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| | issue date = 04/25/1990 | | | issue date = 04/25/1990 |
| | title = Responds to NRC 900326 Ltr Re Violations Noted in Insp Repts 50-259/89-56,50-260/89-56 & 50-296/89-56.Corrective Actions: Administrative Control Sdsp 29.1 Revised to Provide Guidance on Process to Evaluate Measuring & Test Equipment | | | title = Responds to NRC 900326 Ltr Re Violations Noted in Insp Repts 50-259/89-56,50-260/89-56 & 50-296/89-56.Corrective Actions: Administrative Control Sdsp 29.1 Revised to Provide Guidance on Process to Evaluate Measuring & Test Equipment |
| | author name = MEDFORD M O | | | author name = Medford M |
| | author affiliation = TENNESSEE VALLEY AUTHORITY | | | author affiliation = TENNESSEE VALLEY AUTHORITY |
| | addressee name = | | | addressee name = |
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| | page count = 7 | | | page count = 7 |
| }} | | }} |
| See also: [[followed by::IR 05000259/1989056]]
| |
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| =Text= | | =Text= |
| {{#Wiki_filter:ACCELERATED | | {{#Wiki_filter:ACCELERATED DISTjUBUTION DEMONSTjRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| DISTjUBUTION | | CESSION NBR:9004270289 DOC.DATE: 90/04/25 NOTARIZED: NO DOCKET FACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee 05000259 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH. NAME AUTHOR AFFILIATION MEDFORD,M.O. Tennessee Valley Authority RECIP.NAME RECXPIENT AFFILIATION Document Control Branch (Document Control Desk) |
| DEMONSTjRATION | | |
| SYSTEM REGULATORY | | ==SUBJECT:== |
| INFORMATION | | Responds to NRC 900326 50-259/89-56,50-260/89-56 ltr & |
| DISTRIBUTION | | re violations noted in Insp Repts 50-296/89-56. |
| SYSTEM (RIDS)CESSION NBR:9004270289 | | DISTRIBUTION CODE: IE01D COPIES RECEIVED:LTR ENCL SIZE: |
| DOC.DATE: 90/04/25 NOTARIZED: | | TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES:1 05000259 on, 05000260 1 Copy each to: S. Black,D.M.Crutchfield,B.D.Liaw, 05000296 R.Pierson,B.Wilson RECIPIENT RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD ROSS,T. 1 1 ACRS 2 2 AEOD 1 1 AEOD/DEIXB 1 1 AEOD/TPAD 1 1 DEDRO 1 1 NRR SHANKMAN,S 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA DIR 11 1 1 NOTES'OPXES NRR/DREP/PEPB9D NRR/DST/DIR 8E2 NUDOCS-ABSTRACT 1 |
| NO FACIL:50-259 | | 1 1 |
| Browns Ferry Nuclear Power Station, Unit 1, Tennessee 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee AUTH.NAME AUTHOR AFFILIATION | | 1 1 |
| MEDFORD,M.O. | | 1 NRR/ DRI S/ DIR BI I |
| Tennessee Valley Authority RECIP.NAME | | NRR/PMAS/ LRB1 2 1 |
| RECXPIENT AFFILIATION | | 1 1 |
| Document Control Branch (Document Control Desk)DOCKET 05000259 05000260 05000296 SUBJECT: Responds to NRC 900326 ltr re violations | | 1 1 |
| noted in Insp Repts 50-259/89-56,50-260/89-56
| | 1 OGC/HDS2 <<1 1 REG FIL 02 1 1 RES/DSR/HFB/HFS 1 1 RGN'ILE 01 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 5 5 NVIZTO ALL "RIDS" RECIPIENIS: |
| &50-296/89-56.
| | P~ HELP US TO REDUCE WASTE! CONTACT THE. DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION TOTAL NUMBER OF COPXES REQUIRED: LTTR 29 ENCL 29 |
| DISTRIBUTION | | |
| CODE: IE01D COPIES RECEIVED:LTR | | if TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 6N 38A Lookout Place APR 25 III U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C. 20555 Gentlemen: |
| ENCL SIZE: TITLE: General (50 Dkt)-Insp Rept/Notice | | In the Matter of Docket Nos. 50-259 Tennessee Valley Authority 50-260 50-296 BRONNS FERRY NUCLEAR PLANT (BFN) NRC INSPECTION REPORTS NOS. 50-259/89-56, 50-260/89-56, AND 50-296/89-56 RESPONSE TO NOTICE OF VIOLATION This letter provides TVA's response to the notice of violation transmitted by letter from B. A. Hilson to 0. D. Kingsley, Jr. dated March 26, 1990. NRC cited TVA with a Sever>ty Level IV violation pertaining to calibration of measuring and test equipment (I'&TE). In the example given, two pieces of'&TE were not calibrated with a standard at least four times as accurate as the M&TE being calibrated. A justification for use of the M&I'E was not documented by responsible management as required by procedure. TVA. has reviewed this event and is taking appropriate corrective actions. contains TVA's response to the notice of violation. The violation is discussed along with the corrective actions taken. Enclosure 2 is a listing of the commitments made in this response. |
| of Violation Response NOTES:1 on, 1 Copy each to: S.Black,D.M.Crutchfield,B.D.Liaw, R.Pierson,B.Wilson | | If you have any questions regarding this response, please contact Patrick P. Carier at (205) 729-3570. |
| 05000259 05000260 05000296 RECIPIENT ID CODE/NAME PD ACRS AEOD/DEIXB
| | Very truly yours, TENNESSEE VALLEY AUTHORITY Mark 0.'edford, 1 e President Nuclear Technology nd Licensing Enclosures cc: See page 2 9C) 0425 9r) 042702~'9 05'.) |
| DEDRO NRR/DLPQ/LPEB10
| | c., |
| NRR/DREP/PEPB9D | | Og25 pDR pDQCK @pc 0 |
| NRR/DST/DIR | | ggo/ |
| 8E2 NUDOCS-ABSTRACT | | An Equa) Opportunity Emp)oyer I/( |
| OGC/HDS2 RES/DSR/HFB/HFS
| | |
| EXTERNAL: LPDR NSIC NOTES'OPXES
| | APR RS 1SSO I |
| LTTR ENCL 2 2 1 1 1 1 1 1 1 1 1 1 1 1<<1 1 1 1 1 1 1 1 5 5 RECIPIENT ID CODE/NAME ROSS,T.AEOD AEOD/TPAD NRR SHANKMAN,S
| | cc (Enclosures): |
| NRR/DOEA DIR 11 NRR/DRI S/DIR NRR/PMAS/I LRB 1 2 BI REG FIL 02 RGN'ILE 01 NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 NVIZ TO ALL"RIDS" RECIPIENIS:
| | Ms. S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockvi lie, Maryland 20852 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000 Mr. B. A. Wilson, Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 |
| P~HELP US TO REDUCE WASTE!CONTACT THE.DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION
| | |
| TOTAL NUMBER OF COPXES REQUIRED: LTTR 29 ENCL 29
| | ENCLOSURE 1 RESPONSE BROWNS FERRY NUCLEAR PLANT (BFN) |
| if
| | NRC INSPECTION REPORT NOS. 50-259/89-56, 50-260/89-56, AND 50-296/89-56 LETTER FROM B. A. WILSON TO O. D. KINGSLEY, JR. |
| TENNESSEE VALLEY AUTHORITY CHATTANOOGA.
