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| {{Adams | | {{Adams |
| | number = ML20202B940 | | | number = ML20217D659 |
| | issue date = 02/06/1998 | | | issue date = 03/25/1998 |
| | title = Insp Rept 50-458/97-19 on 971130-980110.Violations Noted. Major Areas Inspected:Licensee Operations,Maint,Engineering & Plant Support | | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-458/97-19. Implementation of CAs Will Be Reviewed During Future Insp to Determine That Full Compliance Has Been Achieved |
| | author name = | | | author name = Collins E |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| | addressee name = | | | addressee name = Mcgaha J |
| | addressee affiliation = | | | addressee affiliation = ENTERGY OPERATIONS, INC. |
| | docket = 05000458 | | | docket = 05000458 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-458-97-19, NUDOCS 9802120129 | | | document report number = 50-458-97-19, NUDOCS 9803300131 |
| | package number = ML20202B904 | | | title reference date = 03-09-1998 |
| | document type = INSPECTION REPORT, NRC-GENERATED, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE |
| | page count = 22 | | | page count = 5 |
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| | *"8009 UNITED STATES |
| ENCLOSURE 2 U.S. NUCLEAR REGULATORY COMMISSION
| | .7 A+t NUCLEAR REGULATORY COMMISSION |
| | $ REclON IV |
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| | 611 RYAN PLAZA DRIVE, SUITE 400 0[ AR LlNGTON, TEXAS 760118064 |
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| | MAR 2 51998 John R. McGaha, Vice President - Operations River Bend Station Entergy Operations, Inc. |
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| | P.O. Box 220 St. Francisville, Louisiana 70775 l l' |
| | SUBJECT: NRC INSPECTION REPORT 50-458/97-19 |
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| | ==Dear Mr. McGaha:== |
| | j Thank you for your letter of March 9,1998, in response to our letter and Notice of Violation dated December 24,1997. We have reviewed your reply and find it responsive to the issues raised in our Notice of Violation: a failure of plant workers to maintain appropriate separation criteria l between a safety-related cable tray and a temporary cable; the failure to maintain the postaccident sample system to ensure the capability to take gaseous and liquid samples following an accident; and ineffective corrective actions to address air entrapment in reactor core isolation system instrument lines. |
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| | We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintained. |
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| | Sincerely, (( 0 |
| | .O L Elmo E. Collins, Chief Project Branch C f Division of Reactor Projects I Docket No.: 50-458 License No.: NPF-47 f i cc: I Executive Vice President and Chief Operating Officer Entergy Operations, Inc. |
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| ==REGION IV==
| | P.O. Box 31995 - |
| Docket No.: 50-458 License No.: - NPF-47 3 Report No.: 50-458/97-19 Licensee: Entergy Operations, In Facility: River Bend Station Location: 5485 U.S. Highway 61 St. Francisville, Louisiana Dates: November 30,1997, through January 10,1998 Inspectors: G. D. Replogie, Senior Resident inspector Approved By: E. E. Collins, Chief, Project Branch C ,
| | Jackson, Mississippi 39286-1995 9903300131 980325 PDR ADOCK 05000458 G PDR I |
| Division of Reactor Projects Attachment: SupplementalInformation
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| F 9902120129 980206 PDR ADOCK 05000458 G PDR
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| | Entergy Operations, Inc. -2-Vice President Operations Support Entergy Operations, Inc. |
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| | P.O. Box 31995 Jackson, Mississippi 39286-1995 General Manager Plant Operations River Bend Station Entergy Operations, Inc. |
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| EXECUTIVE SUMMARY River Bend Station NRC inspection Report 50-458/9719 This inspection included aspects of licensee operations, maintenance, engineering, and plant support. The report covers a 6-week period of resident inspectio DRatatiODS
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| * The conduct of operations was generally professional and safety-co7ss lous (Section 01.1).
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| - | | P.O. Box 220 St. Francisville, Louisiana 70775 Director- Nuclear Safety River Bend Station Entergy Operations, Inc. |
| The separation criteria between a temporary cable and an uncovered safety-related cable tray was not maintained consistent with the Updated Final Safety Analysis Report and plant procedures (Section O2.2).
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| * A nuclear equipment operator trainee demonstrated excellent attention to detail during a diesel generator surveillance. While looking for fluid discharge on the cylinder head test valves, the operator noticed oil residue on piping adjamnt to the number eight cylinder (versus the cylinder head test valve itself, Section M1.2,
| | P.O. Box 220 St. Francisville, Louisiana 70775 Wise, Carter, Child & Caraway P.O. Box 651 Jackson, Mississippi 39205 Mark J. Wetterhahn, Esq. |
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| Operations and Maintenance personnel were not effective in maintaining the postaccident sampling system (PASS). The PASS was out of service for approximately 50 percent of the time during the past 10 months. Repairs were often not performed in a timely manner, and the overall material condition of the system was poor (Section M8.1).
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| | Winston & Strawn 1401 L Street, N.W. |
| A shift technical advisor failed to consider the Technical Specifications Limiting Conditions for Operability when determining operability for emergency core cooling system minimum flow valve instruments (Section E8.1).
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| Maintenance
| | Washington, D.C. 20005-3502 Manager- Licensing River Bend Station Entergy Operations, Inc. |
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| Maintenance activities were generally completed thoroughly and professionally (Section M1.1).
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| . | | P.O. Box 220 St. Francisville, Louisiana 70775 The Honorable Richard P. leyoub Attorney General Department of Justice State of Louisiana P.O. Box 94005 Baton Rouge, Louisiana 70804-9005 |
| On-line risk assessments were not always thorough. In one instance operators assumed that a delay in placing standby service water pumps in service would not adversely affect the availability of the standby service water pumps or the associated diesel generators without fully understanding equipment response, in another case, the potential consequences associated with a freeze seal failure were not pioperly considered in the risk assessment (Section M1.3).
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| While overall plant material condition was good, there were notable equipinent and system performance problems. The inspector noted material condition concerns involving excessive main generator hydrogen leakage, an inoperable PASS, an inoperable suppression pool pumpback pump, a degraded control rod drive pump, a
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| 2-failed containment isolation damper, and air entrapment in the instrument sensing lines to safety-related instruments. Conversely, spent fuel cooling Pump 18 and the suppression pool cleanup mode of the alternate decay heat remr' val system were repaired and returned to service (Section M2,1).
| | Entergy Operations, Inc. -3-H. Anne Plettinger 3456 Villa Rose Drive Baton Rouge, Louisiana 70806 President of West Feliciana Police Jury P.O. Box 1921 St. Francisville, Louisiana 70775 William H. Spell, Administrator Louisiana Radiation Protection Division P.O. Box 82135 Baton Rouge, Louisiana 70884-2135 |
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| - | | Entergy Operations, Inc. -4- MAR 2 51998 |
| The diesel generator system engineers promptly and effectively evaluated the significance of fuel oil discharge coming from a diesel generator cylinder. The prompt assessment helped to minimize the out of service time for the diesel generator
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| . (Section M1.2).
| | - bec to DCD (IE01) |
| | bec distrib. by RIV: |
| | Regional Administrator |
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| | Senior Resident inspector (Grand Gulf) |
| | DRP Director DRS-PSB Branch Chief (DRP/C)~ MIS System Project Engineer (DRP/C) RIV File Branch Chief (DRPfrSS) Resident inspector DOCUMENT NAME: R:\_RB\RB719AK.GDR l To receive copy of document, indicate in box: "C" = Copy without enclosures "E" = Copy wth enclosures "N" = No copy - |
| | RIV:DRP/C- ,, |
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| | PJAltor,df /16 EEColle#M/ |
| | 3/tv /98 U 3/$/98 |
| | - OFFICIAL RECORD COPY |
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| Engineers did not assess in a timely manner the significance of exceeding the flammability thresho'd for hydrogen cc centration at the seal oil detrainment tank ven Consequently, the flammability threshold was exceeded before safety issues were thoroughly evaluated (Section E2.1).
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| * Corrective actions to add,ess air entrapment in reactor core isolation coo:ing minimum flow valve instrument lines (January 1997) were not comprehensive and did not prevent recurrence. Subsequently, one high pressure core spray and two residual heat removal systam minimum flow valves malfunctioned for the same or similar causes (air entrapment in the instrument lines, Section E8.1).
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| | Entergy Operations, Inc. -4- WF . 5 i998 bec distrib. by RIV: |
| | Regional Administrator Senior Resident inspector (Grand Gulf) |
| | DRP Director DRS-PSB Branch Chief (DRP/C) MIS System |
| | ' Project Engineer (DRP/C) RIV File Brcnch Chief (DRPli SS) Resident inspector I |
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| | i DOCUMENT NAME: R:\_RB\RB719AK.GDR To receive copy of document, Indicate in box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy RIV:DRP/C , C:DRP/Q), |
| | PJAlter;df /f6 l EECollitif(/ |
| | 3/tv /98 ..) 3 % /98 OFFICIAL RECORD COPY 300001 |
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| Plant Suo;-ort
| | 8. Ent:rgy operations. Inc. |
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| Housekeeping was considered good (Section 02,1).
