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| {{Adams | | {{Adams |
| | number = ML20247E750 | | | number = ML20247H332 |
| | issue date = 07/21/1989 | | | issue date = 09/11/1989 |
| | title = Discusses Insp Rept 50-458/89-18 on 890501-05 & 15-19 & Forwards Notice of Violation | | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-458/89-18 |
| | author name = Martin R | | | author name = Milhoan J |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| | addressee name = Deddens J | | | addressee name = Deddens J |
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| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = EA-89-122, NUDOCS 8907260303 | | | document report number = NUDOCS 8909190296 |
| | package number = ML20247E757 | | | title reference date = 08-21-1989 |
| | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | page count = 4 | | | page count = 2 |
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| c[ %g UNITEo STATES
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| .f 611 RYAN PLAZA ORIVE. SU'TE 1000 | | ~ SEP ! l~ 1989 |
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| | In Reply Refer To: |
| | b , Docket: 50-458/89-18 9 .,, |
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| | Gulf States Utilities |
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| | ~ ATTN: Mr. James C. Deddens SeniorVicePresident(RBNG) |
| | , P.O. Box 220 St.,Francisville, Louisiana 70775 Gentlemen: |
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| | Thank you for your letter of August 21, 1989, in response to our letter and Notice of Violation dated July 21, 1989. We have reviewed your reply and find it responsive to the concerns raised in our Notice of Violation. We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintaine |
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| | Sincerely, Original Soned By: |
| | Thomas P. Gwynn |
| | ' James L. M11hoan, Director Division of Reactor Projects o cc: |
| | Gulf States Utilities ATTN: J. E. Booker, Manager- |
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| | River Bend Oversight P.O. Box 2951 7 Beaumont, Texas 77704 Gulf States Utilities |
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| | ATTN: Les England, Director - |
| | Nuclear Licensing - RBNG e ~ P.O. Box'220: |
| | ,J8 . St. Francisv111e, Louisiana 70775 |
| | . ~ o Louisiana State University, Government Documents Department 7 f r$$ |
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| | Td LouisianaRediationCcntrolProgramDirecto[ j |
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| | RIV:RI:MQPS* .C:MQPS* D:DRSth T .BStewart/cjg- .IBarnes {. LJCallan LMilhoan |
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| ARLINGTON, TEXAS 76011 ,
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| I l L JUL 211989 {
| | Gulf. States Utilities |
| Docket No. 50-458 License No. NPF-47 {
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| EA 89-122 Gulf States Utilities ATTN: Mr. James C. Deddens SeniorVicePresident(RBNG)
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| Post Office Box 220 St. Francisville, Louisiana 70775 i Gentlemen:
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| SUBJECT: NOTICE OF VIOLATION (NRC INSPECTION REPORT N0. 50-458/89-18)
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| | - R. D.- Martin, RA Section Chief (DRP/C) |
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| | .Lisa;Shea,RM/ALF MIS System RPB-DRSS' , . RSTS Operato ' ' |
| | 'ProjectEngineer(DRP/C) RIV File W.=Paulson,-NRR Project Manager (MS:~ 13-D-18) |
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| | B. Stewart l':: I; Barnes |
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| This is in reference to the NRC inspection conducted during the period May 1-5 and May 15-19, 1989, at the River Bend Station (RBS), located in St. Francisville, and to NRC's~ discussion of the inspection findings with Gulf States Louisiana,(GSU) officials at an enforcement conference in Arlington, Texas, on Utilities June 9, 198 As you know, NRC's concerns stenning from this inspection focused on the failure to establish a test program which would have assured the operability of the safety-related ventilation systems associated with the fuel building and the main control room. The results of the inspection were documented in NRC
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| ' Inspection Repcrt No. 89-18, dated June 6,198 During the June 9 enforcement conference, two apparent violations resulting from this inspection were discussed. The violation in the enclosed Notice of Violation (Notice) involves an apparent failure to assure, through the establishment of a test program, the operability of two independent fuel building ventilation subsystems and two subsystems associated with the main stem in accordance with the requirements of control room airSpecifications plant Technical conditioning sy(T.S.) 3.6.5.6 and 3.7.2. As a result of River Bend Station's self-initiated Safety System Functional Inspection (SSFI) of the Instrument Air System (IAS) and SSFI followup actions, GSU discovered design and installation flaws that would have prevented these required subsystems from performing their intended function under certain condition NRC has concluded that GSU's failure to have developed an adequate test program resulted in a significant violation of RBS's T.S. in that GSU failed to assure operability of fuel building ventilation and main control room air conditioning subsystems. These subsystems are important for ensuring the maintenance of a negative pressure within the fuel building and limiting any release of radio-activity within 10 CFR Part 100 limits following a design basis or fuel handling accident, and ensuring that the control room will remain habitable for operations personnel during and following all design basis accident ADOCK 05000458 (Q l PDR Q PDC g I
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| | - r GULF STATES UTILITfES COMPANY " |
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| | August 21, 1989 RBG- 31384 File Nos. G9.5, G15. ~ . . |
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| | U. S. Nuclear Regulatory Commission S [$ !; L _ |
| | Document Control Desk o Washington, D.C. 20555 i |
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| | gggg4jggg Gentlemen: , Ih River Bend Station - Unit 1 Refer to: Region IV Docket No. 50-458/89-18 |
| | - Pursuant to 10CFR2.201, this letter provides Gulf States Utilities Company's (GSU) response to the Notice of Violation for NRC Inspection Report No. 50-458/89-18. The inspection was performed by Messrs. C. Stewart, L. E. Ellershaw and W. B. Jones during the periods of Mt .t 1-5 and 15-19, 1989 of activities authorized by NRC Operating License NPF-47 for River Bend Station - |
| | Unit GSU's response to the violation is provided in Attachment 1. GSU's response to the concerns addressed in the body of the letter is provided in Attachment GSU's response to the rotice of violation is complet Should you have any questions, please contact Mr. L. A. England at (504) 381-414 |
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| | Sincerely, |
| | , p J. E. Booker Manager-River Bend Oversight River Bend Nuclear Group JEB/LAE/RJK/MSF/RGW/AJK/ch Attachments cc: U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Senior Resident Inspector P.O. Box 1051 St. Francisville, LA 70775 |
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| -2- DOL 211989 Gulf States Utilities Had GSU established an adequate testing and surveillance program to evaluate IAS design and operation, it would have been determined that the subsystem associated with the fuel building ventilation was inoperable from initial fuel load in August 1985 and that the subsystem associated with the main control room air conditioning was inoperable for an indeterminate tim Generic Letter 88-14, " Instrument Air Supply System Problems Affecting Safety-Related Equipment," alerted licensees to potential IAS problems and required a response verifying that IAS quality, functional characteristics, and design were 1 as intended. A response was required by February 8, 1989, or if operations were affected, the next refueling or scheduled outage in order to avoid adverse j system interactions. GSU determined through a self-initiated SSFI conducted during the period November 17 to December 21, 1988, and through SSFI followup actions that solenoid operated valves, check valves, and accumulator tanks would not function as designed for the subsystems associated with the main control room air conditioning and fuel building ventilation systems. These conditions were corrected promptly upon discover The NRC has classified the violation in the enclosed Notice at Severity Level III in accordance with Supplement I of the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (Enforcement Policy), as published in the Federal Register on October 13, 1988. While the NRC could consider imposing a monetary civil penalty for a Severity Level III violation, I have determined in this case after consultation with the Director, Office of Enforcement, and the Deputy Executive Director for Nuclear Materials Safety, Safeguards and Operations Support, that no penalty will be assesse I base this decision on discretionary provisions in Section V.G. of the Enforcement Policy. The NRC encourages and supports licensee efforts for self-initiated identification and correction of problems and intends on applying enforcement discretion in cases such as this one in which the problems were identified by a GSU self-initiated SSFI and were promptly corrected. However, the NRC is concerned that upon discovery GSU did not consider the deportability j | | ~ ' |