| | DATED MARCH 26, 1990 Violation 10 CFR 50, Appendix B, Criteria V, as implemented by TVA Topical Report TVA-TR75-1A, requires compliance with procedures. Procedure SDSP-29.1 states that measuring and test equipment must be calibrated with standards which are at least four times as accurate as the equipment being calibrated. It permits use of measuring and test equipr"ent not meeting this requirement if the basis for acceptance is documented and authorized by responsible management. |
| TENNESSEE 37401 6N 38A Lookout Place APR 25 III U.S.Nuclear Regulatory
| | Contrary to the above, on January 9, 1990 this procedure requirement had not been met for Browns Ferry meesuring and test equipment in that two pressure gauges (Serial Nos. US-TVA-522068 and 517116) had been released for use even though records on site showed that the four times accuracy requirements had not been met in the calibration and no justification for use had been t |
| Commission
| | documented by responsible management. |
| ATTN: Document Control Desk Hashington, D.C.20555 Gentlemen:
| | : 1. Admission or Denial of the Violation TVA admits the violation. |
| In the Matter of Tennessee Valley Authority Docket Nos.50-259 50-260 50-296 BRONNS FERRY NUCLEAR PLANT (BFN)-NRC INSPECTION
| | : 2. Reason for the Violation This violation has been attributed to inadequate administrative controls. SDSP 29.1 "Control of Measuring and Test Equipment," required that MKTE be calibrated by standards that are at least four times as accurate as the equipment being calibrated. Deviations from this requirement were allowed if the basis for acceptance was documented and authorized. However, SDSP 29.1 did not provide adequate guidance for the implementation of this process. As a result, METE which did not meet this requirement were issued for use without appropriate justification and authorization. |
| REPORTS NOS.50-259/89-56, 50-260/89-56, AND 50-296/89-56
| | : 3. Corrective Ste s Which Have Been Taken and Results Achieved SDSP 29.1 has been revised to provide guidance on the process to evaluate MKTE that was not calibrated with a standard four times more accurate. |
| -RESPONSE TO NOTICE OF VIOLATION This letter provides TVA's response to the notice of violation transmitted
| | Subsequent management review of SDSP 29.1 has identified additional changes that are needed to improve the process. These changes will ensure that calibrated METE r;ceived at BFN that does not meet the four to one calibration ratio and has not been calibrated by a state-of-the-art standard will be evaluated prior to use. |
| by letter from B.A.Hilson to 0.D.Kingsley, Jr.dated March 26, 1990.NRC cited TVA with a Sever>ty Level IV violation pertaining
| | |
| to calibration
| | Enclosure 1 Page 2 For the two pressure gauges 'specifically identified in this violation, a recalculation of the accuracy of the standard used in their calibration was performed. This recalculation demonstrated that the calibration standard was actually four times as accurate as the two pressure gauges. |
| of measuring and test equipment (I'&TE).In the example given, two pieces of'&TE were not calibrated | | A review of other MINUTE in use at BFN has been performed to determine if any generic implications existed. As a result of this review, additional MINUTE was identified to be evaluated. A Condition Adverse to Quality Report was initiated to track the corrective actions. |
| with a standard at least four times as accurate as the M&TE being calibrated.
| | An evaluation process is in progress to determine the effects of these discrepancies on plant equipment. Approximately 270 pieces out of 3000 pieces of METE in use at BFN have been identified with this type discrepancy. A sample of M~TE will be evaluated by reviewing their use logs and assuring that their uses have been acceptable. Based upon the results of this sample, evaluations will be performed as necessary. The MINUTE evaluated to date has determined that all their uses have been acceptable. |
| A justification
| | : 4. Corrective Ste s Which Will Be Taken to Avoid Further Violations Future cases in which calibrated MINUTE received by BFN do not meet the four to one calibration ratio will be justified and authorized prior to their use. METE currently in use that does not meet this requirement will continue to be evaluated as discussed above. |
| for use of the M&I'E was not documented
| | : 5. Date When Full Com .liance Will be Achieved The evaluation process of MINUTE currently in use that does not meet the four to one calibration accuracy requirement will be completed prior to Unit 2 fuel load. Administrative controls resulting from these reviews will be implemented prior to Unit 2 fuel load. |
| by responsible
| | |
| management
| | ENCLOSURE 2 RESPONSE BRONNS FERRY NUCLEAR PLANT (BFN) |
| as required by procedure.
