amends 153 & 161 to Licenses NPF-52 & NPF-35,respectively ML20149K8281997-07-29029 July 1997 SER Granting Request for Exemption from Requirements of 10CFR70.24 for Units 1 & 2 ML20141E1121997-06-16016 June 1997 Safety Evaluation Approving Licensee Position That UFSAR Table 6-77 Be Revised to Identify SA-1 & SA-4 Instead of SA-3 & SA-6 as Containment Isolation Valves ML20148H2501997-06-0505 June 1997 Safety Evaluation Accepting Proposed Restructuring of Util Through Acquisition Of,& Merger W/Panenergy Corp ML20141G6701997-05-20020 May 1997 Safety Evaluation Accepting Proposed Alternative Use of TS Requirement for Code Class Snubbers ML20135B3051997-02-27027 February 1997 Safety Evaluation Granting Second 10 Yr ISI Program Plan & Associated Requests for Relief ML20134P2421997-02-20020 February 1997 Safety Evaluation Accepting TR BAW-10199P for Ref in Plants Licensing Documentation & Use in Licensing Applications ML20134P7521996-11-25025 November 1996 Safety Evaluation Supporting Amends 156 & 148 to Licenses NPF-35 & NPF-52,respectively ML20134L4081996-11-19019 November 1996 SER Accepting Performance of Plant Standby Nuclear Svc Water Pond ML20134G5551996-11-0707 November 1996 Safety Evaluation Accepting Proposed Application of BWU-Z CHF Correlation for Plants Mark-BW 17x17 Type Fuel ML20129J3451996-10-30030 October 1996 Safety Evaluation Supporting Amends 155 & 147 to Licenses NPF-35 & NPF-52,respectively ML20129F9021996-10-24024 October 1996 Safety Evaluation Supporting Amends 154 & 146 to Licenses NPF-35 & NPF-52 ML20129E4851996-10-0101 October 1996 Safety Evaluation Recommending That Relief Request 96-02 Be Granted,Per 10CFR50.55a(g)(6)(i),per Request ML20129E7461996-09-28028 September 1996 Safety Evaluation Supporting Amends 153 & 145 to Licenses NPF-35 & NPF-52,respectively ML20116D6461996-07-30030 July 1996 Safety Evaluation Supporting Amend 150 to Operating License NPF-35 ML20112H9401996-06-12012 June 1996 Safety Evaluation Supporting Amends 148 & 142 to Licenses NPF-35 & NPF-52,respectively 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212J1891999-10-0101 October 1999 Safety Evaluation Supporting Exemption from 10CFR54.17(c)re Schedule to Apply for Renewed Operating Licenses ML20212A6271999-09-30030 September 1999 Rev 0 to WCAP-15243, Anaylsis of Capsule V & Capsule Y Dosimeters from Duke Energy Catawba Unit 2 Reactor Vessel Radiation Surveillance Program ML20217H0201999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Catawba Nuclear Station,Units 1 & 2 05000413/LER-1999-015, :on 990616,discovered That Auxiliary Bldg Filtered Ventilation Exhaust Sys Was Inoperable.Caused by Improperly Positioned Vortex Damper.Damper Was Repositioned Correctly & Sys Was Retested Successfully1999-09-27027 September 1999
- on 990616,discovered That Auxiliary Bldg Filtered Ventilation Exhaust Sys Was Inoperable.Caused by Improperly Positioned Vortex Damper.Damper Was Repositioned Correctly & Sys Was Retested Successfully
05000414/LER-1999-004-01, :on 980906,error During Tagout Caused de-energization of Vital Bus & Actuation of Ltop.Caused by Inadequate Work Practices.Individuals Involved Were Counseled1999-09-27027 September 1999
- on 980906,error During Tagout Caused de-energization of Vital Bus & Actuation of Ltop.Caused by Inadequate Work Practices.Individuals Involved Were Counseled
ML20212G2511999-09-22022 September 1999 Safety Evaluation Supporting Amends 180 & 172 to Licenses NPF-35 & NPF-52,respectively 05000413/LER-1999-008, :on 990610,operations Prohibited by TS 3.5.2, Was Violated.Caused by Inoperable Centrifugal Charging Pump. Operators Swapped to CCP 1A & Sys Parameters Were Returned to Normal.With1999-09-21021 September 1999
- on 990610,operations Prohibited by TS 3.5.2, Was Violated.Caused by Inoperable Centrifugal Charging Pump. Operators Swapped to CCP 1A & Sys Parameters Were Returned to Normal.With
05000414/LER-1999-005-02, :on 990727,missed Emergency DG TS Surveillance Concerning Verification of Availability of Offsite Power Sources,Was Declared.Caused by Defective Procedure.Revised Affected Procedure1999-09-20020 September 1999
