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| {{#Wiki_filter:Qi Arizona Nuclear Power Project P.o.BOX 52034~PHOENIX, ARIZONA 85072-2034 RK8~iEO HRI: iS86 JUL lt;PH l: 02 July 7, 1986 ANPP-00015-JGH/TDS/96.03 hkGtON V lKf: Mr.John B.Martin, Regional Administrator U.S.Nuclear Regulatory Commission Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596-5368 | | {{#Wiki_filter:Qi RK8~iEO HRI: |
| | Arizona Nuclear Power Project P.o. BOX 52034 ~ PHOENIX, ARIZONA 85072-2034 iS86 JUL lt; PH l: 02 July 7, 1986 ANPP-00015-JGH/TDS/96.03 hkGtON V lKf: |
| | Mr. John B. Martin, Regional Administrator U.S. Nuclear Regulatory Commission Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596-5368 |
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| ==Subject:== | | ==Subject:== |
| Palo Verde Nuclear Generating Station (PVNGS)Unit 2 Docket No STN 50-529 (License NPF-51)Notice of Violation: | | Palo Verde Nuclear Generating Station (PVNGS) |
| 50-529/86-17-02 File: 86-001-493 | | Unit 2 Docket No STN 50-529 (License NPF-51) |
| | Notice of Violation: 50-529/86-17-02 File: 86-001-493 |
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| ==Reference:== | | ==Reference:== |
| | Letter from A. E. Chaffee (NRC) to E. E. Van Brunt, Jr. (ANPP), |
| | dated June 13, 1986, NRC Inspection Reports 50-528/86-16, 50-529/86-17 and 50-530/86-11. |
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| Letter from A.E.Chaffee (NRC)to E.E.Van Brunt, Jr.(ANPP), dated June 13, 1986, NRC Inspection Reports 50-528/86-16, 50-529/86-17 and 50-530/86-11.
| | ==Dear Mr. Martin:== |
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| ==Dear Mr.Martin:==
| | This letter is provided in response to the inspection conducted by Messrs. R. |
| This letter is provided in response to the inspection conducted by Messrs.R.Zimmerman, C.Bosted, G.Fiorelli and J.Ball of the NRC Staff on April 14 through May 26, 1986.Based on the results of the inspection, one (1)violation of NRC requirements was identified (failure to follow procedure during contain-ment air lock seal leak test).The violation is discussed in Appendix A of the referenced letter.The violation and ANPP's response is provided in Attach-ment A.The response to the concern of general procedural adherence as discussed in the referenced letter is provided in Attachment B.Very truly yours, 8608040233 860729 PDR ADOCK 05000529 , PDR~J.G.Haynes Vice.President Nuclear Production JGH/TDS/kj Attachments cc: E.E.Van Brunt Jr.L.F.Miller R.P.Zimmerman E.A.Licitria A.C.Gehr (w/attachment)(w/attachment)(w/attachment)(w/attachment)(w/o attachment) | | Zimmerman, C. Bosted, G. Fiorelli and J. Ball of the NRC Staff on April 14 through May 26, 1986. Based on the results of the inspection, one (1) violation of NRC requirements was identified (failure to follow procedure during contain-ment air lock seal leak test). The violation is discussed in Appendix A of the referenced letter. The violation and ANPP's response is provided in Attach-ment A. The response to the concern of general procedural adherence as discussed in the referenced letter is provided in Attachment B. |
| | Very truly yours, 8608040233 860729 PDR ADOCK 05000529 |
| | , PDR~ J. G. Haynes Vice. President Nuclear Production JGH/TDS/kj Attachments cc: E. E. Van Brunt Jr. (w/attachment) |
| | L. F. Miller (w/attachment) |
| | R. P. Zimmerman (w/attachment) |
| | E. A. Licitria (w/attachment) |
| | A. C. Gehr (w/o attachment) |
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| Mr.John B.Martin Palo Verde Nuclear Generating Station Notice of Violation ANPP-00015-JGH/TDS/96.03 Page 2 bcc: R.M.Butler J.R.Bynum W.E.Ide 0.J.Zeringue T.D.Shriver W.F.Quinn LCTS Coordinator (all w/attachments) 0 ANPP-00015-JGH/TDS/96.03 NOTICE OF VIOLATION Arizona Nuclear Power Project Post Office Box 52034 Phoenix, Arizona 85072-2034 Docket No.50-529 License No.NPF-51 Technical Specification 6.8.1.c requires that written procedures be estab-lished and implemented for surveillance and test activities of safety-related equipment. | | Mr. John B. Martin Palo Verde Nuclear Generating Station Notice of Violation ANPP-00015-JGH/TDS/96.03 Page 2 bcc: R. M. Butler (all w/ attachments) |
| PVNGS Manual Procedure 73ST-9CL03, Containment Airlock Seal Leak Test, Revision 1 (through procedure change notice number 3), effective February 7, 1986, paragraph 10.0, Contingencies, states that when the inner door fails the seal leak test and requires repair, the outer door shall remain closed until repair and retest have been satisfactorily completed.
| | J. R. Bynum W. E. Ide |
| Contrary to the above, on April'll, 1986, the Unit 2 140'ontainment air-lock inner door failed a seal leak test performed'using procedure 73ST-9CL03, and the outer door was opened prior to satisfactory repair and retest of the inner door.
