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| {{Adams | | {{Adams |
| | number = ML20247K836 | | | number = ML20236S713 |
| | issue date = 05/11/1998 | | | issue date = 06/29/1998 |
| | title = Special Insp Repts 50-348/98-09 & 50-364/98-09 on 980323-25. Violations Noted.Major Areas Inspected:Follow Up on OI Rept 2-97-011 Issued on 980209 Re Improper Weld Repair | | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-348/98-09. Statement Made in Ltr Interpreted to Be Assurance to NRC to Have Confidence That NRC Requirements Will Be Adhered to |
| | author name = | | | author name = Fredrickson P |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| | addressee name = | | | addressee name = Chesser L |
| | addressee affiliation = | | | addressee affiliation = AFFILIATION NOT ASSIGNED |
| | docket = 05000348, 05000364 | | | docket = 05000348 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-348-98-09, 50-348-98-9, 50-364-98-09, 50-364-98-9, NUDOCS 9805220219 | | | document report number = 50-348-98-09, 50-348-98-9, IA-98-030, IA-98-30, NUDOCS 9807270184 |
| | package number = ML20247K816 | | | title reference date = 06-03-1998 |
| | document type = INSPECTION REPORT, NRC-GENERATED, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE |
| | page count = 7 | | | page count = 1 |
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| . | | UNITED STATES |
| . | | /pn rf49'o,' NUCLEAR REGULATORY COMMISSION 8 n REGION 11 |
| U.S. NUCLEAR REGULATORY COMMISSION (NRC)
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| | y ATLANTA FEDERAL CENTER e 61 FORSYTH STREET. SW, SUITE 23T85 |
| | . h, ATLANTA. GEORGIA 30303-3415 |
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| | , June 29, 1998 IA 98-030 I' |
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| | 'Mr. Lloyd .[HOME ADDRESS DELETED PURSUANT TO 10 CFR 2.206] |
| | SUBJECT: NOTICE OF VIOLATION (NRC INSPECTION REPORT NOS. 50-348/98-09 AND OFFICE OF INVESTIGATIONS REPORT N0. 2-97-011) |
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| ==REGION II== | | ==Dear Mr. Chesser:== |
| Docket Nos: 50-348 and 50-364 License Nos: NPF-2 and NPF-8 Report No: 50-348/98-09 and 50-364/98-09 Licensee: Southern Nuclear Operating Company (SNC)
| | Thank you for your response which we received on June 3. 1998, to our Notice t |
| Facility: Farley Nuclear Plant (FNP). Units 1 and 2 Location: 7388 North State Highway 95 Columbia, AL 36319 Dates: March 23-25, 1998 Inspectors: William P. Kleinsorge. P.E., Reactor Inspector Approved by: #st /i /IN Bruce S. Mallett. Deputy Director D/.e signed Division of Reactor Safety i
| | of Violation issued on May 15, 1998. We have evaluated your response and found that it meets the intent of 10 CFR 2.201. |
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| 9905220219 990511 PDR ADOCK 05000349 G FDR
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| | ' Although your letter did not explicitly state the specific actions you have taken and any additional actions you plan to prevent recurrence, the tone of 1 your. letter indicates that the type of activities which caused this violation i will not be repeated. .Specifically, you stated in your letter that "I will not be worried about deadlines in the future. I will be more concerned about. |
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| l EXECUTIVE SUMMARY Farley Nuclear Powi:r Plant. Units 1 and 2 NRC Inspection Report 50-348/98-09. 50-364/98-09 This inspection was conducted to follow up on an investigation by the NRC Office of Investigations (OI) conducted during the period May 12. 1997 through February 9. 1998. The findings of the investigation are documented in the syno] sis to 01 Report No. 2-97-011. issued on February 9. 1998. The purpose of t1e inspection was to determine whether violations of NRC requirements occurred and to determine whether the licensee's corrective actions for a March 5.1997, improper weld repair were adequate to address the identified problems. The improper weld repair was ident1fied by the 11u-nsee ir, Occurrence Report No. 1-97-071. The inspection was co announced, special inspection conducted from March 23-25, 199 Maintenance A welder failed to document a deficiency and deviated from the work sequence by making a base material weld repair to a safety-related pipe without a properly authorized repair plan. This failure resulted in a weld that was not in compliance with the ASME Boiler and Pressure Vessel Code; however, the licensee's program detected an, _orrected the improper wel (Section M1.1)
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| | the quality of work I do from now on." The NRC has interpreted this statement |
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| REPORT DETAILS M1 Conduct of Maintenance M1.1 Review of Occurrence Reports (OR) Insoection Scope (62700)
| | to be your assurance to the NRC. that we can have confidence that you will l adhere to NRC requirements should you be employed in the nuclear industry in |
