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| {{#Wiki_filter:~'REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR: 8408300243 | | {{#Wiki_filter:~ |
| .DOC~DATE: 84/08/24 NOTAR I ZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant~Unit 1<Carolina 05000400 AUTH, NAME AUTHOR AFFILIATION ZIMMERMANiS | | REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| ~RE Carolina Power L Light Co.REC IP~NAME RECIPIENT AFFILIATION DENTON~H~Ri" Office of Nuclear Reactor Regulationi Di,rector | | ACCESSION NBR: 8408300243 . DOC ~ DATE: 84/08/24 NOTAR I ZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant~ Unit 1< Carolina 05000400 AUTH, NAME AUTHOR AFFILIATION ZIMMERMANiS ~ RE Carolina Power L Light Co. |
| | REC IP ~ NAME RECIPIENT AFFILIATION DENTON~H ~ Ri " |
| | Office of Nuclear Reactor Regulationi Di,rector |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Forwards responses to written L verval questions raised by Equipment Qualification Branch reviewers during insp conducted on 840809 L 10.DISTR I BUT I ON CODE A 048D COP IES RECEI VED LTR Ef<CL S I ZE~TITLE: OR/Licensing Submittal: | | Forwards responses to written L verval questions raised by Equipment Qualification Branch reviewers during insp conducted on 840809 L 10. |
| Equipment Qualification NOTES: RECIPIENT ID CODE/NAME NRR LB3 BC 12 COPIES LTTR ENCL 1 0 RECIPIENT COPIES ID CODE/NAME LTTR ENCL BUCKLEYiB 01 1 1 INTERNAL: ADM/LFMB GC 13 NRR KARSCHiR NRR/DL DIR 14 NRR/DSI/AEB RGN2 1 0 1 1 1 1 1 1 1 1 1 ELD/HDS1 12 IE FILE 09 NRR/DE/EQB 07 N RAB 06 G FILE 04 1 1 1 1 2 2 1 1 EXTERNALS AC'RS NRC PDR NTIS 15 02 31 8 8 1 1 1 1 LPDR NSIC 03 05 TOTAL NUMBER, OF COPIES REQUIRED:, LTTR 26 ENCL 24 1 o I , f 14 f~'p~f~1 I,'i't e'II r).S f CXQE, Carolina Power&Light Company NJG 3 4 t984 SERIAL: NLS-84-376 Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO.1-DOCKET NO.50-400 ENVIRONMENTAL QUALIFICATION PROGRAM | | DISTR I BUT I ON CODE A 048D COP IES RECEI VED LTR Ef<CL S I ZE ~ |
| | TITLE: OR/Licensing Submittal: Equipment Qualification NOTES: |
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR LB3 BC 12 1 0 BUCKLEYiB 01 1 1 INTERNAL: ADM/LFMB 1 0 ELD/HDS1 12 1 1 GC 13 1 IE FILE 09 1 1 NRR KARSCHiR 1 1 NRR/DE/EQB 07 2 2 NRR/DL DIR 14 1 1 N RAB 06 1 NRR/DSI/AEB 1 1 G FILE 04 1 RGN2 1 1 EXTERNALS AC'RS 15 8 8 LPDR 03 NRC PDR 02 1 1 NSIC 05 NTIS 31 1 1 TOTAL NUMBER, OF COPIES REQUIRED:, LTTR 26 ENCL 24 |
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| ==Dear Mr.Denton:== | | 1 o I |
| Carolina Power&Light Company hereby provides responses to the written and verbal questions raised by the Equipment Qualification Branch reviewers during the inspection conducted on August 9 and 10, 1984 at the Shearon Harris site.The questions and responses are contained in the attachment. | | , f 14 f ~' p ~ f e |
| Should you have any questions with regard to this issue, please contact Mr.Pedro Salas at (919)836-8015.Yours very truly, S.R.immerman Manager Nuclear Licensing Section PS/pgp (496PSA/pgp) | | ~ 1 I,' i' t II |
| Attachment Cc1 Hr.B.C.Buckley (NRC)Mr.Armand Masciantonio (NRC-NRR/EQ) | | |
| Hr.Bob Legrange (NRC-NRR/EQ) | | r). |
| Mr.G.F.Maxwell (NRC-SHNPP) | | S f CXQE, Carolina Power & Light Company NJG 3 4 t984 SERIAL: NLS-84-376 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 DOCKET NO. 50-400 ENVIRONMENTAL QUALIFICATION PROGRAM |
| Mr.J.P.O'Reilly (NRC-RII)Mr.Travis Payne (KUDZU)Mr.Daniel F.Read (CHANGE/ELP) | | |
| Chapel Hill Public Library Wake County Public Library Hr.Wells Eddleman Hr.John D.Runkle Dr.Richard D.Wilson Mr.G.0.Bright (ASLB)Dr.J.H.Carpenter (ASLB)Mr.J.L.Kelley (ASLB)8408300243 8408~4 PDR ADOCK 05000400 PDR 411 Fayettevilte Street o P.O.Box 1551 o Raleigh.N.C.27602 r | | ==Dear Mr. Denton:== |
| fy ATTACHMENT LIMITOR UE MOTOR OPERATOR 1.Verify that the[Limitorque] | | |
| motor operator orientation of the tested equipment is the same as those motor operators being qualified in this[Limitorque] | | Carolina Power & Light Company hereby provides responses to the written and verbal questions raised by the Equipment Qualification Branch reviewers during the inspection conducted on August 9 and 10, 1984 at the Shearon Harris site. The questions and responses are contained in the attachment. |
| package.Provide justification or analysis for those operators not having the same orientation as the tested equipment. | | Should you have any questions with regard to this issue, please contact Mr. Pedro Salas at (919) 836-8015. |
| ~Res onse: Motor operators are installed per piping drawings at Shearon Harris'hese drawings are prepared by the design engineering group with input from each vendor to assure that orientation of the operator is the same as during testing, or that any changes are justified. | | Yours very truly, S. R. immerman Manager Nuclear Licensing Section PS/pgp (496PSA/pgp) |
| The field uses these drawings as installation criteria.Isometrics are verified in the field and the results transmitted to the site design engineering group.In addition, motor operator orientation of active valves in harsh environments will be verified in our equipment qualification walkdown which has already begun.To date, no deviations have been found.2.The material analysis performed in Section E[Limitorque Report], under aging, only addresses the insulation materials. | | Attachment Cc1 Hr. B. C. Buckley (NRC) Hr. Wells Eddleman Mr. Armand Masciantonio (NRC-NRR/EQ) Hr. John D. Runkle Hr. Bob Legrange (NRC-NRR/EQ) Dr. Richard D. Wilson Mr. G. F. Maxwell (NRC-SHNPP) Mr. G. 0. Bright (ASLB) |
| A more in-depth analysis of the non-metallic materials found on the Limitorque operator should be presented (the 0-rings should be included). | | Mr. J. P. O'Reilly (NRC-RII) Dr. J. H. Carpenter (ASLB) |
| ~Res onse: A more expanded materials analysis will be included in Section E of the reviewed document.However, there is no safety concern because: a)Limitorque has stated that the insulation material has the lowest activation energy of the non-metallic materials used;i.e., it is the limiting material.b)Limitorque has certified that Equipment Qualification Report Nos.600456 and B0058 are applicable to our valves.Report B0058 includes an analysis of the non-metallic materials, including 0-rings.(Material information of a more detailed nature is considered proprietary by Limitorque.) | | Mr. Travis Payne (KUDZU) Mr. J. L. Kelley (ASLB) |
| c)Report B0058 has been certified to be adequate by CPSL, as documented in the equipment qualification package and has been accepted at other plants by the NRC.3.What is the maximum normal temperature that these operators will experience, and provide justification for not using the maximum normal temperature in the aging methodology. | | Mr. Daniel F. Read (CHANGE/ELP) |
| | Chapel Hill Public Library Wake County Public Library 8408300243 8408~4 PDR ADOCK 05000400 PDR 411 Fayettevilte Street o P. O. Box 1551 o Raleigh. N. C. 27602 |
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| | r fy ATTACHMENT LIMITOR UE MOTOR OPERATOR |
| | : 1. Verify that the [Limitorque] motor operator orientation of the tested equipment is the same as those motor operators being qualified in this |
| | [Limitorque] package. Provide justification or analysis for those operators not having the same orientation as the tested equipment. |
| | ~Res onse: |
| | Motor operators are installed per piping drawings at Shearon drawings are prepared by the design engineering group with input Harris'hese from each vendor to assure that orientation of the operator is the same as during testing, or that any changes are justified. The field uses these drawings as installation criteria. Isometrics are verified in the field and the results transmitted to the site design engineering group. |
| | In addition, motor operator orientation of active valves in harsh environments will be verified in our equipment qualification walkdown which has already begun. To date, no deviations have been found. |
| | : 2. The material analysis performed in Section E [Limitorque Report], under aging, only addresses the insulation materials. A more in-depth analysis of the non-metallic materials found on the Limitorque operator should be presented (the 0-rings should be included). |
| | ~Res onse: |
| | A more expanded materials analysis will be included in Section E of the reviewed document. However, there is no safety concern because: |
| | a) Limitorque has stated that the insulation material has the lowest activation energy of the non-metallic materials used; i.e., it is the limiting material. |
| | b) Limitorque has certified that Equipment Qualification Report Nos. 600456 and B0058 are applicable to our valves. Report B0058 includes an analysis of the non-metallic materials, including 0-rings. (Material information of a more detailed nature is considered proprietary by Limitorque.) |
| | c) Report B0058 has been certified to be adequate by CPSL, as documented in the equipment qualification package and has been accepted at other plants by the NRC. |
