|
|
(One intermediate revision by the same user not shown) |
Line 1: |
Line 1: |
| {{Adams | | {{Adams |
| | number = ML20154H059 | | | number = ML20195B711 |
| | issue date = 05/12/1988 | | | issue date = 10/24/1988 |
| | title = Corrected Page 3 of Insp Repts 50-413/88-07 & 50-414/88-07 | | | title = Discusses Insp Repts 50-413/88-07 & 50-414/88-07 on 880201-05 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty |
| | author name = | | | author name = Ernst M |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| | addressee name = | | | addressee name = Tucker H |
| | addressee affiliation = | | | addressee affiliation = DUKE POWER CO. |
| | docket = 05000413, 05000414 | | | docket = 05000413, 05000414 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-413-88-07, 50-413-88-7, 50-414-88-07, 50-414-88-7, NUDOCS 8805250212 | | | document report number = EA-88-132, NUDOCS 8811020163 |
| | package number = ML20154H055 | | | package number = ML20195B713 |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | page count = 1 | | | page count = 5 |
| }} | | }} |
|
| |
|
Line 19: |
Line 19: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:. ;~ ENCLOSURE | | {{#Wiki_filter:% |
| * | | '' |
| | , |
| | fll0lA) |
| | ... . |
| | . . |
| | . |
| | OCT 241988 Docket Nos. 50-413 and 50-414 License Nos. NPF-35 and NPF-52 EA 88-132 Duke Power Company ATTN: Mr. H. B. Tucker, Vice President Nuclear Production Departmr't 422 South Church Street Charlotte, NC 28242 Gentlemen: |
| | SUBJECT: NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF CIVIL PENALTY (NRC INSPECTION REPORT N05. 50-413/88-07 AND 50-414/88-07) |
| | This refers to the Nuclear Regulatory Commission (NRC) inspection conducted at both the Catawba Nuclear Station, Units 1 and 2, and the Duke Power Company (DPC) Design Offices in Charlotte, NC, during the period February 1-5, 1988. The inspection included a review of the program for the environ-mental qualification (EQ) of electrical equipment under 10 CFR 50.4 During the inspection, violations of NRC requirements were identified involving the lack of environmental qualification for cert. tin components of electrical equipment in isolated systems in both units. The inspection also included a review of the circumsty:es surrounding your identification of the unqualified wide range Reactor Coolant System (RCS) hot and cold leg resistance temperature detectors (RTD), which were unqualified because they were not installed in accordance with the tested configuration. The report documenting this inspection was sent to you by letter dated May 4, 1988. As a result of this inspection, a significant failure to comply with regulatory requirements was identified, and accordingly, NRC concerns relating to the |
| | , inspection were discussed in an Enforcement Conference held on July 1, 1988. |
| | |
| | l The letter summarizing this Conference was sent to you on July 25, 1988. |
| | |
| | . |
| | . The violations described in the enclosed Notice of Violation and Proposed |
| | ! Imposition of Civil Penalty (Notice) involved the failure to comply with |
| | ' |
| | the requirements of 10 CFR 50.49 for both units. Unit 1 is subject to the |
| | "Modified Enforcement Policy Relating to 10 CFR 50.49. Environmental Quali-fication of Electrical Equipment Important to Safety for Nuclear Power Plants " contained in NRC Generic Letter 88-07. Unit 2, by virtue of its being licensed after the November 30, 1985, deadline for EQ compliance, is suh.iect to the normal Enforcement Policy of 10 CFR Part 2, Appendix C. The duali g of Enforcement Policy notwithstanding, a single Notice of Violation and Proposed Imposition of Civil Penalty is appropriate in this case because of the similarity of the violations for both units; equitability in applying i |
| | the Enforcement Policies in this case is achieved by addressing the overall EQ program at the Catawba Nuclear Station; and, in fairness, it is appro-l l |
| | priate to assess the EQ problem at the facility as a whole. |
| | |
| | l 8811020163 881024 PDR ADOCK 05 COO 413 Q PNU 9% |
| | = |
| | |
| | ! . .- |
| | - - . : , |
| | . . |
| | , |
| | ' |
| | Duke Power Company, 2 OCT 2 41988 The violations described in Section I of the enclosed Notice included the failure to properly install the RCS hot and cold lag wida range RTDs in accordance wfth the tested configuration; failure to adequately evaluate the qualification of non-safety valve operators installed inside Unit 1 contain-ment in the Containment Air Return and Hydrogen-Skimmer System (VX); and fit ally, failure to ensure that valve operators on both units had function-ing T-drains installed similar to the qualified test ccnfiguratio The unqualified RTD configuration resulted from a breakdown in your design interface controis to properly translate design specifications for EQ equipment into installation instructions for the craft and your failure to perform adequate walkdowns of EQ equipment. The lack of functioning T-drains on some Limitorque valve operators can also be attributed to your failure to perform adequate walkdowns. The violation involving the instal-lation of non-safety valve operators into the Hydrogen Skimer System resulted from an inadequate engineering evaluation which failed to consider all the facets of proof necessary to qualify a component to the requirements of the EQ rul The NRC believes that Duke Power Company clearly should have known about the environmental qualification deficiencies identified above for Unit 1, and clearly would have discovered the problems had an adequate level of atten-tion been applied to the environmental qualifica'. ion program requirements which included design interface control and fie',d verification inspection The issue regarding the submerged RTD install? cions should have been dis-covered in 1984 when questions were raised by NRR concerning the capability of the RTDs to function while submerged. Not only is the need to install functional T-drains on the inside containment actuators required by the test report for the actuators, but it should be a routine practice to have all actuators fully functional. ..oreover, DPC was informed in 1984 that valve operators in the VX system did not meet their specifications and were not |
| | ; qualified for installation inside containmen It is clear that a program for environmental qualification of electrical equipment should include, as |
| | ; |
| | a fundamental element, a comprehensive as-built field inspection program to verify that equipment was installed in the configuration in which it was tested for qualificatio Such was not the case for the RCS RTDs in Unit I where the RTD wires were not qualified for submergence in the installed configuration and the problem was not discovered during your review of the installation. Finally, Duke Power Company had available information such as IE Circuler 79-05, several IE Notices such as 79-03 and 83-72, and j NUREG-0588, "Interim Staff Position on Environmental Qualification of |