| of the problems. Prompt evaluation fnr deportability and timely reporting are significant issues. Had the problems discovered not been of a highly technical nature, requiring extensive evaluation and review before determining a possible operability problem existed, your failure to promptly repot c them could have resulted in additional enforcement action being take You are required to respond to this letter and should follow the instructions specified in the enclosed Notice when preparing your response. In your response, you should document the specific actions taken and any additional
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| | UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION STATE OF LOUISIANA ) |
| | PARISH OF WEST FELICIANA ) |
| | Docket No. 50--458 In the Matter of ) |
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| | GULF STATES UTILITIES COMPANY ) |
| | (River Bend Station - Unit 1) |
| | AFFIDAVIT |
| | , E. Booker, being duly sworn, states that he is Manager-River Bend Oversight for Gulf States Utilities Company; that he is authorized on the part of said company to l |
| | sign and file with the Nuclear Regulatory Commission the documents attached hereto; that he has read all of the statements contained in such documents attached thereto and i made a part thereof; and that all such statements made and j' matters set forth therein are true and correct to the best of his knowledge, information and belief. |
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| | [J . Booker Subscribed and sworn to before me, a Notary Public in and for the State and Parish above named, this J/ day of h>l d , .< 6( , 1929 . My Commission expires with Lif [ |
| | 0}Clu dALS NtAME Notary Public in and for West Feliciana Parish, Louisiana |
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| | ATTACMENT 1 RESPONSE TO NOTICE OF VIOLATION 50-458/8918-01 LEVEL III |
| | - REFERENCES-Inspection _ Report 89-18 - Letter from J. L. Milhoan to J. Deddens, dated June 6, 198 Meeting Summary of Enforcement Conference held June 6, 1989 - Letter from L. Milhoan to J. C. Deddens, dated June 22, 198 Notice of Violation - Letter from J. D. Martin to J. C. Deddens, dated July 21, 198 FAILURE TO ESTABLISH A TEST PROGRAM Criterion VI of Appendix B to 10CFR50 requires, in part, that a test program shall be established to assure that all testing required to demonstrate .that structures, systems and components will perform satisfactorily in service is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable design document Contrary to the above, in November 1988 it was identified that Gulf $tates Utilities (G5U) had failed to establish a test program at River Bend Station to assure that all testing required to demonstrate that structures, systems and components will perform satisfactorily in service is identified and performe Specifically, GSU failed to establish a test program to demor. strate that two independent fuel building ventilation charcoal filtration subsystems and two independent main control room air handling unit / filter train subsystems would perform satisfactorily in service. As a result, GSU failed to discover design and installation flaws that would. have prevented these subsystems from operating as intended under certain design condition REASON FOR THE VIOLATION Gulf States Utilities Company's (GSU) performed a detailed review to determine the cause 01 the subject violation. During the start-up test program each system or subsystem was considered to be a separate entit This cause was determined to be GSU's failure to adequately test the interface between the instrument air and HVAC systems which is considered to be an isolated inciden GSU considered interconnected instrument ' air systems operable based on each system or subsystem test and did not realize the need for simultaneous testin The control building and auxiliary building heating, venting and air conditioning (HVAC) systems were released for start-up testing prior to the release of the instrument air system. The need for pressure decay testing of the auxiliary, control atid fuel building's instrument air accumulators was Page 1 of 4 L . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ |
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| actions you plan to prevent recurrence. After reviewing your response to this Notice, including your proposed corrective actions, and the results of future inspections, the NRC will determine whether further NRC enforcement action is necessary to ensure compliance with NRC regulatory requirements.
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| | not recognized during initial plant start-up. The ASKE Section XI valve testing program was thought to provide an adequate indication of system operabilit Neither Technical Specifications nor the ASME XI code requires simultaneous interacting system performance start-up testing. GSU did not interpret Criteria XI of Appendix B to 10CFR Part 50 to require testing of interacting systtms in addition to performance testing of structures, systems and component The initial design was inadequate and testing of the instrument air system would have discovered the problem as GSU discovered in subsequent testin However, the RBS current design modification process requires functional tests such that operability of a system can be assured prior to its return to servic GSU initiated a self assessment of the River Bend Station instrument air system by performing a Safety System Functional Inspection (SSFI) during the fall of 1988. During the inspection a question was raised on the instrument air system accumulator supply capacity for post-accident condition Subseque.a testing was performed during refueling outage 2 which showed that the accumulator air supply was not sufficient for the areas identifie Further investigation identified that solenoid valves had been installed in reverse which did not allow the valves to seal in the correct positio RBS submitted Licensee Event Report (LER) No. 89-022. Other aspects relating to the instrument air system were addressed in the LER and GSU's response to Generic Letter 88-14. GSU's response to the notice of violation will focus on the area of testin CORRECTIVE ACTIONS WHICH HAVE BEEN TAKEN AND THE RESULTS ACHIEVED Design Engineering conducted a review of loads which are dependent upon the safety-related headers within the control, auxiliary, and fuel buildings. This study consisted of a review of the two safety related headers within each of these three buildings. As a result of this study: The control building chilled water pressure differential control valves were modified as described in Section C.I.a belo . Five nonsafety-related loads have been removed from the two instrument air headers within the control buildin . Two standby gas treatment and two auxiliary building HVAC outlet air operated dampers within the auxiliary building will be modifie The first design verification testing included the testing of one of the two instrument air headers within the control building to verify that each header would stay pressurized for the calculated two days upc1 loss of the instrument air compressor The results of the first control building header pressure retertion test revealed the volume of the associated accumulator to be significantly undersized and the following design changes and repairs were then implemented: |
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| '. | | ~ Control Building: The major instrument air users, the control building chilled water pressure differential control valves, were modified to remain mechanically secured in a throttled position instead of remaining as air operated control valves, The pressure retention time of each of the two safety-related headers was increased through the 180 degree realignment of the inlet header solenoid operated valves (50V) to an orientation which seated the valves in the correct position to keep air in |
| Gulf States Utilities -3- JUL 211989 In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosure will be placed in the NRC Public Document Roo The response directed by this letter and the enclosed Hotice are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, Pub. L. No. 96-51 Sincerel.y, !