| This inspection was conducted to follow up on the findings and conclusions from an NRC Office of Investigations (01) report. No. 2-97-011. which was completed on February 9. 1998. OI substantiated that a contract employee intentionally made c safety-related weld repair without obtaining a weld repair procedure in 1997. Weld repairs under similar circumstances were identified in 1993. This inspection also included a review of th9 W ensee's Occurrence Report (OR) No. 1-97-07 which documented this issue, licensee procedures, examination of quality records, and discussions with licensee and contractor personnel. The purpose of the review was to determine whether the actions were in violation of NRC requirements for repairing welds and whether the licensee's actions in response to the issue were adequate to prevent recurrenc Observations and Findinas On March 5.1997, while welding weld No.1F of Work Order (WO) 11405, a safety-related socket weld, in the service water system. a welder burned a hole in a pipe adjacent to the weld creating a welding deficiency. Subsequent h , the welder failed to document this deficiency contrary to Procedurc FNP-0-AP-52. " EQUIPMENT STATUS CONTROL AND MAINTENANCE AUTH0R EATION". General Revision 24. dated November 2 paragraph 13.2 which states in Jart that ". . .any deficiencies found while performing the task will 3e documented..." The welder then deviated from the work sequence scope of WO 11405 (which did not include authorization to perform repair welding of base materials) by making a base material weld repair to the pipe without a completed repair pla This action was contrary to Procedure FNP-0-AP-52, paragraph 9.2. which l states in part that "The individual performing the work shall follow the
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| work sequence specified in the WO". and contrary to Procedure FNP-0-M-23. "SPECIAL PROCESSES MANUAL". Section FNP-0-SPP-GW-001, Revision 17. dated December 19, 1995, paragraph 8.1 which states in part that "A repair plan shall be completed prior to the start of the -
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| The inspector confirmed that. as documented in the licensee's OR 1-97-071, the licensee identified this weld defect and unauthorized repair l during a planned ins)ection of welds. The licensee determined that the l welder burned throug1 the pipe and did not stop and obtain an authorized repair procedure. Instead, the individual welded over the defect without a repair procedur _______________-___A
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| | Our review regarding this matter has been completed. This letter closes our |
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| | -actions associated with this violation. In accordance with 10 CFR 2.790 of j |
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| | the NRC's " Rules of Practice." Part 2. Title 10. Code of Federal Regulations, a copy of this letter, with your address removed, will be placed in the NRC Public Document Room. |
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| The licensee's corrective actions and actions to prevent recurrence included the following:
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| . Replaced the pipe section that contained the unauthorized base material repair, to the burn-through.
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| Disciplinary action for individual involved.
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| Trained the contractor welder / fitters in lessons learned from this
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| ! occurrence, emphasizing the importance of procedural complianc Reviewed all welds made by the welder for other improper repair CFR 50. Appendix B. Criteria V and IX and the licensee's Operations l Quality Assurance Program. UFSAR 17.2.5 and 17.2.9. collectively require
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| that activities affecting quality, such as welding. be accomplished in accordance with documented procedure The welder's willful actions placed the licensee in violation of these criteria and the applicabh procedures. The inspector determined that the licensee had taken timely and effective corrective actions, conducted an appropriate survey and determined the extent of the noncompliance, and took appropriate actions to correct and prevent a recurrence of similar circumstances. Although the violation was willful, it was identified by the licensee, it involved the isolated acts of a low-level employee and it was addressed by appropriate remedial actions. Therefore, consistent with Section VII.B.1 of the NRC Enforcement Policy, this licensee-identified violation is identified as a Non-Cited Violation (NCV) 50-348.364/
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| 98-09-01: " Unauthorized Base Metal Repair" These actions also resulted in the weld not being in compliance with the applicable code for Weld No.1F on Work Order 11405. American Society for Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code Section III. 1971 Edition. Summer 1971 Addenda. (71S71). Paragraph No ND-4120. ND-4130. ND-2500. ND-2559 ND-2539.1 and ND-253 For defects in base materials, the ASME B&PV Code requires the removal of those defects or reduction of those defects to an acceptable size verified by nondestructive examination, leaving a cavity suitable for welding. This cavity is required to be repaired (filled) by welding to restore minimum wall thickness. The resulting weld repair is required to be surface examined by liquid penetrant examination and volumetrically examined by radiography. None of these actions were accomplished during the unauthorized weld repai Subsequent to the licensee's identification of the unauthorized weld repair, the licensee corrected the problems associated with the weld not meeting the code and not being adequately examined by replacing the pipe l section and welds were appropriately examined.