| | NRC INSPECTION REPORT NOS. 50-259/89-56, 50-260/89-56, AND 50-296/89-56 LETTER FROM B. A. NILSON TO 0. D. KINGSLEY, JR. |
| TVA.has reviewed this event and is taking appropriate
| | DATED MARCH 26, 1990 COMMITMENTS |
| corrective
| | : 1. The evaluation process for the METE that does not currently meet the four to one calibration accuracy will be completed prior to Unit 2 fuel load. |
| actions.Enclosure 1 contains TVA's response to the notice of violation.
| | : 2. Administrative controls resulting from the reviews will be implemented prior to Unit 2 fuel load.}} |
| The violation is discussed along with the corrective
| |
| actions taken.Enclosure 2 is a listing of the commitments
| |
| made in this response.If you have any questions regarding this response, please contact Patrick P.Carier at (205)729-3570.Very truly yours, TENNESSEE VALLEY AUTHORITY Mark 0.'edford, 1 e President Enclosures
| |
| cc: See page 2 Nuclear Technology
| |
| nd Licensing 9r)042702~'9 05'.)Og25 c., 9C)0425 pDR pDQCK-1-@pc 0 An Equa)Opportunity
| |
| Emp)oyer ggo/I/(
| |
| APR RS 1SSO I cc (Enclosures):
| |
| Ms.S.C.Black, Assistant Director for Projects TVA Projects Division U.S.Nuclear Regulatory
| |
| Commission
| |
| One White Flint, North 11555 Rockville Pike Rockvi lie, Maryland 20852 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000
| |
| Mr.B.A.Wilson, Assistant Director for Inspection
| |
| Programs TVA Projects Division U.S.Nuclear Regulatory
| |
| Commission
| |
| Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
| |
| ENCLOSURE 1 RESPONSE-BROWNS FERRY NUCLEAR PLANT (BFN)NRC INSPECTION
| |
| REPORT NOS.50-259/89-56, 50-260/89-56, AND 50-296/89-56
| |
| LETTER FROM B.A.WILSON TO O.D.KINGSLEY, JR.DATED MARCH 26, 1990 Violation 10 CFR 50, Appendix B, Criteria V, as implemented
| |
| by TVA Topical Report TVA-TR75-1A, requires compliance
| |
| with procedures.
| |
| Procedure SDSP-29.1 states that measuring and test equipment must be calibrated
| |
| with standards which are at least four times as accurate as the equipment being calibrated.
| |
| It permits use of measuring and test equipr"ent
| |
| not meeting this requirement
| |
| if the basis for acceptance
| |
| is documented
| |
| and authorized | |
| by responsible
| |
| management.
| |
| Contrary to the above, on January 9, 1990 this procedure requirement
| |
| had not been met for Browns Ferry meesuring and test equipment in that two pressure gauges (Serial Nos.US-TVA-522068
| |
| and 517116)had been released for use even though records on site showed that the four times accuracy requirements
| |
| had not been met in the calibration
| |
| and no justification | |
| for use had been documented
| |
| by responsible | |
| management.
| |
| t 1.Admission or Denial of the Violation TVA admits the violation.
| |
| 2.Reason for the Violation This violation has been attributed
| |
| to inadequate | |
| administrative
| |
| controls.SDSP 29.1"Control of Measuring and Test Equipment," required that MKTE be calibrated
| |
| by standards that are at least four times as accurate as the equipment being calibrated.
| |
| Deviations
| |
| from this requirement
| |
| were allowed if the basis for acceptance
| |
| was documented
| |
| and authorized.
| |
| However, SDSP 29.1 did not provide adequate guidance for the implementation
| |
| of this process.As a result, METE which did not meet this requirement | |
| were issued for use without appropriate
| |
| justification
| |
| and authorization.
| |
| 3.Corrective
| |
| Ste s Which Have Been Taken and Results Achieved SDSP 29.1 has been revised to provide guidance on the process to evaluate MKTE that was not calibrated
| |
| with a standard four times more accurate.Subsequent
| |
| management
| |
| review of SDSP 29.1 has identified
| |
| additional
| |
| changes that are needed to improve the process.These changes will ensure that calibrated
| |
| METE r;ceived at BFN that does not meet the four to one calibration
| |
| ratio and has not been calibrated | |
| by a state-of-the-art
| |
| standard will be evaluated prior to use.
| |
| Enclosure 1 Page 2 For the two pressure gauges'specifically
| |
| identified
| |
| in this violation, a recalculation | |
| of the accuracy of the standard used in their calibration
| |
| was performed.
| |
| This recalculation
| |
| demonstrated
| |
| that the calibration
| |
| standard was actually four times as accurate as the two pressure gauges.A review of other MINUTE in use at BFN has been performed to determine if any generic implications
| |
| existed.As a result of this review, additional
| |
| MINUTE was identified
| |
| to be evaluated.
| |
| A Condition Adverse to Quality Report was initiated to track the corrective | |
| actions.An evaluation
| |
| process is in progress to determine the effects of these discrepancies | |
| on plant equipment.
| |
| Approximately
| |
| 270 pieces out of 3000 pieces of METE in use at BFN have been identified
| |
| with this type discrepancy.
| |
| A sample of M~TE will be evaluated by reviewing their use logs and assuring that their uses have been acceptable.
| |
| Based upon the results of this sample, evaluations
| |
| will be performed as necessary.
| |
| The MINUTE evaluated to date has determined
| |
| that all their uses have been acceptable.
