SER Re Util Development of Systematic & Thorough Troubleshooting Plans to Investigate 850609 Incident Leaving Redundant source-range Nuclear Instrumentation Channels Inoperable.Restart & Power Operation Now AcceptableML20136B784 |
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Davis Besse ![Cleveland Electric icon.png](/w/images/7/78/Cleveland_Electric_icon.png) |
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Issue date: |
12/24/1985 |
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From: |
NRC |
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To: |
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Shared Package |
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ML20136B780 |
List: |
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References |
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NUDOCS 8601020915 |
Download: ML20136B784 (7) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20211B0271999-08-13013 August 1999 SER Accepting Second 10-year Interval Inservice Insp Requests for Relief RR-A16,RR-A17 & RR-B9 for Plant, Unit 1 ML20195K2871999-06-16016 June 1999 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20199H5931999-01-20020 January 1999 Safety Evaluation Accepting Thermo-Lag Re Ampacity Derating Issues for Plant ML20155B6781998-10-28028 October 1998 Safety Evaluation Accepting Proposed Reduction in Commitment Changes in QA Program Matl Receipt Insp Process ML20236R1441998-07-15015 July 1998 SER Related to Quality Assurance Program Description Changes for Davis-Besse Nuclear Power Station,Unit 1 ML20236K3981998-06-30030 June 1998 SER Accepting in Part & Denying in Part Relief Requests from Some of ASME Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Davis-Besse Nuclear Power Station,Unit 1 ML20236K5131998-06-29029 June 1998 Safety Evaluation Accepting Proposed Alternate Emergency Operations Facility Location for Davis-Besse Nuclear Power Station,Unit 1 ML20198R4771998-01-13013 January 1998 SER Approving Second 10-year Interval Inservice Inspection Program Plan Requests for Relief for Davis-Besse Nuclear Power Station,Unit 1 ML20128L3001996-10-0202 October 1996 SER Supporting Dbnp IPE Process of Identifying Most Likely Severe Accidents & Severe Accident Vulnerabilities ML20058M9591993-09-28028 September 1993 SE Accepting Licensee Response to GL 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants.' ML20057A3791993-08-20020 August 1993 SE Concluding That Second 10-yr Interval Inservice Insp Program Plan for Plant Has Unacceptable Exam Sample as Discussed in Encl Inel TER ML20056G4301993-08-18018 August 1993 Safety Evaluation Re Inservice Testing Program Requests for Relief.Licensee Made Changes to Subj Program to Include Exercising & fail-safe Testing of Auxiliary Feedwater Valves AF-6451 & AF-6452,in Response to TER Anomaly 8 ML20056B2721990-08-20020 August 1990 Safety Evaluation Granting Relief from ASME Code Repair Requirements for ASME Code 3 Piping ML20248D8271989-09-29029 September 1989 Safety Evaluation Accepting Util 890228 & 0630 Submittals Presenting Proposed Designs to Comply w/10CFR50.62 ATWS Rule Requirements ML20247E6901989-09-0505 September 1989 Safety Evaluation of Audit of Facility Design for Resolution of IE Bulletin 79-27 Re Loss of non-Class IE Instrumentation & Control Power Sys Bus During Operation.Preventive Maint & Testing Program Should Be Developed for Bus Power Sources ML20247J8731989-05-18018 May 1989 Safety Evaluation Supporting Amend 133 to License NPF-3 NUREG-0660, Safety Evaluation Accepting Util 840301 & 870420 Responses to NUREG-0737,Item 1.C.1,except Where Noted in Section 21989-05-0303 May 1989 Safety Evaluation Accepting Util 840301 & 870420 Responses to NUREG-0737,Item 1.C.1,except Where Noted in Section 2 ML20196D9601988-12-0808 December 1988 Safety Evaluation Re Util Response Concerning Auxiliary Feedwater Sys Reliability Study.Util Should Ensure That Sys Mods Do Not Result in Net Reduction in Sys Reliability ML20207K7911988-10-0404 October 1988 Safety Evaluation Supporting Operation in Cycle 6 W/O Removing Flaws in Cracked HPI Nozzle ML20148D0391988-01-19019 January 1988 SER Accepting Util 831209 Response to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip reliability-on-line Testing.Unit Designed to Permit on-line Functional Testing of Diverse Trip Features of Reactor Trip Breakers ML20147C2631988-01-12012 January 1988 Safety Evaluation Accepting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Equipment Classification of Reactor Trip Sys Components ML20149F9621988-01-11011 January 1988 SER Accepting License Response to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for safety- Related Components ML20236U6531987-11-27027 November 1987 Safety Evaluation Re Effects of Errors in Util Analysis of Small Break Loca.Use of Incorrect Values in Analysis Results in Incomplete Compliance w/10CFR50,App K.Plant Poses No Risk to Public Health Due to