| | : 0. J. Zeringue T. D. Shriver W. F. Quinn LCTS Coordinator |
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| ~8 ANPP's RESPONSE TO VIOLATION I.THE CORRECTIVE STEPS MiICH HAVE BEEN TAKEN AND THE RESULTS ACHIEVED As an immediate corrective action the engineers involved were counseled on the importance of procedural adherence and ANPP's policy concerning deviations from that position.Additionally, the Tech-nical Support Department Manager issued a memorandum to all personnel in the department addressing the importance of preventing personnel errors during the performance of assigned tasks and reiterating the consequences of committing errors through negligence. | | 0 ANPP-00015-JGH/TDS/96.03 NOTICE OF VIOLATION Arizona Nuclear Power Project Docket No. 50-529 Post Office Box 52034 License No. NPF-51 Phoenix, Arizona 85072-2034 Technical Specification 6.8.1.c requires that written procedures be estab-lished and implemented for surveillance and test activities of safety-related equipment. |
| The procedure, which was being utilized during the airlock seal I leak test, has been revised to clarify the differences between Unit I and Unit II's Technical Specifications. | | PVNGS Manual Procedure 73ST-9CL03, Containment Airlock Seal Leak Test, Revision 1 (through procedure change notice number 3), effective February 7, 1986, paragraph 10.0, Contingencies, states that when the inner door fails the seal leak test and requires repair, the outer door shall remain closed until repair and retest have been satisfactorily completed. |
| An evaluation of the overall effectiveness of these measures is discussed in Attach-ment B.II.THE CORRECTIVE STEPS WHICH MILL BE TAKEN TO AVOID FURTHER ITEMS OF NONCOMPLIANCE An evaluation was conducted to determine the root cause of the identified deficiency. | | Contrary to the above, on April 'll, 1986, the Unit 2 140'ontainment air-lock inner door failed a seal leak test performed 'using procedure 73ST-9CL03, and the outer door was opened prior to satisfactory repair and retest of the inner door. |
| Based upon the results of the evaluation it was determined that the event was caused by a conscious decision made by the responsible personnel to violate the established pro-cedural controls.Their decision was based on a known difference between Unit I and Unit II's Technical Specifications. | | |
| The dif-ference, as explained in the inspection report, permits the operable door to be opened for a cumulative time not to exceed one hour per year in Unit II.The procedure being used during this activity, 73ST-9CL03"Containment Airlock Seal Leak Test", was written to lf 1 address the requirements of Unit I's Technical Specifications and does not provide the option to open the operable door.The respon-sible, personnel were aware that performing the tasks in the manner that they did, had no safety impact and did not violate Unit II's Technical Specification 3.6.1.3.They were also aware that their actions were contrary to the requirements of the approved procedure. | | ~ 8 ANPP's RESPONSE TO VIOLATION I. THE CORRECTIVE STEPS MiICH HAVE BEEN TAKEN AND THE RESULTS ACHIEVED As an immediate corrective action the engineers involved were counseled on the importance of procedural adherence and ANPP's policy concerning deviations from that position. Additionally, the Tech-nical Support Department Manager issued a memorandum to all personnel in the department addressing the importance of preventing personnel errors during the performance of assigned tasks and reiterating the consequences of committing errors through negligence. The procedure, which was being utilized during the airlock seal I |
| Therefore, based on ANPP Management's continued attention to issues such as procedural adherence, a broad scope plan has been developed. | | leak test, has been revised to clarify the differences between Unit I and Unit II's Technical Specifications. An evaluation of the overall effectiveness of these measures is discussed in Attach-ment B. |
| This plan is discussed in Attachment B.III.THE DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED Full compliance was achieved on April ll, 1986 when the Containment Airlock Door was successfully tested and closed. | | II. THE CORRECTIVE STEPS WHICH MILL BE TAKEN TO AVOID FURTHER ITEMS OF NONCOMPLIANCE An evaluation was conducted to determine the root cause of the identified deficiency. Based upon the results of the evaluation it was determined that the event was caused by a conscious decision made by the responsible personnel to violate the established pro-cedural controls. Their decision was based on a known difference between Unit I and Unit II's Technical Specifications. The dif-ference, as explained in the inspection report, permits the operable door to be opened for a cumulative time not to exceed one hour per year in Unit II. The procedure being used during this activity, 73ST-9CL03 "Containment Airlock Seal Leak Test", was written to |
| I ANPP-00015-JGH/TDS-96.03 ATTACHMENT B In response to the general issue discussed in the referenced letter, an evaluation was conducted to address not only the specific incidents identified but the generic question of procedural adherence. | | |
| The in-spection report transmittal letter states that the potential for a more general problem exists based on two previous concerns of procedural noncompliance identified in 1985.The specific incidents described were attributed to willfull violations of procedural controls, committed by knowledgeable individuals without ANPP Management's knowledge. | | lf 1 |
| The incidents cited, when evaluated in the overall context of procedural adherence, appear to be isolated cases which could only be addressed as they were on a case by case basis.However, during the course of the evaluation, potential areas of weakness I.in procedural adherence were identified. | | |
| These areas have been isolated to individual departments and do not appear,,to represent a generic con-II I cern.ANPP Management's continued concern in this area is demonstrated by the implementation of various corrective measures whenever a potential problem such as this was identified. | | address the requirements of Unit I's Technical Specifications and does not provide the option to open the operable door. The respon-sible, personnel were aware that performing the tasks in the manner that they did, had no safety impact and did not violate Unit II's Technical Specification 3.6.1.3. They were also aware that their actions were contrary to the requirements of the approved procedure. |
| Since 1983, ANPP Management has implemented various programs and initi-ated changes to existing programs to reduce both personnel errors and procedural violations. | | Therefore, based on ANPP Management's continued attention to issues such as procedural adherence, a broad scope plan has been developed. |
| These efforts have included: a.Establishment of a"Quality Improvement Report" (QIR)program in the IRC Maintenance area.This program was designed to investigate various incidents, determine the cause and develop the necessary corrective action plan.This program was implemented in IRC Maintenance initially because of | | This plan is discussed in Attachment B. |
| ~~~p~~r specific concerns identified that appeared unique to that area.b.Expansion of the QIR program to include all areas of the Main-tenance Department. | | III. THE DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED Full compliance was achieved on April ll, 1986 when the Containment Airlock Door was successfully tested and closed. |