| |
| 4.Corrective
| |
| Ste s Which Will Be Taken to Avoid Further Violations
| |
| Future cases in which calibrated
| |
| MINUTE received by BFN do not meet the four to one calibration
| |
| ratio will be justified and authorized
| |
| prior to their use.METE currently in use that does not meet this requirement
| |
| will continue to be evaluated as discussed above.5.Date When Full Com.liance Will be Achieved The evaluation
| |
| process of MINUTE currently in use that does not meet the four to one calibration
| |
| accuracy requirement
| |
| will be completed prior to Unit 2 fuel load.Administrative
| |
| controls resulting from these reviews will be implemented
| |
| prior to Unit 2 fuel load.
| |
| ENCLOSURE 2 RESPONSE-BRONNS FERRY NUCLEAR PLANT (BFN)NRC INSPECTION
| |
| REPORT NOS.50-259/89-56, 50-260/89-56, AND 50-296/89-56
| |
| LETTER FROM B.A.NILSON TO 0.D.KINGSLEY, JR.DATED MARCH 26, 1990 COMMITMENTS
| |
| 1.The evaluation
| |
| process for the METE that does not currently meet the four to one calibration
| |
| accuracy will be completed prior to Unit 2 fuel load.2.Administrative
| |
| controls resulting from the reviews will be implemented | |
| prior to Unit 2 fuel load. | |
| }} | |
|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML18039A9021999-10-15015 October 1999 Forwards LER 99-010-00 Re Occurrence of Plant Reactor Scram Due to Main Turbine Trip Which Resulted in Main Steam Moisture Separator.All Plant Safety Systems Operated as Designed in Response to Event ML20217E0711999-10-14014 October 1999 Grants Approval for Util to Submit Original,One Signed Paper Copy & Six CD-ROM Copies of Updates to FSAR as Listed,Per 10CFR50.4(c),in Response to ML18039A8961999-10-14014 October 1999 Forwards LER 99-009-00,re Manual Reactor Scram on Unit 2 from 54% Power,Iaw 10CFR50.73(a)(2)(iv).All Plant Safety Sys Operated as Designed in Response to Event ML20217D3261999-10-0808 October 1999 Responds to Re Event Concerning Spent Fuel Pool Water Temperature Being Undetected for Approx Two Days at Browns Ferry Unit 3 ML20217F7751999-10-0808 October 1999 Confirms 991006 Telcon Between T Abney of Licensee Staff & a Belisle of NRC Re Meeting to Be Conducted on 991109 in Atlanta,Ga to Discuss Various Maintenance Issues ML18039A8931999-10-0808 October 1999 Forwards LER 99-008-00,concerning HPCI Sys Being Declared Inoperable,Iaw 10CFR50.73(a)(2)(v).There Are No Commitments Contained in Ltr ML18039A8881999-10-0808 October 1999 Provides Licensee Supplemental Response to NRC 980713 RAI Re GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. ML20217B5481999-10-0101 October 1999 Requests Exception to 10CFR50.4(c) Requirement to Provide Total of Twelve Paper Copies When Submitting Revs to BFN UFSAR ML20212M1481999-09-28028 September 1999 Refers to Management Meeting Conducted on 990927 at Region II for Presentation of Recent Plant Performance.List of Attendees & Copy of Presentation Handout Encl ML20212F7751999-09-22022 September 1999 Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses ML20212D3651999-09-20020 September 1999 Forwards SE Accepting Licensee 990430 Proposed Rev to Plant, Unit 3 Matl Surveillance Program ML18039A8721999-09-10010 September 1999 Informs of Licensee Decision to Withdraw Proposed Plant risk-informed Inservice Insp Program,Originally Transmitted in Util 981023 Ltr.Licensee Expects to Resubmit Revised Program within Approx 6 Wks ML20211Q5731999-09-0909 September 1999 Submits Response to Administrative Ltr 99-03 Re Preparation & Scheduling of Operator Licensing Exams.Completed NRC Form 536,operator Licensing Exam Data,Which Provides Plant Current Schedules for Specific Info Requested Encl ML20211G6491999-08-26026 August 1999 Confirms Telcon with T Abney on 990824 Re Mgt Meeting Which Has Been re-scheduled from 990830-0927.Purpose of Meeting to Discuss BFN Status & Performance ML20210Q6931999-08-0909 August 1999 Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants ML18039A8371999-08-0606 August 1999 Forwards BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts, for NRC Review.Corrected Inservice Insp Summary Rept for Unit 3 Cycle 8 Operation,Included in Rept ML20210Q4421999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006. Authorized Representative of Facility Must Submit Ltr with List of Individuals to Take exam,30 Days Before Exam Date ML20210N1051999-08-0202 August 1999 Forwards SE Accepting Licensee 990326 Request for Relief from ASME B&PV Code,Section XI Requirements.Request for Relief 3-ISI-7,pertains to Second 10-year Interval ISI for Plant,Unit 3 ML20210G8991999-07-28028 July 1999 Discusses 990726 Open Mgt Meeting for Discussion on Plant Engineering Status & Performance.List of Attendees & Presentation Handout Encl ML18039A8181999-07-26026 July 1999 Forwards LER 99-004-00 Re Inoperability of Two Divisions of Plant CSS Due to Personnel Error During Surveillance Testing.Event Reported Per 10CFR50.73(a)(2)(i)(B) ML20210G8051999-07-22022 July 1999 Discusses DOL Case DC Smith Vs TVA Investigation.Oi Concluded That There Was Not Sufficient Evidence Developed During Investigation to Substantiate Discrimination.Nrc Providing Results of OI Investigation