| | : 3. What is the maximum normal temperature that these operators will experience, and provide justification for not using the maximum normal temperature in the aging methodology. |
| | (493PSA/ccc) |
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| | ~Res onse: |
| | The maximum postulated normal temperature inside containment for these operators is 120'F as shown in Tab E page 2F of 3F of the qualification package. This temperature was used in the aging analysis. |
| | : 4. How is 0-ring qualification assured? |
| | ~Res onse: |
| | Carolina Power & Light Company has maintained written and verbal communications with Limitorque to assure that the valve operators have qualified 0-rings. Limitorque has provided certification letters which provide traceability of the Shearon Harris operators by Limitorque Shop Order Numbers. |
| | : 5. Is walkdown of Limitorque valves to be 100 percent? |
| | ~Res onse: |
| | All Limitorque operators on active valves in a harsh environment will be field verified. |
| | : 6. Will there be walkdowns of other safety-related electrical equipment? |
| | ~Res onse: |
| | Walkdowns will be performed on other safety-related electrical equipment in a harsh environment. The equipment will be selected on a sample basis using good engineering practice to select the sample type and size. |
| | : 7. Are Limitorque operators at Shearon Harris required to be sealed? |
| | ~Res onse: |
| | Limitorque operators on safety-related, active valves are sealed at the conduit entry point. |
| (493PSA/ccc) | | (493PSA/ccc) |
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| ~Res onse: The maximum postulated normal temperature inside containment for these operators is 120'F as shown in Tab E page 2F of 3F of the qualification package.This temperature was used in the aging analysis.4.How is 0-ring qualification assured?~Res onse: Carolina Power&Light Company has maintained written and verbal communications with Limitorque to assure that the valve operators have qualified 0-rings.Limitorque has provided certification letters which provide traceability of the Shearon Harris operators by Limitorque Shop Order Numbers.5.Is walkdown of Limitorque valves to be 100 percent?~Res onse: All Limitorque operators on active valves in a harsh environment will be field verified.6.Will there be walkdowns of other safety-related electrical equipment?
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| ~Res onse: Walkdowns will be performed on other safety-related electrical equipment in a harsh environment.
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| The equipment will be selected on a sample basis using good engineering practice to select the sample type and size.7.Are Limitorque operators at Shearon Harris required to be sealed?~Res onse: Limitorque operators on safety-related, active valves are sealed at the conduit entry point.(493PSA/ccc) li BIW INSTRUMENT CABLE Is the cable (BIW)required to operate submerged?
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| ~Res onse: BIW cable at Shearon Harris is not required to operate submerged.
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| An evaluation is currently being conducted to determine if there are any cables, other than BIW, which will be required to operate submerged.
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| Cables required to operate in a submerged condition will be qualified for the condition.
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| The results will be included in the documentation packages for those cables.2.Insulation Resistance (IR)values during the LOCA test were performed, however, no analysis or summary was presented on how the observed decrease in IR values may affect loop accuracies.
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| ~Res onse: The IR values observed during environmental qualification testing are currently being used to perform a leakage current study for the Class lE instruments utilizing these cables.The results of the study will be evaluated to determine effects on instrument loop accuracies and setpoints.
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| The results of the study and the evaluation will be documented.
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| 3.What is the minimum acceptable IR value before the cable is considered to have failed?~Res onse;Various acceptance criteria were used during the review of the EQ test reports.For the instrument cables the acceptance criteria include: continuity during the LOCA simulation, ability to carry current and hold a voltage during the tests, and the ability to pass the voltage withstand test.In addition, the IR values measured during the tests are reviewed for overall behavior during the tests, in particular that they recover towards the original values.The above tests serve to indicate that the cables are qualified.
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| 4~In Section F of the EQ package, it states that interfaces were not part of the qualification.
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| Where are the cable terminations addressed in the EQ submittal?
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| ~Res onse: Triaxial cable installation interface consists of the connectors, which are qualified by separate documentation packages associated with the individual type of equipment where the connector is required.These packages will be available for site audit.(493PSA/ccc)
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| 5.The description of the test set-up, including the manner in which the cable penetrated the test vessel, has not been placed in the test report.How is the installation kept consistent with the tested configuration? | | li BIW INSTRUMENT CABLE Is the cable (BIW) required to operate submerged? |
| ~Res onse: The attachment to BIW letter dated July 18, 1983 shows the test set-up in the autoclave. | | ~Res onse: |
| BIW utilized a three foot tray section inside the test chamber.The tray is below the chemical spray nozzle.The vendor indicated that the cables were laid on the tray.The cables were brought out through the test chamber opening which was sealed with an epoxy compound.Cable trays are used to route cables inside the plant.As such, the test set-up does represent the field installation. | | BIW cable at Shearon Harris is not required to operate submerged. An evaluation is currently being conducted to determine if there are any cables, other than BIW, which will be required to operate submerged. |
| The above referenced letter is included in the final EQ package for this cable, which is currently under revision.6.Were IR measurements taken on all instrument cables during their environmental qualification tests?~Res onse: The Shearon Harris EQ program includes insulation resistance measurements of all instrument cables during qualification testing.7.Is instrument cable used with safety-related equipment at Shearon Harris qualified without its jacket?~Res onse: The qualification of Class 1E instrument cables, except for coaxial and triaxial cables, is performed using jacketed and unjacketed cable samples.For the coaxial and triaxial cables, the tests are performed with the jacketed cables intact.This is how the cables are installed at the connectors. | | Cables required to operate in a submerged condition will be qualified for the condition. The results will be included in the documentation packages for those cables. |
| A qualified heat shrink material is then put over the connectors of the cables during installation. | | : 2. Insulation Resistance (IR) values during the LOCA test were performed, however, no analysis or summary was presented on how the observed decrease in IR values may affect loop accuracies. |
| (493PSA/ccc) f[V RESISTANCE TEMPERATURE DETECTOR (RTD)1.Please reconcile the following statements made in the RTD Qualification Package: o Qualified life of 20-23 years is claimed by using an activation energy of 0.98 eV for epoxy.~Res onse: | | ~Res onse: |
| | The IR values observed during environmental qualification testing are currently being used to perform a leakage current study for the Class lE instruments utilizing these cables. The results of the study will be evaluated to determine effects on instrument loop accuracies and setpoints. The results of the study and the evaluation will be documented. |
| | : 3. What is the minimum acceptable IR value before the cable is considered to have failed? |
| | ~Res onse; Various acceptance criteria were used during the review of the EQ test reports. For the instrument cables the acceptance criteria include: |
| | continuity during the LOCA simulation, ability to carry current and hold a voltage during the tests, and the ability to pass the voltage withstand test. In addition, the IR values measured during the tests are reviewed for overall behavior during the tests, in particular that they recover towards the original values. The above tests serve to indicate that the cables are qualified. |