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| | March 9.1998 |
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| | U.S. Nuclear Regulatory Commission l" |
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| | 4-Document Control Desk. OPI-17 |
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| | .!9 Washington DC 20555 i MiR 16,nm :y}} |
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| | i Subject: Reply to Notices of Violation in IR 97-019 -- |
| | River Bend Station Unit I -~ ~ |
| | License No. NPF-47 i |
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| | Docket No. 50-458 |
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| | File Nos.: G9.5.G15.4.1 RBG-44415 RBF1 98-0068 |
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| | Ladies and Gentlemen: |
| | Pursuant to the provisions of 10CFR2.201, Attachments A, B and C provide the Entergy Operations. Inc. responses to the Notices of Violation (NOV) described in NRC inspection Report (IR) 50-458/97-019. |
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| | We have aggressively reviewed the subject violatiorts with a self-critical perspective to improve Riser Bend Station perfonnance. The lessons teamed are being addressed and integrated into our practices and programs as described in the attachments. |
| During routine tours, the inspectors noted that the security officers were alert at their posts, security boundaries were being maintained property, and screening processes at the Primary Access Point were appropriately performed (Section S1,1).
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| | Should you have any questions regarding the attached information, please contact Mr. David Lorfing of my staff at (504) 381-4157. |
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| ! Report Details l
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| Summarv of Plant Status At the beginning af this inspection period, the plant was in Operational Mode 1 at 100 percent reactor power. On December 20,1997, power was reduced to approximately 60 percent in support of planned maintenance on reactor feedwater pumps. At the ccactusion of the work on December 21 reactor power was retumed to 100 percent, where it essentially remained for the remainder of the reporting perio l. Qnerations 01 Conduct of Operations 01.1 General Comments.171707)
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| Using Inspection Procedure 71707, the inspectors conducted frequent reviews of ongoing plant operations. The conduct of operations was generally professional and safety-consciou Operational Status of Facilities and Equipment O2.1 Enaineered Safetv Feature System Walkdowns (71707)
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| The inspectors walked down accessible portions of the following safety related systems:
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| High Pressure Core Spray (HPCS)
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| Diesel Generators (DGs) I ano il and HPCS
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| Residual Heat Removal (RHR), Trains A, B, and C
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| Reactor Core Isolation Cooling (RCIC)
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| * Division I, ll, and ill Switchgear and Battery Rooms The systems were found to be properly aligned for the plant conditions and in good material condition. A few minor housekeeping issues were identified but, overall, hcusekeeping was good. One problem associated with electrical separation of safety-related and nonsafety-related cables is discussed in Section O2.2.
| | a Reply to Notice of Violation in 50-458/97-019 March 9,1998 RBG-44415 |
| | ' RBF1-98 0068 Page 2 of 2 cc: Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington,TX 76011 |
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| | NRC Sr. Resident Inspector |
| | - P.O. Box 1050 St. Francisville, LA 70775 David Wigginton NRR Project Manager U.S. Nuclear Regulatory Commission M/S OWFN 13-H-3 Washington, DC 20555 l |
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| | ATTACHMENT A Reply To A Notice of Violation IR 50-458/9719-01 Page 1 of 2 Violation: |
| | 10 CFR Part 50, Appendix B, Criterion V, states, in part, " Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings . . ." |
| | Updated Final Safety Analysis Report Section 8.3.1.4.2 requires that safety-related cables from different divisions and nonsafety-related cables be separated per the minimum allowable separation distances in Table 8.3.9, " Separation Criteria Allowable Versus Tested." Table 8.3-9 requires one foot of separation between a horizontal tray and a cable. |
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| | Procedure ADM-0073, " Temporary Installation Guidelines," Revision 2, Step 5.2, requires that temporary installations adhere to the design separation from divisional cable and that plant personnel be cognizant of the separation requirements of a temporary installation to divisional cabling as specified on Drawing EE-34ZE. |
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| ^ 02.2 Scoaration of Temocrary Cables Observations and Findinas On December 4,1997, while touring the auxiliary building, the inspector identified that an extension cord was draped over the top of uncovered division 11 Cable Tray 1TX817 Procedure ADM-0073, " Temporary Installation Guidelines," Revision 2, Step 5.2, requires that temporary installations adhere to design separation criteria specified on Drawing EE-34ZE. Drawing EE-34ZE, " Standard Details for Separation Requirements," Revision 7,
| | Drawing EE-34ZE, " Standard Details for Separation Requirements," Revision 7, identifies the separation requirements for free air cables to trays as one foot. |
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| | ~ Contrary to the above, on December 4,1997, an extension cord was draped across safety-related cable Tray ITX817B, with free-air cables, and the required one-foot separation was not maintained. |
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| | Reasons for the Violation: , |
| . | | A root cause analysis was performed which determined the root causes to be: |
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| | * Corrective actions from a previous condition report (CR) for a similar event were not ' ' |
| 2-identified the separation requirements for " free air cables to trays" as one foo Additionally, the one foot separation requirement was specified in the Updated Final Safety Analysis Repori, Section 8.3.1.4.2. In response to the inspector's concem, the temporary cable was promptly re-routed and the problem was documented on Condition Report (CR) 97-208 The inspector further noted that CR 97-1610, dated September 1997, was previously initiated to address similar concerns. In that CR, Quality Assurance personnel toured the facility to inspect compliance with cable separation requirements. The Quality Assurance inspectors identified eight instances where cable separation requirements were not me Corrective actions planned or taken in response to CR 97-1610 included: (1) training plant personnel on cable separation requirements (complete); and (2) changing Procedure ADM-0073, to clarify the separation requirements (planned).
| | yet fully implemented. As corrective action from the previous event, procedural changes to ADM-0073," Temporary Installation Guidelines," were made, but l |
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| | Revision 3 of the procedure was not issued and available for plant personnel to use on December 4,1997. Additional means to prevent recurrence (such as temporary power cord tagging) had not been finalized at the time ofinstallation of the cable identified in the subject violation. ; |
| | * Training on the proper installation of temporary electrical cords for the personnel involved had not been completed. |
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| The inspector considered the most recent instance of a cable separation infraction to be repetitive, Corrective actions for previous occurrences were not fully effective at preventing recc.rence. The failure to maintain cable separation in accordance with Procedure ADM 0073 is a violation of 10 CFR Part 50, Appendix B, Criterion V (50-458/97'i9-01). Cnaciusions Ona violation was identified for the failure to comply with procedural cable separation requirement ,
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| ll. Maintenance M1 Conduct of Maintenance M1.1 General Comments Insoection Scoce (61726. 62707)
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| The inspectors observed portions of the following maintenance and surveillance activities (except as noted below):
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| STP-309-0202, " Division 11 Diesel Generator Operability Test," Revision 18E (documentation review)
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| STP-309-0201, " Division 1 Diesel Generator Operability Test," Revision 16C
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| Maintenance Activity item (MAI) 302635, Replacement of Service Water Valve SWP-V-70
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| MAI 341613, Replacement of Service Water Valve SWP-V-69
| | Corrective Actions Which Have Been Taken and the Results Achieved: |
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| | * The subject extension cord was removed. |
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| mal 314783, Division i Service Water Cooling Tower Inspection (documentation review)
| | . ADM-0073, Revision 3 was issued on December 15,1997. |
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| MAI 314938, Division il Service Water Cooling Tower Inspection (documentation review)
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| STP-403 7301, " Containment Purge System Isolation Valve Leak Rate Test,"
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| Revision 1 (documentation review) Observations and Findinas The performance of maintenance generally was thorough and professional. Exceptional performance demonstrated during the Division 11 DG surveillance is discussed in Section M1.2. Concerns related to less than thorough on-line risk assessments is addressed in Section M1.3, while the failure of a containment isolation damper is discussed in Section M M1.2 Division 11 DQ_Qperability Test Insoection Scoce (61726) | |
| Fuel oil sprayed out of the Division ll, Cylinder 8 head test valve during the air roll portion of the DG operability surveillance. The inspector performed followup to this licensee observatio Observations and Findinas Licensee Actions: While looking for fluid discharge on the cylinder head test valves, a nuclear equipment operator (NEO) trainee noticed oil residue on piping adjacent to the Cylinder 8 (versus the cylinder head test valve itself). The NEO was concemed because oil discharge could be an indicator of cylinder damag In response to the finding, operators declared the DG inoperable and entered the Technical Specification (TS) ACTION Statement. Subsequently, DG system engineers identified the substance as fuel oil and contacted the vendor for additional guidance. The engineers determined that an unloaded DG run on November 20,1997 (troubleshooting for a different problem), had resulted in leaving a small amount of unbumed fuel in the cylinder. Per the vendor, this was not an uncommon finding following an unloaded run and the additional amount of fuel oil in the cylinder did not adversely impact the s. e operability of the DG. As a precautionary measure, a compression test was satisfactorily completed on the DG prior to retuming the unit to service later that da _ _ _ _ _ _ _ _ _ _
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| | . Potential users of extension cords were notified of the changes to ADM-0073 to ensure that additional emphasis was being provided in Maintenance, Chemistry, l Radiation Protection and Operations. { |
| . | | e Operations crews performed a walkdown of the plant to identify if other separation discrepancies were present. Items found were corrected. ; |
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| | Corrective Actions That Will Be Taken To Avoid Further Violations: l e A briefing sheet will be prepared to provide Operations department personnel with information regarding the changes to ADM-0073. |
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| | . The Operations Superintendent will discuss the requirements of ADM-0073 with Operations crews. |
| NRC Assessment: The NEO trainee demonstrated excellent attention to detail when he found oil residue on piping adjacent to Cylinder 8, as his actions exceeded the ;
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| procedure's inspection requirement In response to the finding; system engineers demonstrated effective problem resolution
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| - capabihties (including good utilization of the DG vendor) and promptly evaluated the -
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| , significance of the oil discharge. The accomplishment of the compression test, as added assurance of their conclusions, demonstrated a good safety focus. The prompt work by the engineers helped to minimize the out of service time for the D Conclusions An NEO trainee demonstrated excellent attention to detail in identifying oil discharge -
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| ' coming from the Division ll DG, Cylinder 8. Additionally, engineering promptly and effectively assessed the significance of Le problem and conservatively performed testing to verify thc!r conclusion M1.3 Risk Assessments for On-Line Maintenance Insoection Scooe (62707)
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| The inspectors observed the licensee's risk assessments in support of on-line maintenance activitie Observations and Findinas Background: The licensee performs a substantial amount of work on-line (versus during | |
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| an outage).l The Maintenance Rule (10 CFR 50.65(a)(3)) states, in part:
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| "In performing monitoring and preventative maintenance activities, an assessment of the total plant equipment that is out of service should be taken into account to determine the overall effect on performance of safety functions."