to Parties ML20210F3031999-07-22022 July 1999 Submits Rept Re Impact of Changes or Errors in Methodology Used to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.One Reportable non-significant Error Was Found During Time Period of 980601-990630 ML20209J0251999-07-16016 July 1999 Forwards SE Which Constitutes Staff Review & Approval of TVA Ampacity Derating Test & Analyses for Thermo-Lag Fire Barrier Configurations as Required in App K of Draft Temporary Instruction, Fpfi, ML20210B2671999-07-14014 July 1999 Confirms 990702 Telcon Between T Abney of Licensee Staff & Author Re Mgt Meeting Scheduled for 990830 at Licensee Request in Atlanta,Ga to Discuss Browns Ferry Nuclear Plant Status & Performance ML20209E3421999-07-0707 July 1999 Confirms Arrangements Made During 990628 Telephone Conversation to Hold Meeting on 990726 in Atlanta,Ga to Discuss Plant Engineering Status & Performance ML20209E5511999-07-0707 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes TACs MA1180,MA1181 & MA1179 ML20196J3531999-06-30030 June 1999 Responds to Re Boeing Rocket Booster Mfg Facility Being Constructed in Decatur,Al.Nrc Has No Unique Emergency Planning Concerns Re Proximity of Boeing Facility to BFN ML20196G9111999-06-28028 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits ML18039A8081999-06-28028 June 1999 Forwards LER 99-004-00 Re Esfas That Occurred When RPS Motor Generator Tripped.Rept Is Submitted IAW Provisions of 10CFR50.73(a)(2)(iv) as Event of Condition That Resulted in Automatic Actuation of ESF ML18039A8111999-06-25025 June 1999 Requests Permanent Relief from Inservice Insp Requirements of 10CFR50.55a(g) for Volumetric Exam of Bfn,Unit 3 Circumferential RPV Welds,Per GL 98-05 ML20196F8741999-06-23023 June 1999 Forwards Safety Evaluation Accepting Util Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20196F8131999-06-22022 June 1999 Forwards Rev 24 to Security Personnel Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld ML18039A8051999-06-22022 June 1999 Forwards LER 99-003-00,re Automatic Reactor Scram Due to Turbine Trip.Rept Numbered 99-001 Should Be Deleted & Replaced with Encl Rept as Result of Error Noted in 990614 Rept ML18039A8031999-06-18018 June 1999 Responds to NRC Staff Verbal Request Re TS Change TS-376, Originally Submitted on 970312, & Proposed Changes to TS to Extend Current 7-day AOT for EDGs to 14 Days ML18039A7931999-06-0101 June 1999 Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage ML20195D3321999-06-0101 June 1999 Informs That Cb Fisher,License OP-5525-4,can No Longer Maintain License at Plant Because of Physical Condition That Causes Licensee to Fail to Meet Requirements of 10CFR55.21 ML18039A7911999-05-24024 May 1999 Informs That by Meeting Test Criteria Established by Test Based on Ansi/Ans 3.5-1985 (License Amends 254 & 214) power- Uprate Simulation Acceptable for Operator Training ML18039A7891999-05-24024 May 1999 Informs That Oscillation Power Range Monitor Module Has Been Enabled for Current Cycle of Operation Following Unit 2 Cycle 10 Refueling Outage Which Was Completed on 990509 ML20195B9361999-05-24024 May 1999 Informs That Do Elkins,License SOP-3392-6,no Longer Needs to Maintain License as Position Does Not Require License ML20206U6551999-05-14014 May 1999 Informs That ML Meek & Wd Dawson Will No Longer Need to Maintain SRO Licenses at Plant,Due to Termination of Employment,Effective 990521 ML20206Q8421999-05-10010 May 1999 Forwards Medical Info on DM Olive,License SOP-20540-2,in Response to NRC 990428 Telcon.Encl Withheld from Public Disclosure IAW 10CFR2.790(a)(6) ML18039A7771999-05-0606 May 1999 Forwards LER 99-003-00,providing Details Re Plant HPCI Sys Being Declared Inoperable Due to Loose Electrical Connection.Ltr Contains No Commitments ML20206G6611999-05-0404 May 1999 Forwards SE Accepting GL 88-20,submitted by TVA Re multi-unit Probabilistic Risk Assessement (Mupra) for Plant, Units 1,2 & 3 ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval ML20206H5901999-04-30030 April 1999 Forwards Notification of Revs to BFN Unit 2 Emergency Response Data Sys Data Point Library.Revs Were Implemented on 990413 DD-99-06, Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 9904281999-04-28028 April 1999 Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 990428 ML18039A7681999-04-27027 April 1999 Requests Relief from Specified Inservice Insp Requirements in Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a(a)(3)(i).Relief Requests 2-ISI-8 & 3-ISI-8,encl for NRC Review & Approval ML18039A7591999-04-27027 April 1999 Forwards Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1998. Rept Includes Results of Land Use Censuses,Summarized & Tabulated Results of Radiological Environ Samples in Format of Reg Guide 4.8 & NUREG-1302 ML18039A7651999-04-27027 April 1999 Forwards Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2,Cycle 11 Colr. ML18039A7541999-04-23023 April 1999 Requests Approval of Bfnp Unit 3 Risk-Informed ISI (RI-ISI) Program,Per 10CFR50.55(a)(3)(i) & GL 88-01.Encl RI-ISI Program Is Alternative to Current ASME Section XI ISI Requirments for Code Class 1,2 & 3 Piping 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18039A9021999-10-15015 