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| | l Pa E. Fredrickson, Chief Maintenance Branch Division of Reactor Safety |
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| l 3 Conclusion A welder's willful failure to follow licensee procedures to document a deficiency and subsequent deviation from the work sequence by making a base material weld repair to the Jipe without a properly authorized
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| repair plan. resulted in a weld tlat was not in compliance with the ASME l
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| B&PV Code. The licensee identified this, corrected the weld, and took actions to correct the root cause X1 Exit Meeting Summary Mr. Paul Fredrickson Chief. Maintenance Branch, presented the inspection results to members of licensee management during a telephone conference of April 17. 1998. The licensee acknowledged the findings presente On March 25, 1998, the inspector also discussed the findings with the licensee and asked the licerze whether any materials examined during the inspection should be considered proprietary. No proprietary information was identifie INSPECTION PROCEPURES USED IP 62700: Maintenance Implementation ITEMS OPENED. CLOSED. AND DISCUSSED TYDe Item Number Description and Reference Onened/ Closed NCV 50-348.364/98-09-01 Unauthorized Base Metal Repair PARTIAL LIST OF PERSONS CONTACTED Licensee
| | PDR ADOCK 05000348 m G PDR h ( |
| *R. Badham SAER Supervisor
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| *J. Brantley. PMMS Supervisor
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| *K. Dyar Security Manager
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| *J. Fitzgerald. Maintenance - Team Leader
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| *R. Fredrico. Sr. Engineer - Engineering Support Performance Review
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| *R. Fucich. Engineering Support Manager
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| *D. Grissette. Operations Manager
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| ** *R. Hill. FNP General Manager | |
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| *C. Letchman. PMMS Weld Engineer
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| *R. fiartin. Maintenance Team Leader
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| ** *C. Nesbitt Assistant General Manager - Support
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| *C. Schaule. Security - NSOS
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| ** *B. Yance. Plant Modifications and Maintenance Support Manager
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| **L. Stinson. Assistant General Manager - Operations
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| Williams Power Kinney. Site Manager NRC
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| *J. Bartley, Sr. Resident Inspector (Acting)
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| *R. Caldwell, Resident Inspector
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| **P. Fredrickson. Chief, Maintenance Branch
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| **T. Ross, Sr. Resident inspector
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| * Attended onsite exit interview March 25. 1998
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| ** Participated in telephonic exit interview on. April 17, 1998 l | |
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| SYN 0PSIS The U.S. Nuclear Regulatory Commission, Region II, Office of Investigations initiated this investigation on May 12, 1997, to determine if a contract ,
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| employee intentionally failed to obtain a welding repair procedure while l working at the Southern Nuclear Operating Company Joseph M. Farley Nuclear Plan l The evidence developed during this investigation substantiated that the I contract employee intentionally made safety related weld repairs without obtaining weld repair procedures in 1993 and 199 NOT IOR PUOLIC CISCLOSURE WIT"OUT APPR0t'AL Or ENCIINRE 2 JIELO OIIICE DIRECTOR. 0FEICE Or ink' ESTIMATIONS, REGION II Case No. 2 97 011 1 I NVM b est m My /1, Mft
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Category:CORRESPONDENCE-LETTERS
MONTHYEARL-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999
Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld
ML20217G0801999-10-0707 October 1999
