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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217G1001999-10-14014 October 1999 Errata to Safety Evaluation Supporting Amend 215 to FOL DPR-50.Credit Given for Delay in ECCS Leakage ML20216F9231999-09-22022 September 1999 Safety Evaluation Supporting Amend 216 to License DPR-50 ML20211E8731999-08-24024 August 1999 Safety Evaluation Supporting Amend 215 to License DPR-50 ML20211B1931999-08-19019 August 1999 Safety Evaluation Supporting Amend 214 to License DPR-50 ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20212H9101999-06-21021 June 1999 Safety Evaluation Supporting Amend 212 to License DPR-50 ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML20205Q6111999-04-15015 April 1999 Safety Evaluation Supporting Amend 210 to License DPR-50 ML20205Q5981999-04-13013 April 1999 Safety Evaluation Supporting Amend 209 to License DPR-50 ML20206P2841999-04-12012 April 1999 SER Approving Transfer of License for Tmi,Unit 1,held by Gpu Nuclear,Inc to Amergen Energy Co,Llc & Conforming Amend, Per 10CFR50.80 & 50.90 ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20153A9941998-09-16016 September 1998 Safety Evaluation Denying Request to Remove Missile Shields from Plant Design ML20151U8821998-09-0808 September 1998 SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2 ML20237A8331998-08-12012 August 1998 Safety Evaluation Accepting USI A-46 Program Implementation at Plant,Unit 1 ML20217K4851998-04-24024 April 1998 Safety Evaluation Supporting Amend 207 to License DPR-50 ML20199G8371998-01-22022 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Three Mile Island Nuclear Station,Unit 1 ML20198K2281997-10-16016 October 1997 Safety Evaluation Supporting Amend 206 to License DPR-50 ML20211G8561997-10-0202 October 1997 Safety Evaluation Supporting Amend 204 to License DPR-50 ML20210Q9991997-08-28028 August 1997 Safety Evaluation Concluding That Since 25th Tendon Surveillance on Few Yrs Away,Adequacy of Remaining Prestressing Force Will Be Critical to Verify ML20217Q7341997-08-27027 August 1997 Safety Evaluation Supporting Amend 203 to License DPR-50 ML20149F9961997-07-18018 July 1997 Safety Evaluation Re Gpu Nuclear Operational Quality Assurance Plan,Rev 10 for Three Mile Island Nuclear Generating Station,Unit 1 & Oyster Creek Nuclear Generating Station ML20149D2671997-07-11011 July 1997 SER Concluding That Exemption from Listed Fire Areas Should Be Granted & Exemption from Fire Area FH-FZ-5 Should Be Denied ML20138H6671996-12-19019 December 1996 Safety Evaluation Accepting Util IPE Submittal in Response to GL 88-20 ML20134D7811996-10-24024 October 1996 Safety Evaluation Supporting Amend 51 to License DPR-73 ML20128L6741996-10-11011 October 1996 Safety Evaluation Accepting Third ten-year Interval for Pump & Valve Inservice Testing Program for Facility ML20128K1981996-10-0808 October 1996 Safety Evaluation Supporting Amend 50 to License DPR-73 ML20094Q0301995-11-24024 November 1995 Safety Evaluation Supporting Amend 199 to License DPR-50 ML20092N2551995-10-0202 October 1995 Safety Evaluation Supporting Amend 197 to License DPR-50 ML20087G5771995-08-14014 August 1995 Safety Evaluation Supporting Amend 195 to License DPR-50 ML20086R7421995-07-24024 July 1995 Safety Evaluation Supporting Amend 194 to License DPR-50 ML20078H3961995-01-31031 January 1995 Safety Evaluation Supporting Amend 193 to License DPR-50 ML20077C2901994-11-28028 November 1994 Safety Evaluation Supporting Amend 192 to License DPR-50 ML20071N3991994-08-0101 August 1994 Safety Evaluation Supporting Amend 191 to License DPR-50 ML20071K8921994-07-25025 July 1994 Safety Evaluation Supporting Amend 188 to License DPR-50 ML20071K8741994-07-25025 July 1994 Safety Evaluation Supporting Amend 190 to License DPR-50 ML20071L2381994-07-25025 July 1994 Safety Evaluation Supporting Amend 189 to License DPR-50 ML20070H2851994-07-14014 July 1994 Safety Evaluation Supporting Amend 187 to License DPR-50 ML20073S3941994-05-23023 May 1994 Safety Evaluation Supporting Amend 184 to License DPR-50 ML20059D1771993-12-28028 December 1993 Safety Evaluation Supporting Amend 48 to License DPR-73 ML20062M2481993-12-21021 December 1993 Safety Evaluation Supporting Amend 180 to License DPR-50 ML20062K1041993-12-0606 December 1993 Safety Evaluation Supporting Amend 47 to License DPR-73 ML20058F0311993-11-16016 