|
---|
Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217K9441999-10-15015 October 1999 SER Accepting Util Alternative Proposed Relief Request RR-ENG-2-4 for Second 10-year ISI Interval at Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) ML20217K9151999-10-15015 October 1999 SER Authorizing Util Relief Request RR-ENG-2-3 for Second 10-year ISI Interval of Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) ML20211P7811999-09-0909 September 1999 SER Approving Second 10-year Interval Inservice Insp Program Plan Relief Request RR-ENG-2-8 (to Use Code Case N-491-2) for South Texas Project,Units 1 & 2 ML20211Q6731999-09-0909 September 1999 Safety Evaluation Accepting First 10-yr Interval ISI Program Plan Request for Relief from ASME Code Case N-498 ML20211P8411999-09-0909 September 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Surface Exam to Perform Boroscopic VT-1 Visual Exam of Pump Casing Welds within Pump Pits for Welds Covered by Relief Request RR-ENG-24 ML20211F4531999-08-24024 August 1999 Safety Evaluation Supporting Licensee Proposed Alternative to Defer Partial First Period Exams of flange-to-shell Weld to Third Period & Perform Required Ultrasonic Exams,Both Manual & Automated,During Third Period ML20211F5111999-08-23023 August 1999 Safety Evaluation Supporting Licensee Proposed Alternative Contained in Request for Relief RR-ENG-30 ML20210D9161999-07-23023 July 1999 Safety Evaluation Accepting Inservice Testing Relief Request RR-56 Re Component Cooling Water & Safety Injection Sys Containment Isolation Check Valve Closure Test Frequency ML20207H6361999-07-0808 July 1999 Safety Evaluation Approving 2nd 10 Yr Interval ISI Program Plan Request to Use ASME Section XI Code Case N-546 for Licenses NPF-76 & NPF-80,respectively ML20195J6871999-06-17017 June 1999 Safety Evaluation Supporting Proposed Alternative Contained in RR-ENG-2-5.Proposed Alternative Authorized Per 10CFR50.55a(a)(3)(i) for 2nd ISI Interval ML20204B2711999-03-15015 March 1999 Safety Evaluation Authorizing 990201 Request to Authorize Alternative to Regulations Per 10CFR50.55a(a)(3)(i) That Would Revise Start of Second 120-month IST Interval to No Later than 011201 ML20203H8361999-02-17017 February 1999 Safety Evaluation Supporting Request for Relief from ASME Code Requirements for Class 3 Piping for Plant ML20202H9621999-02-0303 February 1999 SER Accepting Change to EALs Used in Classification of Emergency Conditions ML20199K7711999-01-21021 January 1999 Safety Evaluation Accepting ISI Program Request for Relief for ASME Cose Repair Requirements for Code Class 3 Piping ML20199G8161999-01-19019 January 1999 SER Accepting Util 970707 Response to NRC 970509 RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers. NRC Finds No Significant Safety Hazards Based on Application of Util Ampacity Derating Methodology ML20198M3431998-12-28028 December 1998 SER Accepting Util Request for Relief from ASME Code Repair Requirements for ASME Code Class 3 Piping for South Texas Project,Unit 2 ML20198B4111998-12-15015 December 1998 Staff Evaluation Rept of Individual Plant Exam of External Events (IPEEE) Submittal on South Texas Project,Units 1 & 2 ML20198B3491998-12-15015 December 1998 Safety Evaluation Accepting Relief Request to Use ASME Section XI Code Cases 2142-1 & 2143-1 for Replacement SGs ML20195B9601998-11-0606 November 1998 Safety Evaluation Accepting Proposed long-term C/As for Assuring Operability of MSSVs ML20195C8581998-11-0505 November 1998 SER Accepting Order Approving Application Re Proposed Corporate Merger of Central & South West Corp & American Electric Power Co,Inc ML20154N3371998-10-15015 October 1998 Safety Evaluation Re Licensee Request for Deviation from Fire Protection Program Incorporating Requirements of Section III.G.2.c of 10CFR50,App R ML20237D5281998-08-21021 August 1998 Safety Evaluation Re Proposed Increase in Sf Pool Heat Loads for Plant ML20237D4931998-08-21021 August 1998 Safety Evaluation Approving Request to Use ASME Section XI Code Case N-498-1 at STP ML20249A1831998-06-11011 June 1998 SER Accepting Request for Temporary Relief from ASME Code, Section XI Requirements,To Repair Flaws in Essential Cooling Water Sys Piping ML20217Q6881998-05-0606 May 1998 Safety Evaluation Accepting