Informs That on 990930,staff Conducted mid-cycle PPR of Farley & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Will Conduct Regional Insps Associated with SG Removal & Installation
ML20217P0661999-10-0606 October 1999
Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs
ML20217B1891999-10-0404 October 1999
Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity
ML20212J8391999-09-30030 September 1999
Forwards RAI Re Request for Amends to Ts.Addl Info Needed to Complete Review to Verify That Proposed TS Are Consistent with & Validate Design Basis Analysis.Request Discussed with H Mahan on 990930.Info Needed within 10 Days of This Ltr
ML20212J8801999-09-30030 September 1999
Discusses GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps. Util 980731,990607 & 03 Ltrs Provided Requested Info in Subj Gl.Nrc Considers Subj GL to Be Closed for Unit 1
ML20212E7031999-09-23023 September 1999
Responds to GL 98-01, Year 2000 Readiness of Computer Sys at Npps. Util Requested to Submit Plans & Schedules for Resolving Y2K-related Issues
ML20212F1111999-09-21021 September 1999
Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals
ML20212C2351999-09-16016 September 1999
Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal
L-99-031, Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-13013 September 1999
Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams
ML20212D4581999-09-10010 September 1999
Responds to to D Rathbun,Requesting Review of J Sherman Expressing Concerns That Plant & Other Nuclear Plants Not Yet Y2K Compliant
ML20212C8041999-09-10010 September 1999
Responds to to D Rathbun Requesting Review of J Sherman Re Y2K Compliance.Latest NRC Status Rept on Y2K Activities Encl
ML20212A6951999-09-0909 September 1999
Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics
ML20212A8341999-09-0909 September 1999
Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics
ML20211N4301999-09-0808 September 1999
Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues
ML20211N8041999-09-0808 September 1999
Informs That on 990930 NRC Issued GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Condition, to Holders of Nuclear Plant Operating Licenses
ML20212C0071999-09-0202 September 1999
Forwards Insp Repts 50-348/99-05 & 50-364/99-05 on 990627- 0807.No Violations Noted.Licensee Conduct of Activities at Farley Plant Facilities Generally Characterized by safety-conscious Operations & Sound Engineering
ML20211Q4801999-09-0101 September 1999
Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl
ML20211K2131999-08-31031 August 1999
Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2
ML20211K4101999-08-31031 August 1999
Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC
ML20211G6851999-08-26026 August 1999
Informs That During Insp,Technical Issues Associated with Design,Installation & fire-resistive Performance of Kaowool Raceway fire-barriers Installed at Farley Nuclear Plant Were Identified
ML20211B9211999-08-17017 August 1999
Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp
ML20211B9431999-08-17017 August 1999
Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters
ML20210R5101999-08-12012 August 1999
Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments
ML20212C8141999-08-0909 August 1999
Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures
ML20210T2021999-08-0606 August 1999
Forwards Draft SE Accepting Licensee Proposed Conversion of Plant,Units 1 & 2 Current TSs to Its.Its Based on Listed Documents
ML20210Q4641999-08-0505 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr to La Reyes,As Listed,With List of Individuals to Take exam,30 Days Before Exam Date
ML20210J8341999-07-30030 July 1999
Forwards Second Request for Addl Info Re Util 990430 Amend Request to Allow Util to Operate Unit 1,for Cycle 16 Based on risk-informed Probability of SG Tube Rupture & Nominal accident-induced primary-to-second Leakage
ML20210G4901999-07-30030 July 1999
Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, Issued 990603.Ltr Contains NRC License Commitment to Utilize ASTM D3803-1989 with Efficiency Acceptance Criteria Utilizing Safety Factor of 2
L-99-028, Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines1999-07-30030 July 1999
Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines
ML20210G8181999-07-26026 July 1999
Forwards Insp Repts 50-348/99-04 & 50-364/99-04 on 990516- 0626.One Violation Identified & Being Treated as Noncited Violation
ML20210E4071999-07-22022 July 1999
Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines
L-99-027, Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines1999-07-22022 July 1999
Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines
L-99-026, Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments1999-07-19019 July 1999
Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments
L-99-264, Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 20011999-07-13013 July 1999
Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001
ML20209H4721999-07-13013 July 1999
Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001
05000364/LER-1999-001, Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed1999-07-0202 July 1999
Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed
ML20196J6571999-07-0202 July 1999
Discusses Closure to TAC MA0543 & MA0544 Re GL 92-01 Rev 1, Suppl 1,RV Structural Integrity.Nrc Has Revised Rvid & Releasing It as Rvid,Version 2 as Result of Review of Responses
ML20196J7471999-07-0202 July 1999
Forwards RAI Re Cycle 16 Extension Request.Response Requested within 30 Days of Date of Ltr
ML20196J5781999-07-0202 July 1999
Forwards RAI Re 981201 & s Requesting Amend to TS Associated with Replacing Existing Westinghouse Model 51 SG with Westinghouse Model 54F Generators.Respond within 30 Days of Ltr Date
ML20196J6191999-07-0202 July 1999
Forwards Final Dam Audit Rept of 981008 of Category 1 Cooling Water Storage Pond Dam.Requests Response within 120 Days of Date of Ltr
L-99-249, Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA1999-06-30030 June 1999
Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA
ML20196J3591999-06-30030 June 1999
Forwards SE of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs
L-99-024, Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA1999-06-30030 June 1999
Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA
L-99-025, Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.211999-06-30030 June 1999
Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.21
ML20196J8631999-06-30030 June 1999
Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA
ML20196D1931999-06-22022 June 1999
Discusses Requesting Approval & Issuance of Plant Units 1 & 2 ITS by 990930.New Target Date Agrees with Requested Date
ML20196A3401999-06-10010 June 1999
Forwards Insp Repts 50-348/99-03 & 50-364/99-03 on 990404-0515.No Violations Noted
ML20196H9801999-06-10010 June 1999
Submits Two RAI Re ITS Section 4.0 That Were Never Sent. Reply to RAI Via e-mail
ML20195F1731999-06-0707 June 1999
Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld
1999-09-09
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217G0801999-10-0707 October 1999
Informs That on 990930,staff Conducted mid-cycle PPR of Farley & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Will Conduct Regional Insps Associated with SG Removal & Installation
ML20212J8391999-09-30030 September 1999
Forwards RAI Re Request for Amends to Ts.Addl Info Needed to Complete Review to Verify That Proposed TS Are Consistent with & Validate Design Basis Analysis.Request Discussed with H Mahan on 990930.Info Needed within 10 Days of This Ltr
ML20212J8801999-09-30030 September 1999
Discusses GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps. Util 980731,990607 & 03 Ltrs Provided Requested Info in Subj Gl.Nrc Considers Subj GL to Be Closed for Unit 1
ML20212E7031999-09-23023 September 1999
Responds to GL 98-01, Year 2000 Readiness of Computer Sys at Npps. Util Requested to Submit Plans & Schedules for Resolving Y2K-related Issues
ML20212F1111999-09-21021 September 1999
Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals
ML20212C8041999-09-10010 September 1999
Responds to to D Rathbun Requesting Review of J Sherman Re Y2K Compliance.Latest NRC Status Rept on Y2K Activities Encl
ML20212D4581999-09-10010 September 1999
Responds to to D Rathbun,Requesting Review of J Sherman Expressing Concerns That Plant & Other Nuclear Plants Not Yet Y2K Compliant
ML20212A8341999-09-0909 September 1999
Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics
ML20212A6951999-09-0909 September 1999
Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics
ML20211N4301999-09-0808 September 1999
Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues
ML20211N8041999-09-0808 September 1999
Informs That on 990930 NRC Issued GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Condition, to Holders of Nuclear Plant Operating Licenses
ML20212C0071999-09-0202 September 1999