November 1993 SE Informing That Changes to Pdms Requirements & Commitments List of 930115,does Not Constitute Unreviewed Safety Question,Nor Do They Involve Significant Hazard or an Environmental Impact ML20059K3001993-11-0808 November 1993 Safety Evaluation Supporting Amend 46 to License DPR-73 ML20057A8321993-09-10010 September 1993 Safety Evaluation Supporting Amend 178 to License DPR-50 ML20057A3641993-09-0101 September 1993 SER Denying Licensee 930216 & 0416 Requests for Relief from Certain Requirements of ISI Program ML20056F0171993-08-0505 August 1993 Safety Evaluation Accepting Proposed Changes to Pdms Requirements & Commitments List of 930115 ML20045H5401993-07-12012 July 1993 Safety Evaluation Supporting Amend 44 to License DPR-73 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G1001999-10-14014 October 1999 Errata to Safety Evaluation Supporting Amend 215 to FOL DPR-50.Credit Given for Delay in ECCS Leakage ML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML20216F9231999-09-22022 September 1999 Safety Evaluation Supporting Amend 216 to License DPR-50 05000289/LER-1999-010, :on 990830,discovery of Condition Outside UFSAR Design Basis for Flood Protection Was Noted.Caused Because Original Problem Was Not Corrected by Design Change.Flood Procedure Was Immediately Revised.With1999-09-21021 September 1999
- on 990830,discovery of Condition Outside UFSAR Design Basis for Flood Protection Was Noted.Caused Because Original Problem Was Not Corrected by Design Change.Flood Procedure Was Immediately Revised.With
ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With ML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20211E8731999-08-24024 August 1999 Safety Evaluation Supporting Amend 215 to License DPR-50 ML20211B1931999-08-19019 August 1999 Safety Evaluation Supporting Amend 214 to License DPR-50 ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With 05000289/LER-1999-009, :on 990626,automatic Start of EDG 1A Occurred. Caused by Failure of Fault Pressure Relay on Auxiliary Transformer 1B.Failed Pressure Relay Has Been Replaced1999-07-22022 July 1999
- on 990626,automatic Start of EDG 1A Occurred. Caused by Failure of Fault Pressure Relay on Auxiliary Transformer 1B.Failed Pressure Relay Has Been Replaced
ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209H1421999-06-30030 June 1999 Monthly Operating Rept for June 1999 for TMI-1.With ML20212H9101999-06-21021 June 1999 Safety Evaluation Supporting Amend 212 to License DPR-50 05000289/LER-1999-007, :on 990528,increasing Failure Rate of ESAS Relays Characterized by Coil Overheating & Failing to Fully re-close After Being de-energized Was Discovered.Cause Indeterminate.Relay Check Procedure Has Been Changed1999-06-18018 June 1999
- on 990528,increasing Failure Rate of ESAS Relays Characterized by Coil Overheating & Failing to Fully re-close After Being de-energized Was Discovered.Cause Indeterminate.Relay Check Procedure Has Been Changed
05000289/LER-1999-005, :on 990514,open Flood Path Between Turbine Bldg & Control Bldg Was Noted.Caused by Failure to Recognize That Mods Affected Flood Protection.Revised Flood Procedures.With1999-06-14014 June 1999
- on 990514,open Flood Path Between Turbine Bldg & Control Bldg Was Noted.Caused by Failure to Recognize That Mods Affected Flood Protection.Revised Flood Procedures.With
ML20195H0751999-06-0808 June 1999 Drill 9904, 1999 Biennial Exercise for Three Mile Island ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With ML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 05000289/LER-1999-003-01, :on 990310,discovered Failure of Manual Balancing Damper in Supply Duct of Control Bldg Evs.Caused by Failure to Adequately Review Risk & Consequences of Change.Failed Damper Was Clamped Open1999-05-0707 May 1999
- on 990310,discovered Failure of Manual Balancing Damper in Supply Duct of Control Bldg Evs.Caused by Failure to Adequately Review Risk & Consequences of Change.Failed Damper Was Clamped Open
ML20206R0571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML20205Q6111999-04-15015 April 1999 Safety Evaluation Supporting Amend 210 to License DPR-50 ML20205Q5981999-04-13013 April 1999 Safety Evaluation Supporting Amend 209 to License DPR-50 ML20206P2841999-04-12012 April 1999 SER Approving Transfer of License for Tmi,Unit 1,held by Gpu Nuclear,Inc to Amergen Energy Co,Llc & Conforming Amend, Per 10CFR50.80 & 50.90 ML20205K6851999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) 05000289/LER-1999-002, :on 990212,potential Failure of Multiple Containment Monitoring Sys CIV (CM-V-1,2,3 & 4) Was Noted. Caused by Inappropriate Use of Vendor Info.Personnel Will Be Trained on Mgt Expectations.With1999-03-14014 March 1999