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| | the accumulato , The inlet check valve of each of the two safety-related headers received seat relapping and spring change-ou . Auxiliary Building: The pressure retention time of each of the two safety-related headers was increased through the 180 degree realignment of the inlet header S0Vs to an orientation which seated the valves in the correct position to keep air in the accumulato . Fuel Building: The pressure retention time of each of the two safety-related headers was increased through the 180 degree realignment of the inlet header 50Vs to an orientation which seated the valves in the correct position to keep air in the accumulato The damper fail positions of four dampers were changed to " fail open" from " fail closed", thereby resulting in instrument air not being required within the fuel building to mitigate the release of radioactivity after an acciden D. The final design verification testing included the testing of the two safety related headers of the control building and the two safety related headers of the auxiliary building to verify that each header remained pressurized to assure the respective HVAC systems would perform their design basis functions following an acciden . Control Building: Each of the two safety related accumulators, along with its associated header, was tested for pressure retention time upon the failure of the instrument air compressor Each safety related header was found to remain pressurized for an adequate time period to assure the control building atmosphere would remain habitable after an accident only when an auxiliary compressed air source is also connected to each heade Page 3 of 4 |
| '(. bb e ^G l q<}$ 3 Robert D. Martin Regional Administrator Enclosure: Notice of Violation cc:
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| | ~ '' Auxiliary Building: Ecch of the two safety related accumulators, alcng with its i associated header, were tested for pressure retention time upon the failure of the instrument air compressors. Each header was found to remain pressur4 zed for an adequate time period to assure the auxiliary, containment, and drywell building HVAC systems would perform their design basis functions following an accident only when an auxiliary compressed air source is connected to each heade The control bailding and auxiliary building safety related accumulator pressure retention times were then increased through the following design modifications: Control Building: |
| | Each of the two accumulators' capacities van ir.creas?d through the installation of two banks of high pre:sure air bottles at each accumulator inle . Auxiliary Building: |
| | Each of the two accumulators' capacities was increased through the installation of two banks of high pressure air bottles at each accumulator inlet. These bottles are subject to removal upon the installation of the backdraft damper CORRECTIVE ACTIONS WHICH WILL BE TAKEN TO AVOID FURTHER VIOLATIONS A-. The two standby gas treatment and two auxiliary butiding HVAC outlet air operated dampers wili be replaced by self-actuating back draft dampers thereby eliminating the need for safety related instrument ai Field Engineering is establishing a control building safety-related accumulator air retention test to be performed every refueling outag C.. In addition, GSU will review the testing methods, the bases for ASME categorization and the leak rate criterion for check valve DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED The River Bend Station instrument air system is currently in full complianc The current system configuration is adequate and the follcwing are enhancements to increase system performance and reliabilit The back draft dampers will be installed in the standby gas treatment and HVAC system prior to start-up fcllowing the third refueling outag The control building accumulator air retention test procedure will be developed by November 15, 198 The review of testing methods, the bases for ASME categorization and the leak rate criterion for check v61ves will be completed prior to start-up following the third refueling outag Page 4 of 4 |
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| | ATTACIMENT 2 As discussed in your letter dated July 21, 1989 transmitting Notice of Violation 8918-01, GSU is providing its response concerning your questions about deportability and operability of the instrument air system at River Bend Station. The reporting requirements contained in 10CFR Parts 50.72 a .73 and GSU's reporting evaluation process via the condition report procedure (ADM-0019), will be emphasized in required training for engineering department personnel. Operability of systems or components with questionable characteristics, as identified on condition reports, will be documented in greater detail in the disposition of the condition report justifying continued operatio Determination of the extent of the nonconforming conditions will be an important element in resolution of the reported conditio Page 1 of I |
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| P JUL 211989 -
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| Gulf State Utilities i DISTRIBUTION:
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| SECY-CA
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| 'JMTaylor, DEDR HThompson, DEDS TMurley, NR J..Partlow, NRR i JLieberman, OE
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| :JGoldberg, 0GC Enforcement Coordinators RI, RII, RIII, RIV, RV F. Ingram, GPA/PA EJordan, AEOD i MHalsch, 0lG BHayes, 01 OE:ES
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| .0E:EA File OE:Chron M $-
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| RIV DISTRIBUTION:
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| RMartin JMontgomery LJCallan-JLMilhoan JPJaudon
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| .IBarnes RStewart LE11ershaw W. B. Jones, RI, RB JG11111and(1trhd)
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| CHackney WBrown RWise E0 Files RIV Files DRS Division Files DRP Division Files RSTS Operator MIS Coordinator G \"
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| OE y :n RIV D:0E DEDS HThompson k I\
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| JLaphman RDMJrtin JLieberman 7/iq/89 7/h/89 7/9()/89 7SO/89 ,
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L7681999-10-19019 October 1999 Forwards Insp Rept 50-458/99-12 on 990822-1002.Four Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy RBG-45125, Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams1999-10-18018 October 1999 Forwards Voluntary Response to Administrative Ltr 99-03, Preparation & Scheduling of Operating Licensing Exams ML20217J3751999-10-15015 October 1999 Informs That Applicable Portions of NEDC-32778P, Safety Analysis Rept for River Bend 5% Power Uprate, Marked as Proprietary Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) IR 05000458/19990071999-10-0505 October 1999 Refers to Util Ltr Re Apparent Violations Described in Insp Rept 50-458/99-07 Issued on 990804 & Forwards Nov.Insp Described Two Apparent Violations Related to River Bend Station Division I EDG RBG-45123, Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required1999-09-30030 September 1999 Informs That Error Reported to NRC by GE on 990630 Resulted from Changes to SAFER Code Models Counter Current Flow Limiting (Ccfl) in Upper Part of Fuel Bundle at Upper Tie Plate (Utp).No