- on 990727,missed Emergency DG TS Surveillance Concerning Verification of Availability of Offsite Power Sources,Was Declared.Caused by Defective Procedure.Revised Affected Procedure
05000413/LER-1999-009, :on 990518,inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits Was Noted. Caused by Inadequate Retest Following Surveillance Test Failure.Valve Was Retested & Returned to Service1999-09-15015 September 1999
- on 990518,inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits Was Noted. Caused by Inadequate Retest Following Surveillance Test Failure.Valve Was Retested & Returned to Service
ML20216E5401999-09-0707 September 1999 Special Rept:On 990826,discovered That Meteorological Sys Upper Wind Speed Cup Set Broken,Causing Upper Wind Channel to Be Inoperable.Cup Set Replaced & Channel Restored to Operable Status on 990826 05000413/LER-1999-014, :on 990816,missed Surveillances & Operation Prohibited by TS Was Noted.Caused by Defective Procedures or Programs Inappropriate TS Requirements.Affected Procedures/ Programs Were Revised & Testing Was Performed1999-09-0101 September 1999
- on 990816,missed Surveillances & Operation Prohibited by TS Was Noted.Caused by Defective Procedures or Programs Inappropriate TS Requirements.Affected Procedures/ Programs Were Revised & Testing Was Performed
05000414/LER-1999-004, :on 990616,CIV 2NM-221A Was Returned to Svc Without Testing,As Required by TS 3.6.3.Caused by Programmatic Deficiency.Test Procedure Has Been Revised & Subject Valve Was Successfully Tested & Returned to Svc1999-09-0101 September 1999
- on 990616,CIV 2NM-221A Was Returned to Svc Without Testing,As Required by TS 3.6.3.Caused by Programmatic Deficiency.Test Procedure Has Been Revised & Subject Valve Was Successfully Tested & Returned to Svc
ML20212B4711999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 05000414/LER-1999-003, :on 990612,unplanned Actuation of ESFAS Occurred Due to a SG High Level.Caused by Inadequate Procedural Guidance.Msiv 2SM-7 Was Closed & SG 2A Level Was Returned to Normal1999-08-31031 August 1999
- on 990612,unplanned Actuation of ESFAS Occurred Due to a SG High Level.Caused by Inadequate Procedural Guidance.Msiv 2SM-7 Was Closed & SG 2A Level Was Returned to Normal
ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20217H0321999-08-31031 August 1999 Revised Monthly Operating Rept for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 05000413/LER-1999-012, :on 990727,adverse Sys Interaction Between Annulus Ventilation Sys & Auxiliary Building Ventilation Sys Was Discovered.Caused by Inadequate Design.Compensatory Actions Developed & Implemented.With1999-08-26026 August 1999
- on 990727,adverse Sys Interaction Between Annulus Ventilation Sys & Auxiliary Building Ventilation Sys Was Discovered.Caused by Inadequate Design.Compensatory Actions Developed & Implemented.With
ML20211A9791999-08-20020 August 1999 Safety Evaluation Granting Licensee Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section Xi,For Plant,Unit 2 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20211C1291999-08-17017 August 1999 ISI Rept Unit 1 Catawba 1999 RFO 11 ML20210U8341999-08-13013 August 1999 Safety Evaluation Supporting Amends 179 & 171 to Licenses NPF-35 & NPF-52,respectively ML20210R1051999-08-0606 August 1999 Special Rept:On 990628,cathodic Protection Sys Was Declared Inoperable After Sys Did Not Pass Acceptance Criteria of Bimonthly Surveillance.Work Request 98085802 Was Initiated & Connections on Well Anode Were Cleaned or Replaced ML20210S2891999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2 ML20212B4871999-07-31031 July 1999 Revised Monthly Operating Rept for July 1999 for Catawba Nuclear Station,Units 1 & 2 05000413/LER-1999-009, :on 990518,inoperability of Containment Valve Injection Water Sys Valve Was Noted in Excess of TS Limits. Caused by Inadequate Testing Following Surveillance Test Failure.Valve Was Retested & Restored to Service1999-07-19019 July 1999
- on 990518,inoperability of Containment Valve Injection Water Sys Valve Was Noted in Excess of TS Limits. Caused by Inadequate Testing Following Surveillance Test Failure.Valve Was Retested & Restored to Service