- on 990212,potential Failure of Multiple Containment Monitoring Sys CIV (CM-V-1,2,3 & 4) Was Noted. Caused by Inappropriate Use of Vendor Info.Personnel Will Be Trained on Mgt Expectations.With
ML20210C0161999-03-0101 March 1999 Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246 ML20207M8461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for TMI-1.With 05000289/LER-1999-001-01, :on 990122,short Sections of Piping Caused by Misplacement of Sensing Elements & Insulation.Caused by Failure to Adhere to Vendor instruction.Re-installed Heat Trace Sys1999-02-19019 February 1999
- on 990122,short Sections of Piping Caused by Misplacement of Sensing Elements & Insulation.Caused by Failure to Adhere to Vendor instruction.Re-installed Heat Trace Sys
ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits 05000289/LER-1998-014-01, :on 981210,missed TS Surveillance Was Noted. Caused by Human Error.Absolute & Relative Control Rod Positions Were Obtained Immediately & Verified to Agree within Required Range.With1999-01-11011 January 1999
- on 981210,missed TS Surveillance Was Noted. Caused by Human Error.Absolute & Relative Control Rod Positions Were Obtained Immediately & Verified to Agree within Required Range.With
ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20198B8641998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for TMI-1.With ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20196B7191998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for TMI-1.With ML20203G1211998-10-30030 October 1998 Informs Commission About Staff Preliminary Views Concerning Whether Proposed Purchase of TMI-1,by Amergen,Inc,Would Cause Commission to Know or Have Reason to Believe That License for TMI-1 Would Be Controlled by Foreign Govt ML20155E7511998-10-15015 October 1998 Rev 1 to Form NIS-1 Owners Data Rept for Isi,Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing 05000289/LER-1998-013, :on 980916,failure to Perform Fire Protection Program Surveillances at Required Frequency Was Noted.Caused by Changes Not Being Made to Surveillance Schedule.Performed Missed Insp Surveillance1998-10-15015 October 1998
- on 980916,failure to Perform Fire Protection Program Surveillances at Required Frequency Was Noted.Caused by Changes Not Being Made to Surveillance Schedule.Performed Missed Insp Surveillance
05000289/LER-1998-010-01, :on 980825,potential Violation of Design Criteria During Single Auxiliary Transformer Operation Occurred.Caused by Failure to Adequately Define Job Performance Stds.Temporary Change Notice Issued1998-10-0909 October 1998
- on 980825,potential Violation of Design Criteria During Single Auxiliary Transformer Operation Occurred.Caused by Failure to Adequately Define Job Performance Stds.Temporary Change Notice Issued
ML20154L5541998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for TMI Unit 1.With 05000289/LER-1998-011, :on 980825,Thermo-Lag Fire Barrier Was Found Installed Outside Approved Joint Design Arrangement.Caused by Personnel Error.Initiated Continuous Fire Watch & Installed Trowel Grade Thermo-Lag in Void & on Outer Edge1998-09-23023 September 1998
- on 980825,Thermo-Lag Fire Barrier Was Found Installed Outside Approved Joint Design Arrangement.Caused by Personnel Error.Initiated Continuous Fire Watch & Installed Trowel Grade Thermo-Lag in Void & on Outer Edge
05000289/LER-1998-009-01, :on 980820,discovered Potential Loss of HPI During Postulated Loca.Caused by Misapplication or Interpretation of Design Inputs.Revised OL Was Implemented & Mut Pressure & Level Limits Analysis Revised1998-09-18018 September 1998
- on 980820,discovered Potential Loss of HPI During Postulated Loca.Caused by Misapplication or Interpretation of Design Inputs.Revised OL Was Implemented & Mut Pressure & Level Limits Analysis Revised
1999-09-30
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UNITED STATES g
j NUCLEAR RECULATORY COMMISSION t
WASHINGTON, D.C. 20616 4001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION GPU NUCLEAR. INC.