| | 4 ~ In Section F of the EQ package, it states that interfaces were not part of the qualification. Where are the cable terminations addressed in the EQ submittal? |
| | ~Res onse: |
| | Triaxial cable installation interface consists of the connectors, which are qualified by separate documentation packages associated with the individual type of equipment where the connector is required. These packages will be available for site audit. |
| | (493PSA/ccc) |
| | : 5. The description of the test set-up, including the manner in which the cable penetrated the test vessel, has not been placed in the test report. How is the installation kept consistent with the tested configuration? |
| | ~Res onse: |
| | The attachment to BIW letter dated July 18, 1983 shows the test set-up in the autoclave. BIW utilized a three foot tray section inside the test chamber. The tray is below the chemical spray nozzle. The vendor indicated that the cables were laid on the tray. |
| | The cables were brought out through the test chamber opening which was sealed with an epoxy compound. Cable trays are used to route cables inside the plant. As such, the test set-up does represent the field installation. The above referenced letter is included in the final EQ package for this cable, which is currently under revision. |
| | : 6. Were IR measurements taken on all instrument cables during their environmental qualification tests? |
| | ~Res onse: |
| | The Shearon Harris EQ program includes insulation resistance measurements of all instrument cables during qualification testing. |
| | : 7. Is instrument cable used with safety-related equipment at Shearon Harris qualified without its jacket? |
| | ~Res onse: |
| | The qualification of Class 1E instrument cables, except for coaxial and triaxial cables, is performed using jacketed and unjacketed cable samples. For the coaxial and triaxial cables, the tests are performed with the jacketed cables intact. This is how the cables are installed at the connectors. A qualified heat shrink material is then put over the connectors of the cables during installation. |
| | (493PSA/ccc) |
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| ==Reference:==
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| 1.WCAP 8587, Appendices B and U 2.WCAP 8687-ESE 5 and 6 Carolina Power&Light Company evaluated the accelerated aging part of the RTD test program (Reference 2)utilizing the Arrhenius methodology and 0.98 eV as the controlling activation energy (E)(Epoxy: Ea=0.98 eV as specified by Reference 2).Results of this evaluation indicate that a 23 year qualified life at SHNPP is appropriate. | | RESISTANCE TEMPERATURE DETECTOR (RTD) |
| o"The qualified life is limited to ten (10)years by the expected radiation during the ten (10)year life and the DBE."~Res onse: The Westinghouse generic qualification program included an exposure of 70 megarads which corresponds to that expected over a ten-year normal installed life of the wide range RTDs.Shearon Harris plant specific, worst case, normal radiation exposure is 3.5 megarads for the same RTDs.Therefore, 10 years is a conservative qualified life.0 In calculating the post accident operability time demonstrated, an activation energy of 0.5 eV was used.~Res onse: | | : 1. Please reconcile the following statements made in the RTD Qualification Package: |
| | o Qualified life of 20-23 years is claimed by using an activation energy of 0.98 eV for epoxy. |
| | ~Res onse: |
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| ==Reference:== | | ==Reference:== |
| | : 1. WCAP 8587, Appendices B and U |
| | : 2. WCAP 8687 ESE 5 and 6 Carolina Power & Light Company evaluated the accelerated aging part of the RTD test program (Reference 2) utilizing the Arrhenius methodology and 0.98 eV as the controlling activation energy (E ) |
| | (Epoxy: Ea = 0.98 eV as specified by Reference 2). Results of this evaluation indicate that a 23 year qualified life at SHNPP is appropriate. |
| | o "The qualified life is limited to ten (10) years by the expected radiation during the ten (10) year life and the DBE." |
| | ~Res onse: |
| | The Westinghouse generic qualification program included an exposure of 70 megarads which corresponds to that expected over a ten-year normal installed life of the wide range RTDs. Shearon Harris plant specific, worst case, normal radiation exposure is 3.5 megarads for the same RTDs. Therefore, 10 years is a conservative qualified life. |
| | 0 In calculating the post accident operability time demonstrated, an activation energy of 0.5 eV was used. |
| | ~Res onse: |
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| 1.WCAP-8587, Appendices B and D 2.WCAP-8687-ESE 5 and 6 An activation energy of 0.5 eV was utilized initially by CP&L and Westinghouse as the controlling activation energy (Ea)for the post accident evaluation since Westinghouse developed the conservative generic post accident test profile using 0.5 eV as the reference Ea (Reference 1).As previously indicated, 0.98 eV is the controlling activation energy and is being used by CP&L in revising the RTD qualification package.(493PSA/ccc) | | ==Reference:== |
| | : 1. WCAP-8587, Appendices B and D |
| | : 2. WCAP-8687 ESE 5 and 6 An activation energy of 0.5 eV was utilized initially by CP&L and Westinghouse as the controlling activation energy (Ea) for the post accident evaluation since Westinghouse developed the conservative generic post accident test profile using 0.5 eV as the reference Ea (Reference 1). As previously indicated, 0.98 eV is the controlling activation energy and is being used by CP&L in revising the RTD qualification package. |
| | (493PSA/ccc) |
| | : 2. What is the maximum expected normal temperature for these RTDs? |
| | ~Res onse: |
| | The maximum expected normal temperature for the narrow range/wide range RTDs is based on a 50'C service temperature for ambient conditions plus an additional 50'C temperature rise resulting from heat transfer from the reactor coolant system. Thus the total expected maximum normal temperature for the well mounted and bypass manifold RTDs is 100'C or 212'F. This is presently documented in CP&L's qualification report. |
| | : 3. Justify the 50'C temperature rise assured in the aging calculations. |
| | ~Res onse: |
| | Westinghouse has performed a heat transfer calculation using 620'F as a reactor coolant system fluid temperature, a maximum of 140'F as the ambient temperature around the area of the epoxy potting material and a minimum air velocity of 5.0 ft/sec in this area. This results in a conservative temperature rise of 50'C. |
| | : 4. The basis for activation energy used in calculations could not be located in the file. Provide the reference and basis for the activation energy used. |
| | ~Res onse: |
| | The 0.98 eV activation energy used for the epoxy has two sources: |
| | a) WCAP-8587 "Methodology for Qualifying Westinghouse WRD Supplied NSSS Safety Related Electrical Equipment" page D-12 documents the results of a study conducted by Westinghouse and shows that the minimum activation energy for a cast epoxy is 0.98 eV. |
| | b) EPRI Report NP-1558 (September 1980) "A Review of Equipment Aging Theory and Technology" page 84 documents an activation energy of 0.98 eV for epoxy based on 50% retention of flexural strength. |
| | (493PSA/ccc) |
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| 2.What is the maximum expected normal temperature for these RTDs?~Res onse: The maximum expected normal temperature for the narrow range/wide range RTDs is based on a 50'C service temperature for ambient conditions plus an additional 50'C temperature rise resulting from heat transfer from the reactor coolant system.Thus the total expected maximum normal temperature for the well mounted and bypass manifold RTDs is 100'C or 212'F.This is presently documented in CP&L's qualification report.3.Justify the 50'C temperature rise assured in the aging calculations.
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| ~Res onse: Westinghouse has performed a heat transfer calculation using 620'F as a reactor coolant system fluid temperature, a maximum of 140'F as the ambient temperature around the area of the epoxy potting material and a minimum air velocity of 5.0 ft/sec in this area.This results in a conservative temperature rise of 50'C.4.The basis for activation energy used in calculations could not be located in the file.Provide the reference and basis for the activation energy used.~Res onse: The 0.98 eV activation energy used for the epoxy has two sources: a)WCAP-8587"Methodology for Qualifying Westinghouse WRD Supplied NSSS Safety Related Electrical Equipment" page D-12 documents the results of a study conducted by Westinghouse and shows that the minimum activation energy for a cast epoxy is 0.98 eV.b)EPRI Report NP-1558 (September 1980)"A Review of Equipment Aging Theory and Technology" page 84 documents an activation energy of 0.98 eV for epoxy based on 50%retention of flexural strength.(493PSA/ccc) c n H!'