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| To meet the intent of the above, maintenance is controlled via the "On-Line Maintenance
| | e Tags will be procured which provide the separation criteria of ADM-0073. These ; |
| - Guidelines," Revision 3. These guidelines specify the use of a " blended approach," when assessing the potential risk of maintenance. The blended approach consists of quantitative as well as qualitative aspects of risk assessments. Risk is evaluated quantitatively via the equipment out of service (EOOS) computer, which provides numerical values for " instantaneous" as well as " cumulative'' risk (which are then compared to predetermined acceptance criteria). ' Due, in part, to limitations with the
| | tags will be placed on extension cords in the tool room and distributed to other j departments with guidance for their use. j |
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| EOOS computer model, engineering judgement is also utilized to qualitatively evaluate
| | e Training covering ADM-0073 will be developed and implemented for plant l |
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| | e ADM-0073 requirements will be added to the outage handbook. |
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| \ 5-The Maintenance Guidelines stipulate that equipment may be considered "available"in the EOOS computer program when it ic capable of performing its safety function, even when it is tagged out of service or declared inoperable. The guidelines stress, however, that conservative and safe opwation must be the foremost consideration when making a determination involving availability of plant equipmen Standby Service Water (SSW) Tower Inspections: The inspector identified that the ncensee had not appropnately considere risk for work on the SSW cooling towe The licensee performed visual inspections of the SSW cooling tower (one safety-related division at a time). To ensure the personal safety of the workers, the licensee had placed the service water pumps in the " pull-to-lock" position, declared the service water division and its associated DG inoperable, and entered the applicable T3 ACTION Statement However, the equipment was considered svailable (in the EOOS program) because the service water pumps could be started in a short period of time. Operators estimated that evacuation of the SSW cooling tower and starting of the SSW pumps would take approximately 3-4 minute The inspectors contacted a DG system engineering supervisor and inquired how long a DG could operate without service water The supervisor stated that the DG vendor had demonstrated that a DG could operate for approximately 2 minutes (while fully loaded)
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| before failure might be experienced. Without the load of the SSW pumps, however, the
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| < DG could operate for an additional unknown period of tim Based on the above, the inspector concluded that the licensee's action were inconsistent with the recommendations contained in the "On-Line Maintenance Guidelines."
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| Specifically, the licensee did not have reasonable assurance that the DG (which powers the SSW pumps during events that include a loss of offsite power) was capable of performing its safety function. This issue demonstrated poor attention to detail when assessing overall plant risk for this jo Service Water Valve Replacements: The inspector observed the on-line replacement of four SSW valves (service water isolation valves to the Division i HVK chillers). The inspectors noted that the train of SSW and its associated DG were unavailable in the EOOS program and this resulted in a risk level at the upper administrative limit for
| | * The process for handling temporary power cables will be changed to ensure that these cables are issued by the tool room. |
| " acceptable risk." Additionally, the work required the use of two freeze seals to isolate the valves from the SSW system (6-inch diameter lines). This method of isolation, in itself, had the potential for causing an additional event (loss of freeze seals and flooding of the control building).
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| The contingency actions associated with the potentiailoss of freeze seals included:
| | Date When Full Compliance Will Be Achieved: |
| (1) installation of blind flanges over the open valve bodies; and (2) isolation of the normal service water header to Division I components. While the contingency actions seemed l
| | Full compliance was achieved on December 4,1997 when the subject extension cord was removed. Subsequent plant walkdowns were completed by January 31,1998 to ensure , |
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| | ATTACHMENT B Reply To A Notice Of Violation I IR 50-458/9719-03 Page 1 of 2 Violation: 1 |
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| | Technical Specification 5.5 states, in part, "the following programs and manuals shall be established, implemented, and maintained ... |
| | 5.5.3 Post Accident Sampling... This program provides controls that ensure the capability to obtain and analyze reactor coolant, radioactive gases, and particulates in plant gaseous effluents and containment atmosphere samples under accident conditions. The program shall include the following... Provisions for maintenance of sampling and analysis { |
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| 6-appropriete for the work, the EOOS computer model did not have the capability to evaluate te potential risk associated with a loss of freeze seal event. The risk significant aspects included:
| | Contrary to the above, between March 3 and December 12,1997, provisions for maintenance of sampling and analysis equipment were inadequate to effectively ensure the capability to obtain and analyze reactor coolant, radioactive gases, and particulates in plant gaseous effluents and containment atmosphere samples under accident conditions. |
| * lsolation of normal service water to the safety-related loads (normal service water is a risk significant system).
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| * Flooding of the control building. Divisions I and 11 switchgear are located on the same floor of the control building. The licensee's generic flooding analysis considered minimal flooding (approximately 120 gpm), which did not approach the flow rate that could be expected from a freeze seal failure, The inspector considered the use of freeze seals to constitute some unquantifiable additional risk with this job. Since the quantified risk (per the EOOS program) was already at the administrative limit, the qualitative evaluation for the job was not well focussed on safety and did not appear to provide additional value to the risk assessment process, Conclusions
| | The post accident sampling system was out of service for approximately 50 percent of the time during the subject period. |
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| On-line risk evalurfion assessments were not always thorough. In one instance operators assumed that a delay in placing SSW pumps in service would not adversely affect the availability of SSW pumps and Dgs without fully understanding equipment response. In another case, the potential consequences associated with a freeze seal failure were not properly considered in the risk assessment, M1,4 Containmant Purae Damner (HVR-AOV-165) Found Inocerable insoection Scone (61726)
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| Containment purge Damper HVR-AOV 165 failed during local leak rate testing (LLRT).
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| The inspector performed followup to this licensee observatio Observations and Findinas Background: HVR-AOV-165 is a 36 inch diameter butterfly valve (damper) located in the containment purge system and is the outboard containment isolation damper. The unit is air operated to open, spring to close, but is also equipped with a separate hydraulic actuator to manually open the damper during maintenance. For manual operation, a skid mounted petcock valve is closed and the hydraulic actuator is manually pumped to open the damper. For damper closure, the petcock valve is opened, which releases the hydraulic lock and permits the actt,ator to retract. Drawing 410318 requires that the petcock be at least one turn open when the damper was operated in the pneumatic mode (the safety-related mode). | | Reason For The Violation: |
| | A root cause determination provided the following primary causes: j i |
| | e Monitoring and ownership of the post accident monitoring system (PASS) were ineffective. Some personnel involved in monitoring of the system did not fully understand the scope of their responsibilities or have proper understanding of the impact ofissues on the system. Responsibility for ensuring prompt performance of corrective maintenance was not clearly understood. ., |
| | * The design configuration allowed water intrusion into the dry nitrogen portion of the _ |
| | system. Some valves were found to be incorrectly installed. This led to equipment j degradation and system malfunction. |
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| . | | Corrective Actions That Have Been Taken and the Results Achieved: j |
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| | * A system engineer was assigned responsibility for PASS. |
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| The inspector noted that closure of the petcock, alone, will not necessarily render a damper inoperable. The hydraulic actuator would slso have to be manually operated (jacked) at least one time before the actuator piston would extend and affect damper closur Damper Failure: During the performance of Procedure STP-403-7301," Containment Purge System Isolation Valve Leak Rate Test," Revision 1, on January 8,1998, leakage through Damper HVR AOV 165 was in excess of the capacity of the leak rate monitor (2000 sccm). Further examination revealed that the maintenance actuator petcock valve was out of position (closed) and the actuator was partially extended (preventing the damper from reaching the full closed position). Operators promptly declared the damper inoperable and completed the ACTIONS required by TSs. The petcock was then opened and the damper was observed to go to the fully closed position. The LLRT was then successfully performe in response to the finding the licensee checked the position of the petcocks on the other similar dampers in the system. The petcock for the penetration's inboard damper (HVR-AOV-123) was found open. However, the petcocks for the containment isolation dampers on the ventilation portion of the system (HVR-AOV-128 and HVR AOV-166) were found closed. A maintenance supervisor opened the petcocks for the containment ventilation dampers and reported that no damper movement was observed. The LLRT for that penetration was subsequently performed without even At the close of the inspection, the licensee had not determined the root cause of the damper failure or the length of time that the damper may have been inoperabl However, the previous LLRT for Damper HVR-AOV-165 was successfully completed approximately 90 days prior to the damper failure. As such, the damper had not been inoperable for more than 90 days. This is considered an unresolved item pending further NRC review of the licensee's root cause evaluation (50-450/9719-02).