| c.Modifying the existing administrative controls which specify how approved procedures may be revised or changed.This was done to expedite the process and enable the user to easily modify an existing procedure whenever an error was discovered or a potential enhancement was identified. | | |
| d.Establishment of the"Operations Department Experience Report"\((ODER)program.This program was designed to achieve the same objecti'ves as the QIR program.In conjunction with the specific programs described above additional generic actions were taken.These included: a.The production of a video tape by the Executive Vice President in which he stressed the criticality of procedural adherence. | | I ANPP-00015-JGH/TDS-96.03 ATTACHMENT B In response to the general issue discussed in the referenced letter, an evaluation was conducted to address not only the specific incidents identified but the generic question of procedural adherence. The in-spection report transmittal letter states that the potential for a more general problem exists based on two previous concerns of procedural noncompliance identified in 1985. The specific incidents described were attributed to willfullviolations of procedural controls, committed by knowledgeable individuals without ANPP Management's knowledge. The incidents cited, when evaluated in the overall context of procedural adherence, appear to be isolated cases which could only be addressed as they were on a case by case basis. |
| This video was required to be viewed by all PVNGS personnel and is currently being used during the new employee indoctrina-tion.b.The topic of procedure adherence was repeatedly used as a topic in the"Quality Talks" program.c.Including the topic of"Procedural Adherence" in the"Site Access Training" program (SAT).As described above various approaches had been taken in the past to address not only the generic issue of procedural adherence but to speci-fically address identified weaknesses and concerns.The individual successes of these programs varied.However, the implementation of the QIR and accelerated disciplinary programs in the I&C Maintenance area proved effective. | | However, during the course of the evaluation, potential areas of weakness I. |
| Based upon the success achieved the decision | | in procedural adherence were identified. These areas have been isolated to individual departments and do not appear,,to represent a generic con-II I cern. ANPP Management's continued concern in this area is demonstrated by the implementation of various corrective measures whenever a potential problem such as this was identified. |
| ~~~0 l l( | | Since 1983, ANPP Management has implemented various programs and initi-ated changes to existing programs to reduce both personnel errors and procedural violations. These efforts have included: |
| area proved effective. | | : a. Establishment of a "Quality Improvement Report" (QIR) program in the IRC Maintenance area. This program was designed to investigate various incidents, determine the cause and develop the necessary corrective action plan. This program was implemented in IRC Maintenance initially because of |
| Based upon the success achieved the decision t was made to utilize this approach to address the recently identified concerns.The basic program is being expanded to include all individuals reporting to the Plant Manager.The initial implementation of this program was begun on July 7, 1986, when the Plant Manager issued a memo-randum to all PVNGS personnel stressing the necessity to reduce personnel errors and to comply with all station procedures. | | |
| The memorandum also emphasized the potential for administering accelerated disciplinary action for any individual who, through willfull intent or negligence, commits an error or procedural violation. | | ~ ~ |
| The Compliance Manager has been assigned the responsibility to develop the remaining portions of the program which includes: a.Expansion of the existing QIR program philosophy to encompass all departments reporting to the Plant Manager.This approach will ensure that a comprehensive review is conducted for all incidents effecting the department, that'the root cause is identified and that effective corrective actions are initiated. | | ~ ~ |
| I b.Establishment of a committee, consisting of the Plant Manager and his direct reports, to review incidents and interview per-sonnel found to have willfully or through negligence committed an error or procedural violation. | | p |
| This committee will evaluate the incidents on a case by case basis and recommend appropriate disciplinary actions.ANPP Management believes that full implementation of this comprehensive program, expected by October 1, 1986, will successfully control and reduce both personnel errors and procedural violations. | | ~r specific concerns identified that appeared unique to that area. |
| r P}} | | : b. Expansion of the QIR program to include all areas of the Main-tenance Department. |
| | : c. Modifying the existing administrative controls which specify how approved procedures may be revised or changed. This was done to expedite the process and enable the user to easily modify an existing procedure whenever an error was discovered or a potential enhancement was identified. |
| | : d. Establishment of the "Operations Department Experience Report" |
| | \( |
| | (ODER) program. This program was designed to achieve the same objecti'ves as the QIR program. |
| | In conjunction with the specific programs described above additional generic actions were taken. These included: |
| | : a. The production of a video tape by the Executive Vice President in which he stressed the criticality of procedural adherence. |
| | This video was required to be viewed by all PVNGS personnel and is currently being used during the new employee indoctrina-tion. |
| | : b. The topic of procedure adherence was repeatedly used as a topic in the "Quality Talks" program. |
| | : c. Including the topic of "Procedural Adherence" in the "Site Access Training" program (SAT). |
| | As described above various approaches had been taken in the past to address not only the generic issue of procedural adherence but to speci-fically address identified weaknesses and concerns. The individual successes of these programs varied. However, the implementation of the QIR and accelerated disciplinary programs in the I&C Maintenance area proved effective. Based upon the success achieved the decision |
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| | 0 l |
| | l( |
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| | t area proved was made concerns. |
| | to effective. |
| | utilize this The Based upon the success approach to address basic program reporting to the Plant Manager. |
| | is achieved the decision the recently being expanded to include The initial implementation identified all program was begun on July 7, 1986, when the Plant Manager issued a memo-individuals of this randum to all PVNGS personnel stressing the necessity to reduce personnel errors and to comply with all station procedures. The memorandum also emphasized the potential for administering accelerated disciplinary action for any individual who, through willfullintent or negligence, commits an error or procedural violation. The Compliance Manager has been assigned the responsibility to develop the remaining portions of the program which includes: |
| | : a. Expansion of the existing QIR program philosophy to encompass all departments reporting to the Plant Manager. This approach will ensure that a comprehensive review is conducted for all incidents effecting the department, that 'the root cause is identified and that effective corrective actions are initiated. |
| | I |
