Responds to NRC 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
HNP-99-091, Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs
ML18016A974
ML20212H752
HNP-99-103, 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
HNP-99-094, Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service, .Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration
ML18016A996
ML18016A988
ML18016A992
ML20212H774
ML18016A998
ML18016B002
ML18016A997
HNP-99-104, 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
HNP-99-114, Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP
HNP-99-113, 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
HNP-99-119, Informs That in Ltr CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998
HNP-99-116, 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
05000400/LER-1999-006-01, 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
ML18016B055
ML18016B054
HNP-99-163, Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl
HNP-99-128, Corrects Statement Made in ,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment
ML18017A844
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 10CFR73.21
ML18017A848
HNP-99-130, Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided
ML14314A777
HNP-99-136, 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
HNP-99-129, Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity
HNP-99-127, 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
HNP-99-140, 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)
ML18017A884
ML18017A907
HNP-99-143, Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations
ML18017A885
ML18017A902
ML18017A903
HNP-99-145, Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii)
ML20212J074
ML20216G350
HNP-99-142, Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves
ML20212M108
ML18017A891
ML18017A899
ML14181A464
ML18017A895
HNP-99-148, 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
IR 05000400/1999007
HNP-99-153, Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon
HNP-99-156, 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
HNP-99-017, 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
HNP-99-032, 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
ML18016A869
HNP-99-053, Submits Response to RAI Re Spent Fuel Pool Water Level & Revised Fuel Handling Accident Analyses,Per 990317 Telcon with NRC
HNP-99-034, 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
HNP-99-051, Responds to NRC 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
HNP-99-024, 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
HNP-99-059, 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
HNP-99-058, Forwards Diskette Containing Data Re Annual Exposure Rept for Individual Monitoring for Personnel Shnpp,Per 10CFR20.2206(b).Without Encl
HNP-99-065, 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
HNP-99-067, Informs of HNP Personnel Changes to Facilitate Proper Distribution of Correspondence.Records Should Be Updated to Reflect Noted Change
HNP-99-072, 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)
HNP-99-070, 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
HNP-99-076, 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)
HNP-99-068, Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld
HNP-99-074, Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp
HNP-99-069, 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
HNP-99-060, Notifies NRC of Util Completion of Actions Re GL 96-01, Testing of Safety-Related Logic Circuits at Plant
HNP-99-084, 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)
ML20206R261
HNP-99-085, 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)
HNP-99-088, Submits Info Re Estimated Effect of Change to ECCS Evaluation Model,As Required by 10CFR50.46
HNP-99-087, 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
ML18016B001
HNP-99-091, Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs
ML20212H752
HNP-99-103, 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
HNP-99-094, Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service, .Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration
HNP-99-104, 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
HNP-99-114, Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP
HNP-99-113, 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
HNP-99-116, 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
HNP-99-119, Informs That in Ltr CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998
05000400/LER-1999-006-01, 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
HNP-99-163, Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl
HNP-99-128, Corrects Statement Made in ,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment
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 10CFR73.21
HNP-99-130, 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-99-136, 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
HNP-99-129, Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity
HNP-99-127, 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
HNP-99-140, 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)
HNP-99-143, Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations
HNP-99-145, Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii)
ML20212J074
HNP-99-142, Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves
ML18017A891
HNP-99-148, 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
HNP-99-153, Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon
HNP-99-156, 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
Document Control Desk United States Nuclear Regulatory Commission Washington, DC 20555 NRC-694 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400 LICENSE NO. NPF-63 REPLY TO A NOTICE OF VIOLATION Gentlemen:
In reference to your letter of November 8,
1989, referring to I.E.
Report RII:
50-400/89-21, the attached is Carolina
Power, and Light Company's reply to the violation identified in Enclosure 1.
It is considered that the corrective actions taken/planned are satisfactory for resolution of the item.
Via telephone conversation between Mr, Michael Wallace (CPhL), Mr. Jeff Tedrow and Bob Carrol of your staff on December 7,
1989 an extension was granted to CPBL for responding to the violation.
The reason for the extension was due to a delay in the Harris Plants receipt of the Notice of Violation.
Attachment to CP6L Letter of Res onse to NRC I. E.
Re ort Rll:
50-400/89-21 Re orted Violation.'0 CFR Part 50, Appendix B, Criterion III, Design
Control, requires that measures be established for the selection and review for suitability of materials,
parts, equipment, and processes that are essential to the safety-related functions of structures, systems and components.
Contrary to the above, commercial grade ITE Molded Case Circuit Breakers were installed in safety-related electrical systems and the review for suitability of equipment by the CP6L Engineering Department was inadequate.
The breakers were physically changed by the manufacturer (i.e.,
instantaneous trip and voltage rating) and the seismic qualifications of the breakers were not verified prior to installation in safety-related applications.
Further, the modified breakers were not fully qualified by testing in that all of the required critical characteristic tests (i.e.,
a dielectric test between the line and load terminals with the breaker
open, a full load starting current
test, contact resistance measurement with the breaker
closed, or testing with the breaker properly oriented) were not considered or performed.
change to the subject breakers and requested an engineering evaluation of the change via Plant Change Request (PCR) 4007.
The Nuclear Engineering Department (NED) understood the scope of PCR-4007 to be limited to evaluating the acceptability of the changes in the time current curves in regards to the electrical coordination/protection studies.
PCR 4007 did not evaluate the seismic qualification of the subject breakers.
Further, the dedication process for the subject breakers did not testing of critical characteristics.
During the time frame the breakers were received at HNP, testing was not being performed of received based on several breaker manufacturers indicating that testing was detrimental to the breaker.
include subject breakers initial Corrective Ste s Taken and Results Achieved:
A field revision to PCR-4007 has been initiated and is currently being worked to evaluate the acceptability of using the subject commercial grade breakers in safety-related applications.
At present the breakers installed in safety-related applications are acceptable from an electrical standpoint and are considered to be seismically qualifiable based on the Seismic MEM/H0-8901710/2/OS1
Qualification Utility Group (SQUG) curves which envelope this application.
However, additional seismic testing (through Wyle Test Labs) and evaluation of test results will be performed to provide documentation of seismic qualification.
This effort will be completed by January 31, 1990.
The subject breakers installed in safety-related application have been tested per procedure CM-E0010, 480 VAC Molded Case Circuit Breaker Test or equivalent surveillancelperiodic test procedures with acceptable results achieved.
Tests include smooth breaker operation, breaker continuity, megger measurement, thermal trip test and instantaneous trip test.
Corrective Ste s Taken to Avoid Further Violations'.
This incident has been reviewed by both plant and NED personnel to avoid future miscommunication as to the scope of PCRs.
Molded case circuit breakers purchased for safety related applications are purchased commercial grade and are tested for critical characteristics upon receipt per procedure CM-E0010.
This requirement has been added to the receipt inspection instructions.
Test data sheets are kept with each breaker placed in stock.