| | * A modification was installed to provide separation between the dry and wet sides of i |
| | the nitrogen supply to PASS. |
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| M2 Maintenance and Material Condition of Facilities and Equipment M2.1 Review of Material Condition Durina Plant Totgs Insoection Scoce (62702)
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| During this inspection period, the inspectors conducted routine plant tours to evaluate plant material conditio Observations and Findinas
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| Main Generator Hydrogen Leakage: Main generator hydrogen leakage was considered excessive. The identified leakage pathway was through the collector
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| 8-i end generator seal and out the roof vent. A further worsening of this condition could require a plant shutdown to support repairs.- A detailed discussion is provided in Section E2.1 of this repor PASS: The PASS was found inoperable on November 12,1997, when two system fuses blew during a surveillance. Repairs on the system were completed on December 11,1997. However, extensive work was ctill planned to inspect and repair air operated valve actuator,' *st may have been damaged due to water intrusion into the system. PASS has been unavailable approximately 50 percent over the past year and, overall, material condition was considered poor (see Section M8.1).-
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| | e The PASS has been thoroughly inspected for degradation caused by the water intrusion. |
| Suppression Pool Pumpback Pump DFR P5B: The subject pump failed inservice testing on December 22,1997, and remained out of service for the remainder of the inspection period. Pump DFR P5B is one of four pumps provided to pump emergency core cooling system (ECCS) leakage from the auxiliary building sump back to the suppression pool during a design basis even The loss of the pump leaves one train of the suppression pool pumpback system in a degraded condition (each train consists of two pumps).
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| | e The incorrectly installed valves in the PASS sample station have been correctly installed. |
| Contrc,1 Rod Drive Pump 1 A: The subject pump was experiencing higher than normal vibration, which was believed to be caused by a damaged coupling. The licensee considered the pump degraded but operable. The pump may utilized during emergency operating procedure implementation for manual contsc! rod movement and as a backup source of primary coolan .
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| Containment Isolation Damper HVR AOV 165: The damper was found inoperable during a surveillance on January 8,1997. Although corrective actions to restore the damper were prompt, the length of time that the condition existed was not known (see Section M1,4).
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| | * Other potential sources of water intrusion were researched and determined not to be { |
| ECCS and RCIC Flow Transmitters: Air entrapment was identified as a generic problem in the instrument sensing lines for the ECCS and RCIC flow transmitter This resulted in the misoperation of the HPCS, RHR B and C minimum flow valves. Additionally, the generic ramifications of the problem were not yet fully investigated (see Section E8.1).
| | valid sources of water intrusion. |
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| Material condition improvements included:
| | * A walkdown was performed to ensure that plant configuration and design configuration match. |
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| Spent fuel pool cooling (SFC) Pump 1B: The SFC Pump 1B was repaired recently (new impeller) and returned to service. The pump had been in a degraded condition for approximately one year. The recent repaire restored the original design margin to the pum _ _ _ _ _ _ _ _ _ _ _
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| | * Chemistry PASS sampling procedure, COP-1001, has been revised to include information related to pressurization of the system water tank. This will minimize the potential for water intrusion. |
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| . * Alternate Decay Heat Removal (ADHR), Suppression Pool Cleanup (SPC)
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| Mode: The SPC mode of ADHR was repaired and retumed to service this inspection period. Suppression pool clarity has steadily improved since the system was restore ConclusiQDA
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| Whila overall plant material condition was good, there were notable equipment and system performance problems. The inspector noted material condition concems with main generator hydrogen leakage, the PASS, suppression pool pumpback Pump DFR-PSB, control rod drive Pump 1 A, containment isolation Damper HVR AOV-165, and ECCS and RCIC flow instruments. Conversely, SFC Pump 18 and the SPC mode of the
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| ADHR system were repaired and returned to servic M8 Miscellaneous Maintenance issues (92700)
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| M8.1 Poor Availability for the PASS Insoection Set.9e (61726)
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| The inspector reviewed maintenance records associated with the PAS Qblorvations and Findinas Background: Out-of service time for the PASS is administratively controlled vin
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| " Operations Policy 6," which states, in part:
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| "The Pass System shall be given the same level of attention as a 30 day LCO [ Limiting Ccndition for Operability). This will ensure the appropriate level of management oversight for restoring the sys'em to an operable status. . ."
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| "For 30 day LCOs, a daily assessment SHALL be made. Information should be obtained at the moming meeting to ensure an action plan is in place and satisfactory progress is being made to clear the LCO in a timely manner,"
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| Additionally, the "On-Line Maintenance Guidelines," Revision 2, states, in part:
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| "Out of service time should be minimized for system outages. No more than 50% of the Technical Specification allowable out of service time should be scheduled for a system outage."
| | Corrective Action That Will Be Taken To Avoid Further Violations: |
| | * Operations shift superintendents, control room supervisors, maintenance supervisors and work week managers will review Operations Policy 6," Active Limiting Conditions of Operation," to reinforce management expectations with respect to the use oflimiting conditions of operation. |
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| Failure to Minimize PASS Unavailability: The inspector identified that Maintenance and Operations personnel did not meet management expectations with regard to
| | l e An evaluation will be performed to determine if a process to review the accumulated effects of repeated entry into tracking LCOs (Limiting Conditions of Operation) is needed. l |
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| | e Other maintenance rule scoped systems will be evaluated to ensure proper assignment j of system ownership. |
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| , accomplishing maintenance in less than half the administrative Lc0 and ensuring that satisfactory progress was made to clear the administrative LCO in a timely manner, The inspector observed that the PASS failed a monthly surveillance, due to blown fuses (shorted limit switch), and remained inoperab;9 from November 12 through December 11, 1997 (29 days). During this period, there were long periods of time where the PASS was not worked. For example, between November 12 and November 20 little or no maintenance was performed on the PASS. Likewise, between November 23 and November 30, no maintenance was accomplishe Poor Availability History: The inspector also observed that the PASS was inoperable for approximately 50 percent of the past 10 months. Additionally, material condition was considered poor and long standing equinment problems were not fixed in a timely manner. For example:
| | clarified. Personnel outside system engineering who "own" a system will be informed of their responsibilities. |
| a in March 1997, water was found in the PASS control cabinet and was determined to be caused by leakage past Check Valve D24 VF010 (boundary valve between the nitrogen supply and the domineralized water tank). Water leaked past the valve, into the air lines for multiple air-operated valves, and entered the valve ac.tuators. When the air-operated valves v are repositioned, the actuators wcre vented and water sprayed inside the PASS pane NOTE: A normally closed manualisolation valve (D24 VF012) was in the t
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| nitrogen line adjacent to Valve D24 VF010. The manual valve was opened during surveillane.es (only). It was during this time that leakage traveled past Valve D24 VF010 and into the nitrogen lines, Initially, the licensee believed that sediment prevented Valve D24 VF010 from seating properly and flushed the valve (a small amount of corrosion products was observed during the flush). The valve was considered operational even though minimal postmaintenance testing was perforred and no actions were taken to address the source of the sedimen * On May 9 the PASS failed due to a faulty sample needle. The licensee attempted to return PASS to service on June 1 * On June 12 leakage past three valves (in series, including D24 VF010) allowed leakage out of the reactor coolant system and into the PASS nitrogen lines. The nitrogen supply system relief valve lifted and sprayed the PASG area with contaminated water. Shortly thereafter, MAI 312853 was initiated to repair the leaky valves. However, the licensee returned the PASS to service on July 12 without repairing Valve D24 VF01 _ _ __ -- b
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| - _ _ _ _ _ _ _ . _ _ _ _ - ._ _ . . _ _ . _ _ _ _ _ . _ . _ _ . _ _ _ . _ . . . _ _ _ _ _ | | * A procedure will be developed describing how PASS satisfies Technical Specification 5.5.3 including the expectations and responsibilities of the various departments involved, o Engineering will evaluate and take appropriate action to ensure proper - |
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| | implementation of other similar programs identified in Technical Specification 5.5. |
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| * On September 11 power was lost to the PASS control cabinet when water sprayed the circuitry (due to leakage past Valve D24 VF010). The PASS was returned to service on October 13 without effecting repairs to Valve D24 VF01 '
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| * On November 20, aftar the most recent PASS failure, Valve D24 VF010 was finally repaired. Maintenance craftenen reported that the valve was not seating '
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| properly. The valve seats were lapped and the valve reassemble '
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| Due to water intrusion into the nitrogen lines, the licensee was concerned that the reliability of some of the air operated valves could be compromised. An extended PASS outage was scheduled to start January 12,1998, to inspect some of these salve c C9nclualons The high PASS unavailability was indicative of ineffective maintenance. The PASS was taken out of service and often not worked in a timely manner. The amount of time taken to return the PASS to service (approximately 30 days in all cases) was considered excessive when considering the actual work accomplishe The inspector concluded that the failure to maintain the PASS system operable, to a reasonable extent, was a violation of TS 5.5.3. This TS requires the licensee to have 1 provisions for maintenance of sampling and analysis equipment sufficient to ensure the '
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| capability to obtain and analyze vanous samples under accident conditions. These provisions were inadequate (VIO 50-458/9719 03). I lit. Engineering E2 Engineering Support of Facilities and Equipment E2.1 Excessive Main Generator Hydrogen Leakage Insoection Scoce (37551)
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| The inspectors observed Engineering's involvement addressing excessive main generator hydrogen leakag Qhsgrvations and Findin96 NRC Inspection Report 9717 discussed excessive main generator hydrogen leakag Leakage was approximately four times normal at the close of the previous inspection .