Monitoring for Leakage in Normal & Alternate Charging & Auxiliary Spray Lines at STP ML20199D0251997-11-17017 November 1997 SER Accepting Relief Requests for Inservice Testing Program for Pumps & Valves ML20199B2751997-11-0606 November 1997 Safety Evaluation Accepting Methodology for Graded QA Initiative in Operations QA Description for Plant ML20149E0741997-07-14014 July 1997 Safety Evaluation of First ten-year Interval Inservice Insp Program Plan Request to Use ASME Section XI Code Case N-416-1,Houston Lighting & Power Co,South Texas Projects, Units 1 & 2 ML20141A8531997-05-12012 May 1997 Safety Evaluation Accepting Licensee Request to Use ASME Section XI Code Case N-546, Alternative Requirements for Qualification of VT-2 Exam Personnel,Section XI Div 1, for First 10-yr Interval Inservice Insp Program Plan ML20137U3811997-04-0808 April 1997 Safety Evaluation Approving Transfer of Operating Authority to New Operating Company ML20137E4861997-03-24024 March 1997 Safety Evaluation Accepting Revised Response to NRC Bulletion 88-08, Thermal Stresses in Piping Connected to Reactor Coolant Sys, for Plant,Units 1 & 2 ML20132B0561996-12-11011 December 1996 Safety Evaluation Accepting Licensee Structural Integrity & Operability Assessments ML20059B8281993-10-21021 October 1993 SER Granting Relief & Concluding That Code Required Exam Impractical to Perform to Extent Required by Code & That Limited Section XI Surface Exam Provide Results Which Demonstrated to Be Superior or Equivalent to Surface Exam ML20057A0161993-08-31031 August 1993 Safety Evaluation Concluding That Licensee Has Demonstrated That External Events Not Major Contributor to Core Damage Scenarios at Plant ML20056C3231993-05-10010 May 1993 Supplemental SE Accepting Util Responses Re Operator Response Times During Sgtr.Licensee Satisfied All Four Criteria Required to Complete NRC Review ML20127M7241993-01-19019 January 1993 SE Concluding That Relief Requests Submitted on 920507 Are Covered by Rulemaking on 920908,which Was Incorporated Into 10CFR50.55a(b) ML20059N7881990-09-24024 September 1990 Safety Evaluation Accepting Util First 10-yr Inservice Insp Plan ML20248E6151989-09-21021 September 1989 Safety Evaluation Re Deletion of Dynamic Rod Drop Test, Static Rod Cluster Control Assembly (Rcca) Drop & Rcca below-bank Position Measurement Tests.Deletion Acceptable ML20246L6511989-02-22022 February 1989 Sser Accepting Util Efforts Re Action Items 1.a & 1.b of NRC Bulletin 88-011,per NRC Findings of Westinghouse & Plant Audit ML20207M4061988-10-0505 October 1988 Safety Evaluation Granting Util 880308 & 26 Requests to Increase Spent Fuel Pool Capacity Through Use of High Density Storage Racks ML20195G5531988-06-24024 June 1988 Safety Evaluation Accepting Proposed Reracking of Util Spent Fuel Storage Pools from Criticality Standpoint.Enrichment of Fuel to 4.5 Weight % U-235 May Be in Conflict W/ 10CFR51 Table S4 & Should Be Investigated by NRC ML20149M6941988-02-23023 February 1988 Safety Evaluation Supporting Proposals Re Personnel Air Lock Seal Air Sys Isolation ML20207K1081986-12-31031 December 1986 Safety Evaluation Re Cumulative Usage Factor Criterion for Pipe Break Postulation.Proposal Not to Postulate Pipe Breaks for SI Injection Lines & Pressurizer Surge Line Approved, Pending Resolution of Confirmatory Item Re Vibratory Stress ML20154M2201986-03-0707 March 1986 SER Supporting Licensee Mods,Per Generic Ltr 83-28,Item 4.3, Reactor Trip Breaker Automatic Shunt Trip ML20138N8121985-10-30030 October 1985 SER Supporting Util 850717 Response to Generic Ltr 83-28, Items 4.1,4.2.1 & 4.2.2 Re Preventive Maint Program for Reactor Trip Breakers/Maint & Trending ML20134L5551985-07-31031 July 1985 Draft Safety Evaluation Re Elimination of Arbitrary Intermediate Pipe Breaks ML20137G8061985-07-31031 July 1985 Safety Evaluation Supporting Util Proposal for Elimination of Arbitrary Intermediate Pipe Breaks in High Energy Piping Sys from Design Considerations in SRP Section 3.6.2 ML20140B7991977-06-0606 June 1977 Safety Evaluation Supporting Subcompartment Pressure Analysis & Proposed Valve Room Design,Per Low Stress Superpipe Requirements of Branch Technical Position Meb 3-1 Re Protection Against Main Steam or Feedwater Line Breaks 