Changes in SAR or COLR Required RBG-45124, Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl1999-09-24024 September 1999 Suppl to 990907 Response to Violations Noted in Insp Rept 50-458/99-07.Info to Address Specific Requests in 990920 Conference Call Re DG Assessment Completion Dates for Corrective Actions & DG Maint Rule (a)(1) Status,Encl RBG-45122, Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-471999-09-23023 September 1999 Forwards Rev 3 to RBS COLR for Ninth Fuel Cycle, IAW TS 5.6.5 of App a of FOL NPF-47 RBG-45113, Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp1999-09-21021 September 1999 Clarifies Statement Contained in NRC SER for Licensing RBS, Per Error That Became Evident During Plant Fire Protection Functional Insp ML20212D8901999-09-16016 September 1999 Discusses 6 Month Review of Plant Midcycle Ppr.Advises of Plans for Future Insp Activities.Forwards Historical Listing of Plant Issues,Referred to as PIM ML20216F7881999-09-15015 September 1999 Forwards Insp Rept 50-458/99-10 on 990830-990903.No Violations Noted.Insp Covered Licensed Operators Requalification Training Program & Observation of Requalification Activities 05000458/LER-1998-003, Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents1999-09-0909 September 1999 Forwards LER 98-003-02,revising Previous Rept Dtd 981005, Submitted to Clarify Reported Condition & to Incorporate Final Root Cause Analysis & Corrective Action Plan for Event.Complete Rev & No Change Bars Used in Documents ML20211Q7721999-09-0909 September 1999 Expresses Appreciation for ,In Response to NRC 990702 Re Denial of Notice of Violation Cited in Concerning Insp Rept 50-458/98-16.Reply Found to Be Responsive to Concerns Raised in NOV RBG-45109, Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted1999-09-0808 September 1999 Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted ML20211Q3921999-09-0808 September 1999 Forwards Insp Rept 50-458/99-08 on 990711-0821.One Violation Being Treated as Noncited Violation ML20211Q5541999-09-0808 September 1999 Discusses Meeting Conducted on 990830 in St Francisville,La Re Overall Performance Issues During 990403-0703 Refueling/ Maintenance Outage.Due to Proprietary Nature of Some Subject Matters,Meeting Closed to Public.Attendance List Encl ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) RBG-45095, Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status1999-09-0707 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/99-07.Corrective Actions:Fuel Pump Coupling Was Reworked Using Loctite & Division I DG Was Returned to Operable Status RBG-45097, Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves1999-08-31031 August 1999 Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves RBG-45094, Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation1999-08-25025 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation ML20211E2071999-08-23023 August 1999 Discusses Insp Rept 50-458/99-07 in Which 2 Violations Were Identified & Being Considered for Escalated Enforcement Action.Response Should Be Submitted Under Oath or Affirmation ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 RBG-45093, Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept1999-08-17017 August 1999 Forwards FFD six-month Program Performance Data Rept for Rept Period 990101 Through 990630,containing Statistical Data & Trend Analysis Compiled by FFD Dept ML20211A9291999-08-17017 August 1999 Forwards Insp Rept 50-458/99-11 on 990719-23.Areas Examined Included Portions of Licensee Physical Security Program. No Violations Noted ML20210T8881999-08-16016 August 1999 Forwards Replacement Pages 9-18 for Insp Rept 50-458/99-09, Issued on 990730 IR 05000458/19980101999-08-13013 August 1999 Forwards Summary of 990805 Mgt Meeting with Licensee in Arlington,Tx Re Radiological Control Problems Noted in Insp Repts 50-458/98-10 & 50-458/99-04.With Attendance List & Licensee Presentation 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 ML20210U3751999-08-12012 August 1999 Informs That Info Contained in Presentation, River Bend Station Fuel Recovery Project,Dtd 990622, Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20210Q7691999-08-11011 August 1999 Forwards Request for Addl Info Re Licensee River Bend Individual Plant Exam External Events,Under GL 88-20,suppl 4,dtd 910628 ML20210R4591999-08-10010 August 1999 Ack Receipt of Which Transmitted Plant Emergency Plan,Rev 20 Under Provisions of 10CFR50,App E,Section V.Nrc Approval Not Required,Based on Determination That Changes Does Not Decrease Effectiveness of EP ML20210N1641999-08-0404 August 1999 Forwards Insp Rept 50-458/99-07 on 990530-0710.One Violation of NRC Requirements Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20210K4641999-08-0303 August 1999 Forwards SE Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Power-Operated Gate Valves, Issued on 950817 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 ML20210K1351999-07-30030 July 1999 Forwards Insp Rept 50-458/99-09 on 990510-28 with in-office Insp Until 990701.Three Violations Being Treated as Noncited Violations ML20210J9691999-07-30030 July 1999 Discusses 990719 Meeting with Util in Arlington,Tx Re Region IV Staff Findings of Root Cause Investigation Into Fuel Cladding Failures That Occurred During Recent Cycle 8 Operation.List of Attendees & Organization Chart Encl RBG-45072, Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL1999-07-23023 July 1999 Submits Final Response to GL 94-02, Long-Term Solution & Upgrade of Interim Operating Recommendations for Thermal- Hydraulic Instabilities in Bwrs. Ltr Documents Completion of Reporting Requirements Contained in Subject GL ML20210E9001999-07-23023 July 1999 Informs That as Result of Staff Review of Licensee 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 RBG-45073, Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl1999-07-20020 July 1999 Requests Withholding of Info Presented in 990719 Meeting of EOI & NRC Region IV Re Recent Anomalous Conditions Found During Insp of Fuel Bundles During 1999 RFO at Rbs.Affidavit Executed IAW Provisions of 10CFR2.790(b)(1),encl RBG-45071, Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl1999-07-19019 July 1999 Forwards Rev 2 to River Bend COLR for Ninth Fuel Cycle,Iaw TS 5.6.5 of App A.Affected Pages of GE Suppl Reload Licensing Rept, May 1999 Submittal & List of Effective Pages,Encl 05000458/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 11999-07-15015 July 1999 Forwards LER 99-002-01,IAW 10CFR50.73.Supplemental Rept Details Root Cause Analysis for Reported Condition. Commitments in Document Annotated on Commitment Identifier Form,Attachment 1 ML20196L0501999-07-0606 July 1999 Informs That NRC Insp Rept 50-458/99-03 Issued on 990519 with Errors in Tracking Numbers Assigned to Seven Noncited Violations & Error Re Actual Location of SRO During Refueling Activities.Revised Pages 2 & 4 Encl ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl ML20196K6851999-06-30030 June 1999 Ack Receipt of & Denial of NOV in Response to Transmitting NOV & Insp Rept 50-458/98-16.Listed Info Documents Results of Review of Response to Violation Re fire-induced Circuit Faults ML20196K0671999-06-30030 June 1999 Forwards Insp Rept 50-458/99-04 on 990412-16 & 28-29.Five Violations of NRC Requirements Occurred & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy.Meeting Scheduled for 990726 RBG-45048, Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept1999-06-29029 June 1999 