| | : b. Establishment of a committee, consisting of the Plant Manager and his direct reports, to review incidents and interview per-sonnel found to have willfullyor through negligence committed an error or procedural violation. This committee will evaluate the incidents on a case by case basis and recommend appropriate disciplinary actions. |
| | ANPP Management believes that full implementation of this comprehensive program, expected by October 1, 1986, will successfully control and reduce both personnel errors and procedural violations. |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17313B0991999-10-14014 October 1999 Forwards LER 99-005-00 Reporting Findings & Corrective Actions Taken as Result of Out of Tolerance MSSV Condition in Unit 1 Which Was Discovered During pre-outage Testing ML17313B0881999-10-12012 October 1999 Forwards Response to NRC 990831 RAI Re Several Relief Requests That Accompanied Second ten-yr Interval ISI Program Submitted on 980317.Revised Relief Request 6 Is Provided in Encl 2 ML17300B3501999-09-29029 September 1999 Forwards Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7,in Response to NRC RAI Re Proposed Amend to TS 3.8.1 & 3.3.7 ML17300B3551999-09-28028 September 1999 Responds to Aministrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams. Proposed Palo Verde Operator Licensing Exam Schedule & Estimated Number of Applicants Planning to Take Exams Encl ML17313B0851999-09-24024 September 1999 Requests Approval of Alternative to Repair Requirements of 10CFR50.55a,authorizing Alternative Use of Mechanical Nozzle Seal Assemblies,As Described in Encl,For RCS Hot Leg Instrumentation & Sampling Nozzles for Two Operating Cycles ML17313B0781999-09-20020 September 1999 Forwards Rev 22 to PVNGS Emergency Plan. Summary Description of Changes,Included ML17300B3331999-09-14014 September 1999 Forwards MOR for August 1999 & Revised MOR for Jul 1999 for Pvngs,Units 1,2 & 3 ML17300B3351999-09-0808 September 1999 Informs That Repairs to Plant EDG 2A Jacket Water Cooling sub-sys Were Completed & EDG Was Declared Operable on 990903 at Approx 21:45 Mst.Noed Was Not Necessary,Since 72 Hour Completion Time Was Met ML17313B0761999-09-0303 September 1999 Requests Enforcement Discretion to TS Section 3.8.1, AC Sources - Operating. Enforcement Discretion Would Allow,On One Time Basis,Extension of Completion Time in Required Action B.4 of TS 3.8.2 from 72 H to 108 H ML17313B0731999-08-31031 August 1999 Informs That RR Bean (License OP-50452-1) Has Been Permanently Reassigned to Position That Does Not Require License & Requests That Individuals License Be Expired Per 10CFR55.55 ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML17313B0581999-08-0606 August 1999 Forwards Rev 1 of Changes to TS Bases Implemented Between Aug 1998 & Jul 1999.Insertion Instructions & List of Affected Pages Included ML17313B0311999-08-0303 August 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001 ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML17313B0431999-07-30030 July 1999 Advises of Listed Senior Mgt Changes That Have Taken Place at Plant ML17313B0441999-07-30030 July 1999 Forwards Comments on Draft NRC Repts Evaluation of AOVs at Us Light-Water Reactors (1999) & Idaho Natl Engineering & Environ Lab Rept (INEEL)EXT-98-00383,Study of AOVs in Npps. ML17313B0151999-07-20020 July 1999 Submits Request to Obtain All Data Previously Sent by PVNGS & Currently in REIRS for OLs NPF-41,NPF-51 & NPF-74.Data Is Requested in Electronic Form (Ascii Format) as It Currently Exists in REIRS Sys ML17313B0091999-07-20020 July 1999 Forwards Requested Calculations Performed to Verify That Increase in Max Radially Averaged Enrichment for Fuel Assemblies from 4.3 Weight Percent to 4.8 Weight Percent Did Not Affect Requirements for TSs 3.7.15,3.7.17 & 4.3.1 ML17313B0171999-07-16016 July 1999 Forwards LER 99-005-00,re Automatic Rt Which Occurred on 990618,following Sensor Failure in Core Protection Calculators.Corrective Actions Described in LER Are Not Necessary to Maintain Compliance with Regulations ML17300B3111999-07-15015 July 1999 Forwards PVNGS Unit 2 ISI Rept for Eighth Refueling Outage. No Commitments Made to NRC by Ltr ML17300B3141999-07-15015 July 1999 Forwards Corrected Electronic Files for Individual Monitoring Repts for 1998.Original Electronic Files Were Found to Have Two Administrative Errors,Which Has Been Corrected.Encl Withheld,Per 10CFR2.790 ML20209G6771999-07-0808 July 1999 Forwards Supplemental Info to Confirm That Decommissioning Funding Plans of Public Service Co of Nm for Interests in PVNGS Have Been Reviewed by Nm Public Regulation Commission. Final Order & Recommended Decisions in Case 2742,also Encl ML17300B2931999-07-0202 July 1999 Submits Withdrawal of Relief 5 for Second ISI Interval for Units 1,2 & 3.Proposed Alternative Is Related to Exam Requirements for Component Supports for Second ISI Interval ML17313A9951999-06-26026 June 1999 Provides Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. ML17300B2831999-06-26026 June 1999 Requests NRC Approval of Proposed Alternative IAW Provisions of 10CFR50.55a(a)(3)(i) to 10CFR50.55a(g) & Requirements of ASME Boiler & Pressure Vessel Code Section XI for Repairs & Installation.Description of Proposed Alternative,Encl ML17313A9901999-06-15015 June 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. No Commitments Being Made to NRC by Ltr ML17313A9521999-05-24024 May 1999 Notifies NRC That Ja Proctor,License SOP-50314,has Been Permanently Reassigned to Position That Does Not Require License.License Should Be Expired,Per 10CFR55.55 ML20206Q3111999-05-18018 May 1999 Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety ML17313A9311999-05-13013 May 1999 Notifies NRC That Rev 2 to COLR for Unit 2 Remains Applicable Following Recently Completed Unit 2 Reload ML17313A9481999-05-12012 May 1999 Informs of Change Needed in Order to Update Current Mailing List.Future Mailings for J Horne Should Be Forwarded to Listed Address ML17313A9261999-05-0707 May 1999 Forwards LER 99-004-00,per 10CFR50.73.LER Repts Findings & Corrective Actions Taken as Result of Unit 2 Out of Tolerance Pressurizer Safety Valve (Psv) Condition Which Was Discovered During Outage Testing ML20206H1931999-05-0303 May 1999 Forwards 1998 Annual Rept, for SONGS Units 2 & 3 & PVNGS Units 1,2 & 3.SCEs Form 10K Annual Rept to Securites & Exchange Commission for Fiscal Yr Ending 981231,encl ML17313A9091999-04-30030 April 1999 Forwards Proprietary Proposed Test Outlines for Initial License Exams to Be Administered at PVNGS in Aug/Sept 1999. No Commitments Are Contained in Ltr.Proprietary Info Withheld ML17313A9181999-04-30030 April 1999 Forwards Electronic File of Individual Monitoring Repts for 1998.Encl Withheld Per 10CFR2.790 ML17313A9191999-04-30030 April 1999 Forwards Special Rept 2-SR-99-001 Re SG Tube Plugging in PVNGS Unit 2,per TS Reporting Requirement 5.6.8.Complete Results of SG Tube Inservice Insp Will Be Submitted by 000422 ML17300B3751999-04-23023 April 1999 Forwards LER 99-003-00,reporting Condition Prohibited by TS 3.7.17 Where Spent Fuel Assembly Was Stored in Inappropriate Region in Spent Fuel Pool ML17313A9081999-04-23023 April 1999 Documents 990421 Telcon with E Emeigh,Which Requested Extension for Submitting Next Matl Balance Rept for Pvngs,As Required by 10CFR70.53 & 74.13.Required Info Will Be Submitted by 990531 ML20205T7421999-04-21021 April 1999 Forwards Partially Withheld Insp Repts 50-528/99-05, 50-529/99-05 & 50-530/99-05 on 990322-26.Determined That Security Program Properly Implemented.Insp Repts Details Withheld (Ref 10CFR73.21) ML17313B0271999-04-21021 April 1999 Forwards Proprietary Epec Pro