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| pe riod (2 5 percent concentration of hydrogen in air at the seal oil detrainment tank vent).
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| During this inspection period, the hydrogen leakage worsened and exceeded the 4.0 percent flammability threshold on December 17,1997. On the following day,
| | Date When Full Compliance Will Be Achieved: |
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| | Full compliance was achieved on March 7,1998 when the limiting condition on operation was removed. |
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| 12-i hydrogen leakage increased and the concentration approached 6.0 percent, before positive actions were taken to reduce the leakage, in response to the problem, management directed operations to reduce hydrogen pressure in the main generator (within desigra allowables), which resulted in a significant -
| | a ATTACHMENT C Reply To A Notice of Violation IR 50-458/9719-05 Violation |
| reduction in the effluent hydrogen concentration. At the clnse "'.he inspection period, the effluent concentration was approximately 3 percent and a, ad to be slowly worsenin Continued degradat on of the problem could result in a plar , nutdown to effect repair The inspector observed that Engineering had identified the excessive main generator leakage shortly after startup and had been actively trending the effluent concentration, but had not appropriately evaluated the safety consequences of the leakage before the flammability limit was exceeded. Furthermore, senior plant managers were not adequately informed of the magnitude of the problem untilit was too late to avoid exceeding the flammability threshold Engineers had demonstrated a poor safety focus in their failure to recognize the significance of the issue and accomplish an appropriate engineering evaluation in a timely manne CODelusions Engineering did not evaluate in a timely manner the significance of exceeding the flammability threshold for hydrogen concentration (measured at th9 seal oil detrainment tank vent). Consequently, the flammability threshold was exceeded before safety issues
| | "10 CFR Part 50, Appendix B, Criterion XVI, states, in part, " Measures shall be established to assure that conditions adverse to quality, such as . . malfunctions ... are promptly identified and corrected. In the case of significant conditions adverse to quality, the measures shall assure that the cause of the condition is determined and corrective |
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| | . actions taken to preclude repetition . . ." |
| were thoroughly evaluated.
| | Contrary to the above, on January 23,1997, a significant amount of air was found in reactor core isolation cooling flow instrument sensing lines (a significant condition adverse to quality) but established measures did not assure the cause of the air entrapment was identified, and actions were not taken to preclude repetition. Consequently, the following problems were observed due to air entrapment in other system flow instrument lines: (1) on November 11,1997, the high pressure core spray minimum flow valve malfunctioned; (2) on December 11,1997, the residual heat removal Train C minimum flow valve malfunctioned; and (3) on December 12,1997, the residual heat removal Train B minimum flow valve malfunctioned." |
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| I E8 Miscellaneous Engineering Issues (37551)
| | Reasons for the Violation: |
| E8.1 (Closed) Unresolved item (URI) 50-458/9717 05: air in HPCS flow-meter instrument lines caused minimum flow valve malfunction. During the performance of inservice testing on
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| , the HPCS system (November 11,1997), the minimum flow valve failed to open when the I test return valve was closed. Additionally, later in the surveillance, the minimum flow valve unexpectedly closed when the HPCS suction was swapped from the suppression pool to the condensate storage tank, in both instances the va've closure resulted in
| | Spurious gross failure nuisance alarms had been received in the RCIC (Reactor Core Isolation Cooling) flow transmitter circuit while running the HPCS (High Pressure Core Spray) system and were identified on a condition report in 1993. The condition report was dispositioned with the cause not determined. During the course of a follow-up review of the spurious gross failure alarms including the documented reports, an engineer was led to suspect air in the instrument sensing lines. A maintenance action item was generated on January 23,1997, and RCIC flow instrument sensing line high point vents were vented as part of the investigation into the above' mentioned long standing problem |
| " dead heading" the HPCS pump. An operator manually opened the minimum flow valve after each misoperation. In response to the malfunction, HPCS was declared inoperable and operators entered the TS ACTION Statement.
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| | involving the receipt of spurious gross failure alarms. Air was found in the high point vent. The system engineer realized that other ECCS (Emergency Core Cooling Systems) |
| | systems could have a simila problem and investigated further by reviewing the ADM-0064 log (Spurious Instrument Trip Log), walking down ECCS systems, checking system l |
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| | indications and discussing the situation with other engineers and operations personnel. |
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| l During troubleshooting, air was found in the HPCS flow transmitter instrument sensing lines. The Rosemont flow transmitter provl des an input to the minimum flow valve control circuits. Since the trip setpoint (minimum o,710 g,nm per TSs) corresponds to a very
| | . Based on this investigation, he concluded that other systems were not exhibiting symptoms of this problem and that a Condition Report (CR) was not warranted. |
| . tall differential pressure across the flow meter (6 inches water column), a small amount of air in the lines could have a significant impact on the instrument setpoint. At the close of the inspection period, the licensee had not demonstrated that the instrument setpoint had remained within a range permitted by TSs.
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| | A root cause team was assigned to investigate the cause of the Criterion XVI violation. |
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| | The root cause was determined to be less than adequate communication and enforcement |
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| | e of the condition report initiation threshold. The definition of when to initiate a condition report versus a maintenance work document while troubleshooting equipment is not clear. |
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| | The root cause team also evaluated previous similar conditions. Causes for these conditions were identified and are being addressed as part of the River Bend Station (RBS) corrective action program. |
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| | Corrective Actions That Have Been Taken and the Results Achieved: |
| | As an interim action, a memorandum was issued by the General Manager Plant Operations to RBS personnel addressing management expectations conceming condition report initiation threshold. |
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| | Corrective actions involving the presence of air in transmitter sensing lines was discussed in LER 97-010 as submitted on December 11,1997 and supplemented on February 26, l 1998. The completed actions to resolve this issue included: |
| During subsequent reviews, the licensee determined that the controllogic had reset itself after each misoperation and, had the operator not repositioned the valve, the valve would have automatically repositioned to the open position in a short time (10 to 15 seconds),
| | . Maintenance and System Engineering personnel conducted troubleshooting to j determine the cause of the minimum flow valve failure. |
| As such, the licensee did not believe that the pump could have been damaged by the valve misoperations. Nonetheless, as a minimum, the condition represented a significant distraction to the operators.
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| | e The sensing lines from the HPCS pipe to the flow transmitter were vented at the high point vents to remove air indicated by troubleshooting. |
| . Additional Events: During this inspection period, additional operational problems were | | |
| | . The HPCS pump was run and no abnormalities were noted. |
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| experienced with two other ECCS minimum flow valves:
| | . Following the discovery of air in Residual Heat Removal (RHR) B and C transmitter sensing lines, a team of engineering, operations, and maintenance personnel reviewed safety related instrumentation to determine other susceptible transmitters. As a result, six additional locations were vented. |
| * On December 11, prior to the operation of RHR C, the RHR C pump minimum flow valve was found closed (it should have been open in the standby lineup).