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| LUBRICATION In the case where specific brands of lubricants are not recommended by the equipment manufacturer, how does CP&L assure that lubricants used are environmentally qualified? | | LUBRICATION In the case where specific brands of lubricants are not recommended by the equipment manufacturer, how does CP&L assure that lubricants used are environmentally qualified? |
| ~Res oese: Carolina Power&Light Company has contracted a leading lubrication vendor to perform a lubrication study for Shearon Harris.The study has been received and it documents the lubricants that can be used in the cases where the vendor has not specifically recommended a particular brand.CP&L is currently reviewing the lubricant vendor's documentation which was produced to support the report.An equipment qualification package will be generated using the same procedure used for other equipment. | | ~Res oese: |
| In the study, radiation stability, or conversely the amount of radiation damage, is measured using conventional physical and chemical analysis and by comparing the results with the unirradiated material.In addition, standard performance tests are performed on previously irradiated material or as a dynamic procedure during irradiation. | | Carolina Power & Light Company has contracted a leading lubrication vendor to perform a lubrication study for Shearon Harris. The study has been received and it documents the lubricants that can be used in the cases where the vendor CP&L is currently has not specifically recommended a particular brand. |
| These test results are compared to the original equipment manufacturer's test reports to assure that the lubrication performance criteria have been enveloped. | | reviewing the lubricant vendor's documentation which was produced to support the report. An equipment qualification package will be generated using the same procedure used for other equipment. In the study, radiation stability, or conversely the amount of radiation damage, is measured using conventional physical and chemical analysis and by comparing the results with the unirradiated material. In addition, standard performance tests are performed on previously irradiated material or as a dynamic procedure during irradiation. |
| This information will be available in an equipment qualification package when complete.(493PSA/ccc) t}} | | These test results are compared to the original equipment manufacturer's test reports to assure that the lubrication performance criteria have been enveloped. |
| | This information will be available in an equipment qualification package when complete. |
| | (493PSA/ccc) |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18017A9241999-10-15015 October 1999 Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools 'C' & 'D' in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18017A9141999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon ML18017A9131999-10-0606 October 1999 Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld ML18017A8911999-09-30030 September 1999 Submits Comment on Encl 2 to 990617 Memo Titled Summary of Meeting with Nuclear Energy Inst. Encl 2 Was Titled Draft Technical Study of Spent Fuel Pool Accidents for Decommissioning Plants. Rept Which Provides Info Encl Also ML20216G3501999-09-29029 September 1999 Confirms Conversations Re NRC Staff Voluntary Response to Orange County Discovery Requests.Staff Will Voluntarily Answer Discovery Requests & Will Not Waive Any Objection or Privilege Under NRC Regulations.Related Correspondence ML20212M1081999-09-29029 September 1999 Confirms Intent to Meet with Utils on 991025 in Atlanta,Ga to Discuss Pilot Plants,Shearon Harris & Sequoyah Any Observations & Lessons Learned & Recommendations Re Implementation of Pilot Program ML20212J0741999-09-29029 September 1999 Refers to Proposed License Amend for Harris NPP Which Would Allow Licensee to Activate Two of Plant Spent Fuel Pools.Serves Copy of Orange County Second Set of Document Requests to NRC Staff,Dtd 990929.Related Correspondence ML18017A8941999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves. ML18017A8881999-09-27027 September 1999 Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii) ML18017A8861999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18017A8821999-09-14014 September 1999 Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6) ML18017A8651999-09-0808 September 1999 Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety ML18017A8581999-09-0303 September 1999 Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity ML18017A8551999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS ML18017A8541999-08-20020 August 1999 Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided HNP-99-134, Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.211999-08-18018 August 1999 Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.21 ML18017A8351999-08-10010 August 1999 Corrects Statement Made in 980923 Ltr,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment ML18016B0531999-08-0606 August 1999 Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl ML18016B0461999-08-0404 August 1999 Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS Requirements ML18016B0391999-07-30030 July 1999 Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed ML18016B0421999-07-30030 July 1999 Informs That in Ltr Dtd 950330 CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998 ML18016B0221999-07-26026 July 1999 Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 990930 ML18016B0171999-07-16016 July 1999 Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP ML18016B0051999-07-0101 July 1999 Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl ML20212H7741999-06-23023 June 1999 Responds to Re Petition Filed by Orange County Board of Commissioners Re Proposed Expansion of Sf Storage Capacity at Shearon Harris Npp.Public Meeting Will Be Held at Later Date.With Certificate of Svc.Served on 990624 ML18016A9871999-06-14014 June 1999 Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service,Dtd 981223.Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18016A9831999-06-10010 June 1999 Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated ML20212H7521999-06-0404 June 1999 Encourages NRC to Schedule Open Public Forum Which Would Allow Local Citizens to Express Concerns Re Proposed Expansion of high-level Radwaste Storage Capacity at Shearon Harris Npp.With Certificate of Svc.Served on 990624 ML18016A9721999-05-28028 May 1999 Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. ML18016B0011999-05-26026 May 1999 Forwards Ltr Received from Hj Jaffe Expressing Concern Re Cpl Proposal to NRC on Dec of 1998 to Make Harris Nuclear Plant Largest Storage Area for High Level Nuclear Waste in Nation ML18016A9631999-05-25025 May 1999 Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend ML20206R2511999-05-19019 May 1999 Responds to Addressed to Chairman Jackson Requesting That NRC Grant Standing to Orange County Board of Commissioners in Shearon Harris Proceeding Currently Before Board.With Certificate of Svc.Served on 990519 ML20206Q5281999-05-17017 May 1999 Responds to 990304 Request for Two Rail Routes to Be Used for Transport of Spent Fuel from Brunswick Steam Electric Plant,Southport,Nc & Hb Robinson Steam Electric Plant, Hartsville,Sc to Shearon Harris Npp,Near New Hill,Sc ML18016A9511999-05-13013 May 1999 Submits Info Re Estimated Effect of Change to ECCS Evaluation Model,As Required by 10CFR50.46 ML18016A9601999-05-11011 May 1999 Forwards Resolution Adopted by Carrboro Board of Aldermen at 990504 Meeting.Resolution Expresses Town Concern Re Util Plans to Double high-level Nuclear Waste Storage at Shnpp ML18016A9481999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Examination by Facility Licensee, for Senior Reactor Operator Licensed to Operate Hnp.Individuals Info Is Proprietary & Is Being Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20206R2611999-05-0505 May 1999 Requests That NRC Grant Standing to Intervention Sought by Orange County Board of Commissioners Re Proposal by CP&L to Expand Storage of Hlrw at Shnpp.With Certificate of Svc. Served on 990519 ML18016A9451999-05-0404 May 1999 Provides Proprietary Notification That One SRO Has Been Reassigned from Position for Which Util Certified Need for SRO License & Another SRO Has Terminated Employment with Util.Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9441999-05-0404 May 1999 Notifies NRC of Util Completion of Actions Re GL 96-01, Testing of Safety-Related Logic Circuits at Plant ML18016A9351999-04-30030 April 1999 Forwards Info Requested in 990324 RAI as Suppl to 981223 Application for Amend to License NPF-63 for Alternative Plan for Spent Fuel Pool Cooling & Cleanup Sys Piping ML18016A9311999-04-30030 April 1999 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp HNP-99-068, Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld1999-04-28028 April 1999 Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld ML18016A9211999-04-27027 April 1999 Provides Rev 2 to ISI Relief Request 2RG-008, ISI of Class 1,2 & 3 Snubbers (Code Category F-A) Per Plant TS in Lieu of ASME Code Section XI, in Response to 990408 Telcon with NRC ML18016A9221999-04-27027 April 1999 Forwards Proprietary Notification That SRO Licensed on Shnpp Has Terminated Employment with Cp&L,Per 10CFR50.74(b). Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9161999-04-22022 April 1999 Forwards Proprietary NRC Form 396, Certification of Medical Exam by Facility Licensee, for SRO Licensed to Operate Hnp. License for Individual Should Be Amended IAW Change Noted on Form.Proprietary Encl Withheld,Per 10CFR2.790(a)(6) ML18016A9201999-04-20020 April 1999 Informs of HNP Personnel Changes to Facilitate Proper Distribution of Correspondence.Records Should Be Updated to Reflect Noted Change ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML18016A9121999-04-12012 April 1999 Forwards Diskette Containing Data Re Annual Exposure Rept for Individual Monitoring for Personnel Shnpp,Per 10CFR20.2206(b).Without Encl ML18016A9021999-04-12012 April 1999 Forwards Rev 34 to PLP-201, Shearon Harris NPP Emergency Plan, Replacing All Pages of Previous Rev with Exception of EAL Flow Path,Side 1 & 2 & Annex H Operations Map & Aperture Card.Changes,Listed.Rev Summary,Encl IR 05000400/19982011999-04-12012 April 1999 Discusses Safeguards Insp Rept 50-400/98-201 (Operational Safeguards Response Evaluation) on 980908-11.No Violations Noted.Licensee Performance During Evaluation Indicated Excellent Overall Contingency Response Capability 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18017A9241999-10-15015 October 1999 Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools 'C' & 'D' in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18017A9141999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon ML18017A9131999-10-0606 October 1999 Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld ML18017A8911999-09-30030 September 1999 Submits Comment on Encl 2 to 990617 Memo Titled Summary of Meeting with Nuclear Energy Inst. Encl 2 Was Titled Draft Technical Study of Spent Fuel Pool Accidents for Decommissioning Plants. Rept Which Provides Info Encl Also ML20212J0741999-09-29029 September 1999 Refers to Proposed License Amend for Harris NPP Which Would Allow Licensee to Activate Two of Plant Spent Fuel Pools.Serves Copy of Orange County Second Set of Document Requests to NRC Staff,Dtd 990929.Related Correspondence ML18017A8941999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves. ML18017A8881999-09-27027 September 1999 Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii) ML18017A8861999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18017A8821999-09-14014 September 1999 Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6) ML18017A8651999-09-0808 September 1999 Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety ML18017A8581999-09-0303 September 1999 Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity ML18017A8551999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS ML18017A8541999-08-20020 August 1999 Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided HNP-99-134, Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.211999-08-18018 August 1999 Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.21 ML18017A8351999-08-10010 August 1999 Corrects Statement Made in 980923 Ltr,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment ML18016B0531999-08-0606 August 1999 Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl ML18016B0461999-08-0404 August 1999 Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS Requirements ML18016B0421999-07-30030 July 1999 Informs That in Ltr Dtd 950330 CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998 ML18016B0391999-07-30030 July 1999 Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed ML18016B0221999-07-26026 July 1999 Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 990930 ML18016B0171999-07-16016 July 1999 Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP ML18016B0051999-07-0101 July 1999 Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl ML18016A9871999-06-14014 June 1999 Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service,Dtd 981223.Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18016A9831999-06-10010 June 1999 Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated ML20212H7521999-06-0404 June 1999 Encourages NRC to Schedule Open Public Forum Which Would Allow Local Citizens to Express Concerns Re Proposed Expansion of high-level Radwaste Storage Capacity at Shearon Harris Npp.With Certificate of Svc.Served on 990624 ML18016A9721999-05-28028 May 1999 Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. ML18016B0011999-05-26026 May 1999 Forwards Ltr Received from Hj Jaffe Expressing Concern Re Cpl Proposal to NRC on Dec of 1998 to Make Harris Nuclear Plant Largest Storage Area for High Level Nuclear Waste in Nation ML18016A9631999-05-25025 May 1999 Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend ML18016A9511999-05-13013 May 1999 Submits Info Re Estimated Effect of Change to ECCS Evaluation Model,As Required by 10CFR50.46 ML18016A9481999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Examination by Facility Licensee, for Senior Reactor Operator Licensed to Operate Hnp.Individuals Info Is Proprietary & Is Being Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20206R2611999-05-0505 May 1999 Requests That NRC Grant Standing to Intervention Sought by Orange County Board of Commissioners Re Proposal by CP&L to Expand Storage of Hlrw at Shnpp.With Certificate of Svc. Served on 990519 ML18016A9451999-05-0404 May 1999 Provides Proprietary Notification That One SRO Has Been Reassigned from Position for Which Util Certified Need for SRO License & Another SRO Has Terminated Employment with Util.Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9441999-05-0404 May 1999 Notifies NRC of Util Completion of Actions Re GL 96-01, Testing of Safety-Related Logic Circuits at Plant ML18016A9351999-04-30030 April 1999 Forwards Info Requested in 990324 RAI as Suppl to 981223 Application for Amend to License NPF-63 for Alternative Plan for Spent Fuel Pool Cooling & Cleanup Sys Piping ML18016A9311999-04-30030 April 1999 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp HNP-99-068, Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld1999-04-28028 April 1999 Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld ML18016A9221999-04-27027 April 1999 Forwards Proprietary Notification That SRO Licensed on Shnpp Has Terminated Employment with Cp&L,Per 10CFR50.74(b). Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9211999-04-27027 April 1999 Provides Rev 2 to ISI Relief Request 2RG-008, ISI of Class 1,2 & 3 Snubbers (Code Category F-A) Per Plant TS in Lieu of ASME Code Section XI, in Response to 990408 Telcon with NRC ML18016A9161999-04-22022 April 1999 Forwards Proprietary NRC Form 396, Certification of Medical Exam by Facility Licensee, for SRO Licensed to Operate Hnp. License for Individual Should Be Amended IAW Change Noted on Form.Proprietary Encl Withheld,Per 10CFR2.790(a)(6) ML18016A9201999-04-20020 April 1999 Informs of HNP Personnel Changes to Facilitate Proper Distribution of Correspondence.Records Should Be Updated to Reflect Noted Change ML18016A9121999-04-12012 April 1999 Forwards Diskette Containing Data Re Annual Exposure Rept for Individual Monitoring for Personnel Shnpp,Per 10CFR20.2206(b).Without Encl ML18016A9021999-04-12012 April 1999 Forwards Rev 34 to PLP-201, Shearon Harris NPP Emergency Plan, Replacing All Pages of Previous Rev with Exception of EAL Flow Path,Side 1 & 2 & Annex H Operations Map & Aperture Card.Changes,Listed.Rev Summary,Encl ML18016A8911999-04-0505 April 1999 Forwards non-proprietary App 4A,pages 20-25 & Proprietary Page 4-6 to re-issued Rev 3 of Holtec International Licensing Rept HI-971760.Pages Were Inadvertently Omitted from Reissued Rept.Proprietary Page 4-6 Withheld ML18016A8891999-04-0101 April 1999 Forwards Rev 99-1 to Plant EALs for NRC Review & Approval, Per 10CFR50,App E.Encl Provides Comparison of Currently Approved EALs & Proposed Rev 99-01.Approval of EALs Prior to June 1999,requested.With Four Oversize Drawings ML18016A8811999-03-31031 March 1999 Responds to NRC 990301 Ltr Re Violations Noted in Insp Rept 50-400/98-11.Corrective Actions:Post Trip/Safeguards Actuation Rept for 981023,RT Was Corrected,Required Reviews Completed & Approval Obtained on 990219 ML18016A8671999-03-19019 March 1999 Submits Response to RAI Re Spent Fuel Pool Water Level & Revised Fuel Handling Accident Analyses,Per 990317 Telcon with NRC ML18016A8631999-03-19019 March 1999 Forwards Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept, IAW 10CFR55.45(b)(5)(ii). NRC Form 474 & Required Info Re Simulator Performance Test Results & Schedules Also Encl ML18016A8691999-03-18018 March 1999 Forwards Resolution Adopted by Lee County,North Carolina Board of Commissioners Re Proposed Expansion of high-level Radioactive Waste Storage Facilities at Carolina Power & Light Shearon Harris Nuclear Power Plant ML18016A8511999-03-15015 March 1999 Forwards Proprietary & non-proprietary Version of Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFPs 'C' & 'D'. Repts Are Reissued to Reflect Reduction in Proprietary Info.Proprietary Info Withheld ML18016A8601999-03-15015 March 1999 Informs NRC of Mod to Commitment for Hnp,Re Comprehensive Review of Implementation of TS Sr.Upon Completion of Listed Reviews,Surveillance Procedure Review Project Will Be Considered Complete 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L0911990-09-12012 September 1990 Confirms That Fee Electronically Transferred to Dept of Treasury for Payment of NRC Review Fees ML18009A6581990-09-11011 September 1990 Submits Addl Info Re Use of Hafnium Control Rods at Facility.All Rods Will Be Removed During Spring 1991 Outage ML20059H4181990-09-0606 September 1990 Responds to NRC Re Violations Noted in Insp Rept 50-400/90-13.Corrective Action:Changes to EST-717 in Area of Power Normalization Under Study for Past Several Months ML17348B4941990-08-30030 August 1990 Forwards Semiannual 10CFR26 fitness-for-duty Program Data for 900103-0630.Mgt Decision Made to Utilize Alcohol Breath Instruments as Screening Devices for Unscheduled Work Call Outs in Determining fitness-for-duty ML20059D3511990-08-30030 August 1990 Forwards Decommissioning Financial Assurance Certification Rept Submitted by North Carolina Eastern Municipal Power Agency ML18009A6261990-08-10010 August 1990 Informs That Action Committed to in Response to Generic Ltr 88-14, Instrument Air Supply Sys, Completed ML18009A6241990-08-0303 August 1990 Forwards Addl Info Re Operator Action Times Assumed in Steam Generator Tube Rupture Analyses for Plant,Per 900712 Telcon ML18009A6081990-07-31031 July 1990 Forwards Plan for Shearon Harris Nuclear Power Plant Emergency Exercise - 900919, Per NRC Request.W/O Encl ML20055J4171990-07-30030 July 1990 Forwards Rev 5 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20055F9431990-07-12012 July 1990 Advises That Stated Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900711 for Payment of Operator License Exam Fees for Listed Insp Invoices ML18009A5991990-07-0606 July 1990 Comments on Electrical Distribution Sys Functional Insp Rept 50-400/90-200 on 900212-0316.Seismic Qualification Package Subsequently Upgraded to Include Qualification Info Based on Receipt of Part 21 from Transamerica Delaval ML18009A5851990-06-28028 June 1990 Advises That Emergency Preparedness Exercise Scheduled on 900919.Exercise Will Consist of Simulated Accident at Plant Site & Will Involve Planned Response Actions.Objectives to Be Fulfilled Encl ML18009A5621990-05-30030 May 1990 Responds to NRC 900504 Ltr Re Violations Noted in Insp Rept 50-400/90-06.Corrective Actions:Procedures OST-1008 & OST-1108 Revised to Delete Stroke Testing of Valve 1ST-359 on Quarterly Basis ML18009A5141990-05-0303 May 1990 Forwards Eddy Current Exam CP&L Shearon Harris Nuclear Power Plant Steam Generators A,B & C, Providing Results of Inservice Insps Performed During Plant Second Refueling Outage in Oct 1989 ML18009A4941990-04-26026 April 1990 Forwards Radiological Environ Operating Rept,1989, Radiological Environ Operating Rept,Vol II,Jan-June 1989, Sample Analyses Data & Radiological Environ Operating Rept,Vol III,Jul-Dec 1989,Sample Analyses Data. ML18009A5031990-04-25025 April 1990 Submits Suppl 2 to Relief Request R2-001 Re Plant 10-yr Inservice Insp Plan,Per 880129 Request ML18009A4911990-04-24024 April 1990 Forwards Addl Info Re Proposed Wakesouth Regional Airport to Be Located Near Facility,Per 900411 Request.Info Previously Provided to NRC During 900320 & 23 Telcons ML18009A4841990-04-24024 April 1990 Forwards Corrected Bases marked-up Page to 900226 Tech Spec Change Request Re Surveillance Intervals ML18009A4251990-03-30030 March 1990 Submits Supplemental Response to Station Blackout Rule Based on Guidelines Provided in NUMARC 87-00, Guidelines & Technical Bases for NUMARC Initiatives.... No Changes to Previous Calculations Necessary & One Deviation Noted ML18009A4231990-03-29029 March 1990 Suppls Response to NRC 900216 Ltr Re Violations Noted in Insp Rept 50-400/89-23.Corrective Actions:Surveys Performed to Determined Extent & Level of Contamination & Personnel Involved Decontaminated ML18009A4111990-03-23023 March 1990 Responds to NRC 900227 Ltr Re Violations Noted in Insp Rept 50-400/90-02.Corrective Actions:Personnel Involved W/ Quadrant Power Tilt Ratio Calculations & Operability Determination Counseled ML18009A4121990-03-23023 March 1990 Forwards Rev 17 to PLP-201, Emergency Plan & Fission Product Barrier Analysis.Rev to Emergency Plan Incorporates Comments Received During Recent Licensed Operator Requalification Training in Emergency Plan Procedures ML18009A4151990-03-22022 March 1990 Responds to NRC SALP Rept for Jul 1988 - Nov 1989.Contrary to Statement in Rept Significant Amount of Refresher Training Was Conducted During SALP Assessment Period Including Termination & Splicing & Motor & Bus Relays ML18009A4081990-03-19019 March 1990 Responds to NRC 900226 Ltr Re Violations Noted in Insp Rept 50-400/90-01.Corrective Actions:All Calibr Required by Tech Specs for Power Range Nuclear Instrumentation Satisfactorily Completed ML18022A7891990-03-0909 March 1990 Forwards Vols 1 & 2 of Inservice Insp Summary 1st Interval 1st Period,2nd Refueling Outage Completed 891222. ML18022A7881990-03-0606 March 1990 Confirms Understanding of Status of NRC Activities Re Proposed Wakesouth Regional Airport Located Near Plant Site. Pending Issues Should Be Resolved by 900331 to Enable Util to Complete Negotiations W/Airport Authority ML18022A7851990-03-0202 March 1990 Responds to NRC 900131 Ltr Re Violations Noted in Insp Rept 50-400/89-34.Corrective Actions:Valve SI-332 Closed & Gravity Drain Path Isolated & Shift Foreman Required to Review MMM-012 Re Priority/Emergency Maint Work Control ML18022A7721990-02-26026 February 1990 Forwards Application for Amend to License NPF-63,revising Tech Spec Surveillance 4.0.2 to Permit Surveillances to Be Extended Up to 25% of Specified Interval & Removing 3.25 Limitation from Spec,Per Generic Ltr 89-14 ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML18022A7701990-02-14014 February 1990 Notifies of Issuance of Renewal of NPDES Permit for Plant. Permit Encl ML18009A3831990-02-0909 February 1990 Responds to 900112 Ltr Re