Forma Cashflow Statement for 1999.Proprietary Info Withheld,Per 10CFR2.790.Affidavit Encl ML17313A9031999-04-21021 April 1999 Forwards Rev to Relief Request 12 Submitted 990420 to Second 10-yr ISI Interval.Revised Relief Request Discusses in More Detail Actions APS Will Take When There Is Identified Leakage from Bolted Connection ML17313A8971999-04-20020 April 1999 Requests Use of Alternatives to 10CFR50.55a(g) Inservice Insp Requirements.Proposed Alternatives Are Related to Visual Exam of Bolted Connections 05000529/LER-1999-002, Forwards LER 99-002-00 Re Findings & Corrective Actions Taken as Result of Plant Out of Tolerance MSSV Condition Which Was Discovered During pre-outage Testing1999-04-19019 April 1999 Forwards LER 99-002-00 Re Findings & Corrective Actions Taken as Result of Plant Out of Tolerance MSSV Condition Which Was Discovered During pre-outage Testing ML17313A8931999-04-14014 April 1999 Forwards LER 99-003,reporting Condition Prohibited by TSs That Existed When Surveillance Requirement to Verify Essential Chilled Water Sys Valve Positions Was Not Met ML20205Q0821999-04-13013 April 1999 Forwards Second ISI Interval Relief Request 10 from ASME Section XI & Applicable Addenda Re Visual Exams Performed Subsequent to Repair or Replacement of Component or Alteration of Item ML17313A8901999-04-13013 April 1999 Forwards LER 98-003-01 Re MSSV as-found Lift Pressures out- Side of TS Limits.Ler Suppl Provides Evaluation Findings from Unit 3 out-of-tolerance MSSVs Conditions Which Were Discovered During pre-outage Testing ML17313A8831999-04-0808 April 1999 Forwards 1998 Annual Radioactive Effluent Release Rept for Pvngs,Units 1,2 & 3 & Rev 13 to ODCM, for Pvngs,Units 1,2 & 3 IAW TS 5.6.3 ML20205F3491999-03-30030 March 1999 Forwards Proprietary & non-proprietary Info Re Status of Decommissioning Funding for Pvngs,Units 1,2 & 3,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per Requirements of 10CFR2.790(b)(1) ML17313A8671999-03-24024 March 1999 Submits Info Re Present Levels & Sources of Property Insurance Maintained for Pvngs,Per 10CFR50.54(w)(3) ML17313A8601999-03-16016 March 1999 Forwards Revised Relief Requests PRR-05,PRR-06 & PRR-11 to Clarify That Proposed Design Flow Testing for Lpsi,Hpsi & Containment Spray Pumps Will Be Performed Using Instruments That Comply with Code Requirements,Per 990226 Telcon ML17313A8551999-03-0505 March 1999 Requests Proposed Code Alternative IAW 10CFR50.55a(e)(3),as Acceptable Alternative to Requirements of 10CFR50.55a(e)(1), for Installation of in-line safety-related Flow Measurement Instrument in ASME Class 3 Pipe 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17313B0991999-10-14014 October 1999 Forwards LER 99-005-00 Reporting Findings & Corrective Actions Taken as Result of Out of Tolerance MSSV Condition in Unit 1 Which Was Discovered During pre-outage Testing ML17313B0881999-10-12012 October 1999 Forwards Response to NRC 990831 RAI Re Several Relief Requests That Accompanied Second ten-yr Interval ISI Program Submitted on 980317.Revised Relief Request 6 Is Provided in Encl 2 ML17300B3501999-09-29029 September 1999 Forwards Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7,in Response to NRC RAI Re Proposed Amend to TS 3.8.1 & 3.3.7 ML17300B3551999-09-28028 September 1999 Responds to Aministrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams. Proposed Palo Verde Operator Licensing Exam Schedule & Estimated Number of Applicants Planning to Take Exams Encl ML17313B0851999-09-24024 September 1999 Requests Approval of Alternative to Repair Requirements of 10CFR50.55a,authorizing Alternative Use of Mechanical Nozzle Seal Assemblies,As Described in Encl,For RCS Hot Leg Instrumentation & Sampling Nozzles for Two Operating Cycles ML17313B0781999-09-20020 September 1999 Forwards Rev 22 to PVNGS Emergency Plan. Summary Description of Changes,Included ML17300B3331999-09-14014 September 1999 Forwards MOR for August 1999 & Revised MOR for Jul 1999 for Pvngs,Units 1,2 & 3 ML17300B3351999-09-0808 September 1999 Informs That Repairs to Plant EDG 2A Jacket Water Cooling sub-sys Were Completed & EDG Was Declared Operable on 990903 at Approx 21:45 Mst.Noed Was Not Necessary,Since 72 Hour Completion Time Was Met ML17313B0761999-09-0303 September 1999 Requests Enforcement Discretion to TS Section 3.8.1, AC Sources - Operating. Enforcement Discretion Would Allow,On One Time Basis,Extension of Completion Time in Required Action B.4 of TS 3.8.2 from 72 H to 108 H ML17313B0731999-08-31031 August 1999 Informs That RR Bean (License OP-50452-1) Has Been Permanently Reassigned to Position That Does Not Require License & Requests That Individuals License Be Expired Per 10CFR55.55 ML17313B0581999-08-0606 August 1999 Forwards Rev 1 of Changes to TS Bases Implemented Between Aug 1998 & Jul 1999.Insertion Instructions & List of Affected Pages Included ML17313B0311999-08-0303 August 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001 ML17313B0441999-07-30030 July 1999 Forwards Comments on Draft NRC Repts Evaluation of AOVs at Us Light-Water Reactors (1999) & Idaho Natl Engineering & Environ Lab Rept (INEEL)EXT-98-00383,Study of AOVs in Npps. ML17313B0431999-07-30030 July 1999 Advises of Listed Senior Mgt Changes That Have Taken Place at Plant ML17313B0151999-07-20020 July 1999 Submits Request to Obtain All Data Previously Sent by PVNGS & Currently in REIRS for OLs NPF-41,NPF-51 & NPF-74.Data Is Requested in Electronic Form (Ascii Format) as It Currently Exists in REIRS Sys ML17313B0091999-07-20020 July 1999 Forwards Requested Calculations Performed to Verify That Increase in Max Radially Averaged Enrichment for Fuel Assemblies from 4.3 Weight Percent to 4.8 Weight Percent Did Not Affect Requirements for TSs 3.7.15,3.7.17 & 4.3.1 ML17313B0171999-07-16016 July 1999 Forwards LER 99-005-00,re Automatic Rt Which Occurred on 990618,following Sensor Failure in Core Protection Calculators.Corrective Actions Described in LER Are Not Necessary to Maintain Compliance with Regulations ML17300B3111999-07-15015 July 1999 Forwards PVNGS Unit 2 ISI Rept for Eighth Refueling Outage. No Commitments Made to NRC by Ltr ML17300B3141999-07-15015 July 1999 Forwards Corrected Electronic Files for Individual Monitoring Repts for 1998.Original Electronic Files Were Found to Have Two Administrative Errors,Which Has Been Corrected.Encl Withheld,Per 10CFR2.790 ML20209G6771999-07-0808 July 1999 Forwards Supplemental Info to Confirm That Decommissioning Funding Plans of Public Service Co of Nm for Interests in PVNGS Have Been Reviewed by Nm Public Regulation Commission. Final Order & Recommended Decisions in Case 2742,also Encl ML17300B2931999-07-0202 July 1999 Submits Withdrawal of Relief 5 for Second ISI Interval for Units 1,2 & 3.Proposed Alternative Is Related to Exam Requirements for Component Supports for Second ISI Interval ML17313A9951999-06-26026 June 1999 Provides Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. ML17300B2831999-06-26026 June 1999 Requests NRC Approval of Proposed Alternative IAW Provisions of 10CFR50.55a(a)(3)(i) to 10CFR50.55a(g) & Requirements of ASME Boiler & Pressure Vessel Code Section XI for Repairs & Installation.Description of Proposed Alternative,Encl ML17313A9901999-06-15015 June 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. No Commitments Being Made to NRC by Ltr ML17313A9521999-05-24024 May 1999 Notifies NRC That Ja Proctor,License SOP-50314,has Been Permanently Reassigned to Position That Does Not Require License.License Should Be Expired,Per 10CFR55.55 ML17313A9311999-05-13013 May 1999 Notifies NRC That Rev 2 to COLR for Unit 2 Remains Applicable Following Recently Completed Unit 2 Reload