Forwards Rev 1 to Rbs,Cycle 9 COLR, IAW TS 5.6.5 of License NPF-47.GE Suppl Reload Licensing Rept,Dtd May 1999, Is Included.Without GE Rept RBG-45047, Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output1999-06-29029 June 1999 Informs of Util Expectation to Complete Review of Final Rept Supporting Power Uprate & Submits TS Changes in Jul 1999,per Licensee to NRC Re Increasing Power Output ML20196H5171999-06-21021 June 1999 Requests Withholding of Info Being Presented in Meeting of Entergy,General Electric & NRC Staff.Licensee Requested Meeting with NRC to Present Info on Recent Anomalous Conditions Found During Insp of Fuel Bundles.W/Affidavit 05000458/LER-1999-012, Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form1999-06-21021 June 1999 Forwards LER 99-012-00,IAW 10CFR73.Commitments Contained in Document Identified on Commitment Identification Form RBG-45035, Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld1999-06-21021 June 1999 Requests That Encl RBS Fuel Recovery Info Be Withheld from Public Disclosure,Per Provisions of 10CFR2.790(a)(4).Info Is Being Presented at Meeting to Discuss Recent Anomalous Conditions Found.Proprietary Info Withheld ML20196E0601999-06-18018 June 1999 Forwards Insp Rept 50-458/99-05 on 990418-29.Four Violations Identified & Being Treated as Noncited Violations 05000458/LER-1999-011, Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl1999-06-0909 June 1999 Forwards LER 99-011-00 for River Bend Station,Unit 1,IAW 10CFR50.73.Commitments Identified in Rept,Encl 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062G5771990-11-23023 November 1990 Forwards Insp Rept 50-458/90-31 on 901105-09.No Violations or Deviations Noted IR 05000458/19900151990-11-21021 November 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-458/90-15 ML20062E4031990-11-15015 November 1990 Discusses Util Response to NRC Bulletin 88-010, Nonconforming Molded-Case Circuit Breakers ML20058H5481990-11-14014 November 1990 Informs That Util 900529 Changes to Physical Security Plan Unacceptable Under Provisions of 10CFR50.54.Proposed Changes Decrease Effectiveness of Physical Security Plan ML20217A3511990-11-0909 November 1990 Forwards Insp Rept 50-458/90-25 on 900924-28 & 1015-19. Violation Noted But Not Cited ML20058D0401990-10-29029 October 1990 Forwards Physical Security Insp Rept 50-458/90-24 on 900910-14. Violations Not Cited Per 10CFR2 IR 05000458/19900161990-10-20020 October 1990 Ack Receipt of 900830 & 1011 Ltrs Responding to 900730 Notice of Deviation & 900907 & 22 Telcons,Per Insp Rept 50-458/90-16 ML20058B0131990-10-19019 October 1990 Forwards Insp Rept 50-458/90-28 on 901009-12.No Violations or Deviations Noted ML20058D9531990-10-18018 October 1990 Forwards Ref Matl Requirements for Reactor/Senior Reactor Operator Licensing Exams Scheduled for 901114 ML20058A5421990-10-17017 October 1990 Forwards Insp Rept 50-458/90-23 on 900910-14.No Violations or Deviations Noted ML20058A2191990-10-11011 October 1990 Forwards Summary of 900917 Mgt Meeting at Licensee Site Re Activities Conducted Under License NPF-47 IR 05000458/19900021990-10-0808 October 1990 Ack Receipt of Re Violations Noted in Insp Rept 50-458/90-02 ML20059N4721990-10-0303 October 1990 Forwards Insp Rept 50-458/90-22 on 900827-31.No Violations or Deviations Noted ML20059D6411990-08-29029 August 1990 Forwards Insp Rept 50-458/90-15 on 900611-15.No Violations or Deviations Noted ML20056B2461990-08-22022 August 1990 Forwards Insp Rept 50-458/90-20 on 900723-26.No Violations or Deviations Noted.However,Inability to Acquire & Retain Seasoned Instructors W/Substantial Operations Experience Apparently Affecting Quality of Operator Training IR 05000458/19900061990-08-21021 August 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Weaknesses Noted in Insp Rept 50-458/90-06 ML20056B2921990-08-14014 August 1990 Requests Submittal of Final Analysis of Combustible Gas Control Sys,Per 10CFR50.44,by 910301,addressing Key Elements in Encl SER IR 05000458/19892001990-08-0909 August 1990 Discusses Insp Rept 50-458/89-200 on 891023-27 & 1113-17 & Forwards Notice of Violation ML20056A7521990-08-0303 August 1990 Discusses Util 891220 Response to Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & Surveillance. Util Schedule for Completing Phase I of motor-operated Valve Program in Four Refueling Outages Acceptable ML20056A7681990-08-0202 August 1990 Ack Withdrawal of Proposed Amend to License NPF-47,allowing One Loop of RHR to Be Used for ECCS & for Shutdown Cooling. Util Resubmittal of Proposed Amend Following Completion of Generic Study Recommended ML20058L5361990-08-0101 August 1990 Forwards Electrical Distribution Sys Functional Insp Rept 50-458/90-200 on 900521-0622 & Notice of Violation ML20055G5241990-07-18018 July 1990 Forwards Fr Notice Re Util Withdrawal of 900202 Amend to License NPF-47,per .Amend Modifies Tech Specs Re Div I & II Diesel Generator Crankshaft Insp Scheduling & Surveillance Requirements IR 05000458/19900411990-07-0505 July 1990 Ack Receipt of 900614 & 0209 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-458/90-41 ML20055D5211990-06-27027 June 1990 Forwards Insp Rept 50-458/90-14 on 900521-22.One self-identified Violation Noted But Not Cited ML20055F1861990-06-27027 June 1990 Forwards Safety Evaluation Accepting Util Proposed Changes Re Scram Accumulator Check Valves ML20055D0981990-06-25025 June 1990 Reviews Util 900406 Response to Violation Noted in Investigation Rept 50-458/90-43 Re Unescorted Access for Two Welding Svcs,Inc Employees to Plant Protected Area. Violation Properly Classified as Severity Level IV ML20055D6581990-06-20020 June 1990 Ack Receipt of 900531 & s Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-458/89-31 ML20059M9441990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055D0021990-06-11011 June 1990 Discusses Util 900514 Application for Amend to License NPF-47,increasing Suppression Pool Temp from 95 F to 100 F. Requests That Util Demonstrate Applicability of Items Addressed in Encl Hatch Safety Evaluation to Facility ML20055C3071990-02-23023 February 1990 Advises That 891027 Changes to Emergency Plan,Acceptable ML20248A3051989-09-26026 September 1989 Forwards Insp Rept 50-458/89-33 on 890801-31.No Violations or Deviations Noted ML20247Q7221989-09-22022 September 1989 Forwards FEMA Exercise Evaluation Rept of Plant Emergency Preparedness Exercise on 890301.No Deficiencies Observed During Exercise.W/O Encl ML20248E5681989-09-21021 September 1989 Forwards Amend 3 to Indemnity Agreement B-104,reflecting Increase in Primary Layer of Nuclear Energy Liability Insurance ML20247P4951989-09-19019 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-458/89-28 IR 05000458/19890181989-09-11011 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-458/89-18 ML20247D4661989-09-11011 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-458/89-27. Understands That Comparison of Expanded Unreviewed Safety Question Committee Data Base Will Be Reviewed by Committee ML20247B0381989-09-0101 September 1989 Forwards Insp Rept 50-458/89-31 on 890701-31 & Notice of Violation ML20247C3081989-09-0101 September 1989 Summarizes 890822 Meeting W/Util in Region IV Ofc to Discuss Results of INPO Evaluation of Facility.List of Attendees Encl ML20247A1241989-08-30030 August 1989 Forwards Summary of Region Iv/Senior Util Executive Meeting on 890818.No plant-specific Issues Discussed at Meeting. Agenda & Attendees List Also Encl ML20247A6751989-08-28028 August 1989 