Violation Noted in Insp Rept 50-400/89-35.Corrective Actions:Valves ICS-775 & ICS-776 Added to Inservice Insp Program for Back Seat & Full Flow Testing & ICS-525 Revised to Satisfy Tech Spec Requirements ML18009A3751990-02-0101 February 1990 Forwards Retyped Tech Spec Pages Re 890630 Application for Amend to License NPF-63 Concerning RCS Pressure Temp Limits ML18009A3701990-02-0101 February 1990 Informs That Planned Corrective Actions Re Violations Noted in Insp Rept 50-400/89-28 Will Not Be Completed Until 900301 IR 05000400/19890281990-02-0101 February 1990 Informs That Planned Corrective Actions Re Violations Noted in Insp Rept 50-400/89-28 Will Not Be Completed Until 900301 ML18009A3631990-01-26026 January 1990 Responds to NRC Bulletin 88-008, Thermal Stratification in Piping Connected to Rcs. Design Differences That Either Minimize Potential of Occurrence or Enhance Possibility of Detection Should Scenario Be Created at Plant Determined ML18009A3531990-01-25025 January 1990 Forwards Reactor Containment Bldg Integrated Leak Rate Test Conducted in Oct 1989.Util Believes That Packing Leaks Discovered Are Isolated Failures & That Repair Should Prevent Recurrence ML18009A3501990-01-22022 January 1990 Forwards Revised Tech Spec Table 3.7-6, Area Temp Monitoring, Per 891218 Tech Spec Amend Request ML18022A7591990-01-17017 January 1990 Submits Results of Aircraft Hazards Study Associated W/ Proposed Wakesouth Regional Airport & Facility ML20005G5731990-01-16016 January 1990 Forwards Response to Insp Rept 50-400/89-32.Encl Withheld (Ref 10CFR73.21) ML18009A3351990-01-0505 January 1990 Forwards Rev 16 to Vol 1,Part 2 of Plant Operating Manual PLP-201, Emergency Plan. Revised NUREG-0654 Comparison W/ Plant Emergency Action Level Flow Path Also Encl for Review ML18009A3171989-12-21021 December 1989 Responds to NRC 891108 Ltr Re Violations Noted in Insp Rept 50-400/89-21.Corrective Actions:Incident Reviewed by Both Plant & Nuclear Engineering Dept Personnel to Avoid Future Miscommunication ML18009A3181989-12-15015 December 1989 Forwards Retyped Amend Bar Pages to Tech Spec Table 3.3-3 Re Auxiliary Feedwater Manual Initiation,Per 891026 Application for Amend to License NPF-63 ML18009A3011989-12-15015 December 1989 Forwards Proprietary WCAP-12403 & Nonproprietary WCAP-12404, LOFTTR2 Analysis for Steam Generator Tube Rupture W/Revised Operator Action Times for Shearon Harris Nuclear Power Plant. WCAP-12403 Withheld (Ref 10CFR2.790(b)(4)) ML18022A7371989-12-13013 December 1989 Forwards Change 3 to Rev 2 to State of Nc Emergency Response Plan in Support of Shearon Harris Nuclear Power Plant, Incorporating Administrative Enhancements. W/One Oversize Encl ML18009A2971989-12-0808 December 1989 Responds to NRC 891108 Ltr Re Violations Noted in Insp Rept 50-400/89-23.Corrective Action:Min of Four Decontamination Personnel Will Be Assigned 24 H Per Day During Fuel/Cask Handling to Maintain Cleanliness in Fuel Handling Bldg ML18009A2841989-11-30030 November 1989 Forwards Rev 0 to Core Operating Limits Rept in Support of Cycle 3 Operations ML18005B1531989-11-27027 November 1989 Forwards Retyped Amend Bar Pages to 890630 Request for Rev to License NPF-63 Re RCS pressure-temp Limits ML18022A7311989-11-27027 November 1989 Forwards Response to Generic Ltr 89-21, Request for Info Re Status of Implementation of USI Requirements. ML18005B1511989-11-17017 November 1989 Forwards 15-day Special Rept Identifying Number of Steam Generator Tubes Plugged During Current Inservice Insp Period ML18005B1501989-11-13013 November 1989 Suppls 890403 Response to NRC Bulletin 88-010, Nonconforming Molded-Case Circuit Breakers. Addl Nontraceable Molded Case Circuit Breakers (MCCB) & MCCBs Traceable to Refurbishers Noted During Records Review 1990-09-06
[Table view] |
Text
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR: 8408300243 . DOC ~ DATE: 84/08/24 NOTAR I ZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant~ Unit 1< Carolina 05000400 AUTH, NAME AUTHOR AFFILIATION ZIMMERMANiS ~ RE Carolina Power L Light Co.
REC IP ~ NAME RECIPIENT AFFILIATION DENTON~H ~ Ri "
Office of Nuclear Reactor Regulationi Di,rector
SUBJECT:
Forwards responses to written L verval questions raised by Equipment Qualification Branch reviewers during insp conducted on 840809 L 10.
DISTR I BUT I ON CODE A 048D COP IES RECEI VED LTR Ef<CL S I ZE ~
TITLE: OR/Licensing Submittal: Equipment Qualification NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR LB3 BC 12 1 0 BUCKLEYiB 01 1 1 INTERNAL: ADM/LFMB 1 0 ELD/HDS1 12 1 1 GC 13 1 IE FILE 09 1 1 NRR KARSCHiR 1 1 NRR/DE/EQB 07 2 2 NRR/DL DIR 14 1 1 N RAB 06 1 NRR/DSI/AEB 1 1 G FILE 04 1 RGN2 1 1 EXTERNALS AC'RS 15 8 8 LPDR 03 NRC PDR 02 1 1 NSIC 05 NTIS 31 1 1 TOTAL NUMBER, OF COPIES REQUIRED:, LTTR 26 ENCL 24
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S f CXQE, Carolina Power & Light Company NJG 3 4 t984 SERIAL: NLS-84-376 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 DOCKET NO. 50-400 ENVIRONMENTAL QUALIFICATION PROGRAM
Dear Mr. Denton:
Carolina Power & Light Company hereby provides responses to the written and verbal questions raised by the Equipment Qualification Branch reviewers during the inspection conducted on August 9 and 10, 1984 at the Shearon Harris site. The questions and responses are contained in the attachment.
Should you have any questions with regard to this issue, please contact Mr. Pedro Salas at (919) 836-8015.
Yours very truly, S. R. immerman Manager Nuclear Licensing Section PS/pgp (496PSA/pgp)
Attachment Cc1 Hr. B. C. Buckley (NRC) Hr. Wells Eddleman Mr. Armand Masciantonio (NRC-NRR/EQ) Hr. John D. Runkle Hr. Bob Legrange (NRC-NRR/EQ) Dr. Richard D. Wilson Mr. G. F. Maxwell (NRC-SHNPP) Mr. G. 0. Bright (ASLB)
Mr. J. P. O'Reilly (NRC-RII) Dr. J. H. Carpenter (ASLB)
Mr. Travis Payne (KUDZU) Mr. J. L. Kelley (ASLB)
Mr. Daniel F. Read (CHANGE/ELP)
Chapel Hill Public Library Wake County Public Library 8408300243 8408~4 PDR ADOCK 05000400 PDR 411 Fayettevilte Street o P. O. Box 1551 o Raleigh. N. C. 27602
r fy ATTACHMENT LIMITOR UE MOTOR OPERATOR
- 1. Verify that the [Limitorque] motor operator orientation of the tested equipment is the same as those motor operators being qualified in this
[Limitorque] package. Provide justification or analysis for those operators not having the same orientation as the tested equipment.
~Res onse:
Motor operators are installed per piping drawings at Shearon drawings are prepared by the design engineering group with input Harris'hese from each vendor to assure that orientation of the operator is the same as during testing, or that any changes are justified. The field uses these drawings as installation criteria. Isometrics are verified in the field and the results transmitted to the site design engineering group.
In addition, motor operator orientation of active valves in harsh environments will be verified in our equipment qualification walkdown which has already begun. To date, no deviations have been found.
- 2. The material analysis performed in Section E [Limitorque Report], under aging, only addresses the insulation materials. A more in-depth analysis of the non-metallic materials found on the Limitorque operator should be presented (the 0-rings should be included).
~Res onse:
A more expanded materials analysis will be included in Section E of the reviewed document. However, there is no safety concern because:
a) Limitorque has stated that the insulation material has the lowest activation energy of the non-metallic materials used; i.e., it is the limiting material.
b) Limitorque has certified that Equipment Qualification Report Nos. 600456 and B0058 are applicable to our valves. Report B0058 includes an analysis of the non-metallic materials, including 0-rings. (Material information of a more detailed nature is considered proprietary by Limitorque.)
c) Report B0058 has been certified to be adequate by CPSL, as documented in the equipment qualification package and has been accepted at other plants by the NRC.
- 3. What is the maximum normal temperature that these operators will experience, and provide justification for not using the maximum normal temperature in the aging methodology.
