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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 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 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 ML20216J4211998-03-18018 March 1998 SER Approving Alternative to Insp of Reactor Pressure Vessel Circumferential Welds for Grand Gulf Nuclear Station 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 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 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 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 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 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 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 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 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 ML20151P0291988-08-0505 August 1988 Safety Evaluation Supporting Generic Ltr 83-28,Position 4.5.1 Re on-line Testing of Reactor Trip Sys ML20234D9021987-12-30030 December 1987 Safety Evaluation Supporting 870612,0814,1026 & 1119 Relief Requests from First 10-yr Interval Inservice Insp Program Requirements of Section XI of ASME Code ML20149E7091987-12-30030 December 1987 Safety Evaluation Supporting Amend 41 to License NPF-29 ML20234C7671987-12-23023 December 1987 Safety Evaluation Granting 870612,0814,1026 & 1119 Requests for Relief from Certain Section XI ASME Code Requirements Re First 10-yr Interval Inservice Insp Program ML20236B1021987-10-15015 October 1987 Safety Evaluation of 870630 Submittal Supplemented on 870821 & 0911 Re Deferral of Certain Insps of Tdi Div II Emergency Diesel Generators.Deferral of Certain Design Review & Quality Revalidation Baseline Insps Approved ML20235V1701987-10-0707 October 1987 Safety Evaluation Re 861022 Rev 2 to Process Control Program (PCP) for Processing & Packaging of Wet Radwastes.Pcp Acceptable ML20234A9471987-09-0404 September 1987 Safety Evaluation Re Util 870702 Submittal Re Containment Isolation for Various Instrument Lines.Util Proposed Alternate Basis to Meet GDC 55 to 10CFR50 App a Acceptable ML20237H1711987-08-21021 August 1987 Safety Evaluation Supporting Util 851014,870403 & 870622 Submittals Providing Info Re ATWS-related Design Features, Alternate Rod Injection,Standby Liquid Control Sys & Recirculation Pump Trip ML20236M3841987-07-31031 July 1987 Safety Evaluation on Generic Ltr 83-28,Items 3.1.1,3.1.2, 3.2.1 & 3.2.2 Re post-maint Testing.Licensee Programmatic Controls & Procedures for post-maint Testing of Components in Reactor Trip & safety-related Sys Acceptable ML20215J1351987-05-0404 May 1987 Safety Evaluation Re Spill of Sulphuric Acid at Plant on 860322.Licensee Monitoring & Recovery Sys Adequate to Contain & Eliminate Existing Acid Plume.No Addl Measures Recommended ML20210C3391987-04-30030 April 1987 Safety Evaluation Accepting Licensee 870129 Proposed Solution to Concern Re Control of Activities within Exclusion Areas ML20204J1451987-03-23023 March 1987 SER Supporting Licensee Responses to Humphrey Concerns on Safety of Mark III Containment Design ML20207R1051987-03-0505 March 1987 Safety Evaluation Supporting Util 861125 Rept on Conformance to Reg Guide 1.133,Rev 1, Loose-Part Detection Program for ...Sys of Light Water Cooled Reactors. License Condition 2.C(14) Adequately Addressed ML20212M3861987-03-0404 March 1987 Safety Evaluation Accepting Util 861223 Response to IE Bulletin 79-26, Boron Loss from BWR Control Blades, Per License Condition 2.C.(12) ML20207N2761987-01-12012 January 1987 SER Supporting License Condition 2.C.(17) Which Replaces Check Valve Disc in Train B Feedwater Line Into Which Cold Water from Condensate Storage Tank Injected by RCIC ML20212G3421987-01-12012 January 1987 Safety Evaluation Accepting Util 850228 & 860214 Submittals on Conformance to Reg Guide 1.97,Rev 2 ML20211P3901986-12-12012 December 1986 SER Supporting Util 860825 Request for Rev to Relief Request I-00007 Seeking Relief from Surface Exam for Welds within Flued Heads & Guard Pipes ML20214W8161986-12-0808 December 1986 Safety Evaluation Granting Util 861015 Request for Release from Commitment to Compare Performance of on-line Instrumentation Vs Grab Sampling Techniques 1999-09-23