05000414/LER-1999-004-02, :on 990610,violation of TS 3.6.3 Was Noted Due to CIV 2NM-221A Being Returned to Service Without Testing. Caused by Procedure Deficiency.Civ 2NM-221A Was Tested & Returned to Operable Status1999-07-15015 July 1999
- on 990610,violation of TS 3.6.3 Was Noted Due to CIV 2NM-221A Being Returned to Service Without Testing. Caused by Procedure Deficiency.Civ 2NM-221A Was Tested & Returned to Operable Status
ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation 05000414/LER-1999-003-02, :on 990612,unplanned Actuation of Esfa Sys Due to a SG High Level Was Noted.Caused by Inadequate Procedural Guidance.Long Term Corrective Actions to Prevent Recurrence of Event Are Being Developed1999-07-0808 July 1999
- on 990612,unplanned Actuation of Esfa Sys Due to a SG High Level Was Noted.Caused by Inadequate Procedural Guidance.Long Term Corrective Actions to Prevent Recurrence of Event Are Being Developed
ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20210S2951999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Catawba Nuclear Station,Units 1 & 2 ML20209H4501999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2 05000414/LER-1999-002-03, :on 990504,plant Was Forced to Shutdown as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Affected Piping Was Cleaned & Flow Tested1999-06-0303 June 1999
- on 990504,plant Was Forced to Shutdown as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Affected Piping Was Cleaned & Flow Tested
ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20196A0001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Catawba Nuclear Station,Units 1 & 2 ML20209H4561999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20206P5201999-05-14014 May 1999 Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20206N8391999-05-0404 May 1999 Rev 16 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr ML20206R1811999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20196A0041999-04-30030 April 1999 Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206N8261999-04-22022 April 1999 Rev 15 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr. Page 145 of 270 of Incoming Submittal Not Included ML20205S5551999-04-21021 April 1999 Safety Evaluation Accepting Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions 05000413/LER-1999-004, :on 990310,operation Prohibited by TSs Was Noted.Caused by Incorrect TS Requirements for Cravs & Auxiliary Bldg Filtered Ventilation Exhaust Sys Actuation Instrumentation.Submitted Lar.With1999-04-12012 April 1999
- on 990310,operation Prohibited by TSs Was Noted.Caused by Incorrect TS Requirements for Cravs & Auxiliary Bldg Filtered Ventilation Exhaust Sys Actuation Instrumentation.Submitted Lar.With
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 ML20205N3651999-04-12012 April 1999 Safety Evaluation Accepting IPE of External Events Submittal ML20205N2381999-04-0909 April 1999 Safety Evaluation Supporting Amends 178 & 170 to Licenses NPF-35 & NPF-52,respectively ML20205P9521999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206R1931999-03-31031 March 1999 Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20205B3101999-03-26026 March 1999 Safety Evaluation Supporting Amends 176 & 168 to Licenses NPF-35 & NPF-52,respectively 05000413/LER-1999-001-01, :on 990215,inoperable Refueling Water Storage Tank Level Channels Resulted in Operation Outside Design Basis.Caused by Inadequate Program Design.Reviewed Procedure & Communication Improvements Between Groups1999-03-17017 March 1999
- on 990215,inoperable Refueling Water Storage Tank Level Channels Resulted in Operation Outside Design Basis.Caused by Inadequate Program Design.Reviewed Procedure & Communication Improvements Between Groups
1999-09-07
[Table view] |
Text
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lt UNITEte STATES NUCLEAR REGULATORY COMMISSION If WASHINGTON. D.C. 20555-0001
\\ ** *,+s[AFETY EVALUATION BY THE OFFICE OF NUCLEAR REA
_RELATED TO AMENDMENT NO.179 TO FACILITY OPERATING LICENSE NPF-35 AND AMENDMENT NO.171 TO FACILITY OPERATING LICENSE NPF-52 DUKE ENERGY CORPORATION. ET AL.