ML17313A9481999-05-12012 May 1999 Informs of Change Needed in Order to Update Current Mailing List.Future Mailings for J Horne Should Be Forwarded to Listed Address ML17313A9261999-05-0707 May 1999 Forwards LER 99-004-00,per 10CFR50.73.LER Repts Findings & Corrective Actions Taken as Result of Unit 2 Out of Tolerance Pressurizer Safety Valve (Psv) Condition Which Was Discovered During Outage Testing ML20206H1931999-05-0303 May 1999 Forwards 1998 Annual Rept, for SONGS Units 2 & 3 & PVNGS Units 1,2 & 3.SCEs Form 10K Annual Rept to Securites & Exchange Commission for Fiscal Yr Ending 981231,encl ML17313A9191999-04-30030 April 1999 Forwards Special Rept 2-SR-99-001 Re SG Tube Plugging in PVNGS Unit 2,per TS Reporting Requirement 5.6.8.Complete Results of SG Tube Inservice Insp Will Be Submitted by 000422 ML17313A9181999-04-30030 April 1999 Forwards Electronic File of Individual Monitoring Repts for 1998.Encl Withheld Per 10CFR2.790 ML17313A9091999-04-30030 April 1999 Forwards Proprietary Proposed Test Outlines for Initial License Exams to Be Administered at PVNGS in Aug/Sept 1999. No Commitments Are Contained in Ltr.Proprietary Info Withheld ML17313A9081999-04-23023 April 1999 Documents 990421 Telcon with E Emeigh,Which Requested Extension for Submitting Next Matl Balance Rept for Pvngs,As Required by 10CFR70.53 & 74.13.Required Info Will Be Submitted by 990531 ML17300B3751999-04-23023 April 1999 Forwards LER 99-003-00,reporting Condition Prohibited by TS 3.7.17 Where Spent Fuel Assembly Was Stored in Inappropriate Region in Spent Fuel Pool ML17313B0271999-04-21021 April 1999 Forwards Proprietary Epec Pro Forma Cashflow Statement for 1999.Proprietary Info Withheld,Per 10CFR2.790.Affidavit Encl ML17313A9031999-04-21021 April 1999 Forwards Rev to Relief Request 12 Submitted 990420 to Second 10-yr ISI Interval.Revised Relief Request Discusses in More Detail Actions APS Will Take When There Is Identified Leakage from Bolted Connection ML17313A8971999-04-20020 April 1999 Requests Use of Alternatives to 10CFR50.55a(g) Inservice Insp Requirements.Proposed Alternatives Are Related to Visual Exam of Bolted Connections 05000529/LER-1999-002, Forwards LER 99-002-00 Re Findings & Corrective Actions Taken as Result of Plant Out of Tolerance MSSV Condition Which Was Discovered During pre-outage Testing1999-04-19019 April 1999 Forwards LER 99-002-00 Re Findings & Corrective Actions Taken as Result of Plant Out of Tolerance MSSV Condition Which Was Discovered During pre-outage Testing ML17313A8931999-04-14014 April 1999 Forwards LER 99-003,reporting Condition Prohibited by TSs That Existed When Surveillance Requirement to Verify Essential Chilled Water Sys Valve Positions Was Not Met ML20205Q0821999-04-13013 April 1999 Forwards Second ISI Interval Relief Request 10 from ASME Section XI & Applicable Addenda Re Visual Exams Performed Subsequent to Repair or Replacement of Component or Alteration of Item ML17313A8901999-04-13013 April 1999 Forwards LER 98-003-01 Re MSSV as-found Lift Pressures out- Side of TS Limits.Ler Suppl Provides Evaluation Findings from Unit 3 out-of-tolerance MSSVs Conditions Which Were Discovered During pre-outage Testing ML17313A8831999-04-0808 April 1999 Forwards 1998 Annual Radioactive Effluent Release Rept for Pvngs,Units 1,2 & 3 & Rev 13 to ODCM, for Pvngs,Units 1,2 & 3 IAW TS 5.6.3 ML20205F3491999-03-30030 March 1999 Forwards Proprietary & non-proprietary Info Re Status of Decommissioning Funding for Pvngs,Units 1,2 & 3,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per Requirements of 10CFR2.790(b)(1) ML17313A8671999-03-24024 March 1999 Submits Info Re Present Levels & Sources of Property Insurance Maintained for Pvngs,Per 10CFR50.54(w)(3) ML17313A8601999-03-16016 March 1999 Forwards Revised Relief Requests PRR-05,PRR-06 & PRR-11 to Clarify That Proposed Design Flow Testing for Lpsi,Hpsi & Containment Spray Pumps Will Be Performed Using Instruments That Comply with Code Requirements,Per 990226 Telcon ML17313A8551999-03-0505 March 1999 Requests Proposed Code Alternative IAW 10CFR50.55a(e)(3),as Acceptable Alternative to Requirements of 10CFR50.55a(e)(1), for Installation of in-line safety-related Flow Measurement Instrument in ASME Class 3 Pipe ML17313A8241999-02-23023 February 1999 Advises That Kp Jarvis,License OP-50287-1,no Longer Needs to Maintain License as Permanently Assigned to Position Requiring No License ML17313A8111999-02-18018 February 1999 Forwards PVNGS Unit 3 7th Refueling Outage, Which Provides Complete Results of SG Tube Inservice Insp Performed,Per TS 5.6.8 ML17313A8721999-02-16016 February 1999 Discusses Resolution of Generic Safety Issue 171, ESF Failures from Loss-of-Offsite Power Subsequent to Loca. Util Has Low Vulnerability to Loca/Grid Collapse/Loop Scenario ML17313A7611999-01-22022 January 1999 Forwards PVNGS Unit 3 Inservice Insp Rept Seventh Refueling Outage, Per 10CFR50.55a.Ltr Contains No New Commitments 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML17305B0681990-09-17017 September 1990 Forwards Response to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule. Exam Dates,Anticipated Number of Candidates & Requalification Exam Schedules for FY91-FY94 Also Encl ML17305B0491990-09-12012 September 1990 Forwards Palo Verde Nuclear Generating Station Unit 2 Steam Generator Eddy Current Exam,Second Refueling Outage Apr 1990. ML17305B0281990-08-27027 August 1990 Forwards fitness-for-duty Semiannual Performance Rept for Period of Jan-June 1990,per 10CFR26.71(d) ML17305B0111990-08-15015 August 1990 Responds to Request for Addl Info Re Emergency Lighting,Per Insp Repts 50-528/90-25,50-529/90-25 & 50-530/90-25. Availability Info Provided in Ref 2,most Appropriate Analysis of Lighting Sys Availability ML17305B0021990-08-0909 August 1990 Provides Update on Status of Record 546 post-restart Item, Per 900412 Ltr.Record Will Revise Procedures for Analyzing & Disseminating Incident Investigation,Operations & Maint Experience to Appropriate Dept ML17305A9871990-08-0303 August 1990 Forwards Rev 1 to Abb Impell Rept 01-1658-1815, Emergency Lighting Independent Review, Per Insp Repts 50-528/90-25, 50-529/90-25 & 50-530/90-25 ML17305A9791990-07-31031 July 1990 Forwards, Conceptual Design for Palo Verde Nuclear Generating Station for Diverse Auxiliary Feedwater Actuation Sys (Dafas) for Review.Schedule of Implementation as Indicated ML20056A4161990-07-31031 July 1990 Forwards Revised Security Plan Implementing Procedures.Encl Withheld (Ref 10CFR2.790) ML17305A9831990-07-27027 July 1990 Requests Temporary Waiver of Compliance from Limiting Condition for Operation 3.6.3 to Allow Corrective Maint to Be Performed on Main Feedwater Isolation Valves by Extending Allowed Outage Time to 12 H Instead of 4 H ML20055J2671990-07-25025 July 1990 Forwards Info Constituting Decommissioning Financial Assurance Certification Rept,Per 10CFR50.33(k)(2) & 50.75(b) ML17305A9771990-07-25025 July 1990 Forwards Status of Corrective Actions to Min Multiple Control Element Assembly Drop Events at Plant.Insp of Insulation Coils & Replacement of Defective Coils for Units 1 & 2 Completed ML20055J1711990-07-25025 July 1990 Forwards Certification of Decommissioning Financial Assurances for Plant,Per 10CFR50.75(b) & 50.33(k)(2) ML20055J1031990-07-25025 July 1990 Forwards Certification of Decommissioning Financial Assurances ML17305A9411990-07-20020 July 1990 Forwards Response to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. ML17305A9431990-07-17017 July 1990 Forwards Rev 1 to Palo Verde Nuclear Generating Station Annual Radiological Environ Operating Rept for 1987. Rev Results from Internal Review Bu Nuclear Safety Group & Audit Performed