(493PSA/ccc)
I
~Res onse:
The maximum postulated normal temperature inside containment for these operators is 120'F as shown in Tab E page 2F of 3F of the qualification package. This temperature was used in the aging analysis.
- 4. How is 0-ring qualification assured?
~Res onse:
Carolina Power & Light Company has maintained written and verbal communications with Limitorque to assure that the valve operators have qualified 0-rings. Limitorque has provided certification letters which provide traceability of the Shearon Harris operators by Limitorque Shop Order Numbers.
- 5. Is walkdown of Limitorque valves to be 100 percent?
~Res onse:
All Limitorque operators on active valves in a harsh environment will be field verified.
- 6. Will there be walkdowns of other safety-related electrical equipment?
~Res onse:
Walkdowns will be performed on other safety-related electrical equipment in a harsh environment. The equipment will be selected on a sample basis using good engineering practice to select the sample type and size.
- 7. Are Limitorque operators at Shearon Harris required to be sealed?
~Res onse:
Limitorque operators on safety-related, active valves are sealed at the conduit entry point.
(493PSA/ccc)
li BIW INSTRUMENT CABLE Is the cable (BIW) required to operate submerged?
~Res onse:
BIW cable at Shearon Harris is not required to operate submerged. An evaluation is currently being conducted to determine if there are any cables, other than BIW, which will be required to operate submerged.
Cables required to operate in a submerged condition will be qualified for the condition. The results will be included in the documentation packages for those cables.
- 2. Insulation Resistance (IR) values during the LOCA test were performed, however, no analysis or summary was presented on how the observed decrease in IR values may affect loop accuracies.
~Res onse:
The IR values observed during environmental qualification testing are currently being used to perform a leakage current study for the Class lE instruments utilizing these cables. The results of the study will be evaluated to determine effects on instrument loop accuracies and setpoints. The results of the study and the evaluation will be documented.
- 3. What is the minimum acceptable IR value before the cable is considered to have failed?
~Res onse; Various acceptance criteria were used during the review of the EQ test reports. For the instrument cables the acceptance criteria include:
continuity during the LOCA simulation, ability to carry current and hold a voltage during the tests, and the ability to pass the voltage withstand test. In addition, the IR values measured during the tests are reviewed for overall behavior during the tests, in particular that they recover towards the original values. The above tests serve to indicate that the cables are qualified.
4 ~ In Section F of the EQ package, it states that interfaces were not part of the qualification. Where are the cable terminations addressed in the EQ submittal?
~Res onse:
Triaxial cable installation interface consists of the connectors, which are qualified by separate documentation packages associated with the individual type of equipment where the connector is required. These packages will be available for site audit.
(493PSA/ccc)
- 5. The description of the test set-up, including the manner in which the cable penetrated the test vessel, has not been placed in the test report. How is the installation kept consistent with the tested configuration?
~Res onse:
The attachment to BIW letter dated July 18, 1983 shows the test set-up in the autoclave. BIW utilized a three foot tray section inside the test chamber. The tray is below the chemical spray nozzle. The vendor indicated that the cables were laid on the tray.
The cables were brought out through the test chamber opening which was sealed with an epoxy compound. Cable trays are used to route cables inside the plant. As such, the test set-up does represent the field installation. The above referenced letter is included in the final EQ package for this cable, which is currently under revision.
- 6. Were IR measurements taken on all instrument cables during their environmental qualification tests?
~Res onse:
The Shearon Harris EQ program includes insulation resistance measurements of all instrument cables during qualification testing.
- 7. Is instrument cable used with safety-related equipment at Shearon Harris qualified without its jacket?
~Res onse:
The qualification of Class 1E instrument cables, except for coaxial and triaxial cables, is performed using jacketed and unjacketed cable samples. For the coaxial and triaxial cables, the tests are performed with the jacketed cables intact. This is how the cables are installed at the connectors. A qualified heat shrink material is then put over the connectors of the cables during installation.
(493PSA/ccc)
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RESISTANCE TEMPERATURE DETECTOR (RTD)
- 1. Please reconcile the following statements made in the RTD Qualification Package:
o Qualified life of 20-23 years is claimed by using an activation energy of 0.98 eV for epoxy.
~Res onse:
Reference:
- 1. WCAP 8587, Appendices B and U
- 2. WCAP 8687 ESE 5 and 6 Carolina Power & Light Company evaluated the accelerated aging part of the RTD test program (Reference 2) utilizing the Arrhenius methodology and 0.98 eV as the controlling activation energy (E )
(Epoxy: Ea = 0.98 eV as specified by Reference 2). Results of this evaluation indicate that a 23 year qualified life at SHNPP is appropriate.
o "The qualified life is limited to ten (10) years by the expected radiation during the ten (10) year life and the DBE."
~Res onse:
The Westinghouse generic qualification program included an exposure of 70 megarads which corresponds to that expected over a ten-year normal installed life of the wide range RTDs. Shearon Harris plant specific, worst case, normal radiation exposure is 3.5 megarads for the same RTDs. Therefore, 10 years is a conservative qualified life.
0 In calculating the post accident operability time demonstrated, an activation energy of 0.5 eV was used.
~Res onse:
Reference:
- 1. WCAP-8587, Appendices B and D
- 2. WCAP-8687 ESE 5 and 6 An activation energy of 0.5 eV was utilized initially by CP&L and Westinghouse as the controlling activation energy (Ea) for the post accident evaluation since Westinghouse developed the conservative generic post accident test profile using 0.5 eV as the reference Ea (Reference 1). As previously indicated, 0.98 eV is the controlling activation energy and is being used by CP&L in revising the RTD qualification package.
(493PSA/ccc)
- 2. What is the maximum expected normal temperature for these RTDs?
~Res onse:
The maximum expected normal temperature for the narrow range/wide range RTDs is based on a 50'C service temperature for ambient conditions plus an additional 50'C temperature rise resulting from heat transfer from the reactor coolant system. Thus the total expected maximum normal temperature for the well mounted and bypass manifold RTDs is 100'C or 212'F. This is presently documented in CP&L's qualification report.
- 3. Justify the 50'C temperature rise assured in the aging calculations.
~Res onse:
Westinghouse has performed a heat transfer calculation using 620'F as a reactor coolant system fluid temperature, a maximum of 140'F as the ambient temperature around the area of the epoxy potting material and a minimum air velocity of 5.0 ft/sec in this area. This results in a conservative temperature rise of 50'C.
- 4. The basis for activation energy used in calculations could not be located in the file. Provide the reference and basis for the activation energy used.
~Res onse:
The 0.98 eV activation energy used for the epoxy has two sources:
a) WCAP-8587 "Methodology for Qualifying Westinghouse WRD Supplied NSSS Safety Related Electrical Equipment" page D-12 documents the results of a study conducted by Westinghouse and shows that the minimum activation energy for a cast epoxy is 0.98 eV.
b) EPRI Report NP-1558 (September 1980) "A Review of Equipment Aging Theory and Technology" page 84 documents an activation energy of 0.98 eV for epoxy based on 50% retention of flexural strength.
(493PSA/ccc)
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LUBRICATION In the case where specific brands of lubricants are not recommended by the equipment manufacturer, how does CP&L assure that lubricants used are environmentally qualified?
~Res oese:
Carolina Power & Light Company has contracted a leading lubrication vendor to perform a lubrication study for Shearon Harris. The study has been received and it documents the lubricants that can be used in the cases where the vendor CP&L is currently has not specifically recommended a particular brand.
reviewing the lubricant vendor's documentation which was produced to support the report. An equipment qualification package will be generated using the same procedure used for other equipment. In the study, radiation stability, or conversely the amount of radiation damage, is measured using conventional physical and chemical analysis and by comparing the results with the unirradiated material. In addition, standard performance tests are performed on previously irradiated material or as a dynamic procedure during irradiation.
These test results are compared to the original equipment manufacturer's test reports to assure that the lubrication performance criteria have been enveloped.
This information will be available in an equipment qualification package when complete.
(493PSA/ccc)
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