1999-09-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K9441999-10-15015 October 1999 SER Accepting Util Alternative Proposed Relief Request RR-ENG-2-4 for Second 10-year ISI Interval at Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) ML20217K9151999-10-15015 October 1999 SER Authorizing Util Relief Request RR-ENG-2-3 for Second 10-year ISI Interval of Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) NOC-AE-000676, Monthly Operating Repts for Sept 1999 for South Texas Project,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for South Texas Project,Units 1 & 2.With ML20217D0531999-09-30030 September 1999 Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr ML20217D0481999-09-30030 September 1999 Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 Colr ML20211P8411999-09-0909 September 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Surface Exam to Perform Boroscopic VT-1 Visual Exam of Pump Casing Welds within Pump Pits for Welds Covered by Relief Request RR-ENG-24 ML20211P7811999-09-0909 September 1999 SER Approving Second 10-year Interval Inservice Insp Program Plan Relief Request RR-ENG-2-8 (to Use Code Case N-491-2) for South Texas Project,Units 1 & 2 ML20211Q6731999-09-0909 September 1999 Safety Evaluation Accepting First 10-yr Interval ISI Program Plan Request for Relief from ASME Code Case N-498 NOC-AE-000643, Monthly Operating Repts for Aug 1999 for South Texas Project,Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for South Texas Project,Units 1 & 2.With ML20212E5191999-08-31031 August 1999 Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment ML20211F4531999-08-24024 August 1999 Safety Evaluation Supporting Licensee Proposed Alternative to Defer Partial First Period Exams of flange-to-shell Weld to Third Period & Perform Required Ultrasonic Exams,Both Manual & Automated,During Third Period ML20211F5111999-08-23023 August 1999 Safety Evaluation Supporting Licensee Proposed Alternative Contained in Request for Relief RR-ENG-30 ML20210C9411999-07-31031 July 1999 Rev 1 to SG-99-07-002, South Tx,Unit 1 Cycle 9 Voltage- Based Repair Criteria 90-Day Rept, Jul 1999 ML20210R3631999-07-31031 July 1999 Monthly Operating Repts for July 1999 for South Tx Project, Units 1 & 2.With ML20210D9161999-07-23023 July 1999 Safety Evaluation Accepting Inservice Testing Relief Request RR-56 Re Component Cooling Water & Safety Injection Sys Containment Isolation Check Valve Closure Test Frequency ML20210D4821999-07-21021 July 1999 1RE08 ISI Summary Rept for Steam Generator Tubing of South Texas Project Electric Generating Station Unit 1 ML20210D4491999-07-21021 July 1999 Revised Chapters to Operations QA Plan, Including Rev 9 to Chapter 1.0, Organization & Rev 6 to Chapter 16.0, Independent Technical Review NOC-AE-000583, LER 99-S03-00:on 990619,failure to Revitalize Sdg Number 11 Was Noted.Caused by Failure to Communicate Status of Sdg. Subject Sdg Revitalized on 990619 & Licensee Will Develop Security Force Instruction Re Sdgs.With1999-07-15015 July 1999 LER 99-S03-00:on 990619,failure to Revitalize Sdg Number 11 Was Noted.Caused by Failure to Communicate Status of Sdg. Subject Sdg Revitalized on 990619 & Licensee Will Develop Security Force Instruction Re Sdgs.With ML20207H6361999-07-0808 July 1999 Safety Evaluation Approving 2nd 10 Yr Interval ISI Program Plan Request to Use ASME Section XI Code Case N-546 for Licenses NPF-76 & NPF-80,respectively ML20216D7481999-07-0707 July 1999 1RE08 ISI Summary Rept for Welds & Component Supports of STP Electric Generating Station,Unit 1 NOC-AE-000593, Monthly Operating Repts for June 1999 for Stp,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Stp,Units 1 & 2. with NOC-AE-000570, LER 99-S01-00:on 990527,discovered That Unescorted Access Had Been Inappropriately Granted.Caused by Failure to Follow Procedure.Util Verified That Individual Did Not Have Current Unescorted Access at STP or Any Other Util.With1999-06-28028 June 1999 LER 99-S01-00:on 990527,discovered That Unescorted Access Had Been Inappropriately Granted.Caused by Failure to Follow Procedure.Util Verified That Individual Did Not Have Current Unescorted Access at STP or Any Other Util.With ML20196G5821999-06-23023 June 1999 LER 99-S02-00:on 990601,failure to Maintain Positive Control