AMPACITY DERATING ISSUES THREE MILE ISLAND NUCLEAR STATION. UNIT 1 DOCKET NO. 50-289 L
1.0 BACKGROUND
By letter dated June 24,1997, as supplemented by letter dated July 31,1997, GPU Nuclear, Inc., submitted a response to the second NRC Request for Additional Information (RAI) related to Generic Letter (GL) 92-08, "Thermo-Lag 330-1 Fire Barriers," for Three Mile Island, Unit 1 (TMI-1) dated May 8,1997.
The original licensee methodology which was the subject of the RAI utilized the insulated Power Conductor Engineers Association (IPCEA) Standard P-46-426 rather than ICEA Standard P-54-440 and assumed all cable ampacity limits based upon a cladded cable tray i
configuration regardless of the actualinstallation. Given these two critical starting assumptions, the licensee ampacity assessment proceeds as follows:
The initial baseline ampacity of a given cable is taken from manufacturer recommended I
i ampacity limits for cables installed in open air. These values appear to correspond closely to the IPCEA P-46-426 ampacity tables, again, assuming operation in open air.
This value of the open air ampacity is then adjusted for the assumed ambient temperature.
A value of either 35*C (95*F) or 40*C (104*F) has been assumed for all cables with one exception that involves a winter heating load, and for winter conditions assumption of a lower ambient appears appropriate.
The corrected open air baseline ampacity is then further adjusted to account for the i
placement of the cable within a cable tray. This is based on the application of an Ampacity Correction Factor (ACF) value taken from Table Vill of the IPCEA P-42-426 standard. This ACF is based on the total number of conductors in the tray. The result is an estimate of the cable tray installation baseline ampacity.
The cable tray baseline ampacity is then adjusted for the presence of the fire barrier system. All assessments have assumed a fire barrier Ampacity Derating Factor (ADF) of 32% (ACF of 0.68). The result is an estimate of the derated ampacity limit for a given cable in a given cable tray including the fire barrier impact.
Finally the derated ampacity limits are compared to actualin plant cable loads for an initial assessment of acceptability. This assessment has included consideration of potential undervoltage conditions of operation.
9901260482 990122 ENCLOSURE PDR ADOCK 05000209 P
PDR
l l.
For three cables nominally identified as overioeded, the licensee assessment uses an L
altamate National Electrical Code Eppiesch which allows for slightly higher ampacity limits.
The subject staff RAI had identified a number of open issues and concems requiring clarification by the licensee. The licensee's submittal dated June 24,1997, contained the l
response to staff questions regarding its ampacity dorating methodology and the licensee's submittal dated July 31,1997, updated the subject ampacity calculations. The staff evaluation of the ampacity dorating methodology for TMl-1 follows.
2.0 EVALUATION After reviewing the licensee's submittals and SNL Technical Letter Report (see Attachment),
l the staff agrees with the SNL analyses and conclusions. The ampacity dorating analysis l
questions, the licensee's responses, and the staff's evaluations of the responses follow.
Ampacity Derating Analysis Review Question 1 Sandia National Laboratories (SNL) made the following finding after a review of the licensee's cable ampacity assessment method which is based on the random fill tray l
correction factors from IPCEA P-46-426:
The methodology applied by the licensee was taken from IPCEA P-46-426, which in tum cites IPCEA publication P-33 440 as i
the basis for the cited ampacity correction factors for random fill trays.
ICEA P-54-440 specifically states that the P-33 440 (a.k.a., P-46-426) methodology for random fill trays is superseded by the P-54-440 approach. Hence, SNL finds that the licensee has applied an outdated and inappropriate methodology to the analysis of its cable tray ampacity limits. While licensee approach may actually be conservative for some of the cases examined, SNL also demonstrated that the approach can lead to nonconservative results as well. SNL finds that the P-54-440 methodology is applicable to the licensee cases and should be included in the evaluation.