October 1999 Forwards LER 99-010-00 Re Occurrence of Plant Reactor Scram Due to Main Turbine Trip Which Resulted in Main Steam Moisture Separator.All Plant Safety Systems Operated as Designed in Response to Event ML18039A8961999-10-14014 October 1999 Forwards LER 99-009-00,re Manual Reactor Scram on Unit 2 from 54% Power,Iaw 10CFR50.73(a)(2)(iv).All Plant Safety Sys Operated as Designed in Response to Event ML18039A8881999-10-0808 October 1999 Provides Licensee Supplemental Response to NRC 980713 RAI Re GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. ML18039A8931999-10-0808 October 1999 Forwards LER 99-008-00,concerning HPCI Sys Being Declared Inoperable,Iaw 10CFR50.73(a)(2)(v).There Are No Commitments Contained in Ltr ML20217B5481999-10-0101 October 1999 Requests Exception to 10CFR50.4(c) Requirement to Provide Total of Twelve Paper Copies When Submitting Revs to BFN UFSAR ML20212F7751999-09-22022 September 1999 Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses ML18039A8721999-09-10010 September 1999 Informs of Licensee Decision to Withdraw Proposed Plant risk-informed Inservice Insp Program,Originally Transmitted in Util 981023 Ltr.Licensee Expects to Resubmit Revised Program within Approx 6 Wks ML20211Q5731999-09-0909 September 1999 Submits Response to Administrative Ltr 99-03 Re Preparation & Scheduling of Operator Licensing Exams.Completed NRC Form 536,operator Licensing Exam Data,Which Provides Plant Current Schedules for Specific Info Requested Encl ML20210Q6931999-08-0909 August 1999 Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants ML18039A8371999-08-0606 August 1999 Forwards BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts, for NRC Review.Corrected Inservice Insp Summary Rept for Unit 3 Cycle 8 Operation,Included in Rept ML18039A8181999-07-26026 July 1999 Forwards LER 99-004-00 Re Inoperability of Two Divisions of Plant CSS Due to Personnel Error During Surveillance Testing.Event Reported Per 10CFR50.73(a)(2)(i)(B) ML20210F3031999-07-22022 July 1999 Submits Rept Re Impact of Changes or Errors in Methodology Used to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.One Reportable non-significant Error Was Found During Time Period of 980601-990630 ML18039A8081999-06-28028 June 1999 Forwards LER 99-004-00 Re Esfas That Occurred When RPS Motor Generator Tripped.Rept Is Submitted IAW Provisions of 10CFR50.73(a)(2)(iv) as Event of Condition That Resulted in Automatic Actuation of ESF ML18039A8111999-06-25025 June 1999 Requests Permanent Relief from Inservice Insp Requirements of 10CFR50.55a(g) for Volumetric Exam of Bfn,Unit 3 Circumferential RPV Welds,Per GL 98-05 ML20196F8131999-06-22022 June 1999 Forwards Rev 24 to Security Personnel Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld ML18039A8051999-06-22022 June 1999 Forwards LER 99-003-00,re Automatic Reactor Scram Due to Turbine Trip.Rept Numbered 99-001 Should Be Deleted & Replaced with Encl Rept as Result of Error Noted in 990614 Rept ML18039A8031999-06-18018 June 1999 Responds to NRC Staff Verbal Request Re TS Change TS-376, Originally Submitted on 970312, & Proposed Changes to TS to Extend Current 7-day AOT for EDGs to 14 Days ML18039A7931999-06-0101 June 1999 Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage ML20195D3321999-06-0101 June 1999 Informs That Cb Fisher,License OP-5525-4,can No Longer Maintain License at Plant Because of Physical Condition That Causes Licensee to Fail to Meet Requirements of 10CFR55.21 ML20195B9361999-05-24024 May 1999 Informs That Do Elkins,License SOP-3392-6,no Longer Needs to Maintain License as Position Does Not Require License ML18039A7911999-05-24024 May 1999 Informs That by Meeting Test Criteria Established by Test Based on Ansi/Ans 3.5-1985 (License Amends 254 & 214) power- Uprate Simulation Acceptable for Operator Training ML18039A7891999-05-24024 May 1999 Informs That Oscillation Power Range Monitor Module Has Been Enabled for Current Cycle of Operation Following Unit 2 Cycle 10 Refueling Outage Which Was Completed on 990509 ML20206U6551999-05-14014 May 1999 Informs That ML Meek & Wd Dawson Will No Longer Need to Maintain SRO Licenses at Plant,Due to Termination of Employment,Effective 990521 ML20206Q8421999-05-10010 May 1999 Forwards Medical Info on DM Olive,License SOP-20540-2,in Response to NRC 990428 Telcon.Encl Withheld from Public Disclosure IAW 10CFR2.790(a)(6) ML18039A7771999-05-0606 May 1999 Forwards LER 99-003-00,providing Details Re Plant HPCI Sys Being Declared Inoperable Due to Loose Electrical Connection.Ltr Contains No Commitments ML20206H5901999-04-30030 April 1999 Forwards Notification of Revs to BFN Unit 2 Emergency Response Data Sys Data Point Library.Revs Were Implemented on 990413 ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval ML18039A7681999-04-27027 April 1999 Requests Relief from Specified Inservice Insp Requirements in Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a(a)(3)(i).Relief Requests 2-ISI-8 & 3-ISI-8,encl for NRC Review & Approval ML18039A7591999-04-27027 April 1999 Forwards Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1998. Rept Includes Results of Land