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| * On December 12,1997, after securing the RHR B pump, an operator attempted to open the pump's minimum flow valve (the normal standby position) but the valve unexpectedly cycled closed. After making a second attempt at opening the valve, the valve remained ope The licensee vented the instrument lines for the two RHR minimum flow valves tsnd observed relatively large amounts of air coming from the vents. As a precautionary measure, the remaining ECCS minimum flow valve instrument lines were vente Varying amounts of air were observed coming from all of the vent NOTE: Since the instrument lines are isolated during instrument calibration, air in the lines would not be apparent during the evolutio Licensee's Cause Determination: The licensee concluded that air had likely accumulated in the instrument lines over a long period of time. The instrument lines utilize high point vents (versus the preferred installation where the instrument lines are routed with a continuous upward slope from the instrument to the process tap). | | * An Operations Department Standing Order was issued to direct the venting of instrument lines with the high point vents when necessary. |
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| Additionally, there were no provisions for venting the lines periodically to preclude-adversa affects from air entrapmen The licensee had not determined all of the corrective actions necessary to address the air entrapment problem by the close of the inspection period. More than one hundred other r saft.ty related instruments utilize high point vents in the instrument's sensing lines, but none were believed to be as sensitive to air entrapment as the flow monuring instruments. At the close of the inspection period the licensee was still evaluating the necessity of venting other instrument tensing line Historical Problems: The inspector noted one recent instance of a similar pioblem. Air w
| | * Instrumentation technicians and planners were made aware of the effects of entrapped air on instrumentation, and the need to vent instrumentation high point vents. |
| ' as found in the RCIC minimum flow valve instrument linea in January 199 The RCIC minimum flow valve instrumentation problems were first observed in January 1993 (CR 93-0022A). When the HPCS system was placed in service (with RCIC in a r
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| | Corrective Actions That Will Be Taken To Avoid Further Violations: |
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| | The short term actions to address the Criteria XVI violation include: |
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| standby status) the RCIC minimum flow valve controllogic failed. Since the anomaly did not appear to render the RCIC system inoperable when RCIC was in service, the licensee was not o' rly concerned with the condition. Engineers continued to troubleshoot the '
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| problem for approximately 4 years. On December 31,1996, the CR was closed without correcting the conditio On January 23,1997, at the request of engineering, maintenance workers vented the RCIC minimum llow valve instrument senting lines and found a substantial amount of ai This condition, coupled with HPCS Induced pressure transients (through a common suction line), caused the flow instruments to cycle rapidly and fail. Venting the lines ;
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| appeared to resolve the long standing RCIC problem. No CR was written to document the condition and no actions were taken to vent other instrument lines with high point vents. At the time, engineers did not recall having a similar problem with other instruments so .3y assumed that a generic problem did not exis The following related issues were documented on CR * On October 26,1994, the SSW flow indication was erratic. Further investigation found air in the instrument sensing lines (CR 94-1396). '
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| * On August 30,1991, the indication from the HVK Chiller 1 A flow transmitter was higher than normal when the chi'ler was not in service. Further investigation found '
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| air trapped in the instrument sensing lines (CR 910379). !
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| * On October 25,1987, HPCS instruments were reading erratically. The instrument lines were filled and vented to resolve the proble Prior is the most recent events, River Bend Station engineers had believed that the
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| design of the instrument lines precluded the need for periodic venting, even after system draining. The lines are equipped with a loop seal that inhitits the movement of air from .
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| - the process line to the instrument line NRC ldentified InstaandAttensments:
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| Venting Recommendations: The inspector identified that the licensee did not implement original recommendations for periodic venting of instrument lines with high point vents. In a Stone and Webster document entitled "High Point Vents," dated September 23,1982, the following information was provided to River Bend Str' ion:
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| 'Within the industry, it is understood that high points are undesirable; when they do occur, they must be ventc i . . ."
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| " Anticipated Venting Frequency Required prior to every calibration.
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| _ _ _ _ _ . _ _ _ _ _ ,.. _ __ . __ . ~ _ __ _ __ _ . From a history of venting during calibration, a maintenance schedule could be developed,if required, ' a case by-case basi . When the instruments disagree."
| | * Reinforcement of the expectation that a CR should be generated if a condition investigation or operability determination of a safety related component identifies the potential to affect safety related system operation, indication, or identifies an unexpected response will be provided. |
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| The inspector requested that the licensee provide evidence that the above recommendations were implemented. Ne such evidence was provided to the inspecto Design: The inspector observed that tr's licensee's installation of fbw metenng instruments did not appear to conform with GE design requirements. GE Design
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| - Specification 22A3137AA, Section 4.2.4.2, states, in part:
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| " Installation and arrangement of differential head meters shall conform with the recommendations defined in Chapter 11 - ll of " Fluid Meters" for . . ,
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| onfice and venturi type devices . . , in no case shall the requirements of this specification be violated without specific GE Engineering approval."
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| " Fluid Meters" recommends, in part, the following:
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| For connecting the primary element to the secondary element,1/2 inch tubing and fittings are recommende Contrary to this recommendation,3/8 inch tubing was utilized for portions of the instrument line * Differential oressure measuring gages should be installed in accordance with the specific int,tructions furnished by the manufacturer of the instrument.-
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| The Rosemont vendor manual states that high point vents in liquid instrument sensing lines should be avoide Contrary to this recommendation, Rosemont differential pressure flow transmitters were installed with high points in the instrument line At the close of the inspection pericd, the licensee had not found where approval to deviate from the above recommendations was provided from GE Further NRC review will be necessary to evaluate the apparent failure to: (1) abide by the GE design specification; and (2) follow the Stone and Webster venting recommendations. This is considered an inspector followup item pending further NRC review of these issues (IFl 50-458/9719 04).
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| Corrective Actions: Air in the sensing lines has been a historical problem at River Bend
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| _ Station. Although most CRs were documented several years ago, the licensee missed a more recent opportunity to identify this common mode problem when air was identified in the RCIC minimum flow valve instrument lines in January 1997. Engineering actions in
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| | r e Training will be provided to RBS personnel to emphasize: |
| 16-response to that event were not comprehensive and did not prevent recurrence. More specifically, engineers did not document the problem on a CR, which ultimately resulted in circumynting the licensee's corrective action process. As a result, the cause of the condation was not identified and the potential generic impact of the problem was not properly considered. The failure to take appropriate actions in response to air entrapment in the RCIC minimum flow valve instrument lines (a significant condition adverse to quality)is a violation of 10 CFR Part 50 Appendix 8, Criterion XVI(50-458/9719 05).
| | 1. Expectations with regard to when CRs should be initiated and actions to be taken when the scope of the CR expands. |
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| In addition to the above, the licensee has repeatedly missed opportunities to correct the generic misconception that lines with high point vents don't have to be vented. Even
| | 2. Consideration of broader, generic implications of conditions, including investigation and identification of previous occurrences. |
| , when problems periodically occurred, corrective actions were limited to the instruments directly affected and generic applicability was not properly addresse Weak Operability Oetermination: The inspector observed that, when the HPCS and RHR C minimum flow valve problems were experienced, operators promptly declared the valves inoperable and entered the appropriate TS ACTION Statements. However, when the same problem was observed with RHR B, the valve was not declared inoperable and the TS ACTION was not entere An operations shift superintendent determined that the RHR B minimum flow valve was operable based on a generic operability determination performed by a shift technical advisor (STA). The inspector interviewed the STA to discuss the document and identified that the STA had not properly considered the TS LCO for instrument operability. For example. TS 3.3.5.1 requires, in part, that the RHR B minimum flow valve close at a setpoint greater than 900 gpm - a setpoint less than 900 gpm would require the licensee to call the instrument inoperable. Furthermore, the STA did not have a clear understanding of how the condition (air in the instrument lines) could affect the instrurnent setpoint, potentially affecting instrument operability. The STA indicated that he did not believe that the condition would have resulted in damage to an ECCS pump, but admitted that he did not consider the operability requirements for the flow instruments themselve Since corrective measures were promptly taken to vent the RHR B minimum flow valve, the safety consequences of the oversight were negligible. However, the inspector considered the failure to consider TS operability requirements when making an operability determination to be an example of poor attention to detail when making operability call IV. Plant Suonort Si Conduct of Security and Safeguards Activities S1.1 General Comments (71750) | |
| De routine tours the inspector noted that the security officers were alert at their posts, s6woty boundaries were being maintained properly, and screening processes at the Primary Access Point were performed wel _ _ - _ _ _ _ _
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| | . The trending process will be improved to routinely review maintenance action items, condhion reports and tracking Limiting Conditions of Operation (LCOs) to identify repetitive failures in safety-related equipment and to provide for timely trend CR initiation. |
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| | * ADM-0064 will be revised to clarify when a CR should be initiated during the evaluation ofissues. |
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| V. Management Meetings
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| Xi Exit Meeting Summary The inspectors presented the inspection results to members of licensee management at the conclusion of the inspection on January 15,1998. The licensee acknowledged the findings presente The inspectors asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identifie ,
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| | The long term corrective actions involving the presence of air in transmitter sensing lines included: |
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| | * System configuration will be reviewed to identify other instrumentation with high point vents. |
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| ATTACHMENT SUPPLEMENTAL INFORMATION PARTIAL LIST OF PERSONS CONTACTED Licensta J. P. Dimmette, General Manager, Plant Oporations M. A. Dietrich, Director, Quality Programs
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| D. T. Dormsdy, Manager, System Engineering T. O. Hildebrandt, Manager, Maintenance P. W. Chapman, Superintendent, Chemistry H. B. Hutchens, Superintendent, Plant Security D. N. Lorfing, Supervisor, Licensing J. R. McGaha, Vice President Operations M. G. McHugh, Licensing Engineer lll W. P. O'Malley, Manager, Operations D. L. Pace, Director, Design Engineering ,
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| A. D. Wells, Superintendent, Radiation Control INSPECTION PROCEDURES USED IP 37551: Onsite Engineering IP 61726: Surveillance Observations -i IP 62707: Maintenance Observations I?71707: Plant Operations
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| , IP 71750: Plant Support
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| | * Final procedural guidance will be developed specifying the appropriate venting requirements for instrument line high point vents. This will include a plan for periodic venting. |
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| 2-lTEMS OPENED AND CLOGED Ooened 50-458/9719-01 VIO Failure to Follow Procedures Addressing Electrical deparation Criteria 50-458/9719-02 URI Failure of Containment isolation Damper HVR AOV-165 50-458/9719 03 VIO Failure to Maintain PASS Operable 50-458/9719-04 IFl Failure to Comply with GE Design Recommeridations and Archi'ect Engineers Venting Recommendations for Instrument Sensing Lines 50-458/9719-05 VIO Failure to Take Adequate Corrective Actions to Address Air in Instrument Sensing Lines Closed 50-458/9717 05 URI Air in HPCS Instrument Una Causes Minimum Flow Valve Malfunction
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| 3-LIST OF ACRONYMS USED ADHR alternate decay heat removal CFR Code of Federal Regulations CR condition report ECCS emergency core cooling system EOOS equ:pment out of service computer DG diesel generator HPCS high pressure core spray IFl inspector followup item LCO limiting condition for ope:rability LLRT localle,ak rate testing MAI maintenance ac!ivity item NEO Nuclear Equipment Opsrator NRC U.S. Nuclear Regulatory Commission PASS postaccident sampling system RCIC reactor core isolation cooling RHR residual heat removal SFC spent fuel cooling SPC suppression pool clet.nup SSW standby serWe water -
| | Date When Full Compliance Will Be Achieved: |
| STA shift technical advisor TS Technical Specification URI unresolved item VIO violation
| | Full compliance will be achieved by June 30,1998 upon the completion of the short term i corrective actions. ( |
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.7 A+t NUCLEAR REGULATORY COMMISSION
$ REclON IV
611 RYAN PLAZA DRIVE, SUITE 400 0[ AR LlNGTON, TEXAS 760118064
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MAR 2 51998 John R. McGaha, Vice President - Operations River Bend Station Entergy Operations, Inc.