| | ; Safety-Related Electrical Equipment," which addressed the need to environ- |
| | ' |
| | mentally qualify such items as moisture intrusion seals, moter operators, transmitters, and other safety-related electrical equipment for harsh i environment It is evident that Duke Power Company has taken an overall aggressive |
| | ; approach to EQ and that considerable corporate-wide effort has been applied i |
| | ; |
| | .I w-, -c_-- ., -_.---,,-,7p,- .- . |
| . | | . |
| ' | | ... |
| | .. |
| | . |
| | ' |
| | Duke Power Company, 3 00T 2 41988 to the program; however, there were specific program partions which were deficient as evidenced by these violations. The oromnt corrective action |
| | ~ |
| | which addressed the specific problems was quickly applied to other DPC stations and this is indicative of active management involvemen To emphasize the importance of environmental cualification of electrical equipment at the Catawba Nuclear Station, Units 1 and 2, and that regulatory deadlines are met I have been authorized, after consultation with the Deputy Executive Director for Regional Operations, and the Director, Office of Enforcement, to issue the enclosed Notice of Violation and Proposed Imposition of Civil Penalty in the amount of Fifty Thousand Dollars ($50,000) for the violations described in Section I of the enclosed Notic In accordance vIth the "Modifhd Enforcement Policy Relatin 50.49," contained in NRC Generi. Letter 38-07 (Enclosure 2)g to 10 |
| | , the CFR violations described in Section I of the c 'osed Motice have been determined to be an isolated problem, having af s ed a limited number of systems and components, and therefore is considered to be an EQ Category C proble The base amount of a c'vil penalty for an EQ category C problem is $75,00 In determining the civil penalty amount, the NRC considered the four factors set forth in the "Modified Enforcement Policy Relating to 10 CFR 50.49," for escalation and mitigation of the base civil penalty amount. These factors consist of (1) identification and prompt reporting of the EQ deficiencies ( 50%); (2) best efforts to complete EQ within the deadline ( 50%); |
| | (3) corrective actions to result in full compliance ( 50%); and (4) duration of violation which is significantly below 100 days (-50%). |
| | The escalation and mitigation factors were considered as follows: No escalation or mitigation was applied for identification and prompt reporting after considering botn the fact that the licensee and the NRC each iden-tified one of the two violations for which proper corrective actions were taken, and the fact that although the licensee identified the third violation, it was not properly corrected. Fifty percent mitigation was applied for best effsets to complete EQ within the deadline. Duke Power Company has been sensitive to EQ requirements and generally maintained a high degree of attention to the EQ program. Twenty-five percent mitigation was applied for corrective actions to result in full complianc Specifi-cally, Duke Power Company initiated shutdown to undertake immediate correc-tive action on the RCS RTDs. Further, the corrective actions included extensive training enhancements which were incorporated into the station EQ program which should help to preclude similar problems in the futur However, these efforts were partially offset by the fact that two Limitorque motor operated valves without functioning T-drains were installed in the Unit 1 VX system, after the deadline, to correct Violation With respect to the fourth factor in the Modified Enforcement Policy, mitigation is inappropriate since these EQ violations, with the exception of Violation I.B. existed in excess of 100 days for Unit The application of the mitigation factors reduced the civil penalty to the minimum $50,000 as provided by Generic Letter 88-07 for significant EQ failure l.. |
| | ' |
| | . |
| | . ...- |
| | .. , |
| | l |
| | ' |
| | i Duke Power Company, 4 00T 2 4 588 The first violation described in Section II of the enclosed Notice involved hydrogen skimmer fan motors in Unit 2, which were not installed ir, accord-ance with the tested configuration, in that the breather drains were not installed. This violation was categorized as a Severity. Level IV in accord-ance with 10 CFR Part 2, Appendix C. The second violation involved an-inadequate EQ file for the Unit 1 Hydrogen Recombiner tape splices which was categorized as a Severity Level V violation because prior to the end of the inspection the equipment was shown to, in fact, be qualifiable. |
|
| |
|
| 50-414/88-07-04 Violation, The M Rel f ance fan motors used inside containment on the Hydrogen Skimer fans did not have the breather-drains installed.- This-is not in accordance with the tested configuration and the licensee did not have an adequate evaluation in the file, Paragraph 6.1.(1).
| | l You are required to respond to this letter and should follow the instruc-tions specified in the enclosed Notice when preparing your response. In your response, you should document the specific actions taken and any additional actions you plan to prevent recurrence. After reviewing your response to this Notice, including your proposed corrective actions and the results of future inspections, the NP.C will determine whether further NRC enforcement action is necessary to ensure compliance with NRC regulatory requirement In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Room. |
|
| |
|
| 50-413,414/88-07-05 Violation, Licensee's EQ files did not support qualification for the Minco type RTDs in that the RTDs and associated junction boxes were located below the flood level inside containment. The file did not address submergence at the time of the inspection, Paragraph 6.1.(3).
| | ! |
| | l The responses directed by this letter and its enclosures are not subject to l the clearance procedures of the Office of Management and Budget as required l |
| | by the Paperwork Reduction Act of 1980, Pub. L. No. 96-51 Should you have any questions concerning this letter, please contact u |
|
| |
|
| 50-414/88-07-06 Violation, The cover gasket on a Namco Limit switch (tag no. 2NCLLO251) was missing at one en This configuration is not considered qualified, Paragraph 6.1.(18).
| | Sincerely, ORIGINAL SIGNED fly M. L ERNST Malcolm L. Ernst Acting Regional Administrator Enclosures: Notice of Violation and Proposed Imposition of Civil Penalty Generic Letter 88-07 cc w/encis: |
| | T. B. Owen, Station Manager State of South Carolina |
|
| |
|
| 50-413, 414/88-07-07 Violation, Limitorque valves on Unit ? were observed to have their T-drains painted ove Two out of the three limitorques inspected exhibited some kind of obstructio A walkdown by the licensee identified further
| | . . |
| , examples of T-drains obstructed or their ability to properly drain was uncertain. In addition, some limitorque operators located inside containment on Units 1 and 2 were discovered without any T-drains installed, Paragraph 6.i.(15).