Use Censuses,Summarized & Tabulated Results of Radiological Environ Samples in Format of Reg Guide 4.8 & NUREG-1302 ML18039A7651999-04-27027 April 1999 Forwards Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2,Cycle 11 Colr. ML20206C8591999-04-23023 April 1999 Informs That Util Has Determined,Dr Bateman No Longer Needs to Maintain His License,Effective 990331,per Requirement of 10CFR55.55(a) ML18039A7541999-04-23023 April 1999 Requests Approval of Bfnp Unit 3 Risk-Informed ISI (RI-ISI) Program,Per 10CFR50.55(a)(3)(i) & GL 88-01.Encl RI-ISI Program Is Alternative to Current ASME Section XI ISI Requirments for Code Class 1,2 & 3 Piping ML18039A7581999-04-23023 April 1999 Responds to Item 4 of 981117 RAI Re TS Change Request 376 Re Extended EDG Allowed Outage Time,In Manner Consistent with Rgs 1.174 & 1.177 ML20206C1241999-04-21021 April 1999 Forwards Annual Occupational Radiation Exposure Rept for 1998, IAW TS Section 5.6.1.Rept Reflects Radiation Exposure Data as Tracked by Electronic Dosimeters on Radiation Work Permits ML20205T0971999-04-15015 April 1999 Submits Change in Medical Status for DM Olive in Accordance with 10CFR55.25,effective 990315.Encl Medical Info & Certification of Medical Exam,Considered by Util to Be of Personal Nature & to Be Withheld,Per 10CFR2.790(a)(6) ML18039A7441999-04-0707 April 1999 Forwards LER 99-001-00,providing Details Re Inoperability of Two Trains of Standby Gas Treatment Due to Breaker Trip on One Train in Conjunction with Planned Maint Activities on Other.Ltr Contains No New Commitments ML18039A7431999-03-30030 March 1999 Responds to NRC 990112 RAI Re BFN Program,Per GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs. ML18039A7421999-03-30030 March 1999 Provides Results of Analysis of Design Basis Loca,As Required by License Condition Re Plants Power Uprate Operating License Amends 254 & 214 ML18039A7411999-03-30030 March 1999 Provides Partial Response to NRC 981117 RAI Re TS Change Request 376,proposing to Extend Current 7 Day AOT for EDG to 14 Days ML18039A7371999-03-26026 March 1999 Requests Relief from Specified ISI Requirements in Section XI of ASME Boiler & Pressure Vessel Code,1989 Edition.Encl Contains Request for Relief 3-ISI-7,for NRC Review & Approval ML18039A7331999-03-26026 March 1999 Forwards Rev 4 to TVA-COLR-BF2C10, Bnfp,Unit 2,Cycle 10 COLR, IAW Requirements of TS 5.6.5.d.COLR Was Revised to Extend Max Allowable Nodal Exposure for GE GE7B Fuel Bundles ML18039A7291999-03-22022 March 1999 Forwards Revised Epips,Including Index,Rev 26A to EPIP-1, Emergency Classification Procedure & Rev 26A to EPIP-5, General Emergency. Rev 26A Includes All Changes Made in Rev 26 as Well as Identified Errors ML20204G8471999-03-19019 March 1999 Reports Change in Medical Status for Ma Morrow,In Accordance with 10CFR55.25.Encl Medical Info & Certification of Medical Exam,Considered by Util to Be of Personal Nature & to Be Withheld from Pdr,Per 10CFR2.790(a)(6).Without Encl ML20207M0611999-03-11011 March 1999 Forwards Goals & Objectives for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3,radiological Emergency Plan Exercise.Plant Exercise Is Currently Scheduled for Wk of 990524 ML18039A6971999-02-22022 February 1999 Forwards Typed TS Pages,Reflecting NRC Approved TS Change 354 Requiring Oscillation PRM to Be Integrated Into Approved Power uprate,24-month Operating Cycle & Single Recirculation Loop Operation ML18039A6961999-02-19019 February 1999 Provides Util Response to GL 95-07 Re RCIC Sys Injection Valves (2/3-FCV-71-39) for BFN Units 2 & 3.Previous Responses,Dtd 951215,1016 & 960730,0315 & 0213,supplemented ML18039A6911999-02-19019 February 1999 Forwards Rev 3 to Unit 2 Cycle 10 & Rev 1 to Unit 3 Cycle 9, Colr.Colrs for Each Unit Were Revised to Include OLs Consistent with Single Recirculation Loop Operation ML20203B6031999-02-0404 February 1999 Requests Temporary Partial Exemption from Requirements of 10CFR50.65,maint Rule for Unit 1.Util Requesting Exemption to Resolve Issue Initially Raised in NRC Insp Repts 50-259/97-04,50-260/97-04 & 50-296/97-04,dtd 970521 ML18039A6741999-01-21021 January 1999 Responds to NRC 981209 Ltr Re Violations Noted in Insp Repts 50-259/98-07,50-260/98-07 & 50-296/98-07,respectively. Corrective Actions:Will Revise Procedure NEPD-8 Re Vendor Nonconformance Documentation Submission to TVA ML20199F6951999-01-0808 January 1999 Submits Request for Relief from ASME Section XI Inservice Testing Valve Program to Extend Interval Between Disassembly of Check Valve,Within Group of Four Similar Check Valves for EECW Dgs,From 18 to 24 Months 1999-09-09
[Table view] |
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ACCELERATED DISTjUBUTION DEMONSTjRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
CESSION NBR:9004270289 DOC.DATE: 90/04/25 NOTARIZED: NO DOCKET FACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee 05000259 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH. NAME AUTHOR AFFILIATION MEDFORD,M.O. Tennessee Valley Authority RECIP.NAME RECXPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Responds to NRC 900326 50-259/89-56,50-260/89-56 ltr &
re violations noted in Insp Repts 50-296/89-56.