Advises That 890424 Rev 3 to ODCM Acceptable,Per Encl Eg&G Idaho,Inc Comments.Remaining Questions Re Rev 3 in Encl Should Be Considered in Next Rev ML20246J0751989-08-21021 August 1989 Forwards Insp Rept 50-458/89-30 on 890619-23.Violation Noted ML20245H6631989-08-0707 August 1989 Forwards Insp Rept 50-458/89-32 on 890717-21.No Violations or Deviations Noted ML20245K0101989-08-0606 August 1989 Forwards Summary of 890727 Meeting W/Licensee in Region IV Ofc Re Plant Security Enhancement Program & Personnel Changes ML20247N7601989-07-31031 July 1989 Informs That 890719 Request for Withdrawal of Proposed Tech Specs 3.5.2,3.7.1.1,3.7.1.2 & 3.9.11.1 Changes,Submitted by Ltr W/Other Proposed Changes,Approved.No Addl Work Will Be Performed by NRC ML20247R2641989-07-28028 July 1989 Forwards Insp Rept 50-458/89-28 on 890601-30 & Notice of Violation.Notice of Violation Will Not Be Issued for Item Identified by Licensee ML20247M2581989-07-27027 July 1989 Forwards Insp Rept 50-458/89-25 on 890710-14.No Violations or Deviations Noted ML20247H4611989-07-26026 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp 50-458/89-11 1990-08-09
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217L7681999-10-19019 October 1999 Forwards Insp Rept 50-458/99-12 on 990822-1002.Four Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217J3751999-10-15015 October 1999 Informs That Applicable Portions of NEDC-32778P, Safety Analysis Rept for River Bend 5% Power Uprate, Marked as Proprietary Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) IR 05000458/19990071999-10-0505 October 1999 Refers to Util Ltr Re Apparent Violations Described in Insp Rept 50-458/99-07 Issued on 990804 & Forwards Nov.Insp Described Two Apparent Violations Related to River Bend Station Division I EDG ML20212D8901999-09-16016 September 1999 Discusses 6 Month Review of Plant Midcycle Ppr.Advises of Plans for Future Insp Activities.Forwards Historical Listing of Plant Issues,Referred to as PIM ML20216F7881999-09-15015 September 1999 Forwards Insp Rept 50-458/99-10 on 990830-990903.No Violations Noted.Insp Covered Licensed Operators Requalification Training Program & Observation of Requalification Activities ML20211Q7721999-09-0909 September 1999 Expresses Appreciation for ,In Response to NRC 990702 Re Denial of Notice of Violation Cited in Concerning Insp Rept 50-458/98-16.Reply Found to Be Responsive to Concerns Raised in NOV ML20211Q3921999-09-0808 September 1999 Forwards Insp Rept 50-458/99-08 on 990711-0821.One Violation Being Treated as Noncited Violation ML20211Q5541999-09-0808 September 1999 Discusses Meeting Conducted on 990830 in St Francisville,La Re Overall Performance Issues During 990403-0703 Refueling/ Maintenance Outage.Due to Proprietary Nature of Some Subject Matters,Meeting Closed to Public.Attendance List Encl ML20211E2071999-08-23023 August 1999 Discusses Insp Rept 50-458/99-07 in Which 2 Violations Were Identified & Being Considered for Escalated Enforcement Action.Response Should Be Submitted Under Oath or Affirmation ML20211A9291999-08-17017 August 1999 Forwards Insp Rept 50-458/99-11 on 990719-23.Areas Examined Included Portions of Licensee Physical Security Program. No Violations Noted ML20210T8881999-08-16016 August 1999 Forwards Replacement Pages 9-18 for Insp Rept 50-458/99-09, Issued on 990730 IR 05000458/19980101999-08-13013 August 1999 Forwards Summary of 990805 Mgt Meeting with Licensee in Arlington,Tx Re Radiological Control Problems Noted in Insp Repts 50-458/98-10 & 50-458/99-04.With Attendance List & Licensee Presentation 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 ML20210U3751999-08-12012 August 1999 Informs That Info Contained in Presentation, River Bend Station Fuel Recovery Project,Dtd 990622, Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20210Q7691999-08-11011 August 1999 Forwards Request for Addl Info Re Licensee River Bend Individual Plant Exam External Events,Under GL 88-20,suppl 4,dtd 910628 ML20210R4591999-08-10010 August 1999 Ack Receipt of Which Transmitted Plant Emergency Plan,Rev 20 Under Provisions of 10CFR50,App E,Section V.Nrc Approval Not Required,Based on Determination That Changes Does Not Decrease Effectiveness of EP ML20210N1641999-08-0404 August 1999 Forwards Insp Rept 50-458/99-07 on 990530-0710.One Violation of NRC Requirements Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20210K4641999-08-0303 August 1999 Forwards SE Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Power-Operated Gate Valves, Issued on 950817 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 ML20210K1351999-07-30030 July 1999 Forwards Insp Rept 50-458/99-09 on 990510-28 with in-office Insp Until 990701.Three Violations Being Treated as Noncited Violations ML20210J9691999-07-30030 July 1999 Discusses 990719 Meeting with Util in Arlington,Tx Re Region IV Staff Findings of Root Cause Investigation Into Fuel Cladding Failures That Occurred During Recent Cycle 8 Operation.List of Attendees & Organization Chart Encl ML20210E9001999-07-23023 July 1999 Informs That as Result of Staff Review of Licensee 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 ML20196L0501999-07-0606 July 1999 Informs That NRC Insp Rept 50-458/99-03 Issued on 990519 with Errors in Tracking Numbers Assigned to Seven Noncited Violations & Error Re Actual Location of SRO During Refueling Activities.Revised Pages 2 & 4 Encl ML20196K6851999-06-30030 June 1999 Ack Receipt of & Denial of NOV in Response to Transmitting NOV & Insp Rept 50-458/98-16.Listed Info Documents Results of Review of Response to Violation Re fire-induced Circuit Faults ML20196K0671999-06-30030 June 1999 Forwards Insp Rept 50-458/99-04 on 990412-16 & 28-29.Five Violations of NRC Requirements Occurred & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy.Meeting Scheduled for 990726 ML20196E0601999-06-18018 June 1999 Forwards Insp Rept 50-458/99-05 on 990418-29.Four Violations Identified & Being Treated as Noncited Violations ML20195G3121999-06-0909 June 1999 Ack Receipt of Re Changes to River Bend Station Emergency Plan,Rev 19.No Violations of 10CFR50.47(b) Were Identified ML20195G3671999-06-0909 June 1999 Ack Receipt of Ltr Dtd 981016,which Transmitted River Bend Station Emergency Plan,Rev 18 Under Provision of 10CFR50, App E,Section V.No Violations of 10CFR50.54(q) Identified During Review ML20195D6041999-06-0303 June 1999 Discusses EOI Request That Attachment 4,NEDC-32549P, Safety Review for River Bend Station Cycle 7 Final Feedwater Temp Reduction, Rev 0,be Withheld from Public Disclosure. Determined Info Proprietary & Will Be Withheld DD-99-08, Informs That to Extent That Union of Concerned Scientists Requests Commission Undertake Formal Review of DD-99-08 & Hold Meeting to Directly Receive View on Decision,Request Denied.With Certificate of Svc.Served on 9905211999-05-20020 May 1999 Informs That to Extent That Union of Concerned Scientists Requests Commission Undertake Formal Review of DD-99-08 & Hold Meeting to Directly Receive View on Decision,Request Denied.With Certificate of Svc.Served on 990521 ML20206U4321999-05-18018 May 1999 Forwards Notice of Withdrawal of Licensee 961106 Request for Approval of Deviation from Approved Fire Protection Program to Extent Program Incorporated Technical Requirements of Section III.G.2 of App R to 10CFR50 ML20206U6081999-05-18018 May 1999 Forwards Insp Rept 50-458/99-03 on 990307-0417.Eight Violations of NRC Requirements Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20207A8051999-05-15015 