Forwards Insp Repts 50-348/99-05 & 50-364/99-05 on 990627- 0807.No Violations Noted.Licensee Conduct of Activities at Farley Plant Facilities Generally Characterized by safety-conscious Operations & Sound Engineering
ML20211Q4801999-09-0101 September 1999
Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl
ML20211G6851999-08-26026 August 1999
Informs That During Insp,Technical Issues Associated with Design,Installation & fire-resistive Performance of Kaowool Raceway fire-barriers Installed at Farley Nuclear Plant Were Identified
ML20210T2021999-08-0606 August 1999
Forwards Draft SE Accepting Licensee Proposed Conversion of Plant,Units 1 & 2 Current TSs to Its.Its Based on Listed Documents
ML20210Q4641999-08-0505 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr to La Reyes,As Listed,With List of Individuals to Take exam,30 Days Before Exam Date
ML20210J8341999-07-30030 July 1999
Forwards Second Request for Addl Info Re Util 990430 Amend Request to Allow Util to Operate Unit 1,for Cycle 16 Based on risk-informed Probability of SG Tube Rupture & Nominal accident-induced primary-to-second Leakage
ML20210G8181999-07-26026 July 1999
Forwards Insp Repts 50-348/99-04 & 50-364/99-04 on 990516- 0626.One Violation Identified & Being Treated as Noncited Violation
ML20196J6191999-07-0202 July 1999
Forwards Final Dam Audit Rept of 981008 of Category 1 Cooling Water Storage Pond Dam.Requests Response within 120 Days of Date of Ltr
ML20196J5781999-07-0202 July 1999
Forwards RAI Re 981201 & s Requesting Amend to TS Associated with Replacing Existing Westinghouse Model 51 SG with Westinghouse Model 54F Generators.Respond within 30 Days of Ltr Date
ML20196J7471999-07-0202 July 1999
Forwards RAI Re Cycle 16 Extension Request.Response Requested within 30 Days of Date of Ltr
ML20196J6571999-07-0202 July 1999
Discusses Closure to TAC MA0543 & MA0544 Re GL 92-01 Rev 1, Suppl 1,RV Structural Integrity.Nrc Has Revised Rvid & Releasing It as Rvid,Version 2 as Result of Review of Responses
ML20196J3591999-06-30030 June 1999
Forwards SE of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs
ML20196D1931999-06-22022 June 1999
Discusses Requesting Approval & Issuance of Plant Units 1 & 2 ITS by 990930.New Target Date Agrees with Requested Date
ML20196H9801999-06-10010 June 1999
Submits Two RAI Re ITS Section 4.0 That Were Never Sent. Reply to RAI Via e-mail
ML20196A3401999-06-10010 June 1999
Forwards Insp Repts 50-348/99-03 & 50-364/99-03 on 990404-0515.No Violations Noted
ML20206R4741999-05-13013 May 1999
Informs That Staff Reviewed Draft Operation Insp Rept for Farley Nuclear Station Cooling Water Pond Dam & Concurs with FERC Findings.Any Significant Changes Made Prior to Issuance of Final Rept Should Be Discussed with NRC
ML20206M2321999-05-11011 May 1999
Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Mgt Created
ML20206G7341999-05-0404 May 1999
Forwards Safety Evaluation Re Completion of GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves
ML20206G2411999-04-30030 April 1999
Forwards Revised RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, Program at Farley.Requests to Be Notified of Rev to Original Target Date of 990521
ML20206R2031999-04-29029 April 1999
Forwards Insp Repts 50-348/99-02 & 50-364/99-02 on 990221-0403.No Violations Noted
ML20205T1931999-04-0909 April 1999
Informs That on 990316,J Deavers & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Farley NPP for Y2K.Initial Exam Dates Are Wks of 000508 & 22 for Approx 12 Candidates.Chief Examiner Will Be C Ernstes
ML20205Q1541999-04-0606 April 1999
Forwards Insp Repts 50-348/99-09 & 50-364/99-09 on 990308-10.One non-cited Violation Identified
ML20205M2831999-04-0202 April 1999
Forwards Errata Ltr for Farley Nuclear Power Plant FEMA Exercise Rept.Page 19 of Original Rept Should Be Replaced with Encl Corrected Page 19
ML20196K4881999-03-19019 March 1999
Forwards Insp Repts 50-348/99-01 & 50-364/99-01 on 990110- 0220.One Violation of NRC Requirements Occurred.Violation Being Treated as non-cited Violation Consistent with App C of Enforcement Policy
ML20205A2611999-03-19019 March 1999
Advises of NRC Planned Insp Effort Resulting from Farley Plant Performance Review on 980202.Historical Listing of Plant Issues & Details of NRC Insp Plan for Next 8 Months Encl
ML20204C9561999-03-17017 March 1999
Forwards RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, Program at Plant,Units 1 & 2.Response Requested by 990521
ML20204E6601999-03-11011 March 1999