of Vital Area Security Key Was Noted.Caused by Lack of Attention to Detail.Discussed Event with Operator Involved IAW Constructive Discipline Program ML20195J6871999-06-17017 June 1999 Safety Evaluation Supporting Proposed Alternative Contained in RR-ENG-2-5.Proposed Alternative Authorized Per 10CFR50.55a(a)(3)(i) for 2nd ISI Interval ML20196A2391999-06-15015 June 1999 Change QA-042 to Rev 13 of Operations QAP, Reflecting Current Organizational Alignment for South Texas Project & Culminating Organizational Realigment That Has Been Taking Place During Past Several Months NOC-AE-000563, Monthly Operating Repts for May 1999 for Stp,Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Stp,Units 1 & 2. with ML20206U5411999-05-18018 May 1999 Non-proprietary Errata Pages for Rev 2,Addendum 1 to WCAP-13699, Laser Welded Sleeves for 3/4 Inch Diamete Tube Feedring Type & W Preheater SGs Generic Sleeving Rept ML20206A7721999-04-30030 April 1999 STP Electric Generating Station Unit 1 Cycle 9 Colr NOC-AE-000543, Monthly Operating Repts for Apr 1999 for Stp,Units 1 & 2. with1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Stp,Units 1 & 2. with ML20205H0321999-03-31031 March 1999 Change QA-040 to Rev 13 of Operations QA Plan NOC-AE-000507, Monthly Operating Repts for Mar 1999 for Stp,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Stp,Units 1 & 2. with ML20205A3781999-03-22022 March 1999 STP Electric Generating Station Simulator Certification Four Yr Rept for Units 1 & 2 ML20204B2711999-03-15015 March 1999 Safety Evaluation Authorizing 990201 Request to Authorize Alternative to Regulations Per 10CFR50.55a(a)(3)(i) That Would Revise Start of Second 120-month IST Interval to No Later than 011201 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 NOC-AE-000468, Monthly Operating Repts for Feb 1999 for South Texas Project Electric Generating Station.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for South Texas Project Electric Generating Station.With ML20207D1101999-02-24024 February 1999 Change QA-039 to Rev 13 of Operations QA Plan, for STP ML20203H8361999-02-17017 February 1999 Safety Evaluation Supporting Request for Relief from ASME Code Requirements for Class 3 Piping for Plant ML20202H9621999-02-0303 February 1999 SER Accepting Change to EALs Used in Classification of Emergency Conditions ML20202E8471999-01-31031 January 1999 2RE06 ISI Summary Rept for SG Tubing of STP Electric Generating Station,Unit 2 ML20216G2011999-01-31031 January 1999 City Public Svc of San Antonio Annual Rept 1998-1999 ML20199G5961999-01-31031 January 1999 Cycle 7 Voltage-Based Repair Criteria Rept for Jan 1999 ML20199K7711999-01-21021 January 1999 Safety Evaluation Accepting ISI Program Request for Relief for ASME Cose Repair Requirements for Code Class 3 Piping ML20199G8161999-01-19019 January 1999 SER Accepting Util 970707 Response to NRC 970509 RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers. NRC Finds No Significant Safety Hazards Based on Application of Util Ampacity Derating Methodology ML20199H4981999-01-11011 January 1999 2RE06 ISI Summary Rept for Welds & Component Supports of Stp,Unit 2 ML20206Q3751999-01-0404 January 1999 2RE06 ISI Summary Rept for Sys Pressure Tests (Class 1 & 2) ML20206Q3721999-01-0404 January 1999 2RE06 ISI Summary Rept for Repairs & Replacements ML20216G2171998-12-31031 December 1998 Houston Industries 1998 Annual Rept. App a 1998 Financial Statements & Us Securities & Exchange Commission Form 10-K Encl NOC-AE-000403, Monthly Operating Repts for Dec 1998 for South Texas Project Unit 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for South Texas Project Unit 1 & 2.With ML20216G1521998-12-31031 December 1998 Central & South West Corp 1998 Summary Annual Rept & Securities & Exchange Commission Form 10-K ML20198M3431998-12-28028 December 1998 SER Accepting Util Request for Relief from ASME Code Repair Requirements for ASME Code Class 3 Piping for South Texas Project,Unit 2 1999-09-09
[Table view] |
Text
-- . . . _ --
i om l p UNITED STATES g j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001 o,
\ , . . * ,$
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMPACITY DERATING ISSUES STP NUCLEAR OPERATING COMPANY (STPNOC)
DOCKET NOS. 50-498 AND 50-499 SOUTH TEXAS PROJECT. UNITS 1 AND 2 (STP)