P.O. Box 220 St. Francisville, Louisiana 70775 l l'
SUBJECT: NRC INSPECTION REPORT 50-458/97-19
Dear Mr. McGaha:
j Thank you for your letter of March 9,1998, in response to our letter and Notice of Violation dated December 24,1997. We have reviewed your reply and find it responsive to the issues raised in our Notice of Violation: a failure of plant workers to maintain appropriate separation criteria l between a safety-related cable tray and a temporary cable; the failure to maintain the postaccident sample system to ensure the capability to take gaseous and liquid samples following an accident; and ineffective corrective actions to address air entrapment in reactor core isolation system instrument lines.
We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintained.
Sincerely, (( 0
.O L Elmo E. Collins, Chief Project Branch C f Division of Reactor Projects I Docket No.: 50-458 License No.: NPF-47 f i cc: I Executive Vice President and Chief Operating Officer Entergy Operations, Inc.
P.O. Box 31995 -
Jackson, Mississippi 39286-1995 9903300131 980325 PDR ADOCK 05000458 G PDR I
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Entergy Operations, Inc. -2-Vice President Operations Support Entergy Operations, Inc.
P.O. Box 31995 Jackson, Mississippi 39286-1995 General Manager Plant Operations River Bend Station Entergy Operations, Inc.
P.O. Box 220 St. Francisville, Louisiana 70775 Director- Nuclear Safety River Bend Station Entergy Operations, Inc.
P.O. Box 220 St. Francisville, Louisiana 70775 Wise, Carter, Child & Caraway P.O. Box 651 Jackson, Mississippi 39205 Mark J. Wetterhahn, Esq.
Winston & Strawn 1401 L Street, N.W.
Washington, D.C. 20005-3502 Manager- Licensing River Bend Station Entergy Operations, Inc.
P.O. Box 220 St. Francisville, Louisiana 70775 The Honorable Richard P. leyoub Attorney General Department of Justice State of Louisiana P.O. Box 94005 Baton Rouge, Louisiana 70804-9005
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Entergy Operations, Inc. -3-H. Anne Plettinger 3456 Villa Rose Drive Baton Rouge, Louisiana 70806 President of West Feliciana Police Jury P.O. Box 1921 St. Francisville, Louisiana 70775 William H. Spell, Administrator Louisiana Radiation Protection Division P.O. Box 82135 Baton Rouge, Louisiana 70884-2135
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Entergy Operations, Inc. -4- MAR 2 51998
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Regional Administrator
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Senior Resident inspector (Grand Gulf)
DRP Director DRS-PSB Branch Chief (DRP/C)~ MIS System Project Engineer (DRP/C) RIV File Branch Chief (DRPfrSS) Resident inspector DOCUMENT NAME: R:\_RB\RB719AK.GDR l To receive copy of document, indicate in box: "C" = Copy without enclosures "E" = Copy wth enclosures "N" = No copy -
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Entergy Operations, Inc. -4- WF . 5 i998 bec distrib. by RIV:
Regional Administrator Senior Resident inspector (Grand Gulf)
DRP Director DRS-PSB Branch Chief (DRP/C) MIS System
' Project Engineer (DRP/C) RIV File Brcnch Chief (DRPli SS) Resident inspector I
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i DOCUMENT NAME: R:\_RB\RB719AK.GDR To receive copy of document, Indicate in box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy RIV:DRP/C , C:DRP/Q),
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U.S. Nuclear Regulatory Commission l"
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i Subject: Reply to Notices of Violation in IR 97-019 --
River Bend Station Unit I -~ ~
License No. NPF-47 i
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Docket No. 50-458
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File Nos.: G9.5.G15.4.1 RBG-44415 RBF1 98-0068
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Ladies and Gentlemen:
Pursuant to the provisions of 10CFR2.201, Attachments A, B and C provide the Entergy Operations. Inc. responses to the Notices of Violation (NOV) described in NRC inspection Report (IR) 50-458/97-019.
We have aggressively reviewed the subject violatiorts with a self-critical perspective to improve Riser Bend Station perfonnance. The lessons teamed are being addressed and integrated into our practices and programs as described in the attachments.
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Should you have any questions regarding the attached information, please contact Mr. David Lorfing of my staff at (504) 381-4157.
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a Reply to Notice of Violation in 50-458/97-019 March 9,1998 RBG-44415
' RBF1-98 0068 Page 2 of 2 cc: Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington,TX 76011
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NRC Sr. Resident Inspector
- P.O. Box 1050 St. Francisville, LA 70775 David Wigginton NRR Project Manager U.S. Nuclear Regulatory Commission M/S OWFN 13-H-3 Washington, DC 20555 l
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ATTACHMENT A Reply To A Notice of Violation IR 50-458/9719-01 Page 1 of 2 Violation:
10 CFR Part 50, Appendix B, Criterion V, states, in part, " Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings . . ."
Updated Final Safety Analysis Report Section 8.3.1.4.2 requires that safety-related cables from different divisions and nonsafety-related cables be separated per the minimum allowable separation distances in Table 8.3.9, " Separation Criteria Allowable Versus Tested." Table 8.3-9 requires one foot of separation between a horizontal tray and a cable.
Procedure ADM-0073, " Temporary Installation Guidelines," Revision 2, Step 5.2, requires that temporary installations adhere to the design separation from divisional cable and that plant personnel be cognizant of the separation requirements of a temporary installation to divisional cabling as specified on Drawing EE-34ZE.
Drawing EE-34ZE, " Standard Details for Separation Requirements," Revision 7, identifies the separation requirements for free air cables to trays as one foot.
~ Contrary to the above, on December 4,1997, an extension cord was draped across safety-related cable Tray ITX817B, with free-air cables, and the required one-foot separation was not maintained.
Reasons for the Violation: ,
A root cause analysis was performed which determined the root causes to be:
* Corrective actions from a previous condition report (CR) for a similar event were not ' '
yet fully implemented. As corrective action from the previous event, procedural changes to ADM-0073," Temporary Installation Guidelines," were made, but l
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Revision 3 of the procedure was not issued and available for plant personnel to use on December 4,1997. Additional means to prevent recurrence (such as temporary power cord tagging) had not been finalized at the time ofinstallation of the cable identified in the subject violation. ;
* Training on the proper installation of temporary electrical cords for the personnel involved had not been completed.
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Corrective Actions Which Have Been Taken and the Results Achieved:
* The subject extension cord was removed.
. ADM-0073, Revision 3 was issued on December 15,1997.