Meeting 10CFR50.46 Requirements ML20236T3871987-11-25025 November 1987 SER Re Conformance to Reg Guide 1.97 Concerning post-accident Monitoring Instrumentation.Design Acceptable ML20211G8641987-02-11011 February 1987 Safety Evaluation Supporting Licensee Responses to Generic Ltr 83-28,Item 3.2.3, Post-Maint Testing & All Other Safety-Related Components ML20207Q6711987-01-0909 January 1987 Safety Evaluation Supporting Util Re Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events ML20212C9231986-08-0404 August 1986 Sser Supporting Util Reanalyses of 74 Masonry Walls ML20212G6021986-08-0404 August 1986 Safety Evaluation Accepting Util Response to NRC Request for Addl Info Re Question 29 Concerning Training for Infrequent, Critical & Difficult Tasks ML20212R3421986-06-10010 June 1986 SER Re Progress Made by Licensee in Area of Plant Maint.New Maint Organization Functioning W/No Major Weaknesses.Region III Will Continue to Monitor Maint at Plant to Assure Continued Control & Progress ML20206F3041986-05-27027 May 1986 Safety Evaluation Accepting Util Review Re Cold Pressurization of Secondary Side of Steam Generator During Testing on 850906 ML20203N9141986-04-17017 April 1986 Safety Evaluation Accepting Proposed Mods to Safety Actuation Sys Re Shared Power Supply Returns as Result of 801205 Actuation NUREG-0103, Safety Evaluation Supporting Relief from Inservice Insp Requirements of ASME Boiler & Pressure Vessel Code Requiring Quarterly Stroke Testing of RCS Valves & Denying Relief from Code Requirements for Valve RC-11 Testing1986-03-0606 March 1986 Safety Evaluation Supporting Relief from Inservice Insp Requirements of ASME Boiler & Pressure Vessel Code Requiring Quarterly Stroke Testing of RCS Valves & Denying Relief from Code Requirements for Valve RC-11 Testing ML20137J6891986-01-0808 January 1986 Safety Evaluation Supporting Util Identification of Root Causes for Spurious 850609 Steam & Feedwater Line Rupture Control Sys Low Level Actuation,Closure of MSIVs & Actions Taken to Prevent Recurrence.Plant Restart Acceptable ML20137J7031986-01-0808 January 1986 SER Supporting Util Identification of Root Causes for Source Range Nuclear Instrumentation Channels Inoperability During 850609 Steam & Feedwater Line Rupture Control Sys Low Level Actuation & Corrective Actions Taken.Plant Restart Approved ML20136B7841985-12-24024 December 1985 SER Re Util Development of Systematic & Thorough Troubleshooting Plans to Investigate 850609 Incident Leaving Redundant source-range Nuclear Instrumentation Channels Inoperable.Restart & Power Operation Now Acceptable ML20137R1611985-11-12012 November 1985 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Items 4.2.1 & 4.2.2 Re Preventive Maint & Trending of Parameters ML20138P0681985-10-30030 October 1985 Safety Evaluation Accepting Licensee 831107 & 850709 Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,4.1 & 4.5.1 Re post-maint Testing & Reactor Trip Sys Reliability (vendor-related Mods & Sys Functional Test Description) ML20138P6391985-10-30030 October 1985 SER Re Proposed Mods to Maint Program.Licensee Should Identify Actions to Be Completed Prior to or After Restart. Region Should Actively Monitor Licensee Progress ML20133Q0441985-10-24024 October 1985 Safety Evaluation Supporting Util 831107 Response to Generic Ltr 83-28,Item 3.1.3 Re post-maint Testing (Reactor Trip Sys Components).Eg&G Technical Evaluation Rept Encl ML20062E0871982-07-29029 July 1982 Safety Evaluation Supporting Licensee Request for Relief from ASME Boiler & Pressure Vessel Code Section XI Hydrostatic Test (Insp) Requirements ML20214J2801979-12-20020 December 1979 Safety Evaluation Re Preliminary Design for Upgrading Present control-grade Anticipatory Reactor Trip Sys for Loss of Main Feedwater & Turbine Trip to safety-grade ML20125B1331968-12-16016 December 1968 Safety Evaluation Re Piqua Nuclear Power Facility Retirement.T Hamrick to J Schlesinger Encl 1999-08-13
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & Pnpp QA Program ML20217D5441999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Davis-Besse Nuclear Power Station.With ML20211R0811999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20211B0271999-08-13013 August 1999 SER Accepting Second 10-year Interval Inservice Insp Requests for Relief RR-A16,RR-A17 & RR-B9 for Plant, Unit 1 ML20210Q8541999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20209E6231999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20195K2871999-06-16016 June 1999 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20195F4871999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20207E8011999-05-19019 May 1999 Non-proprietary Rev 2 to HI-981933, Design & Licensing Rept DBNPS Unit 1 Cask Pit Rack Installation Project ML20207F4351999-05-0404 May 1999 Rev 1 to DBNPS Emergency Preparedness Evaluated Exercise Manual 990504 ML20206M6341999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Davis-Besse