CATAWBA NUCLEAR STATION. UNITS 1 AND 2 DOCKET NOS,50-413 AND 50-414 e
1.0 INTRODUCTION
By letter dated March 25,1999, Duke Energy Corporation (the licensee) submitted a request to mend the facility operating licenses NPF-35 and NPF-52 for Catawba Nuclear Station, Units 1 a
and 2. The proposed amendments would revise those parts of the station's Technical Specifications (TS) regarding reactor trip system (RTS) and engineered safety features actuation system (ESFAS) instrumentation trip setpoints (TSP) as follows:
' Remove the inequality signs applied to the TRIP SETPOINT column of TS Tables 3.3.1-1, " Reactor Trip System Instrumentation," and 3.3.2-1, " Engineered Safety Feature Actuation System Instrumentation," and revise the TRIP SETPOINT column heading to read " NOMINAL TRIP SETPOINT." Also change Notes 1 and 2 of this table to replace
" TRIP SETPOINT" with " NOMINAL TRIP SETPOINT."
Add the definition of NOMINAL TRIP SETPOINT to Section 1.1.
Change the column' heading " TRIP SETPOINT" in Table 3.3.6-1, " Containment Purge and Exhaust isolation Instrumentation," to " NOMINAL TRIP SETPOINT."
Delete inequality signs in Surveillance Requirement (SR) 3.3.5.2 and change " TRIP SETPOINT" to " NOMINAL TRIP SETPOINT."
Revise Limiting Condition for Operation (LCO) 3.4.12, " Low Temperature Overpressure Protection (LTOP) System," to remove inequality signs from the lift setting value (400 psig) and change " LIFT SETTING" to " NOMINAL LIFT SETTING."
- Delete the response time associated with Functions 11 and 12 in TS Table 3.3.1-1.
Change the TS Bases to correspond with the TS revisions.
L
2.0 BACKGROUND
The staff identified a generic concern during inspections at the Watts Bar and Sequoyah plants.
The concem deals with the nominal values associated with tolerar.ces beyond maximum and minimum TSPs (inequalities) shown in the TS. The staff concluded that the existing practice of 9908200221 990813 PDR ADOCK 050(X)4 3 y
e.. s setting the TSP in a manner inconsistent with the improved Technical Specifications (ITS) TSP inequalities would render the instrument inoperable on toe basis of the ITS surveillance requirements, LCOs, and Actions / Conditions. The inequalities were being interpreted as limits that would require entry into the appropriate LCO remedial action when exceeded.
The staff has identified a similar concern at the Vogtle plant. The licensee for Vogtle chose to revise the Vogtle TS to adopt the term " NOMINAL TRIP SETPOINT" and to allow calibration tolerance bands (lower and upper bands) around the TSP value. This approach was consistent with the licensee's setpoint methodology and previous revisions to the ITS, and was found acceptable by the staff. The licensee for Catawba has taken a similar approach to resolve the concern.
3.0 EVALUATION The proposed changes by the licensee and the staff's evaluation of the changes are discussed below:
3.1 Tables 3.3.3-1 and 3.3.2-1 The licensee proposed to delete the inequality signs as applied to the TSP column of Tables 3.3.1-1 and 3.3.2-1. The licensee also proposed to revise the TSP column to read " NOMINAL TRIP SETPOINT." In addition the licensee proposes to add the definition of NOMINAL TRIP
' SETPOINT to Section 1.1.
The licensee has defined the limiting safety system setting (LSSS) to be the allowable value, and the nominal TSP is the value set into the instrument. In accordance with the setpoint methodology used at Catawba, no action is required as long as the LSSS value is not exceeded, and it is acceptable for the applicable safety-related instrumentation as-left TSP to be exceeded by the instrumentation calibration setting tolerances.
{
The removal of the inequality signs from the TSPs as assigned to Tables 3.3.1-1 and 3.3.2-1 is consistent with the licensee's setpoint methodology and the ITS as revised by the staff (Watts Bar ITS). The removal of the inequality signs from the TSP value will allow the licensee to set the TSP value consistent with the two-sided calibration tolerance defined in the setpoint methodology.