May 1999 Forwards Insp Rept 50-458/99-06 on 990419-23.No Violations Noted.Inservice Insp Activities at River Bend Station Were Being Implemented in Accordance with ASME Code & Regulatory Requirements ML20206N7081999-05-12012 May 1999 Informs That NRC Ofc of NRR Reorganized,Effective 990328. Reorganization Chart Encl ML20206N8811999-05-12012 May 1999 Forwards Notice of Withdrawal of 981120 Amend Request for License NPF-47.Proposed Amend Would Have Established New TS 3.10.9, Control Rod Pattern - Cycle 8, Added to Section 3.10, Special Operations ML20206H9191999-05-0707 May 1999 Informs That on 990407,NRC Administered Generic Fundamentals Exam Section of Written Operators Licensing Exam.Facility Did Not Participate in Exam,However Copy of Master Exam with Key Encl.Without Encl NUREG-1434, Discusses Licensee 960418 Request for Amend for Plant That Would Permit Addl Method of Fuel Movement & Loading in Core Upon Removal of Control Rods from Defueled Core Cells.Nei TSs Task Force Process Will Be Used to Review TSTF-2261999-05-0505 May 1999 Discusses Licensee 960418 Request for Amend for Plant That Would Permit Addl Method of Fuel Movement & Loading in Core Upon Removal of Control Rods from Defueled Core Cells.Nei TSs Task Force Process Will Be Used to Review TSTF-226 ML20206J2291999-05-0303 May 1999 Discusses Responding to NOV Issued on 990105.NOV Was Based on NRC Conclusions That Licensee Provided NRC Inspector with Info Licensee Knew Was Inaccurate & Incomplete ML20206E6381999-05-0303 May 1999 Ack Receipt of 990305,990315 & s Responding to NOV & Proposed Imposition of Civil Penalty, .EOI Paid Civil Penalty & Requested Withdrawal of NOV & Civil Penalty for Reasons Stated.Finds NOV & Civil Penalty Appropriate ML20206E4531999-04-27027 April 1999 Discusses Request That Attachment 4, Final Calculation of RBS Cycle 9 SLMCPR (Safety Limit for Mcpr), Submitted with 981216 License Amend Request,Be Withheld from Public Disclosure.Determined Info Proprietary & Will Be Withheld ML20206A2031999-04-21021 April 1999 Discusses EOI Second 10-year IST Program for River Bend Station Submitted on 980106 & 980910 Which Included One Pump Relief Request & Two Valve Relief Requests.Forwards SE Authorizing Pump Relief Request & One Valve Relief Request ML20205N7251999-04-13013 April 1999 Forwards Summary of 990408 Meeting with EOI in Jackson, Mississippi Re EOI Annual Performance Assessment of Facilities & Other Issues of Mutual Interest.List of Meeting Attendees & Licensee Presentation Slides Encl ML20205J5331999-04-0606 April 1999 Ack Receipt of Denying Request from NRC That Addl Info Be Provided Prior to Informal Public Hearing Held on 990222 Re River Bend Station & Perry Nuclear Power Plant 10CFR2.206 Petitions ML20205K0681999-04-0505 April 1999 Submits Summary of 990325 Meeting Re Engineering Performance at Site & Assessment of Organization Strengths & Opportunities for Improvement.List of Attendees & Matl Used in Presentation Enclosed ML20205A4531999-03-26026 March 1999 Forwards Insp Rept 50-458/98-10 on 990222-26.Violation Noted & Being Treated as Non-Cited Violation.Concludes That Radiation Work Permit Program Poorly Implemented Until July 1998 Because of Inadequate Program Implementing Procedures ML20205D7691999-03-26026 March 1999 Forwards Insp Rept 50-458/99-02 on 990124-0306.One Violation Identified & Being Treated as non-cited Violation.Licensee Conduct of Activities During Insp Generally Characterized by safety-conscious Operations & Sound Engineering ML20205D5361999-03-26026 March 1999 Forwards Ser,Accepting Util 980107 Request for Alternative to Augmented Reactor Pressure Vessel Exam Requirements for Plant,Unit 1 Pursuant to 10CFR50.55a(g)(6)(ii)(A) for First 10-year Insp Interval.Technical Ltr Rept Also Encl ML20204G8081999-03-24024 March 1999 Refers to 990303 Reply to NRC NOV & Proposed Imposition of Civil Penalty .Since Licensee Paid Civil Penalty & C/A Found Responsive to NRC Concerns,Matter Considered Closed ML20205A4021999-03-23023 March 1999 Forwards Insp Rept 50-458/99-301 on 990222-0303.No Violations Noted.Insp Included Evaluation of Three Applicants for Senior Operator Upgrade & for Senior Operator Instant & Eight Applicants for Reactor Operator License ML20205F3131999-03-19019 March 1999 Advises of Planned Insp Effort Resulting from River Bend PPR Review,Which Was Completed on 990211.Performance of River Bend Staff During Assessment Period Was Acceptable 1999-09-09
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In Reply Refer To:
b , Docket: 50-458/89-18 9 .,,
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Gulf States Utilities
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~ ATTN: Mr. James C. Deddens SeniorVicePresident(RBNG)
, P.O. Box 220 St.,Francisville, Louisiana 70775 Gentlemen:
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Thank you for your letter of August 21, 1989, in response to our letter and Notice of Violation dated July 21, 1989. We have reviewed your reply and find it responsive to the concerns raised in our Notice of Violation. We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintaine
Sincerely, Original Soned By:
Thomas P. Gwynn
' James L. M11hoan, Director Division of Reactor Projects o cc:
Gulf States Utilities ATTN: J. E. Booker, Manager-
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River Bend Oversight P.O. Box 2951 7 Beaumont, Texas 77704 Gulf States Utilities
ATTN: Les England, Director -
Nuclear Licensing - RBNG e ~ P.O. Box'220:
,J8 . St. Francisv111e, Louisiana 70775
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August 21, 1989 RBG- 31384 File Nos. G9.5, G15. ~ . .
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gggg4jggg Gentlemen: , Ih River Bend Station - Unit 1 Refer to: Region IV Docket No. 50-458/89-18
- Pursuant to 10CFR2.201, this letter provides Gulf States Utilities Company's (GSU) response to the Notice of Violation for NRC Inspection Report No. 50-458/89-18. The inspection was performed by Messrs. C. Stewart, L. E. Ellershaw and W. B. Jones during the periods of Mt .t 1-5 and 15-19, 1989 of activities authorized by NRC Operating License NPF-47 for River Bend Station -
Unit GSU's response to the violation is provided in Attachment 1. GSU's response to the concerns addressed in the body of the letter is provided in Attachment GSU's response to the rotice of violation is complet Should you have any questions, please contact Mr. L. A. England at (504) 381-414
Sincerely,
, p J. E. Booker Manager-River Bend Oversight River Bend Nuclear Group JEB/LAE/RJK/MSF/RGW/AJK/ch Attachments cc: U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Senior Resident Inspector P.O. Box 1051 St. Francisville, LA 70775
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION STATE OF LOUISIANA )
PARISH OF WEST FELICIANA )
Docket No. 50--458 In the Matter of )
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GULF STATES UTILITIES COMPANY )
(River Bend Station - Unit 1)
AFFIDAVIT
, E. Booker, being duly sworn, states that he is Manager-River Bend Oversight for Gulf States Utilities Company; that he is authorized on the part of said company to l
sign and file with the Nuclear Regulatory Commission the documents attached hereto; that he has read all of the statements contained in such documents attached thereto and i made a part thereof; and that all such statements made and j' matters set forth therein are true and correct to the best of his knowledge, information and belief.