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217F9921999-09-30030 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 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 ML20211A6921999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Grand Gulf Nuclear Station,Unit 1.With 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 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 ML20196A1161999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Grand Gulf Nuclear Station.With 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 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 ML20206T7991999-01-31031 January 1999 Iodine Revolatizitation in Grand Gulf Loca 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 ML20206D7721998-12-31031 December 1998 South Mississippi Electric Power Association 1998 Annual Rept ML20198E2481998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Grand Gulf Nuclear Station,Unit 1.With 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 ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual ML20154K2391998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Grand Gulf Nuclear Station Unit 1.With ML20155F1961998-09-0101 September 1998 Engineering Rept for Evaluation of BWR CR Drive Mounting Flange Cap Screw ML20153B2161998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20237B6661998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Grand Gulf Nuclear Station,Unit 1 ML20236R0231998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Grand Gulf Nuclear Station,Unit 1 ML20155J0811998-05-31031 May 1998 10CFR50.59 SE for Period Jan 1997 - May 1998 ML20249B1251998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Grand Gulf Nuclear Station,Unit 1 ML20248B6261998-05-11011 May 1998 Rev 6 to Grand Gulf Nuclear Station COLR Safety-Related 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 ML20206J1271998-04-30030 April 1998 Pressure Locking Thrust Evaluation Methodology for Flexible Wedge Gate Valves ML20247F3591998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Grand Gulf Nuclear Plant,Unit 1 ML20217M8951998-04-30030 April 1998 QA Program Manual 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 ML20217A0291998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Grand Gulf Nuclear Sation,Unit 1 ML20216J4211998-03-18018 March 1998 SER Approving Alternative to Insp of Reactor Pressure Vessel Circumferential Welds for Grand Gulf Nuclear Station ML20216J2021998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Grand Gulf Nuclear Station,Unit 1 ML20203A2891998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Grand Gulf Nuclear Station ML20247B4111997-12-31031 December 1997 1997 Annual Financial Rept for South Mississippi Electric Power Association ML20203H9741997-12-31031 December 1997 1997 Annual Operating Rept, for Ggns,Unit 1 ML20198P1121997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Grand Gulf Nuclear Station,Unit 1 ML20203B5581997-12-0404 December 1997 Special Rept 97-003:on 971111,valid Failure of Div 2 EDG Occurred,Due to Jacket Water Leak.Failure Reported,Per Plant Technical Requirements Manual Section 7.7.2.2 ML20203K4031997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Grand Gulf Nuclear Station,Unit 1 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 1999-09-09
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p" k UNITED STATES 4 j 'j NUCLEAR REGULATORY COMMISSION o,, t : WASHINGTON, D.C. 20066 4 001 s,;& * .
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
. GENERIC LETTER 92-08 AMPACITY DERATING ISSUES ENTERGY OPE' RATIONS. INC.
4 GRAND GULF NUCLEAR STATION. UNIT 1 DOCKET NO. 50-416 l
1 1,01 BACKGROUND ' l l
By letter dated December 15,1998, Entergy Operations, Inc. (the licensee), submitted a i response to the third NRC request for additional information (RAI) dated June 19,1998, and a telephone conference meeting held between the staff and licensee representatives on September 24,1998, related to Generic Letter (GL) 92-08, "Thermo-Lag 330-1 Fire Barriers,"
for Grand Gulf Nuclear Station (GGNS), Unit 1.
The determination of ampacity derating factors for Thermo-Lag fire barriers at GGNS is based on a similarity analysis. The licensee provided two engineering reports (GGNS-96-0006 and l GGNS-96-0032) to address ampacity derating issues due to Thermo-Lag fire barriers. The licensee used the results from the TXU Electric Company (TXU Electric) ampacity derating
. tests in its evaluation'(Engineering Reports No. GGNS-96-0006 and No. GGNS-96-0032) of GGNS Thermo-Lag fire barriers with nominal % inch base with or without % inch overlay.