Given the above finding the licensee is requested to provide an assessment of the applicable ampacity limits using the ICEA P-54-440 methodology for any cable in a cable tray with three or more cables and for those cables with an available ampacity margin (i.e.,
after the application of dorating factors) of 30% or less including the following seven circuits recommended by SNL LS6, ME1, ME2, MB11 (winter configuration only), MC12 (s. inter configuration only), CH61 and LSS.
i l
Licensee Resoonse l
l In its submittal dated June 24,1997, the licensee stated that the subject calculation will be
(
revised to include an assessment of ampacity limits using ICEA P-54-440 methodology.
The licensee's submittal dated Juiv 31,1997, provided the revised ampacity calculations for staff review.
i
4
. Staff Response The information provided by the licenses fully resolves the staff's concems.
Question 2 It should be noted that the licensee's response to the staff question regarding an assessment of overloaded cables as detailed in the Request for information dated July 5, 1996, may require reevaluation given satisfactory resolution for the concems stated in item 1 above. In addition, the licensee is requested to conservatively estimate the remaining cable life for any cables which may have operated under overloaded conditions.
1 Licensee Response In its submittal dated June 24,1997, the licensee stated that the preliminary analysis using the P-54-440 methodology indicates that one cable, LS6, is nominally overloaded. An operating life assessment for this cable was performed that indicated a life expectancy extending at least to January 30,1999; however, it could not guarantee operation until end of plant life (i.e., September 1,2014.) Through a surveillance procedure (OPS-S94), the licensee will monitor the actual hours energized for the circuit associated with subject cable until the elapsed time indicates that the end of life condition has been reached for cable LS6. The licensee calculation also notes that " Remedial follow-up actions are required to assure cable LS6 life."
This statement implies that the licensee will take corrective actions as necessary prior to the end of life condition for cable LS6.
Staff Response The information provided by the licensee fully resolves the staff's concems.
Question 3 1
Given that SNL noted apparent depth of fill and conductor discrepancies in the review of the Tray 531/533 case, the licensee is requested to document the applicable calculations in sufficient detail that both the depth of fill and ampacity limit calculations can be verified by SNL. (See Section 2.2.3 of the SNL Letter Report dated April 10,1998, Attachment 1(a))
Licensee Response in its submittal dated June 24,1997, the licensee noted that there was a discrepancy between the cable diameters cited in two different supporting documents. This discrepancy was cited as the basis for the apparent error noted by SNL. Field measurements were made to verify which set of values was correct, and the updated calculations have been performed using these correct diameters.
l l
. Staff Response The information provided by the licensee fully resolves the staffs concems.
Application of Amoscity Deratina "rf;c-dc4c-2v The staff finds that the licensee has adequately resolved all of the previously identified RAI items. Specifically, the licensee has reanalyzed all of its fire barrier cladded power cables in cable tray applications using the accepted methods of ICEA P-54-440. The fire barrier tray derating factor of 32% determined by tests under the sponsorship of Texas Utilities is based on the ampacity of cables tightly packed in a tray with no air flow up through the tray. The tightly packed tray is considered to the be worst case configuration and bounds the configuration where cables are installed in trays without maintained spacing. The tightly packed tray is the configuration assumed by ICEA P-54-440 and is therefore consistent with the testing which determined the dorating factor.
Except for Cable LS6, all cables were found to be operating within acceptable ampacity limits. A monitoring procedure for the nominally overioeded Cable LS6 has been put in place to ensure that remedial actions can be taken before the cable exceeds its life expectancy.
Given the revised methodology and the licensee commitment to monitor for age-related degradation for cable LS6, the staff finds that the licensee has provided adequate information to resolve the ampacity-related points of concem raised in GL 92-08.
3.0 CONCLUSION
From the above evaluation, the staff concludes that although the original licensee thermal model was not acceptable for ampacity dorating assessments the revised model identified in its submittal dated June 24,1997, was appropriate for the analysis of installed electrical raceway ampacity limits in its submittal dated July 31,1997, the licensee stated that i
additional corrective actions will be taken to evaluate and monitor as necessary operating conditions for cable LS6. Therefore, given the I;censee's commitment to address age-related cable degradation there are no outstanding safety concems with respect to ampacity.
Principal Contributor. R. Jenkins Date: January 22, 1999 l