| | . .. |
| | | . |
| 50-414/88-07-08 Unresolved Item, T-drains on limitorque valve No. 2NI-1228 were not installed at the low poin This configuration does not appear to be qualified, Paragraph 6.1.(15). Licensee Action on Previous Enforcement Matters (Closed) Violation 50-413/86-05-05, Use of Unqualified Limitorque Motor Operated Valves Inside Unit 1 Containment
| | . |
| ,
| | Duke Power Compan OCT241999 DISTRIBUTION bcc w/ enc 1: |
| ;
| | PDR SECY CA JMTaylor, DEDRO JLieberman, OE LChandler, 0GC JLuehman, OE Enforcement Coordinators RI, RII, RIII, RIV, RV Fingram, GP EJordan, AE0D BHayes, O! |
| l The inspectors followed up on a previously identified Violation 1 413/86-05-05 which identified the lack of proper documentation for the ) | | SConnelly, OIA OE:ES File OE:EA File BSumers, OE (ltr hd) |
| environmental qualification of IVX1A and IVX28, hydrogen skimmer fan i isolation valves. The initial concern was that these motors operated
| | DCS Document Control Desk OE k OG [ RA:l! D' D JLue man r MLErns',F serman JM hor LChanj88 10/ /88 10/ (V88 10//y 10/ / /88 1 |
| !
| | /7/88 RI - S R ff !.El p RIlh4) |
| l 8805250212 880512 3 ADOCK 0500
| | AFG1 con 'Y[tAReyes V |
| {DR | | ns JP tohr 10/g/88 IO/Jo/88 Og\/88 10 /88 |
| . q ,_ _ _ . _ _
| | .,, . - - - - . ,-_ |
| - - l
| |
| }} | | }} |
|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F8231999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of Catawba Nuclear Station.Based on Review,Nrc Did Not Identify Any New Areas That Warranted More than Core Insp Program Over Next Five Months.Historical Listing of Issues,Encl ML20217H0041999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217F1301999-10-0707 October 1999 Forwards Rev 1 to Request for Relief 99-03 from Requirements of ASME B&PV Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting (Vg) Sys ML20212J3011999-10-0101 October 1999 Forwards Exemption from Certain Requirements of 10CFR54.17(c) Re Schedule for Submitting Application for Operating License Renewal.Se Also Encl ML20217K2651999-10-0101 October 1999 Forwards Retake Exams Repts 50-413/99-302 & 50-414/99-302 on 990921-23.Two of Three ROs & One SRO Who Received Administrative Section of Exam Passed Retake Exam, Representing 75 Percent Pass Rate 05000414/LER-1999-004, Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments1999-09-27027 September 1999 Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments 05000413/LER-1999-015, Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept1999-09-27027 September 1999 Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept ML20217A7911999-09-24024 September 1999 Forwards Insp Repts 50-413/99-05 & 50-414/99-05 on 990718- 0828 at Catawba Facility.Nine NCVs Identified Involving Inadequate Corrective Actions Associated with Degraded Svc Water Supply Piping to Auxiliary Feedwater Sys ML20212E6471999-09-24024 September 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for Catawba NPP & 990615.Informs That NRC Reviewed Response for Catawba & Concluded That All Requested Info Provided.Considers GL 98-01 to Be Closed for Catawba ML20212F0941999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals for Cns,Units 1 & 2 ML20212M2001999-09-20020 September 1999 Confirms 990913 Telcon Between M Purser & R Carroll Re Management Meeting to Be Conducted on 991026 in Atlanta,Ga to Discuss Operator Licensing Issues 05000414/LER-1999-005, Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments1999-09-20020 September 1999 Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20212B4641999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for Catawba Nuclear Station,Units 1 & 2 ML20212A4131999-09-14014 September 1999 Informs That TR DPC-NE-2009P Submitted in 990817 Affidavit, Marked Proprietary,Will Be Withheld from Public Disclosure, Pursuant to 10CFR2.709(b) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20212M1931999-09-13013 September 1999 Refers to 990909 Meeting Conducted at Region II Office Re Presentation of Licensee self-assessment of Catawba Nuclear Station Performance.List of Attendees & Licensee Presentation Handout Encl ML20212A3751999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementation Code Case for Duration of Insp Interval ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 05000413/LER-1999-014, Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment1999-09-0101 September 1999 Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment 05000414/LER-1999-003, Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev1999-08-31031 August 1999 Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev 0 of LER ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting 05000413/LER-1999-013, Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER1999-08-25025 August 1999 Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER ML20211M8191999-08-25025 August 1999 Confirms 990825 Telcon Between G Gilbert & R Carroll Re Mgt Meeting to Be Held on 990909 in Atlanta,Ga,To Allow Licensee to Present self-assessment of Catawba Nuclear Station Performance ML20211A9641999-08-20020 August 1999 Forwards SE Authorizing Licensee 990118 Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section XI for Plant,Units 2 ML20211C1191999-08-18018 August 1999 Forwards ISI Rept Unit 1 Catawba 1999 RFO 11, Providing Results of ISI Effort Associated with End of Cycle 11 ML20211B9471999-08-18018 August 1999 Forwards Request for Relief 99-02,associated with Limited Exam Results for Welds Which Were Inspected During Unit 1 End of Cycle 11 RFO ML20211C3651999-08-17017 August 1999 Forwards Rev 25 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program, Which Includes Reformatting of Manual & Addl Changes as Noted in Attached Summary of Changes ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 05000413/LER-1999-011, Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment1999-08-16016 August 1999 Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire ML20210V0321999-08-13013 August 1999 Forwards Insp Repts 50-413/99-04 & 50-414/99-04 on 990606- 0717.Six Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20210S2751999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210Q3751999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date,In