DISTRIBUTION CODE: IE01D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES:1 05000259 on, 05000260 1 Copy each to: S. Black,D.M.Crutchfield,B.D.Liaw, 05000296 R.Pierson,B.Wilson RECIPIENT RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD ROSS,T. 1 1 ACRS 2 2 AEOD 1 1 AEOD/DEIXB 1 1 AEOD/TPAD 1 1 DEDRO 1 1 NRR SHANKMAN,S 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA DIR 11 1 1 NOTES'OPXES NRR/DREP/PEPB9D NRR/DST/DIR 8E2 NUDOCS-ABSTRACT 1
1 1
1 1
1 NRR/ DRI S/ DIR BI I
NRR/PMAS/ LRB1 2 1
1 1
1 1
1 OGC/HDS2 <<1 1 REG FIL 02 1 1 RES/DSR/HFB/HFS 1 1 RGN'ILE 01 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 5 5 NVIZTO ALL "RIDS" RECIPIENIS:
P~ HELP US TO REDUCE WASTE! CONTACT THE. DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION TOTAL NUMBER OF COPXES REQUIRED: LTTR 29 ENCL 29
if TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 6N 38A Lookout Place APR 25 III U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C. 20555 Gentlemen:
In the Matter of Docket Nos. 50-259 Tennessee Valley Authority 50-260 50-296 BRONNS FERRY NUCLEAR PLANT (BFN) NRC INSPECTION REPORTS NOS. 50-259/89-56, 50-260/89-56, AND 50-296/89-56 RESPONSE TO NOTICE OF VIOLATION This letter provides TVA's response to the notice of violation transmitted by letter from B. A. Hilson to 0. D. Kingsley, Jr. dated March 26, 1990. NRC cited TVA with a Sever>ty Level IV violation pertaining to calibration of measuring and test equipment (I'&TE). In the example given, two pieces of'&TE were not calibrated with a standard at least four times as accurate as the M&TE being calibrated. A justification for use of the M&I'E was not documented by responsible management as required by procedure. TVA. has reviewed this event and is taking appropriate corrective actions. contains TVA's response to the notice of violation. The violation is discussed along with the corrective actions taken. Enclosure 2 is a listing of the commitments made in this response.
If you have any questions regarding this response, please contact Patrick P. Carier at (205) 729-3570.
Very truly yours, TENNESSEE VALLEY AUTHORITY Mark 0.'edford, 1 e President Nuclear Technology nd Licensing Enclosures cc: See page 2 9C) 0425 9r) 042702~'9 05'.)
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Ms. S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockvi lie, Maryland 20852 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000 Mr. B. A. Wilson, Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
ENCLOSURE 1 RESPONSE BROWNS FERRY NUCLEAR PLANT (BFN)
NRC INSPECTION REPORT NOS. 50-259/89-56, 50-260/89-56, AND 50-296/89-56 LETTER FROM B. A. WILSON TO O. D. KINGSLEY, JR.
DATED MARCH 26, 1990 Violation 10 CFR 50, Appendix B, Criteria V, as implemented by TVA Topical Report TVA-TR75-1A, requires compliance with procedures. Procedure SDSP-29.1 states that measuring and test equipment must be calibrated with standards which are at least four times as accurate as the equipment being calibrated. It permits use of measuring and test equipr"ent not meeting this requirement if the basis for acceptance is documented and authorized by responsible management.
Contrary to the above, on January 9, 1990 this procedure requirement had not been met for Browns Ferry meesuring and test equipment in that two pressure gauges (Serial Nos. US-TVA-522068 and 517116) had been released for use even though records on site showed that the four times accuracy requirements had not been met in the calibration and no justification for use had been t
documented by responsible management.
- 1. Admission or Denial of the Violation TVA admits the violation.
- 2. Reason for the Violation This violation has been attributed to inadequate administrative controls. SDSP 29.1 "Control of Measuring and Test Equipment," required that MKTE be calibrated by standards that are at least four times as accurate as the equipment being calibrated. Deviations from this requirement were allowed if the basis for acceptance was documented and authorized. However, SDSP 29.1 did not provide adequate guidance for the implementation of this process. As a result, METE which did not meet this requirement were issued for use without appropriate justification and authorization.
- 3. Corrective Ste s Which Have Been Taken and Results Achieved SDSP 29.1 has been revised to provide guidance on the process to evaluate MKTE that was not calibrated with a standard four times more accurate.
Subsequent management review of SDSP 29.1 has identified additional changes that are needed to improve the process. These changes will ensure that calibrated METE r;ceived at BFN that does not meet the four to one calibration ratio and has not been calibrated by a state-of-the-art standard will be evaluated prior to use.
Enclosure 1 Page 2 For the two pressure gauges 'specifically identified in this violation, a recalculation of the accuracy of the standard used in their calibration was performed. This recalculation demonstrated that the calibration standard was actually four times as accurate as the two pressure gauges.
A review of other MINUTE in use at BFN has been performed to determine if any generic implications existed. As a result of this review, additional MINUTE was identified to be evaluated. A Condition Adverse to Quality Report was initiated to track the corrective actions.
An evaluation process is in progress to determine the effects of these discrepancies on plant equipment. Approximately 270 pieces out of 3000 pieces of METE in use at BFN have been identified with this type discrepancy. A sample of M~TE will be evaluated by reviewing their use logs and assuring that their uses have been acceptable. Based upon the results of this sample, evaluations will be performed as necessary. The MINUTE evaluated to date has determined that all their uses have been acceptable.
- 4. Corrective Ste s Which Will Be Taken to Avoid Further Violations Future cases in which calibrated MINUTE received by BFN do not meet the four to one calibration ratio will be justified and authorized prior to their use. METE currently in use that does not meet this requirement will continue to be evaluated as discussed above.
- 5. Date When Full Com .liance Will be Achieved The evaluation process of MINUTE currently in use that does not meet the four to one calibration accuracy requirement will be completed prior to Unit 2 fuel load. Administrative controls resulting from these reviews will be implemented prior to Unit 2 fuel load.
ENCLOSURE 2 RESPONSE BRONNS FERRY NUCLEAR PLANT (BFN)
NRC INSPECTION REPORT NOS. 50-259/89-56, 50-260/89-56, AND 50-296/89-56 LETTER FROM B. A. NILSON TO 0. D. KINGSLEY, JR.
DATED MARCH 26, 1990 COMMITMENTS
- 1. The evaluation process for the METE that does not currently meet the four to one calibration accuracy will be completed prior to Unit 2 fuel load.
- 2. Administrative controls resulting from the reviews will be implemented prior to Unit 2 fuel load.