Nuclear Station,Unit 1.With ML20205M2931999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Davis-Besse Nuclear Power Station.With ML20207J1461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20199H5931999-01-20020 January 1999 Safety Evaluation Accepting Thermo-Lag Re Ampacity Derating Issues for Plant ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20199E2501998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20206B0101998-12-31031 December 1998 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl ML20205K5781998-12-31031 December 1998 Waterhammer Phenomena in Containment Air Cooler Swss ML20197J3441998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20195D0001998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20155B6781998-10-28028 October 1998 Safety Evaluation Accepting Proposed Reduction in Commitment Changes in QA Program Matl Receipt Insp Process ML20154H5801998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20151W1611998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Dbnps.With ML20237E3171998-08-21021 August 1998 ISI Summary Rept of Eleventh Refueling Outage Activities for Davis-Besse Nuclear Power Station ML20237B1681998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20236U5011998-07-23023 July 1998 Special Rept:On 980624,Unit 1 Site Damaged by Tornado & High Winds.Alert Declared by DBNPS Staff,Dbnps Emergency Response Facilities Activiated & Special Insp Team Deployed to Site by Nrc,As Result of Event ML20236R1441998-07-15015 July 1998 SER Related to Quality Assurance Program Description Changes for Davis-Besse Nuclear Power Station,Unit 1 ML20236N7451998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20236K3981998-06-30030 June 1998 SER Accepting in Part & Denying in Part Relief Requests from Some of ASME Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Davis-Besse Nuclear Power Station,Unit 1 ML20236K5131998-06-29029 June 1998 Safety Evaluation Accepting Proposed Alternate Emergency Operations Facility Location for Davis-Besse Nuclear Power Station,Unit 1 ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A4121998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20196B5221998-05-23023 May 1998 10CFR50.59 Summary Rept of Facility Changes,Tests & Experiments Dbnps,Unit 1 for 960602-980523 ML20236E7581998-05-19019 May 1998 Rev 0 to Davis-Besse Unit 1 Cycle 12 Colr ML20236N7501998-04-30030 April 1998 Rev 2 to Monthly Operating Rept for Apr 1998 for Davis-Besse Nuclear Power Station,Unit ML20247F6721998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Davis-Bess Nuclear Power Station,Unit 1 ML20249A4141998-04-30030 April 1998 Revised Monthly Operating Rept for Apr 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20217P8041998-04-0707 April 1998 11RFO OTSG ECT Insp Scope ML20216B4041998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20216C5131998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20202D3721998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20199G6321998-01-26026 January 1998 Rev 1 to Davis-Besse Unit 1,Cycle 11,COLR ML20198R4771998-01-13013 January 1998 SER Approving Second 10-year Interval Inservice Inspection Program Plan Requests for Relief for Davis-Besse Nuclear Power Station,Unit 1 ML20198K7931997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Davis-Besse Nuclear Power Station,Unit 1 ML20217K6401997-12-31031 December 1997 1997 Annual Rept First Energy ML20203A3931997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Davis-Besse Nuclear Power Plant,Unit 1 ML20198S5371997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Davis-Besse Nuclear Power Station ML20217H7701997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Davis-Besse Nuclear Power Station,Unit 1 ML20216H3261997-08-31031 August 1997 Monthly Operating Rept for August 1997 for DBNPS ML20217K0241997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Davis Besse Nuclear Power Station,Unit 1 1999-09-30
[Table view] |
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3 SAFETY EVALUATION REPORT DAVIS-BESSE INCIDENT OF JUNE 9,1985
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TROUBLESH00 TING REPORTS ON SOURCE RANGE NUCLEAR INSTRUMENTS INTRODUCTION Source range nuclear instrument channel NI-1 (referred to also as Channel 2) wasinoperablepriortoandthrouggouttheJune9,1985 incident,inthatit
- read full downscale (less than 10 counts /sec.). During the event when the I neutron level, as indicated by the intermediate range nuclear channels, fell to a
! predetermined level, the source range nuclear channels were activated. However, remained at less than theredundant-NI-2(referredtoalsoasChannelg) 10-y counts /sec. rather than indicating about 10 counts /sec. This loss of both i nuclear channels was an unnecessary problem that to the already-busy reactor
- operator had to cope with. He was required to verify shutdown margin requirements, which included initiating emergency boration.