Order to Register Individuals for Exam ML20210N9521999-08-0404 August 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual.Documents Constitutes Chapter 16 of Ufsar.With List of Effective Pages IR 05000413/19980131999-08-0202 August 1999 Discusses Integrated Insp Repts 50-413/98-13,50-414/98-13, 50-413/98-16,50-414/98-16 & NRC Special Repts 50/413/99-11 & 50-414/99-11 Conducted Between Aug 1998 & May 1999.Six Violations Occurred,Based on OI Investigation & Insp ML20210M6411999-07-29029 July 1999 Forwards Request for Relief 99-03 from Requirements of ASME Boiler & Pressure Vessel Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting Air (Vg) Sys 05000413/LER-1999-010, Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units1999-07-22022 July 1999 Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units IR 05000413/19990101999-07-22022 July 1999 Discusses Insp Rept 50-413/99-10 & 50-414/99-10 on 990314- 0424 & Forwards Notice of Violation Re Failure to Comply with TS 3.7.13,when Misalignment of Two Electrical Breakers Rendered SSS Inoperable from 981216-29 ML20217G5241999-07-20020 July 1999 Forwards Exam Repts 50-413/99-301 & 50-414/99-301 on 990524- 27,0603,07-10 & 16.Of Fourteen SRO & RO Applicants Who Received Written Exams & Operating Tests,Eight Applicants Passed & Six Failed Exam 05000413/LER-1999-009, Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept1999-07-19019 July 1999 Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept 05000414/LER-1999-001, Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed1999-07-15015 July 1999 Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed ML20209H4431999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for May 1999 on Unit Shutdowns Also Encl ML20210A5771999-07-14014 July 1999 Forwards Revsied Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e),changing Sections 16.7-5,16.8-5,16.9-1,16.9-3,16.9-5 & 16.11-7.Manual Constitute Chapter 16 of UFSAR ML20216D3941999-07-14014 July 1999 Forwards Revs to Catawba Nuclear Station Selected Licensee Commitments Manual NUREG-1431, Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation1999-07-0909 July 1999 Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196L0371999-07-0808 July 1999 Approves Requested Schedule Change of Current two-year Requalification Examinations to non-outage dates.Two-year Cycle Will Start on 991001 & Will End on 020930 05000413/LER-1999-008, Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach1999-07-0808 July 1999 Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach ML20196J9001999-07-0606 July 1999 Informs That 990520 Submittal of Rept DPC-NE-3004-PA,Rev 1, Mass & Energy Release & Containment Response Methodology, Marked Proprietary Will Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 IR 05000413/19990031999-07-0101 July 1999 Discusses Insp Repts 50-413/99-03 & 50-414/99-03 Completed on 990605 & Transmitted by Ltr .Results of Delibrations for Violation Re Discovery of Potentially More Limiting Single Failure Affecting SGTS Analysis Provided 1999-09-08
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058J1251990-11-13013 November 1990 Advises That Re Martin Recently Assigned as Project Manager for Facility ML20058F6161990-10-26026 October 1990 Forwards Insp Repts 50-413/90-28 & 50-414/90-28 on 901001-04.Violation Re Corrective Actions Which Appear to Be Ineffective in Preventing Recurrence of Similar Violation Noted.Enforcement Conference Scheduled for 901105 ML20058F0891990-10-22022 October 1990 Confirms 901031-1102 & 12-16 & 26-30 as Dates for Maint Team Insp of Plant Per 901011 Telcon ML20058B4551990-10-17017 October 1990 Forwards Insp Repts 50-413/90-25 & 50-414/90-25 on 900924-28.No Violations or Deviations Noted ML20062B7051990-10-12012 October 1990 Requests Completion of Analysis of Liquid Samples Spiked W/ Radionuclides within 60 Days of Receipt of Ltr ML20062A0951990-10-0303 October 1990 Forwards Insp Repts 50-413/90-24 & 50-414/90-24 on 900803- 0905 & Notice of Violation ML20059L4141990-09-14014 September 1990 Forwards Insp Repts 50-413/90-23 & 50-414/90-23 on 900730-0803.No Violations or Deviations Noted IR 05000413/19900151990-09-0505 September 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-413/90-15 & 50-414/90-15 ML20059L5241990-09-0505 September 1990 Ack Receipt of 900810 Supplemental Response to Violations Noted in Insp Repts 50-413/90-09 & 50-414/90-09 ML20059H0121990-08-31031 August 1990 Forwards Insp Repts 50-413/90-19 & 50-414/90-19 on 900624- 0802 & Notice of Violation.Util Should Detail Measures to Be Taken to Place Addl Emphasis on Compensatory Actions Program ML20059E3121990-08-30030 August 1990 Advises That Util Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Further NRC Review,If Any,Will Be Performed Either by Insp or Audit ML20059G6171990-08-28028 August 1990 Forwards Insp Repts 50-413/90-20 & 50-414/90-20 on 900724-26.Unresolved Item Identified Re Procedure of Equating self-referral to Employee Assistance Program as First Positive Drug Test ML20056A5571990-08-0202 August 1990 Requests Addl Info Re DPC-NE-2004, Core Thermal-Hydraulic Methodology Using VIPRE-01 for McGuire & Catawba. Requests Response Expeditiously IR 05000413/19900111990-08-0101 August 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-413/90-11 & 50-414/90-11 ML20058P8761990-07-31031 July 1990 Forwards Insp Repts 50-413/90-22 & 50-414/90-22 on 900709-13.No Violations or Deviations Noted ML20055H9131990-07-27027 July 1990 Forwards Safety Evaluation Accepting Actions Taken to Resolve NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes ML20055J2931990-07-23023 July 1990 Forwards Request for Addl Info Re Util 900315 Submittal of General Relief Request for Pumps in Inservice Testing Program.Addl Info Re Certain Areas That Deviate from OM-6, Identified in Encl,Required to Complete NRC Review IR 05000413/19900171990-07-23023 July 1990 Discusses Insp Repts 50-413/90-17 & 50-414/90-17 on 900611- 19 & Forwards Notice of Violation.Insp Included Review of Actions Re 900611 Inadvertent Transfer of Reactor Coolant Water to