The Bases associated with these TS sections provide clarifying information related to the as-left setpoints for the RTS and ESFAS instrumentation. The Bases allow for a channel to be considered operable with a nominal TSP found outside its calibration tolerance band, provided the TSP value is conservative with respect to its allowable value and is readjusted to within the j
established tolerance band of the nominal TSP. The Bases section also clarifies that if the plant condition warrants, the TSP may be set outside the NOMINAL TRIP SETPOINT calibration tolerance band as long as the TSP is conservative with respect to the NOMINAL TRIP SETPOINT.
The licensee has added the definition of NOMINAL TRIP SETPOINT in TS Section 1.1 to incorporate the details previously discussed herein and reads as follows:
l
r s
..s The NOMINAL TRIP SETPOINT shall be the design value of a setpoint. The TSP implemented in plant hardware may be less or more conservative than the NOMINAL TRIP SETPOINT by a calibration tolerance. If plant conditions warrant, the TSP implemented in plant hardware may be set outside the NOMINAL TRIP SETPOINT calibration tolerance band as long as the TSP is conservative with respect to the NOMINAL TRIP SETPOINT.
The staff finds the proposed changes acceptable as thece changes are consistent with the licensee's setpoint methodology.
3.2 Table 3.3.6-1 The licensee proposed to revise the column heading " TRIP SETPOINT" in Table 3.3.6-1 to read
" NOMINAL TRIP SETPOINT."
Table 3.3.6-1 contains the requirements for containment purge and exhaust isolation instrumentation and identifies no additional setpoint requirements beyond those already specified in Table 3.3.2-1 for ESFAS instrumentation. The licensee proposed this administrative change solely to ensure consistency with Table 3.3.2-1. The staff finds this change acceptable.
3.3 SR 3.3.5.2 The licensee proposed to change TRIP SETPOINT to NOMINAL TRIP SETPOINT and to delete the inequality sign. The licensee also proposed to revise the Bases section to incorporate these changes.
This chanDe has been discussed above in Section 3.1 and is, therefore, acceptable to the staff.
3.4 Section 3.4.12 The licensee proposed to revise the LCO to change " LIFT SETTING" to " NOMINAL LIFT SETTING" and to remove the inequality sign from the NOMINAL LIFT SETTING value.
The licensee proposed this change because its review of the safety analyses associated with the power-operated relief valve in the LTOP mode of operation has indicated that the as-left lift setting is indeed a nominal value. The proposed change will thus more accurately describe the nature of the lift setpoint,i.e. as nominal. The staff finds this change acceptable.
3.5 Functions 11 and 12 of Table 3.3.1-1 The licensee proposed to delete the response time associated with Functions 11 and 12 in Table 3.3.1-1.
Functions 11 and 12 pertain to the undervoltage and the underfrequency condition for the reactor coolant pumps. These functions identify a 0.7-and a 0.2-second response time, respectively. The term " response time" is misleading as these values are, in reality, time delays incorporated into the trip circuits to prevent spurious trips. The licensee's justification for removing these time delays from the TS is based on the fact that overall reactor trip response
1 4
- .o times (1.5 seconds and 0.6 seconds, respectively) must be met for these functions, which will account for the time delays. Also, the Westinghouse Standard TS (NUREG-1431) do not specify inclusion of these time delays in the TS. On the basis of this information, the staff finds the proposed change acceptable.
3.6 Summary of Staff Evaluation The staff finds the licensee's proposed TS changes to be acceptable. The proposed changes are consistent with the licensee's setpoint methodology regarding nominal TSP, the Westinghouse Standard TS, NUREG-1431 (two-column format) and the guidance of Regulatory Guide 1.105, Revision 2. The removal of the setpoint column inequalities.is consistent with the use of a nominal TSP by the licensee. As delineated above, the staff found the proposed TS changes for RTS and ESFAS acceptable.
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4.0 STATE CONSULTATION
In accordance with the Commission's regulations, South Carolina State official Mr. Virgil Autrey was notified of the proposed issuance of the amendments to Catawba. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20, and change surveillance requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The staff has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (64 FR 24195 dated May 5,1999). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
i The Commission has concluded, based on 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 the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Hukam C. Garg Date:
August 13, 1999