Problems with this instrumentation have been chronic, with some present since initial construction of the plant. Because of the attention given to the June 9, 1985 incident, the licensee prepared systematic and thorough troubleshooting plans and has now submitted a findings report for each channel. Specifically, Findings Reports Nos. 15A and ISB (Revision 2 of each) are included in the licensee's Supplement No. I to the report " Davis-Besse Course of Action." Review of these reports raised a number of questions in two general categories: open questions and bases for deferral of corrective actions. These questions were discussed with the licensee on October 30, 1985 and on November 6, 1985. The licensee had reasonable answers to the open questior.s and had reasonable bases for action
- deferrals; however, these had not been included in the reports. Accordingly,'the licensee prepared Revision 3 for each of the NI findings reports, which are the objects of this evaluation.
EVALUATION ,
- l. We prepared Tables 1 and 2 from the licensee's finding reports, to list the many
- anomalies that were discovered via the systematic troubleshooting plans for NI-1
! and NI-2, respectively. The number of anomalies for NI-1 and for NI-2 constitute
, prima-facie evidence of lack of proper maintenance of this nuclear safety-related
. equipment. Furthermore, many of the anomalies originated from installation errors during the original construction of the plant that went uncorrected for eight years
[ of plant operation.
Such a long list of anomalies is clearly sufficient to have caused the i
malfunctions related to the June 9,1985 incident. We note that the lists have some general characteristics:
- 1. A large number of the anomalies were related to the preamplifier assembly.
- 2. A large number of the anomalies were related to. triaxial connectors, both bulkhead mounted and on cables.
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s TABLE 1 TROUBLESHOOTING FINDINGS NI-1 (CHANNEL NO. 2)
- 1. DETECTOR ASSEMBLY (3 Anomalies) 1.1 Improper assembly of triax Amphenol connector which interfaces the integral mineral-insulated detector cable to -the triax cable to/from the preamplifier.
1.2 Detector location in thimble not a core midplane.
1.3 Masonite spacers used to block area around detector signal cable in detector thimble plug were too short (i.e., 5 inches vs. 18 inches).
- 2. PREAMPLIFIER ASSEMBLY (7 Anomalies) 2.1 Detector cable connector had its center pin pushed in approximately 1/4" and off center.
2.2 No grounding wire was connected to outer preamp box.
2.3 Bulkhead connectors on preamp inner and outer boxes had high-resistance connections to triax shields, due to connectors being mounted on painted surfaces.
2.4 None of the cable connectors at the preamp had 0-rings installed.
2.5 Detector cable bushing on outer box had inadequate clearance from detector cable connector, causing a potential ground loop.
2.6 Detector and high voltage connectors appear to be
, nickel instead of silver.
! 2.7 Fiber . hipping washers had been left in some bulkhead connectors, preventing proper meshing and tightening of connectors.
- 3. PENETRATION ASSEMBLY (No Anomalies)
- 4. RPS INSTRUMENT CABINET (4 Anomalies) 4.1 Loose connection to station safety ground bus.
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s - 4.2 Output connector for high voltage power supply had a crushed 0-ring.
4.3 Fiber shipping washers had been left in some bulkhead connectors, preventing proper meshing and tightening of connectors.
4.4 " Blue Ribbon" connector on high voltage power supply was chipped and cracked.
- 5. GENERAL (3 Anomalies) 5.1 Operation of instrument cabinet door switches (provide annunciator indication of open door) for RPS, SFAS, and SFRCS cabinets cause high level spikes at input to count rate amplifier module.
5.2 Every Amphenol connector was tarnished; many Amphenol connectors contained metal flakes.
5.3 Operation of some SFAS-controlled motor operated valves caused some spiking observable at the input of the rate-of-change amplifier module.