Refueling Water Storage Tank at Unit 1 ML20056A5071990-07-20020 July 1990 Forwards Insp Repts 50-413/90-15 & 50-414/90-15 on 900527-0623 & Notice of Violation.Violations,Refs Pertinent to Requirements & Elements to Be Included in Response Presented in Encl Notice of Violation ML20055H4191990-07-19019 July 1990 Forwards Insp Repts 50-413/90-21 & 50-414/90-21 on 900627-29.No Violations or Deviations Noted ML20055H4101990-07-18018 July 1990 Forwards Summary of Enforcement Conference on 900712 Re Unit 1 Inadvertent Diversion of Higher Pressure Reactor Coolant Water to Refueling Water Storage Tank on 900611,per Insp Repts 50-413/90-17 & 50-414/90-17.Handouts Also Encl ML20055H5881990-07-13013 July 1990 Forwards Insp Repts 50-413/90-16 & 50-414/90-16 on 900611-15.Violations Noted But Not Cited ML20058M9361990-07-13013 July 1990 Forwards Insp Repts 50-413/90-18 & 50-414/90-18 on 900625-29.No Violations or Deviations Noted ML20055H3601990-07-10010 July 1990 Advises That Reactor Operator & Senior Operator Licensing Exams Scheduled for Wk of 901015.Encl Ref Matls Requested by 900806 ML20055E3711990-07-0909 July 1990 Ack Receipt of Re Payment of Civil Penalties in Amount of $100,000,per NRC ML20055H4411990-07-0202 July 1990 Ack Receipt of 900607 Response to Violations Noted in Insp Repts 50-413/90-09 & 50-414/90-09.Implementation of Corrective Actions Will Be Examined During Future Insp ML20055C9911990-06-27027 June 1990 Confirms Region II Insp of fitness-for-duty Program on 900724-26.Brief Itinerary to Expedite Util Support of Program Encl ML20055C8421990-06-13013 June 1990 Forwards Insp Repts 50-413/90-14 & 50-414/90-14 on 900521-25.No Violations or Deviations Noted ML20059M9241990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248J3891989-10-16016 October 1989 Forwards Insp Repts 50-413/89-28 & 50-414/89-28 on 890911-15.Violations Noted ML20248D2921989-09-28028 September 1989 Discusses Util Response to Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Boundary Components in PWR Plants ML20248B6881989-09-25025 September 1989 Forwards Insp Repts 50-413/89-25 & 50-414/89-25 on 890801-28 & 0912-15.No Notice of Violation Issued for Violations Identified.Enforcement Conference to Discuss Violations Scheduled for 890928 ML20248B0921989-09-22022 September 1989 Confirms Arrangements for Enforcement Conference on 890928 to Discuss Failure to Take Adequate Corrective Action in Response to Failed Surveillance Test on Unit 2 Turbine Driven Auxiliary Feedwater Pump.Items to Discuss Encl IR 05000413/19890021989-09-20020 September 1989 Ack Receipt of Util Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-413/89-02 & 50-414/89-02 IR 05000413/19890161989-09-20020 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-413/89-16 & 50-414/89-16 ML20248B7431989-09-20020 September 1989 Forwards Insp Repts 50-413/89-26 & 50-414/89-26 on 890821-24.No Violations or Deviations Noted.Attention Invited to Unresolved Items Identified IR 05000413/19890091989-09-20020 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-413/89-09 & 50-414/89-09.Extension of Reply Due Date to 891010 for Weaknesses Identified in Insp Approved in 890823 Telcon ML20247G7421989-09-12012 September 1989 Forwards Insp Repts 50-413/89-24 & 50-414/89-24 on 890807-11.No Violations or Deviations Noted ML20246J6491989-08-31031 August 1989 Forwards Order Imposing Civil Penalty in Amount of $75,000, Per Violations Noted in Insp Repts 50-413/88-38 & 50-414/88-38 Re Inoperability of Containment Air Return & Hydrogen Skimmer Sys Due to Electrical Wiring Error IR 05000413/19880381989-08-31031 August 1989 Forwards Order Imposing Civil Penalty in Amount of $75,000, Per Violations Noted in Insp Repts 50-413/88-38 & 50-414/88-38 Re Inoperability of Containment Air Return & Hydrogen Skimmer Sys Due to Electrical Wiring Error IR 05000414/19890191989-08-31031 August 1989 Discusses Insp Rept 50-414/89-19 on 890616-28 & Forwards Notice of Violation.Violation Noted:On 890602,upper-range Pressurizer Transmitter Isolation Valves on Reactor Vessel Level Instrumentation Not Opened Prior to Entering Mode 3 ML20247C5541989-08-30030 August 1989 Advises That 890405 Rev 29 to Crisis Mgt Plan Consistent W/Provisions of 10CFR50.47(b) & Requirements of App E & Acceptable ML20246J9191989-08-29029 August 1989 Requests Addl Info Re Direct Generation Response Spectra & Snubber Reduction Program.Response Requested within 30 Days ML20247A1781989-08-29029 August 1989 Forwards Summary of 890720 & 0815 Enforcement Conferences Re Findings in Insp Repts 50-413/89-19 & 50-414/89-19 on Inoperability of Reactor Vessel Level Instrumentation Sys. List of Attendees & Viewgraphs Also Encl ML20246N1671989-08-28028 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-413/89-17 & 50-414/89-17 ML20246M5061989-08-22022 August 1989 Forwards Insp Repts 50-413/89-22 & 50-414/89-22 on 890723-28.No Violations Noted IR 05000413/19890141989-08-16016 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-413/89-14 & 50-414/89-14 ML20246C7051989-08-14014 August 1989 Forwards Insp Repts 50-413/89-18 & 50-414/89-18 on 890717-21.Violations Noted in Rept But Not Cited ML20245K4051989-08-11011 August 1989 Forwards Insp Repts 50-413/89-20 & 50-414/89-20 on 890717-21.No Violations or Deviations Noted ML20246A7411989-08-0808 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-413/89-13 & 50-414/89-13 1990-09-05