Additionally, the licensee used the results from the Tennessee Valley Authority (TVA) ampacity derating tests in its evaluation (Engineering Report No. GGNS-96-0032) of GGNS Thermo-Lag fire barriers with nominal 1-% inch thick panels and/or pre-formed conduit sections.
The licensee provided submittals dated December 20,1996, and June 5,1997, in response to the . staff RAls dated October 28,1996, and February 26,1997, respectively, which had identified a number of open issues and concerns. The licensee's submittal dated December 15, 1998, contained the response to the latest staff questions regarding its ampacity derating methodology. The staff's evaluation of the ampacity derating methodology for GGNS follows.
2.0 EVALUATION 2.1 Amoacity Deratina Analysis Review The ampacity derating analysis questions, the licensee's responses, and the staff's evaluations l of the responses fellow.
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Enclosure i
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l QUESTION 1 l
l In response to Question 2 (of the statt's RAI dated February 26,1997), the licensee stated that
" Room OC302 has an average temperature of approximately 80 *F and typically at a temperature of less than 86 *F (30 *C)." The staff would like to know what is meant by average l temperature. Ampacity factor of 1.09 per ICEA standard for ambient temperature of 30 *C is acceptable provided the temperature of the room will never exceed 30 *C. (Note that 40 *C for some length of time and 20 *C for the remaining period will not qualify for an ambient temperature of 30 *C). The licensee is requested to identify,in addition to the historical
) temperature range, what procedures,if any, are applicable for monitoring or controlling temperature in the subject area, 1
Licensee Response l In its submittal dated December 15,1998, the licensee responded as follows:
Peak daily room temperature data was obtained from the Plant Data System for a period of several years for the purpose of developing a worst case temperature profile.
l This temperature profile has been used only in performing the service life evaluation for cables 1 AB561041,1 AB561181, and 1 AB561201. The service life evaluation I
conservatively uses 40 degrees C for the entire 3 month summer period and 30 degrees C for the remaining 9 months of the year. Data obtained from the Plant Data System indicates that while the peak daily temperature for Room OC302 does occasionally exceed 30 degrees C during the summer months, it rarely ever approaches 40 degrees C. Therefore, the service life evaluation is very conservative 1 for the conditions normally experienced by the subject cables, and would even I encompass possible increased temperatures resulting during an unexpected fan outage. Therefore, the licensee will use the standard 40 degree C ambient temperature in OC302 for determining derated cable ampacity. l i' Staff Response The information provided by the licensee fully resolves the staff's concerns.
OUESTION 2 l l
Provide the details of analytical method used to calculate ampacity correction factor (ACF) of 44 percent and a copy of the paper entitled," Fire Endurance and Ampacity Testing of One- and Three Hour Rated Thermo-Lag Electrical Raceway Fire Barrier." Was the paper endorsed by IEEE?
Licensee Response l In its submittal dated December 15,1998, the licensee provided the following response:
l The licensee will use the 48% derating published in Omega Point Laboratories Report No.11960-97333, "Ampacity Derating of Cables Enclosed in a Cable Tray with Thermo-Lag 3301/770-1 Upgrade Electrical Raceway fire Barrier System (ERFBS)"
prepared for TVA and TSI. The 44% ampacity derating correlation established in the I
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,2 l* 3 1
- paper entitled," Fire Endurance and Ampacity Testing of One- and Three Hour Rated l Thermo-Lag Electrical Raceway Fire Barrier System," authcred by Mark H. Salley and 1 Kent W. Brown, will not be used.- l Staff Resoorge
( The information provided by the licensee fully resolves the staff's concerns.
QUESTION 3 The staff understands that all loads except one load (Emergency Switchgear and Battery Rooms Cooling motor) will have at least 100 percent of rated voltage for all conditions.
Emergency Switchgear and Battery Rooms Cooling motor will have at least 98 percent of rated voltage at its terminals for all conditions. Hence, no adjustment of full load amperes (FLA) for constant KVA loads due to voltage contingencies is required. The licensee is requested to provide comments regarding the variation in voltage, which has been experienced in the past by the subject equipment.