Discusses Ofc of Investigation Rept 2-1998-024 Re Contract Worker Terminated by General Technical Svc Supervisor for Engaging in Protected Activity.Evidence Did Not Substantiate Allegation & No Further Action Planned
ML20207M2181999-03-11011 March 1999
Advises That Info Contained in 990125 Application CAW-99-1318 & Affidavit Will Be Withheld from Public Disclosure,Per 10CFR2.790
ML20207M1991999-03-0808 March 1999
Partially Withheld Info Re Meeting Held on 990129 at Region II Ofc in Atlanta,Ga to Discuss Physical Protection Measure for Svc Water Intake Structure Located at Facility (Ref 10CFR73.21).List of Attendees Encl
ML20206U1831999-02-0909 February 1999
Responds to Encl Ltrs, & 1223 Re Generic Implication of part-length CRDM Housing Leak.Review Under TAC Numbers MA1380 & MA1381 Considered Closed
ML20203G5541999-02-0505 February 1999
Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 940407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Listing of Candidates for Exam
ML20203G3921999-02-0202 February 1999
Forwards Insp Repts 50-348/98-08 & 50-364/98-08 on 981129- 990109
ML20199L4451999-01-25025 January 1999
Forwards for Review & Comment Revised Draft Info Notice Re Inservice Testing of A-4 Multimatic Deluge Valve for Farley NPP Units 1 & 2.Informs That Comments Submitted on 981120 Were Reviewed & Incorporated Where Appropriate
ML20199K7351999-01-21021 January 1999
Responds to 981123 Request by Providing Copy of Latest Draft of Info Notice Being Prepared Which Discusses Failure of Several Preaction Sprinker Sys Deluge Valves.Requests Submittal of Comments by 981120
ML20199K7231999-01-20020 January 1999
Confirms 990119 Telcon Re Informational Meeting Scheduled for 990129 to Be Held in Atlanta,Ga to Discuss Security Related Issues at Plant.Meeting Will Be Closed to Public,Due to Sensitive Nature of Issues
ML20199D8541999-01-12012 January 1999
Forwards SE Accepting Relief Request for Inservice Insp Program for Plant,Units 1 & 2
ML20199K1381999-01-12012 January 1999
Informs That on 990117,Region II Implemented Staff Reorganization as Part of agency-wide Streamlining Effort, Due to Staffing Reductions in FY99 Budget.Organization Charts Encl
ML20199C9361999-01-0808 January 1999
Forwards Insp Repts 50-348/98-14 & 50-364/98-14 on 981207- 10.No Violations Noted
ML20198S2741999-01-0606 January 1999
Informs That Staff Reviewed SG 90-day Rept, Farley Unit 2 1998 Voltage Based Repair Criteria 90 Day Rept, & Found Assessment to Be Acceptable.Staff Review Encl
1999-09-09
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Inspection Report - Farley - 1998009 |
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UNITED STATES
/pn rf49'o,' NUCLEAR REGULATORY COMMISSION 8 n REGION 11
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y ATLANTA FEDERAL CENTER e 61 FORSYTH STREET. SW, SUITE 23T85
. h, ATLANTA. GEORGIA 30303-3415
.
.....
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, June 29, 1998 IA 98-030 I'
,,
>
'Mr. Lloyd .[HOME ADDRESS DELETED PURSUANT TO 10 CFR 2.206]
SUBJECT: NOTICE OF VIOLATION (NRC INSPECTION REPORT NOS. 50-348/98-09 AND OFFICE OF INVESTIGATIONS REPORT N0. 2-97-011)
Dear Mr. Chesser:
Thank you for your response which we received on June 3. 1998, to our Notice t
of Violation issued on May 15, 1998. We have evaluated your response and found that it meets the intent of 10 CFR 2.201.
' Although your letter did not explicitly state the specific actions you have taken and any additional actions you plan to prevent recurrence, the tone of 1 your. letter indicates that the type of activities which caused this violation i will not be repeated. .Specifically, you stated in your letter that "I will not be worried about deadlines in the future. I will be more concerned about.
the quality of work I do from now on." The NRC has interpreted this statement
..
to be your assurance to the NRC. that we can have confidence that you will l adhere to NRC requirements should you be employed in the nuclear industry in
- _the future.
Our review regarding this matter has been completed. This letter closes our
'
-actions associated with this violation. In accordance with 10 CFR 2.790 of j
the NRC's " Rules of Practice." Part 2. Title 10. Code of Federal Regulations, a copy of this letter, with your address removed, will be placed in the NRC Public Document Room.
Si cerely. $
i i
l Pa E. Fredrickson, Chief Maintenance Branch Division of Reactor Safety
.J h0 h (fY
, 9807270184 980629 f
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PDR ADOCK 05000348 m G PDR h (
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