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217F8231999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of Catawba Nuclear Station.Based on Review,Nrc Did Not Identify Any New Areas That Warranted More than Core Insp Program Over Next Five Months.Historical Listing of Issues,Encl ML20217K2651999-10-0101 October 1999 Forwards Retake Exams Repts 50-413/99-302 & 50-414/99-302 on 990921-23.Two of Three ROs & One SRO Who Received Administrative Section of Exam Passed Retake Exam, Representing 75 Percent Pass Rate ML20212J3011999-10-0101 October 1999 Forwards Exemption from Certain Requirements of 10CFR54.17(c) Re Schedule for Submitting Application for Operating License Renewal.Se Also Encl ML20212E6471999-09-24024 September 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for Catawba NPP & 990615.Informs That NRC Reviewed Response for Catawba & Concluded That All Requested Info Provided.Considers GL 98-01 to Be Closed for Catawba ML20217A7911999-09-24024 September 1999 Forwards Insp Repts 50-413/99-05 & 50-414/99-05 on 990718- 0828 at Catawba Facility.Nine NCVs Identified Involving Inadequate Corrective Actions Associated with Degraded Svc Water Supply Piping to Auxiliary Feedwater Sys ML20212F0941999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals for Cns,Units 1 & 2 ML20212M2001999-09-20020 September 1999 Confirms 990913 Telcon Between M Purser & R Carroll Re Management Meeting to Be Conducted on 991026 in Atlanta,Ga to Discuss Operator Licensing Issues ML20212A4131999-09-14014 September 1999 Informs That TR DPC-NE-2009P Submitted in 990817 Affidavit, Marked Proprietary,Will Be Withheld from Public Disclosure, Pursuant to 10CFR2.709(b) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20212M1931999-09-13013 September 1999 Refers to 990909 Meeting Conducted at Region II Office Re Presentation of Licensee self-assessment of Catawba Nuclear Station Performance.List of Attendees & Licensee Presentation Handout Encl ML20212A3751999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementation Code Case for Duration of Insp Interval ML20211M8191999-08-25025 August 1999 Confirms 990825 Telcon Between G Gilbert & R Carroll Re Mgt Meeting to Be Held on 990909 in Atlanta,Ga,To Allow Licensee to Present self-assessment of Catawba Nuclear Station Performance ML20211A9641999-08-20020 August 1999 Forwards SE Authorizing Licensee 990118 Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section XI for Plant,Units 2 ML20210V0321999-08-13013 August 1999 Forwards Insp Repts 50-413/99-04 & 50-414/99-04 on 990606- 0717.Six Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20210Q3751999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date,In Order to Register Individuals for Exam IR 05000413/19980131999-08-0202 August 1999 Discusses Integrated Insp Repts 50-413/98-13,50-414/98-13, 50-413/98-16,50-414/98-16 & NRC Special Repts 50/413/99-11 & 50-414/99-11 Conducted Between Aug 1998 & May 1999.Six Violations Occurred,Based on OI Investigation & Insp IR 05000413/19990101999-07-22022 July 1999 Discusses Insp Rept 50-413/99-10 & 50-414/99-10 on 990314- 0424 & Forwards Notice of Violation Re Failure to Comply with TS 3.7.13,when Misalignment of Two Electrical Breakers Rendered SSS Inoperable from 981216-29 ML20217G5241999-07-20020 July 1999 Forwards Exam Repts 50-413/99-301 & 50-414/99-301 on 990524- 27,0603,07-10 & 16.Of Fourteen SRO & RO Applicants Who Received Written Exams & Operating Tests,Eight Applicants Passed & Six Failed Exam NUREG-1431, Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation1999-07-0909 July 1999 Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196L0371999-07-0808 July 1999 Approves Requested Schedule Change of Current two-year Requalification Examinations to non-outage dates.Two-year Cycle Will Start on 991001 & Will End on 020930 ML20196J9001999-07-0606 July 1999 Informs That 990520 Submittal of Rept DPC-NE-3004-PA,Rev 1, Mass & Energy Release & Containment Response Methodology, Marked Proprietary Will Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 IR 05000413/19990031999-07-0101 July 1999 Discusses Insp Repts 50-413/99-03 & 50-414/99-03 Completed on 990605 & Transmitted by Ltr .Results of Delibrations for Violation Re Discovery of Potentially More Limiting Single Failure Affecting SGTS Analysis Provided ML20209E2701999-07-0101 July 1999 Forwards Insp Repts 50-413/99-03 & 50-414/99-03 on 990425- 0605.Six Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20209E3931999-06-28028 June 1999 Informs of 990618 Meeting Conducted at Facility to Present Results of Most Recent Periodic Plant Performance Review for Plant.List of Attendees Encl ML20196G8861999-06-24024 June 1999 Discusses GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structrual Integrity 950816 & 960729 Responses.Rvid,Version 2 Released as Result of Review.Rvid Should Be Reviewed & Comments Should Be Received by 990901 If Not Acceptable for Plant ML20196G6541999-06-17017 June 1999 Confirms 990614 Telephone Conversation Re Rescheduling of Two Predecisional Enforcement Conferences Originally Scheduled for 990623.SSS Conference Rescheduled for 990712 & Ice Condenser Conference Rescheduled for 990720 ML20196A5781999-06-14014 June 1999 Discusses Notice of Enforcement Discretion for Duke Energy Corp Re Catawba Nuclear Station Unit 1 TSs 3.5.2 & 3.7.12 ML20195E9171999-06-0303 June 1999 Confirms Conversation with Bradshaw on 990526 Re Rescheduling 990607 Predecisional Enforcement Conference to Discuss Apparent Violation in Insp Repts 50-413/99-10 & 50-414/99-10.Conference Will Be on 990623 in Atlanta,Ga ML20195F4141999-06-0202 June 1999 Forwards Insp Repts 50-413/99-11 & 50-414/99-11 on 990422-23 & 0503.Apparent Violation Identified & Being Considered for Escalated Enforcement Action.Violation Involved Failure to Maintain Unit 1 Ice Condenser Lower Inlet Door Operable ML20207D0671999-05-20020 May 1999 Informs That During Meeting on 990512,arrangements Modified for Administration of Licensing Exams at Catawba Nuclear Station During Weeks of 990524 & 0607,respectively ML20207C8721999-05-20020 May 1999 Forwards Insp Repts 50-413/99-02 & 50-414/99-02 on 990314-0424.Three Violations Occurred & Being Treated as non-cited Violations.Activities Generally Characterized by Safety Conscious Operations & Sound Engineering & Maint ML20207C8061999-05-19019 May 1999 Confirms 990510 Telcon with R Jones Re Predecisional Enforcement Conference Requested by NRC & Scheduled for 990607 in Atlanta,Ga to Discuss Apparent Violation Associated with Potential Inoperability of SSS ML20207C7761999-05-19019 May 1999 Informs That on 990618,NRC Will Meet with Mgt of Duke Energy Corp to Discuss Performance of Catawba Facility & Extends Invitation to Attend Meeting as Observer ML20206P4911999-05-14014 May 1999 Forwards Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20206M4201999-05-11011 May 1999 Informs That NRC Ofc of Nuclear Regulation (NRR) Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt (DLPM) Created.Reorganization Chart Encl ML20206U4091999-05-10010 May 1999 Forwards Insp Repts 50-413/99-10 & 50-414/99-10 on 990314-0424.One Violation Occurred & Being Considered for Escalated Enforcement Action Involving Inoperability of Standby Shutdown Sys from 981216-29 ML20206N4191999-05-0606 May 1999 Informs That Team Will Inspect Dam at Standby Nuclear Service Water Pond on 990609.Purpose of Insp Will Be to Confirm That Structure Conforms with Design Documents & Capability of Performing Design Functions ML20205S5491999-04-21021 April 1999 Forwards SE Discussing DPC Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions. Response Acceptable ML20206B7941999-04-16016 April 1999 Confirms 990331 Telcon Between M Purser of Util & R Franovich of NRC Re Public Meeting Scheduled for 990618 in York,Sc to Discuss Results of NRC Recent Plant Performance Review for Catawba Nuclear Station ML20205N3471999-04-12012 April 1999 Forwards Safety Evaluation & Eri/Nrc 95-506, Technical Evaluation Rept on Submittal Only Review of IPE of External Events at Catawba Nuclear Station,Units 1 & 2 ML20205T3491999-04-0909 April 1999 Informs That on 990317,T Beedle & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Catawba Nuclear Station for Y2K.No Y2K Exam Scheduled.Initial Exam Requested for Apr 2001 for Approx 18 Candidates ML20205N0531999-04-0606 April 1999 Forwards Insp Repts 50-413/99-01 & 50-414/99-01 on 990124-0313.DPC Conduct of Activities at Catawba Facility Generally Characterized by Safety Conscious Operations & Sound Engineering.Five Violations Noted & Treated as NCVs ML20196K9961999-03-30030 March 1999 Forwards Synopsis of NRC OI Completed Rept Re Alleged Compromise of Initial Licensed Operator Exam at Cns.Oi Did Not Substantiate Allegation That Initial Operator Exam Compromised.Plans No Further Action Re Matter ML20205M2651999-03-25025 March 1999 Discusses PPR Completed 990201.Advises of Planned Insp Effort Resulting from Catawba PPR Review.Forwards Plant Issues Matrix & Insp Plan ML20207L7741999-03-15015 March 1999 Requests That NRC Exercise Discretion Not to Enforce Compliance with Actions Required by Plant,Units 1 & 2 Re TS Limiting Conditions for Operation 3.3.7 & 3.3.8 ML20207M9091999-03-0505 March 1999 Informs That Info Submitted by Application, Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20207A5821999-02-17017 February 1999 Forwards Insp Repts 50-413/98-12 & 50-414/98-12 & Notice of Violation.One Violation Being Considered for Escalated Enforcement Action ML20203G5161999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Listing of Candidates for Exam ML20203A2421999-02-0505 February 1999 Forwards SE Accepting Proposal to Revise Methodology in TR DPC-NE-3002-A,to Permit Use of single-node Model,Instead of multi-node Model,To Represent SG Secondary Sys for post-trip Phase of Loss of Normal Feedwater Analysis for Plant,Unit 2 ML20202J4751999-01-29029 January 1999 Responds to Concern Raised on 981020 Re Appropriateness of Interaction of NRC Headquarters Operations Officer with on-shift Operations Staff During Event ML20202C2511999-01-27027 January 1999 Forwards Request for Addl Info Re Util 980331 Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, for Catawba Nuclear Station. Response Requested within 60 Days of Date of Ltr 1999-09-24
[Table view] |
Inspection Report - Catawba - 1988007 |
---|
|
|
Text
%
,
fll0lA)
... .
. .
.
OCT 241988 Docket Nos. 50-413 and 50-414 License Nos. NPF-35 and NPF-52 EA 88-132 Duke Power Company ATTN: Mr. H. B. Tucker, Vice President Nuclear Production Departmr't 422 South Church Street Charlotte, NC 28242 Gentlemen:
SUBJECT: NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF CIVIL PENALTY (NRC INSPECTION REPORT N05. 50-413/88-07 AND 50-414/88-07)
This refers to the Nuclear Regulatory Commission (NRC) inspection conducted at both the Catawba Nuclear Station, Units 1 and 2, and the Duke Power Company (DPC) Design Offices in Charlotte, NC, during the period February 1-5, 1988. The inspection included a review of the program for the environ-mental qualification (EQ) of electrical equipment under 10 CFR 50.4 During the inspection, violations of NRC requirements were identified involving the lack of environmental qualification for cert. tin components of electrical equipment in isolated systems in both units. The inspection also included a review of the circumsty:es surrounding your identification of the unqualified wide range Reactor Coolant System (RCS) hot and cold leg resistance temperature detectors (RTD), which were unqualified because they were not installed in accordance with the tested configuration. The report documenting this inspection was sent to you by letter dated May 4, 1988. As a result of this inspection, a significant failure to comply with regulatory requirements was identified, and accordingly, NRC concerns relating to the
, inspection were discussed in an Enforcement Conference held on July 1, 1988.
l The letter summarizing this Conference was sent to you on July 25, 1988.
.
. The violations described in the enclosed Notice of Violation and Proposed
! Imposition of Civil Penalty (Notice) involved the failure to comply with
'
the requirements of 10 CFR 50.49 for both units. Unit 1 is subject to the
"Modified Enforcement Policy Relating to 10 CFR 50.49. Environmental Quali-fication of Electrical Equipment Important to Safety for Nuclear Power Plants " contained in NRC Generic Letter 88-07. Unit 2, by virtue of its being licensed after the November 30, 1985, deadline for EQ compliance, is suh.iect to the normal Enforcement Policy of 10 CFR Part 2, Appendix C. The duali g of Enforcement Policy notwithstanding, a single Notice of Violation and Proposed Imposition of Civil Penalty is appropriate in this case because of the similarity of the violations for both units; equitability in applying i
the Enforcement Policies in this case is achieved by addressing the overall EQ program at the Catawba Nuclear Station; and, in fairness, it is appro-l l
priate to assess the EQ problem at the facility as a whole.
l 8811020163 881024 PDR ADOCK 05 COO 413 Q PNU 9%
=
! . .-
- - . : ,
. .