by Radiation Protection Stds ML17305A9601990-07-13013 July 1990 Forwards Preliminary Response Re Justification for Continued Operation of Fire Protection Sys Equipment,Per Insp Repts 50-528/90-25,50-529/90-25 & 50-530/90-25 ML17305A9331990-07-12012 July 1990 Discusses Util Compliance w/fitness-for-duty Program Implementation.Lab Specialists,Inc Audited & Monitored W/ Satisfactory Results.Ltr of Agreement Has Been in Place Since 900202 ML17305A9391990-07-0909 July 1990 Forwards Endorsement 44 to Maelu Policy MF-116 & Endorsement 62 to Nelia Policy NF-266 ML17305A9341990-07-0909 July 1990 Submits Results of 900514-18 NUREG-1220 Audit,Per NRC 900608 Request,Per Insp of Plant.Remaining Licensed Operators Found to Be in Conformance W/Medical Exam Requirements of 10CFR50.55 ML17305A9151990-06-29029 June 1990 Forwards Emergency Lighting Failure Data Update,Per 900621 Request ML17305A9061990-06-26026 June 1990 Suppls 891114 Response to Violations Noted in Insp Rept 50-528/89-16.Application for Amend to License NPF-41 Will Be Submitted in Oct 1990 to Permit Lower Flow Rate for RCS & Shutdown Cooling Sys ML17305A9111990-06-25025 June 1990 Responds to Generic Ltr 90-04, Status of Implementation of Generic Safety Issues. ML17305A9081990-06-25025 June 1990 Forwards Schedule Reiterating Util Plans for Implementation of USIs A-9 & A-44 & Provides Current Forecast Refuel Dates ML17305A9051990-06-25025 June 1990 Forwards Endorsement 45 to Maelu Policy MF-116 & Endorsement 63 to Nelia Policy NF-266 ML17305A9121990-06-24024 June 1990 Forwards Discharge Test Voltage Curve,Per 900623 Request for Completion of Emergency Lighting Exide Power Supply Prior to Entry Into Mode 2 ML17305A9171990-06-24024 June 1990 Confirms Compliance W/Agreed Upon Course of Action for Restart of Facility as Outlined in 891224 Ltr & Completion of Items Contained in Restart List Provided as Attachment to 900111 Ltr ML17305A8961990-06-20020 June 1990 Responds to NRC 900521 Ltr Re Violations Noted in Insp Repts 50-528/90-12,50-529/90-12 & 50-530/90-12.Corrective Action: Wiring in PPS Cabinets & Cabinet Drawers Reworked in Accordance W/Approved Work Authorization Documents IR 05000528/19900021990-06-19019 June 1990 Describes Current Status & Provides Description of Actions Taken to Ensure Continued High Reliability of Emergency Lighting Sys,Per Insp Repts 50-528/90-02,50-529/90-02 & 50-530/90-02.Emergency Lights Mfg by Emergi-Lite ML17305A9041990-06-19019 June 1990 Describes Current Status & Provides Description of Actions Taken to Ensure Continued High Reliability of Emergency Lighting Sys,Per Insp Repts 50-528/90-02,50-529/90-02 & 50-530/90-02.Emergency Lights Mfg by Emergi-Lite ML17305A8891990-06-15015 June 1990 Informs NRC That post-restart Items Due Prior to Scheduled Restart Have Been Completed on Schedule W/Listed Exceptions ML17305A8871990-06-14014 June 1990 Advises That Fuel Pool Cooling & Cleanup Procedures Being Restructured,Per Response to Violations in Insp Repts 50-528/89-36 & 50-530/89-36 ML17305A8731990-06-0808 June 1990 Responds to Bulletin 88-005 Re Product Forms Other than Fittings & Flanges for Plant.Significant Number of Lugs Delivered to Plant.Util Should Be Notified,If NRC Previous Review of Records Has Identified Other Product Forms ML17305A9421990-06-0101 June 1990 Forwards Pinnacle West Response to State of Az Corp Commission Complaint Filed W/Us Securities & Exchange Commission on 900521,to Revoke Exemption from Public Utils Holding Co Act ML17305A8661990-05-31031 May 1990 Forwards Projected 1990 Cash Flow Statements ML17305A8391990-05-31031 May 1990 Forwards 1990 Reactor Containment Bldg Integrated Leak Rate Test,Final Rept. ML17305A8571990-05-31031 May 1990 Forwards Amended Pages of Feb,Mar & Apr 1990 Monthly Operating Repts for Palo Verde Nuclear Generating Station Unit 2 ML17305A8201990-05-23023 May 1990 Provides Status of Improvements to Eliminate Possibility of Multiple Control Element Assembly Drop Events.Licensee Developed Mod to Ground Fault Detection Sys to Assure Continuous Monitoring & Annunciation of Any Future Faults ML20043B6421990-05-19019 May 1990 Forwards Amend 26 to Security Plan.Amend Withheld (Ref 10CFR2.790(d) & 10CFR73.21) ML17305A7841990-05-15015 May 1990 Forwards Special Rept 2-SR-90-002 Re Steam Generator Tube Plugging Due to Inservice Insp Activities.Twenty Tubes Plugged in Steam Generator 1 & ninety-one Tubes Plugged in Steam Generator 2 ML17305A8721990-05-14014 May 1990 Forwards Arizona Corp Commission Complaint Filed W/Us Securities & Exchange Commission Seeking Revocation or Mod of Exemption of Pinnacle West Capital Corp.Complaint Wholly W/O Merit ML17305A7621990-05-11011 May 1990 Responds to NRC 900413 Ltr Re Violations Noted in Insp Repts 50-528/90-03,50-529/90-03 & 50-530/90-03.Corrective Actions: Night Order Written for Guidance on Use of Instrumentation W/Maint Tag Present ML17305A7921990-05-0808 May 1990 Forwards Public Version of Rev 2 to EPIP-14, Dose Assessment. W/900523 Release Memo ML20043A0511990-05-0303 May 1990 Forwards Public Version of Revised Epips,Including Procedure Change Notice 11 to Rev 12 to EPIP-04 & Procedure Change Notice 1 to Rev 6 to EPIP-15 ML17305A7421990-05-0303 May 1990 Responds to 900330 Enforcement Conference Re Violations Noted in Insp Repts 50-528/90-04,50-529/90-13 & 50-530/90-13.Corrective Action:Special Locking Mechanisms Installed on Currently Posted Radiation Area Doors & Gates ML17305A8861990-04-30030 April 1990 Forwards EPIP Update,Including Rev 7 to EPIP 02,Rev 12 to EPIP 03 & Rev 9 to EPIP 20.W/o Encl ML17305A7381990-04-30030 April 1990 Forwards Annual Environ Operating Rept for 1989 & Annual Rept for Salt Deposition Monitoring Program 1989. ML17305A7131990-04-20020 April 1990 Responds to NRC 900321 Ltr Re Violations Noted in Insp Rept 50-530/90-08.Corrective Action:Plant Guideline Providing Addl Guidance Re Prioritization of Work Promulgated ML17305A6891990-04-16016 April 1990 Forwards Rev to Cycle 3 Reload Analysis Rept,Submitted 891024.Rev Reflects Early end-of-cycle Unit Shutdown & Replacement of Eight New Fuel Assemblies ML17305A7011990-04-12012 April 1990 Forwards Rev 3 to Palo Verde Nuclear Generating Station Post-Restart Actions, Per JB Martin 891224 Ltr ML17305A7081990-04-0909 April 1990 Forwards post-exam Security Agreements for Dk Hendrick, D Ensign,M Alavi & Author.Agreement Certifies That Signatories Will Not Divulge Info Re 900320 Exams 1990-09-17
[Table view] |
Text
Qi RK8~iEO HRI:
Arizona Nuclear Power Project P.o. BOX 52034 ~ PHOENIX, ARIZONA 85072-2034 iS86 JUL lt; PH l: 02 July 7, 1986 ANPP-00015-JGH/TDS/96.03 hkGtON V lKf:
Mr. John B. Martin, Regional Administrator U.S. Nuclear Regulatory Commission Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596-5368
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 2 Docket No STN 50-529 (License NPF-51)
Notice of Violation: 50-529/86-17-02 File: 86-001-493
Reference:
Letter from A. E. Chaffee (NRC) to E. E. Van Brunt, Jr. (ANPP),
dated June 13, 1986, NRC Inspection Reports 50-528/86-16, 50-529/86-17 and 50-530/86-11.
Dear Mr. Martin:
This letter is provided in response to the inspection conducted by Messrs. R.
Zimmerman, C. Bosted, G. Fiorelli and J. Ball of the NRC Staff on April 14 through May 26, 1986. Based on the results of the inspection, one (1) violation of NRC requirements was identified (failure to follow procedure during contain-ment air lock seal leak test). The violation is discussed in Appendix A of the referenced letter. The violation and ANPP's response is provided in Attach-ment A. The response to the concern of general procedural adherence as discussed in the referenced letter is provided in Attachment B.