. Potential users of extension cords were notified of the changes to ADM-0073 to ensure that additional emphasis was being provided in Maintenance, Chemistry, l Radiation Protection and Operations. {
e Operations crews performed a walkdown of the plant to identify if other separation discrepancies were present. Items found were corrected. ;
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Corrective Actions That Will Be Taken To Avoid Further Violations: l e A briefing sheet will be prepared to provide Operations department personnel with information regarding the changes to ADM-0073.
. The Operations Superintendent will discuss the requirements of ADM-0073 with Operations crews.
e Tags will be procured which provide the separation criteria of ADM-0073. These ;
tags will be placed on extension cords in the tool room and distributed to other j departments with guidance for their use. j
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e Training covering ADM-0073 will be developed and implemented for plant l
personnel.
e ADM-0073 requirements will be added to the outage handbook.
- The process for handling temporary power cables will be changed to ensure that these cables are issued by the tool room.
Date When Full Compliance Will Be Achieved:
Full compliance was achieved on December 4,1997 when the subject extension cord was removed. Subsequent plant walkdowns were completed by January 31,1998 to ensure ,
that other discrepancies were identified and corrected.
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ATTACHMENT B Reply To A Notice Of Violation I IR 50-458/9719-03 Page 1 of 2 Violation: 1
Technical Specification 5.5 states, in part, "the following programs and manuals shall be established, implemented, and maintained ...
5.5.3 Post Accident Sampling... This program provides controls that ensure the capability to obtain and analyze reactor coolant, radioactive gases, and particulates in plant gaseous effluents and containment atmosphere samples under accident conditions. The program shall include the following... Provisions for maintenance of sampling and analysis {
equipment."
Contrary to the above, between March 3 and December 12,1997, provisions for maintenance of sampling and analysis equipment were inadequate to effectively ensure the capability to obtain and analyze reactor coolant, radioactive gases, and particulates in plant gaseous effluents and containment atmosphere samples under accident conditions.
The post accident sampling system was out of service for approximately 50 percent of the time during the subject period.
Reason For The Violation:
A root cause determination provided the following primary causes: j i
e Monitoring and ownership of the post accident monitoring system (PASS) were ineffective. Some personnel involved in monitoring of the system did not fully understand the scope of their responsibilities or have proper understanding of the impact ofissues on the system. Responsibility for ensuring prompt performance of corrective maintenance was not clearly understood. .,
* The design configuration allowed water intrusion into the dry nitrogen portion of the _
system. Some valves were found to be incorrectly installed. This led to equipment j degradation and system malfunction.
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Corrective Actions That Have Been Taken and the Results Achieved: j
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* A system engineer was assigned responsibility for PASS.
- A modification was installed to provide separation between the dry and wet sides of i
the nitrogen supply to PASS.
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e The PASS has been thoroughly inspected for degradation caused by the water intrusion.
e The incorrectly installed valves in the PASS sample station have been correctly installed.
- Other potential sources of water intrusion were researched and determined not to be {
valid sources of water intrusion.
- A walkdown was performed to ensure that plant configuration and design configuration match.
- Chemistry PASS sampling procedure, COP-1001, has been revised to include information related to pressurization of the system water tank. This will minimize the potential for water intrusion.
Corrective Action That Will Be Taken To Avoid Further Violations:
* Operations shift superintendents, control room supervisors, maintenance supervisors and work week managers will review Operations Policy 6," Active Limiting Conditions of Operation," to reinforce management expectations with respect to the use oflimiting conditions of operation.
l e An evaluation will be performed to determine if a process to review the accumulated effects of repeated entry into tracking LCOs (Limiting Conditions of Operation) is needed. l
e Other maintenance rule scoped systems will be evaluated to ensure proper assignment j of system ownership.
- Responsibilities for personnel outside system engineering who "own" systems will be !
clarified. Personnel outside system engineering who "own" a system will be informed of their responsibilities.
* A procedure will be developed describing how PASS satisfies Technical Specification 5.5.3 including the expectations and responsibilities of the various departments involved, o Engineering will evaluate and take appropriate action to ensure proper -
implementation of other similar programs identified in Technical Specification 5.5.
Date When Full Compliance Will Be Achieved:
Full compliance was achieved on March 7,1998 when the limiting condition on operation was removed.
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a ATTACHMENT C Reply To A Notice of Violation IR 50-458/9719-05 Violation
"10 CFR Part 50, Appendix B, Criterion XVI, states, in part, " Measures shall be established to assure that conditions adverse to quality, such as . . malfunctions ... are promptly identified and corrected. In the case of significant conditions adverse to quality, the measures shall assure that the cause of the condition is determined and corrective
. actions taken to preclude repetition . . ."
Contrary to the above, on January 23,1997, a significant amount of air was found in reactor core isolation cooling flow instrument sensing lines (a significant condition adverse to quality) but established measures did not assure the cause of the air entrapment was identified, and actions were not taken to preclude repetition. Consequently, the following problems were observed due to air entrapment in other system flow instrument lines: (1) on November 11,1997, the high pressure core spray minimum flow valve malfunctioned; (2) on December 11,1997, the residual heat removal Train C minimum flow valve malfunctioned; and (3) on December 12,1997, the residual heat removal Train B minimum flow valve malfunctioned."
Reasons for the Violation:
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Spurious gross failure nuisance alarms had been received in the RCIC (Reactor Core Isolation Cooling) flow transmitter circuit while running the HPCS (High Pressure Core Spray) system and were identified on a condition report in 1993. The condition report was dispositioned with the cause not determined. During the course of a follow-up review of the spurious gross failure alarms including the documented reports, an engineer was led to suspect air in the instrument sensing lines. A maintenance action item was generated on January 23,1997, and RCIC flow instrument sensing line high point vents were vented as part of the investigation into the above' mentioned long standing problem
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involving the receipt of spurious gross failure alarms. Air was found in the high point vent. The system engineer realized that other ECCS (Emergency Core Cooling Systems)
systems could have a simila problem and investigated further by reviewing the ADM-0064 log (Spurious Instrument Trip Log), walking down ECCS systems, checking system l
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indications and discussing the situation with other engineers and operations personnel.
. Based on this investigation, he concluded that other systems were not exhibiting symptoms of this problem and that a Condition Report (CR) was not warranted.
A root cause team was assigned to investigate the cause of the Criterion XVI violation.
The root cause was determined to be less than adequate communication and enforcement
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e of the condition report initiation threshold. The definition of when to initiate a condition report versus a maintenance work document while troubleshooting equipment is not clear.
The root cause team also evaluated previous similar conditions. Causes for these conditions were identified and are being addressed as part of the River Bend Station (RBS) corrective action program.
Corrective Actions That Have Been Taken and the Results Achieved:
As an interim action, a memorandum was issued by the General Manager Plant Operations to RBS personnel addressing management expectations conceming condition report initiation threshold.
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Corrective actions involving the presence of air in transmitter sensing lines was discussed in LER 97-010 as submitted on December 11,1997 and supplemented on February 26, l 1998. The completed actions to resolve this issue included:
. Maintenance and System Engineering personnel conducted troubleshooting to j determine the cause of the minimum flow valve failure.
e The sensing lines from the HPCS pipe to the flow transmitter were vented at the high point vents to remove air indicated by troubleshooting.
. The HPCS pump was run and no abnormalities were noted.
. Following the discovery of air in Residual Heat Removal (RHR) B and C transmitter sensing lines, a team of engineering, operations, and maintenance personnel reviewed safety related instrumentation to determine other susceptible transmitters. As a result, six additional locations were vented.
- An Operations Department Standing Order was issued to direct the venting of instrument lines with the high point vents when necessary.
- Instrumentation technicians and planners were made aware of the effects of entrapped air on instrumentation, and the need to vent instrumentation high point vents.
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Corrective Actions That Will Be Taken To Avoid Further Violations:
The short term actions to address the Criteria XVI violation include:
* The guideline delineating when a condition report should be written will be clarified.
- Reinforcement of the expectation that a CR should be generated if a condition investigation or operability determination of a safety related component identifies the potential to affect safety related system operation, indication, or identifies an unexpected response will be provided.
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r e Training will be provided to RBS personnel to emphasize:
1. Expectations with regard to when CRs should be initiated and actions to be taken when the scope of the CR expands.
2. Consideration of broader, generic implications of conditions, including investigation and identification of previous occurrences.
. The trending process will be improved to routinely review maintenance action items, condhion reports and tracking Limiting Conditions of Operation (LCOs) to identify repetitive failures in safety-related equipment and to provide for timely trend CR initiation.
- ADM-0064 will be revised to clarify when a CR should be initiated during the evaluation ofissues.
The long term corrective actions involving the presence of air in transmitter sensing lines included:
* System configuration will be reviewed to identify other instrumentation with high point vents.
- Final procedural guidance will be developed specifying the appropriate venting requirements for instrument line high point vents. This will include a plan for periodic venting.
- Training on this issue will be provided to appropriate operation's and maintenance personnel. !
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Date When Full Compliance Will Be Achieved:
Full compliance will be achieved by June 30,1998 upon the completion of the short term i corrective actions. (
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