,
'
Duke Power Company, 2 OCT 2 41988 The violations described in Section I of the enclosed Notice included the failure to properly install the RCS hot and cold lag wida range RTDs in accordance wfth the tested configuration; failure to adequately evaluate the qualification of non-safety valve operators installed inside Unit 1 contain-ment in the Containment Air Return and Hydrogen-Skimmer System (VX); and fit ally, failure to ensure that valve operators on both units had function-ing T-drains installed similar to the qualified test ccnfiguratio The unqualified RTD configuration resulted from a breakdown in your design interface controis to properly translate design specifications for EQ equipment into installation instructions for the craft and your failure to perform adequate walkdowns of EQ equipment. The lack of functioning T-drains on some Limitorque valve operators can also be attributed to your failure to perform adequate walkdowns. The violation involving the instal-lation of non-safety valve operators into the Hydrogen Skimer System resulted from an inadequate engineering evaluation which failed to consider all the facets of proof necessary to qualify a component to the requirements of the EQ rul The NRC believes that Duke Power Company clearly should have known about the environmental qualification deficiencies identified above for Unit 1, and clearly would have discovered the problems had an adequate level of atten-tion been applied to the environmental qualifica'. ion program requirements which included design interface control and fie',d verification inspection The issue regarding the submerged RTD install? cions should have been dis-covered in 1984 when questions were raised by NRR concerning the capability of the RTDs to function while submerged. Not only is the need to install functional T-drains on the inside containment actuators required by the test report for the actuators, but it should be a routine practice to have all actuators fully functional. ..oreover, DPC was informed in 1984 that valve operators in the VX system did not meet their specifications and were not
- qualified for installation inside containmen It is clear that a program for environmental qualification of electrical equipment should include, as
a fundamental element, a comprehensive as-built field inspection program to verify that equipment was installed in the configuration in which it was tested for qualificatio Such was not the case for the RCS RTDs in Unit I where the RTD wires were not qualified for submergence in the installed configuration and the problem was not discovered during your review of the installation. Finally, Duke Power Company had available information such as IE Circuler 79-05, several IE Notices such as 79-03 and 83-72, and j NUREG-0588, "Interim Staff Position on Environmental Qualification of
- Safety-Related Electrical Equipment," which addressed the need to environ-
'
mentally qualify such items as moisture intrusion seals, moter operators, transmitters, and other safety-related electrical equipment for harsh i environment It is evident that Duke Power Company has taken an overall aggressive
- approach to EQ and that considerable corporate-wide effort has been applied i
.I w-, -c_-- ., -_.---,,-,7p,- .- .
.
...
..
.
'
Duke Power Company, 3 00T 2 41988 to the program; however, there were specific program partions which were deficient as evidenced by these violations. The oromnt corrective action
~
which addressed the specific problems was quickly applied to other DPC stations and this is indicative of active management involvemen To emphasize the importance of environmental cualification of electrical equipment at the Catawba Nuclear Station, Units 1 and 2, and that regulatory deadlines are met I have been authorized, after consultation with the Deputy Executive Director for Regional Operations, and the Director, Office of Enforcement, to issue the enclosed Notice of Violation and Proposed Imposition of Civil Penalty in the amount of Fifty Thousand Dollars ($50,000) for the violations described in Section I of the enclosed Notic In accordance vIth the "Modifhd Enforcement Policy Relatin 50.49," contained in NRC Generi. Letter 38-07 (Enclosure 2)g to 10
, the CFR violations described in Section I of the c 'osed Motice have been determined to be an isolated problem, having af s ed a limited number of systems and components, and therefore is considered to be an EQ Category C proble The base amount of a c'vil penalty for an EQ category C problem is $75,00 In determining the civil penalty amount, the NRC considered the four factors set forth in the "Modified Enforcement Policy Relating to 10 CFR 50.49," for escalation and mitigation of the base civil penalty amount. These factors consist of (1) identification and prompt reporting of the EQ deficiencies ( 50%); (2) best efforts to complete EQ within the deadline ( 50%);
(3) corrective actions to result in full compliance ( 50%); and (4) duration of violation which is significantly below 100 days (-50%).
The escalation and mitigation factors were considered as follows: No escalation or mitigation was applied for identification and prompt reporting after considering botn the fact that the licensee and the NRC each iden-tified one of the two violations for which proper corrective actions were taken, and the fact that although the licensee identified the third violation, it was not properly corrected. Fifty percent mitigation was applied for best effsets to complete EQ within the deadline. Duke Power Company has been sensitive to EQ requirements and generally maintained a high degree of attention to the EQ program. Twenty-five percent mitigation was applied for corrective actions to result in full complianc Specifi-cally, Duke Power Company initiated shutdown to undertake immediate correc-tive action on the RCS RTDs. Further, the corrective actions included extensive training enhancements which were incorporated into the station EQ program which should help to preclude similar problems in the futur However, these efforts were partially offset by the fact that two Limitorque motor operated valves without functioning T-drains were installed in the Unit 1 VX system, after the deadline, to correct Violation With respect to the fourth factor in the Modified Enforcement Policy, mitigation is inappropriate since these EQ violations, with the exception of Violation I.B. existed in excess of 100 days for Unit The application of the mitigation factors reduced the civil penalty to the minimum $50,000 as provided by Generic Letter 88-07 for significant EQ failure l..
'
.
. ...-
.. ,
l
'
i Duke Power Company, 4 00T 2 4 588 The first violation described in Section II of the enclosed Notice involved hydrogen skimmer fan motors in Unit 2, which were not installed ir, accord-ance with the tested configuration, in that the breather drains were not installed. This violation was categorized as a Severity. Level IV in accord-ance with 10 CFR Part 2, Appendix C. The second violation involved an-inadequate EQ file for the Unit 1 Hydrogen Recombiner tape splices which was categorized as a Severity Level V violation because prior to the end of the inspection the equipment was shown to, in fact, be qualifiable.
l You are required to respond to this letter and should follow the instruc-tions specified in the enclosed Notice when preparing your response. In your response, you should document the specific actions taken and any additional actions you plan to prevent recurrence. After reviewing your response to this Notice, including your proposed corrective actions and the results of future inspections, the NP.C will determine whether further NRC enforcement action is necessary to ensure compliance with NRC regulatory requirement In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Room.
!
l The responses directed by this letter and its enclosures are not subject to l the clearance procedures of the Office of Management and Budget as required l
by the Paperwork Reduction Act of 1980, Pub. L. No. 96-51 Should you have any questions concerning this letter, please contact u
Sincerely, ORIGINAL SIGNED fly M. L ERNST Malcolm L. Ernst Acting Regional Administrator Enclosures: Notice of Violation and Proposed Imposition of Civil Penalty Generic Letter 88-07 cc w/encis:
T. B. Owen, Station Manager State of South Carolina
. .
. ..
.
.
Duke Power Compan OCT241999 DISTRIBUTION bcc w/ enc 1:
PDR SECY CA JMTaylor, DEDRO JLieberman, OE LChandler, 0GC JLuehman, OE Enforcement Coordinators RI, RII, RIII, RIV, RV Fingram, GP EJordan, AE0D BHayes, O!
SConnelly, OIA OE:ES File OE:EA File BSumers, OE (ltr hd)
DCS Document Control Desk OE k OG [ RA:l! D' D JLue man r MLErns',F serman JM hor LChanj88 10/ /88 10/ (V88 10//y 10/ / /88 1
/7/88 RI - S R ff !.El p RIlh4)
AFG1 con 'Y[tAReyes V
ns JP tohr 10/g/88 IO/Jo/88 Og\/88 10 /88
.,, . - - - - . ,-_