1.0 BACKGROUND
By letter dated July 7,1997, Houston Lighting & Power Company (the former licensed operator; STPNOC is the current licensed operator) submitted a response to the Nuclear Regulatory i Commission's (NRC's) May 9,1997, request for additional information (RAI) related to Generic Letter 92-08, "Thermo-Lag 330-1 Fire Barriers," for STP. ,
The licensee had previously id entified a total of 24 cable trays that did not pass the " Step 1 Ampacity Analysis," as described in.its November 6,1996, letter. For these 24 trays, the licensee has performed a " Step 2 Heat Analysis." Based upon the information provided in the 1996 letter the staff concluded that the " Watts per foot" methodology had been applied in the l Step 2 Heat Analysis. Earlier staff reviews associated with other licensees has lead to the l conclusion that the " Watts per foot" methodology has fundamental weaknesses in providing an adequate assessment of the ampacity performance limits for individual cables. !
The staff's May 9,1997, RAI ic'entified a number of open issues and concerns associated with the " Watts per foot" methodology which required further clarification by the licensee. The licensee's July 7,1997, letter contained a reassessment of the subject cable trays using an alternate methodology. Further, the licensee's April 15,1998, letter stated the thermo lag fire barrier material will be removed from the subject cable trays by the end of 1998 in order to eliminate any concerns regarding cable ampacity.
l The staff's evaluation of the ampacity derating methodology for STP follows. 1 2.0 EVALVATIQN After reviewing the licensee's letters and Sandia National Laboratories (SNL) Technical Evaluation (see Enclosure 2), the staff agrees with the SNL analyses and conclusions. The ampacity derating analysis questions, the licensee's responses, and the staff's evaluation of the responses follow.
ENCLOSURE 1 i 9901250034 990119 ;
PDR ADOCK 05000498 '
P PDR I
2 Amoacity Deratina Analysis Review
. Question 1 What test data supports and demonstrates the appropriatenecs of this approach?
Licensee Response By letter dated July 7,1997, the licensee provided an ampacity derating analysis reassesement for the subject cables based upon alternate considerations.
3 Staff Response The information provided by the licensee is fully responsive to the subject question.
. Question 2 in general, the ' Watts per foot" methodology provides an inadequate treatment of the impact of cable loading on the allowable heat loads and assumes those effects are largely irrelevant to the overall heat rejection capacity of the cable tray or conduit system.
Licensee Resoonse By letter dated July 7,1997, the licensee provided an ampacity derating analysis reassessment for the subject cables based upon alternate considerations.
Staff Response The information provided by the licensee is fully responsive to the subject question.
. Question 3 See SNL's discussion in Section 2.5 of the SNL Letter Report to NRC, Rev. O, dated April 24,1997, on cable diversity effects (excerpted and restated below):
Cable Diversity Effects: The Watts /ft analysis method provides for no significant treatment of cable diversity effects and how this would impact the total allowable heat loads for the cable tray system. All of the available ampacity tests typically cited as supporting the method are based on cable trays in which all of the cables are powered uniformly. In real applications, cable trays contain a mixture of loaded and unloaded cables. It is unrealistic to assume that a diverse cable load would have the same overall heat rejection capacity as a uniform cable load. Recall that the objective is to ensure a hot spot of no greater than 90 C.
Concentrating the heat generation in just a few cables clearly will create significant localized heating effects that would lead to higher hot spot temperatures. This is not accounted for in the " Watts /ft method."
i
1 i
3 I l
Licensee Resoonse j
i By letter dated July 7,1997, the licensee provided an ampacity derating analysis j reassessment for the subject cables based upon alternate considerations.
l Staff Response The information provided by the licensee is fully responsive to the subject question.