Very truly yours, 8608040233 860729 PDR ADOCK 05000529
, PDR~ J. G. Haynes Vice. President Nuclear Production JGH/TDS/kj Attachments cc: E. E. Van Brunt Jr. (w/attachment)
L. F. Miller (w/attachment)
R. P. Zimmerman (w/attachment)
E. A. Licitria (w/attachment)
A. C. Gehr (w/o attachment)
Mr. John B. Martin Palo Verde Nuclear Generating Station Notice of Violation ANPP-00015-JGH/TDS/96.03 Page 2 bcc: R. M. Butler (all w/ attachments)
J. R. Bynum W. E. Ide
- 0. J. Zeringue T. D. Shriver W. F. Quinn LCTS Coordinator
0 ANPP-00015-JGH/TDS/96.03 NOTICE OF VIOLATION Arizona Nuclear Power Project Docket No. 50-529 Post Office Box 52034 License No. NPF-51 Phoenix, Arizona 85072-2034 Technical Specification 6.8.1.c requires that written procedures be estab-lished and implemented for surveillance and test activities of safety-related equipment.
PVNGS Manual Procedure 73ST-9CL03, Containment Airlock Seal Leak Test, Revision 1 (through procedure change notice number 3), effective February 7, 1986, paragraph 10.0, Contingencies, states that when the inner door fails the seal leak test and requires repair, the outer door shall remain closed until repair and retest have been satisfactorily completed.
Contrary to the above, on April 'll, 1986, the Unit 2 140'ontainment air-lock inner door failed a seal leak test performed 'using procedure 73ST-9CL03, and the outer door was opened prior to satisfactory repair and retest of the inner door.
~ 8 ANPP's RESPONSE TO VIOLATION I. THE CORRECTIVE STEPS MiICH HAVE BEEN TAKEN AND THE RESULTS ACHIEVED As an immediate corrective action the engineers involved were counseled on the importance of procedural adherence and ANPP's policy concerning deviations from that position. Additionally, the Tech-nical Support Department Manager issued a memorandum to all personnel in the department addressing the importance of preventing personnel errors during the performance of assigned tasks and reiterating the consequences of committing errors through negligence. The procedure, which was being utilized during the airlock seal I
leak test, has been revised to clarify the differences between Unit I and Unit II's Technical Specifications. An evaluation of the overall effectiveness of these measures is discussed in Attach-ment B.
II. THE CORRECTIVE STEPS WHICH MILL BE TAKEN TO AVOID FURTHER ITEMS OF NONCOMPLIANCE An evaluation was conducted to determine the root cause of the identified deficiency. Based upon the results of the evaluation it was determined that the event was caused by a conscious decision made by the responsible personnel to violate the established pro-cedural controls. Their decision was based on a known difference between Unit I and Unit II's Technical Specifications. The dif-ference, as explained in the inspection report, permits the operable door to be opened for a cumulative time not to exceed one hour per year in Unit II. The procedure being used during this activity, 73ST-9CL03 "Containment Airlock Seal Leak Test", was written to
lf 1
address the requirements of Unit I's Technical Specifications and does not provide the option to open the operable door. The respon-sible, personnel were aware that performing the tasks in the manner that they did, had no safety impact and did not violate Unit II's Technical Specification 3.6.1.3. They were also aware that their actions were contrary to the requirements of the approved procedure.
Therefore, based on ANPP Management's continued attention to issues such as procedural adherence, a broad scope plan has been developed.
This plan is discussed in Attachment B.
III. THE DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED Full compliance was achieved on April ll, 1986 when the Containment Airlock Door was successfully tested and closed.
I ANPP-00015-JGH/TDS-96.03 ATTACHMENT B In response to the general issue discussed in the referenced letter, an evaluation was conducted to address not only the specific incidents identified but the generic question of procedural adherence. The in-spection report transmittal letter states that the potential for a more general problem exists based on two previous concerns of procedural noncompliance identified in 1985. The specific incidents described were attributed to willfullviolations of procedural controls, committed by knowledgeable individuals without ANPP Management's knowledge. The incidents cited, when evaluated in the overall context of procedural adherence, appear to be isolated cases which could only be addressed as they were on a case by case basis.
However, during the course of the evaluation, potential areas of weakness I.
in procedural adherence were identified. These areas have been isolated to individual departments and do not appear,,to represent a generic con-II I cern. ANPP Management's continued concern in this area is demonstrated by the implementation of various corrective measures whenever a potential problem such as this was identified.
Since 1983, ANPP Management has implemented various programs and initi-ated changes to existing programs to reduce both personnel errors and procedural violations. These efforts have included:
- a. Establishment of a "Quality Improvement Report" (QIR) program in the IRC Maintenance area. This program was designed to investigate various incidents, determine the cause and develop the necessary corrective action plan. This program was implemented in IRC Maintenance initially because of
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~r specific concerns identified that appeared unique to that area.
- b. Expansion of the QIR program to include all areas of the Main-tenance Department.
- c. Modifying the existing administrative controls which specify how approved procedures may be revised or changed. This was done to expedite the process and enable the user to easily modify an existing procedure whenever an error was discovered or a potential enhancement was identified.
- d. Establishment of the "Operations Department Experience Report"
\(
(ODER) program. This program was designed to achieve the same objecti'ves as the QIR program.
In conjunction with the specific programs described above additional generic actions were taken. These included:
- a. The production of a video tape by the Executive Vice President in which he stressed the criticality of procedural adherence.
This video was required to be viewed by all PVNGS personnel and is currently being used during the new employee indoctrina-tion.
- b. The topic of procedure adherence was repeatedly used as a topic in the "Quality Talks" program.
- c. Including the topic of "Procedural Adherence" in the "Site Access Training" program (SAT).
As described above various approaches had been taken in the past to address not only the generic issue of procedural adherence but to speci-fically address identified weaknesses and concerns. The individual successes of these programs varied. However, the implementation of the QIR and accelerated disciplinary programs in the I&C Maintenance area proved effective. Based upon the success achieved the decision
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t area proved was made concerns.
to effective.
utilize this The Based upon the success approach to address basic program reporting to the Plant Manager.
is achieved the decision the recently being expanded to include The initial implementation identified all program was begun on July 7, 1986, when the Plant Manager issued a memo-individuals of this randum to all PVNGS personnel stressing the necessity to reduce personnel errors and to comply with all station procedures. The memorandum also emphasized the potential for administering accelerated disciplinary action for any individual who, through willfullintent or negligence, commits an error or procedural violation. The Compliance Manager has been assigned the responsibility to develop the remaining portions of the program which includes:
- a. Expansion of the existing QIR program philosophy to encompass all departments reporting to the Plant Manager. This approach will ensure that a comprehensive review is conducted for all incidents effecting the department, that 'the root cause is identified and that effective corrective actions are initiated.
I
- b. Establishment of a committee, consisting of the Plant Manager and his direct reports, to review incidents and interview per-sonnel found to have willfullyor through negligence committed an error or procedural violation. This committee will evaluate the incidents on a case by case basis and recommend appropriate disciplinary actions.
ANPP Management believes that full implementation of this comprehensive program, expected by October 1, 1986, will successfully control and reduce both personnel errors and procedural violations.
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P