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g TABLE 2 TROUBLESHOOTING FINDINGS NI-2 (CHANNEL N0. 1)
- 1. DETECTOR ASSEMBLY (1 Anomaly) 1.1 Leaking seal plate allowed rust to form at connection box at top of detector thimble.
- 2. PREAMPLIFIER ASSEMBLY (9 Anomalies) 2.1 Low voltage cable connector loose on cable.
2.2 High voltage bulkhead connector extremely loose --
0-ring not installed.
2.3 High voltage cable connector did not have 0-ring installed.
2.4 Ground wire to outer box not installed.
2.5 Connectors for high voltage and detector appear to be nickel instead of silver.
2.6 Bushings not installed where cables enter outer box. ,
2.7 Bulkhead connectors on outer box for detector and
. high voltage were loose, i.e., mounting nuts only finger tight.
2.8 Printed circuit board was not mounted securely inside preamplifier box.
2.9 Shipping washers were left in some bulkhead connectors, which prevented adequate tightening of connectors.
- 3. PENETRATION ASSEMBLY (3 Anomalies) ;
3.1 Resistance substantially high for signal cable.
3.2 Signal cable connector loose on cable.
3.3 Shipping washers were left in some bulkhead connectors, which prevented adequate tightening of connectors. -
3.4 Intermittent losses of continuity for center conductor of signal cable.
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. 4. RPS INSTRUMENT CABINET (3 Anomalies)
, 4.1 Coax connector to count rate amplifier not locked.
4.2 High voltage cable connector appears to be nickel rather than silver.
4.3 High voltage cable connector did not have 0-ring installed.
- 5. GENERAL (3 Anomalies) 5.1 Cabinet door switches (for annunciator) for RPS, SFAS, and SFRCS cabinets cause high level spikes.
5.2 Every Amphenol connector tarnished; many contained metal flakes.
5.3 Some SFAS-operated MOVs cause spiking on input to SUR meter.
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- 3. The NI-2 channel containment penetration, which is generally considered to be a relatively passive component and hence not as likely to fail as more active components, had serious anomalies. (See Item 3 of Table 2).
These characteristics suggest that components that are either cumbersome to get to or not very likely to fail cannot be neglected. Further, the characteristics suggest a generalized problem with triaxial connectors.
(We note that the licensee is addressing the generalized connector problem with improved procedures and training).
The licensee identified the following root causes for the failures of NI-1 and NI-2, respectively:
NI-1:
- High resistance connections in the bulkhead connectors on the preamp, due to being mounted on painted surfaces (Item 2.3 of Table 1).
- Improper assembly of the triax connector at the detector interface (Item 1.1 of Table 1).
NI-2:
- High resistant and intermittent connections related to the containment penetration assembly (Items 3.1 and 3.4 of Table 2).
- Generalized poor condition of connectors, due to improper assembly, .
lack of proper cleaning, and poor maintenance (Item 5.2 of Table 2).
We view these items as the licensee's determination of the most signifinnt of the anomalies discovered. In our experience, only rarely is a single factor the cause of problems in pulse-type nuclear instrumentation. Most often many factors contribute to the problem, in varying degrees of severity.
Our review of the discovered anomalies indicates that there is reasonable assurance that rost, if not all, significant contributors have been identified.
The basis for our conclusion is very pragmatic. Subsequent to the corrective actions that have already been completed, the channels have been monitored continuously for substantial. periods of time, with no further instances of problems. For NI-1 this period was six weeks; for NI-2, eight weeks.
The licensee's reports state that although most corrective actions will be completed prior to plant restart, certain corrective actions are not major contributors to the problems and thus are planned to be completed after plant restart. We have reviewed the specific basis provided for these deferrals.
In view of the substantial periods of proper operation of the instrumentation channels without problems, we find the deferral of additional corrective actions to be acceptable.
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CONCLUSION The systematic and thorough troubleshooting plans for the source range nuclear instrumentation channels have revealed a substantial number of causes. The most significant causes appear to be improper installation of triaxial connectors on the preamplifier (for NI-1), intermittent high-resistance connections in a containment penetration assembly (for NI-2), and a generalized poor condition of triaxial connectors. Our review of the licensee's findings reports concludes that the significant contributors to the problems have now been identified and that the corrective actions have been effective in improving the performance of these instrumentation channels. Accordingly, as far as the sources range nuclear instrumentation is concerned, plant restart and power operation is now acceptable.
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