AppJintion of Amoacity Deratina Methodoloov lt is important to note that the licensee's April 15,1998, letter states that the Thermo-Lag material will be removed from the 24 Thermo-Lag enclosed cable trays. Hence, in the current -
context of this review, the primary objective is to ensure that formerly protected cables have not been subjected to excessive premature aging.
In its ampacity assessments for cable trays, the licensee has applied a 32% derating factor for 1-hour barriers (based on testing by Texas Utilities Electric (TUE)) and a 48% derating for 3-hour barriers (based on testing by Tennessee Valley Authority (TVA)). The staff has previously approved these values for use. Given that licensee has indicated that the STP Thermo-Lag installations are representative in design and construction of the configurations tested by TVA and TUE, the cited ampacity derating factors can be utilized by the licensee.
The licensee had provided specific ampacity assessments for the 24 cable trays that were previously accepted on the basis of a Watts-per-foot method. Screening ampacity margins assessments identified a total of 30 individual cables (13 cables for Unit 1 and 17 cables for Unit 2) requiring further consideration. The initial assessment uniformly includes a load factor (LF) of 1.25 for all cables.
i As noted in the SNL report dated April 24,1997, one outstanding concern was the finding that i
the Watts-per-foot approach for cable tray ampacity assessment was inadequate and inappropriate for use. The current licensee assessments continue to use a cable tray overall .
heating rate derived from the Watts-per-foot methodology. However, by letter dated July 7, 1997, the licensee provided an attemate approach for its final assessments. Individual reassessments were provided for the subject cables. This reassessment action fully resolves the staff concern regarding the application of the Watts-per-foot-method for these specific STP configurations. The staff finds that all of the cable reassessments were acceptabla. q 1
The staff finds that the licensee has resolved all of the outstanding technical items which had ,
been identified in the previous reviews. In particular, the licensee has abandoned the Watts- !
per-foot methodology in favor of a more conventional margins approach. The staff does not credit the use of the Watts-per-foot approach in the context of the STP assessments.
The staff takes exception to two aspects of the licensee assessments:
- The licensee states that " typical industry practice does not include consideration of undervoltage or overload conditions in ampacity assessments." As a result, for several motor and pump cases, the licensee resolved a nominal ampacity overload by relaxing the LF from 1.25 to 1.0. The staff does not cone'ir with this assumption. Indeed, load
l e
4 factors have no other purpose than to ensure that the ampacity assessment allows for all conditions of operation and they are considered in typical industry practice.
Ultimately, this finding had no impact on the final assessment of aceptability. Givar.
that the fire barriers are being removed, in all of the impacted cases it was determined that the available "LF margin" was adequate to ensure that no adverse life-to-date aging has been realized for the subject cables.
The licensee occasionally referred to a given cable as not being an Appendix R cable; hence,"the adequacy of the cable ampacity is not a concern from an Appendix R standpcint? The staff does not agree with this argument since ampacity limits are a necessary design parameter applicable to all electric power circuits, not just to the Appendix R safe shutdown systems. However, in all such cases, the licensee has provided alternate arguments for acceptability of the subject cables, in all cases there was sufficient information provided by the licensee to conclude that no adverse aging impact had been experienced by the cables independent of the above two points.
It should be noted that SNL has recommended that certain cables that have been operated at overload conditions in the past will remain acceptable for future operation. This assessment is acceptable to the staff based on two specific considerations. First, the licensee has stated that the subject fire barriers will be removed and this action will relieve any potential overload problems during future operations. Second, an assessment made by SNL of the worst-case impact of the cables for life-to-date operation at the stated overload conditions indicates that no adverse equipment aging impact was likely to have occurred in the specific cases.
l Given the above findings and the licensee commitment to remove the Thermo-Lag fire barriers !
l from the subject cable trays, the staff finds that the licensee has provided adequate information I L
to resolve the arnpacity-related points of concern raised in GL 92-08.
3.0 CONCLUSION
S l
Given the above evaluation and the licensee commitment to remove the applicable thermo-lag fire barrier material, the staff concludes that no significant safety hazards exists based upon the l application of the licensee's ampacity derating methodology. Therefore, there are no ampacity I
related safety concerr.s at STP. '
Principal Contributo': R. Jenkins l Date: January 17, 1999 i
i i l