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[J . Booker Subscribed and sworn to before me, a Notary Public in and for the State and Parish above named, this J/ day of h>l d , .< 6( , 1929 . My Commission expires with Lif [
0}Clu dALS NtAME Notary Public in and for West Feliciana Parish, Louisiana
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ATTACMENT 1 RESPONSE TO NOTICE OF VIOLATION 50-458/8918-01 LEVEL III
- REFERENCES-Inspection _ Report 89-18 - Letter from J. L. Milhoan to J. Deddens, dated June 6, 198 Meeting Summary of Enforcement Conference held June 6, 1989 - Letter from L. Milhoan to J. C. Deddens, dated June 22, 198 Notice of Violation - Letter from J. D. Martin to J. C. Deddens, dated July 21, 198 FAILURE TO ESTABLISH A TEST PROGRAM Criterion VI of Appendix B to 10CFR50 requires, in part, that a test program shall be established to assure that all testing required to demonstrate .that structures, systems and components will perform satisfactorily in service is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable design document Contrary to the above, in November 1988 it was identified that Gulf $tates Utilities (G5U) had failed to establish a test program at River Bend Station to assure that all testing required to demonstrate that structures, systems and components will perform satisfactorily in service is identified and performe Specifically, GSU failed to establish a test program to demor. strate that two independent fuel building ventilation charcoal filtration subsystems and two independent main control room air handling unit / filter train subsystems would perform satisfactorily in service. As a result, GSU failed to discover design and installation flaws that would. have prevented these subsystems from operating as intended under certain design condition REASON FOR THE VIOLATION Gulf States Utilities Company's (GSU) performed a detailed review to determine the cause 01 the subject violation. During the start-up test program each system or subsystem was considered to be a separate entit This cause was determined to be GSU's failure to adequately test the interface between the instrument air and HVAC systems which is considered to be an isolated inciden GSU considered interconnected instrument ' air systems operable based on each system or subsystem test and did not realize the need for simultaneous testin The control building and auxiliary building heating, venting and air conditioning (HVAC) systems were released for start-up testing prior to the release of the instrument air system. The need for pressure decay testing of the auxiliary, control atid fuel building's instrument air accumulators was Page 1 of 4 L . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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not recognized during initial plant start-up. The ASKE Section XI valve testing program was thought to provide an adequate indication of system operabilit Neither Technical Specifications nor the ASME XI code requires simultaneous interacting system performance start-up testing. GSU did not interpret Criteria XI of Appendix B to 10CFR Part 50 to require testing of interacting systtms in addition to performance testing of structures, systems and component The initial design was inadequate and testing of the instrument air system would have discovered the problem as GSU discovered in subsequent testin However, the RBS current design modification process requires functional tests such that operability of a system can be assured prior to its return to servic GSU initiated a self assessment of the River Bend Station instrument air system by performing a Safety System Functional Inspection (SSFI) during the fall of 1988. During the inspection a question was raised on the instrument air system accumulator supply capacity for post-accident condition Subseque.a testing was performed during refueling outage 2 which showed that the accumulator air supply was not sufficient for the areas identifie Further investigation identified that solenoid valves had been installed in reverse which did not allow the valves to seal in the correct positio RBS submitted Licensee Event Report (LER) No.89-022. Other aspects relating to the instrument air system were addressed in the LER and GSU's response to Generic Letter 88-14. GSU's response to the notice of violation will focus on the area of testin CORRECTIVE ACTIONS WHICH HAVE BEEN TAKEN AND THE RESULTS ACHIEVED Design Engineering conducted a review of loads which are dependent upon the safety-related headers within the control, auxiliary, and fuel buildings. This study consisted of a review of the two safety related headers within each of these three buildings. As a result of this study: The control building chilled water pressure differential control valves were modified as described in Section C.I.a belo . Five nonsafety-related loads have been removed from the two instrument air headers within the control buildin . Two standby gas treatment and two auxiliary building HVAC outlet air operated dampers within the auxiliary building will be modifie The first design verification testing included the testing of one of the two instrument air headers within the control building to verify that each header would stay pressurized for the calculated two days upc1 loss of the instrument air compressor The results of the first control building header pressure retertion test revealed the volume of the associated accumulator to be significantly undersized and the following design changes and repairs were then implemented:
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~ Control Building: The major instrument air users, the control building chilled water pressure differential control valves, were modified to remain mechanically secured in a throttled position instead of remaining as air operated control valves, The pressure retention time of each of the two safety-related headers was increased through the 180 degree realignment of the inlet header solenoid operated valves (50V) to an orientation which seated the valves in the correct position to keep air in
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the accumulato , The inlet check valve of each of the two safety-related headers received seat relapping and spring change-ou . Auxiliary Building: The pressure retention time of each of the two safety-related headers was increased through the 180 degree realignment of the inlet header S0Vs to an orientation which seated the valves in the correct position to keep air in the accumulato . Fuel Building: The pressure retention time of each of the two safety-related headers was increased through the 180 degree realignment of the inlet header 50Vs to an orientation which seated the valves in the correct position to keep air in the accumulato The damper fail positions of four dampers were changed to " fail open" from " fail closed", thereby resulting in instrument air not being required within the fuel building to mitigate the release of radioactivity after an acciden D. The final design verification testing included the testing of the two safety related headers of the control building and the two safety related headers of the auxiliary building to verify that each header remained pressurized to assure the respective HVAC systems would perform their design basis functions following an acciden . Control Building: Each of the two safety related accumulators, along with its associated header, was tested for pressure retention time upon the failure of the instrument air compressor Each safety related header was found to remain pressurized for an adequate time period to assure the control building atmosphere would remain habitable after an accident only when an auxiliary compressed air source is also connected to each heade Page 3 of 4
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~ Auxiliary Building: Ecch of the two safety related accumulators, alcng with its i associated header, were tested for pressure retention time upon the failure of the instrument air compressors. Each header was found to remain pressur4 zed for an adequate time period to assure the auxiliary, containment, and drywell building HVAC systems would perform their design basis functions following an accident only when an auxiliary compressed air source is connected to each heade The control bailding and auxiliary building safety related accumulator pressure retention times were then increased through the following design modifications: Control Building:
Each of the two accumulators' capacities van ir.creas?d through the installation of two banks of high pre:sure air bottles at each accumulator inle . Auxiliary Building:
Each of the two accumulators' capacities was increased through the installation of two banks of high pressure air bottles at each accumulator inlet. These bottles are subject to removal upon the installation of the backdraft damper CORRECTIVE ACTIONS WHICH WILL BE TAKEN TO AVOID FURTHER VIOLATIONS A-. The two standby gas treatment and two auxiliary butiding HVAC outlet air operated dampers wili be replaced by self-actuating back draft dampers thereby eliminating the need for safety related instrument ai Field Engineering is establishing a control building safety-related accumulator air retention test to be performed every refueling outag C.. In addition, GSU will review the testing methods, the bases for ASME categorization and the leak rate criterion for check valve DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED The River Bend Station instrument air system is currently in full complianc The current system configuration is adequate and the follcwing are enhancements to increase system performance and reliabilit The back draft dampers will be installed in the standby gas treatment and HVAC system prior to start-up fcllowing the third refueling outag The control building accumulator air retention test procedure will be developed by November 15, 198 The review of testing methods, the bases for ASME categorization and the leak rate criterion for check v61ves will be completed prior to start-up following the third refueling outag Page 4 of 4
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ATTACIMENT 2 As discussed in your letter dated July 21, 1989 transmitting Notice of Violation 8918-01, GSU is providing its response concerning your questions about deportability and operability of the instrument air system at River Bend Station. The reporting requirements contained in 10CFR Parts 50.72 a .73 and GSU's reporting evaluation process via the condition report procedure (ADM-0019), will be emphasized in required training for engineering department personnel. Operability of systems or components with questionable characteristics, as identified on condition reports, will be documented in greater detail in the disposition of the condition report justifying continued operatio Determination of the extent of the nonconforming conditions will be an important element in resolution of the reported conditio Page 1 of I
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