Licensee Response In its submittal dated December 15,1998, the licensee provided the following response:
The licensee has used the minimum anticipated grid voltage (0.992 per unit) in deter. mining the minimum available terminal voltage for the continuous duty constant KVA equipment (Z51 - Control Room HVAC and Z77 - Emergency Switchgear and Battery Rooms Ventilation fan motors) that has power cables contained within Thermo-Lag enclosed raceways. As expected, all of these fan motors would experience less than 100% of rated voltage for the 0.992 pu condition.
A detailed service life evaluation was performed for the three cables of concern. The useful service life for cables 1 AB561041 (O2Z77B001 A Low Speed),1 AB561181 (O2Z77C001 AA Low Speed), and 1 AB561201 (Q1Z77C001 AA Low Speed) has been evaluated using Arrhenius methodology and found to be greater than 40 years under the evaluated conditions.
Measures have been established to ensure that the corrected FLA values for these circuits are not exceeded. These measures require that voltage and current measurements are taken when any activity is performed which could cause the corrected FLA value of the equipment to be exceeded. If the corrected FLA value of the equipment exceeds the derated ampacity limits established, the Engineering Department must be notified so that a detailed review can be performed and the appropriate corrective action initiated, if necessary.
The evaluations performed indicate that no corrective actions are currently necessary.
l The measures that are being established will ensure that if conditions change in such a manner as to affect these evaluations, the Engineering staff will be notified so that appropriate corrective actions can be initiated as necessary.
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4 Staff Response The information provided by the licensee fully resolves the staff's concerns. ,
I QUESTION 4 )
In its response to Question 1 (of the staff's RAI dated February 26,1997), the licensee stated
- an ampacity derating factor of 48 percent due to Thermo-Lag. The licensee also calculated an ampacity derating factor of 44 percent using the analytical method described in response to Question 2 (of the staff's RAI dated February 26,'1997). The licensee is requested to clarify which value is correct. In addition, the licensee is requested to identify which raceways .
enclosed by Thermo-Lag fire barriers would have an insufficient design margin given an ampacity derating factor of 40 percent.
Licensee Response -
~
ln its submittal dated December 15,1998, the licensee provided the following response:
The previously used 44% derating did not apply to conduit configurations. Given that the licensee will use only the 48% derating, therefore this clarification is no longer necessary.
SJpff Response The information provided by the licensee fully resolves the staff's concerns.
1 QUESTION 5 (WITHDRAWN) '
' During the telephone conference meeting held with the licensee on September 24,1998, Question 5, which pertained to the grouping factor applied to multiple conduits enclosed by a single Thermo-Lag barrier design, was discussed and clarified to the staff's satisfaction.
2.2 Aoolication of Amoacity Deratina Methodoloav The licensee utilizes' TVA and TXU Electric ' test' data to develop ampacity derating parameters for GGNS Thermo-Lag configurations. The licersee verified that the subject configurations are representative in terms of design and construction of the configurations that were tested by TVA and TXU Electric. , in its submittal dated December 15,1998, the licensee agreed to address future age related cable degradation concerns for the three cables 1 AB561041,
'1 AB561181, and 1 AB561201, which were determined to exceed its design ampacity margin under minimum anticipated voltage conditions (See Question.3). The licensee committed to take voltage and current measurements of the subject cables following any activity that could cause the corrected fullload amperage of the applicable equipment to exceed its analyzed
- limits.-
Given the licensee's response to the~ staff's questions and the licensee's commitment previously described, the staff finds that the licensee has provided adequate information to resolve the ampacity related points of concern raised in Generic Letter 92-08.
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3.0 CONCLUSION
S From the preceding evaluation, the staff concludes that for GGNS, Unit 1, all of the i ampacity-related concerns have been resolved and the licensee has provided an adequate j'
technical basis to assure that all of the Thermo-Lag fire barrier enclosed cables are operating -
within acceptable ampacity limits. Therefore, the staff finds that there are no outstanding safety concerns with respect to the Generic Letter 92-08 ampacity issues.
' Principal Contributor. R. Jenkins Date: September 23, 1999 i
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