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| {{Adams | | {{Adams |
| | number = ML20214D258 | | | number = ML20198E570 |
| | issue date = 11/13/1986 | | | issue date = 05/09/1986 |
| | title = Mgt Meeting Repts 50-277/86-08 & 50-278/86-08 on 861016. Major Areas Discussed:Licensee Identified Noncompliances of 10CFR50,App R Requirements & Plans to Achieve Compliance, Including Timetable for Completing Mods | | | title = Insp Repts 50-277/86-08 & 50-278/86-08 on 860317-21.No Violation Noted.Major Areas Inspected:Fire Protection Features to Ensure Ability to Achieve & Maintain Safe Shutdown in Event of Fire |
| | author name = Anderson C, Krasopoulos A | | | author name = Anderson C, Krosopoulos A |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| | addressee name = | | | addressee name = |
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| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-277-86-08-MM, 50-277-86-8-1, 50-277-86-8-MM, 50-278-86-08, 50-278-86-8, NUDOCS 8611210440 | | | document report number = 50-277-86-08, 50-277-86-8, 50-278-86-08, 50-278-86-8, NUDOCS 8605280063 |
| | package number = ML20214D232 | | | package number = ML20198E563 |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS |
| | page count = 9 | | | page count = 10 |
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| U.S. NUCLEAR REGULATORY COMMISSION | | U.S. NUCLEAR REGULATORY COMMISSION |
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| ==REGION I== | | ==REGION I== |
| 50-277/86-08 Report Nos. 50-278/86-08 50-277 Docket Nos. 50-278 DPR-44 License Nos. DPR-56 Priority --
| | Report N /86-08 and 50-278/86-08 Docket N /50-278 License No. DPR-44 and DPR-56 Priority - |
| Category C Licensee: Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101 Facility Name: Peach Bottom Units 2 & 3 Meeting at: U.S. NRC, Region I, King of Prussia | | Category C Licensee: Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101 Facility Name: Peach Bottom Atomic Power Station Units 2 and 3 Inspection At: Delta, Pennsylvania Inspection Conducted: March 17-21, 1986 Inspector: ie Nf Nac4- Y _ /9/6 A. Krasopoul'os, Re%ctor Engineer, DRS |
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| Meeting conducted: October 16, 1986 NRC Personnel: ~-
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| _g[/ 3 !88 A: 'G.V Kra sopou10:. , Reactor Engineer, DRS ' date Approved by: b //
| | Also participating in the inspection and contributing to the report were: |
| C. #nderson, Chief, Plant Systems Section date Meeting Summary: Management Meeting at the NRC Region I office on October 16, 1986 to discuss licensee identified non-compliances of the 10CFR50, Appendix R requirement The licensee described the non-compliances and the interim compensatory actions taken pendina full compliance with the requirement The licensee also described their plans to achieve full compliance and they presented a timetable for completing the modifications required for compliance.
| | J. Stang, Fire Protection Specialist, NRR K. Parkinson, Electrical System Specialist, BNL A. Coppola, Mechanical Systems Specialist, BNL |
| | , Approved by: ~ St2A,A >>44/ //9 f/o 3 3''d*DRS ElSection, "' " '"T* ' "' * "'V It''** ' '''' |
| | Inspection Summary: Inspection on March 17-21, 1986 (Combined Report N /86-08 and 50-278/86-08) |
| | Areas Inspected: Special, announced team inspection of the licensee's efforts to comply with the requirements of 10 CFR 50, Appendix R, Sections III. G, J and L, concerning fire protection features to ensure the ability to achieve and maintain safe shutdown in the event of a fir Results: No violations were identifie Five items remained unresolved at the end of the inspectio , PDR ADOCK.0500 e - |
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| | DETAILS 1.0 Persons Contacted 1.1 Philadelphia Electric Company (PECO) |
| | * H. Abendroth, Co-owner Site Representative |
| | * W. Birely, St. Licensing Engineer |
| | * W. Boyer, Electrical Supervising Engineer |
| | * G. Brecht, Jr., Chief Electrical Engineer |
| | * G. Cambell, Senior Designer |
| | * R. Dellangelo, Designer |
| | * R. Fleischmann, Plant Manager |
| | * C. Gerdes, Mechanical Engineer |
| | * M. Lohr, Electrical Engineer R. Lonabaugh, Fire Marshal |
| | * J. McCawley, Electrical Engineer |
| | * W. Mindick, Sr. Electrical Engineer |
| | * G. Morley, Supervising Engineer J. Pizzolo, QA Engineer |
| | * G. Reid, Sr. Mechanical Engineer |
| | * M. Ryan, Compliance Engineer |
| | * 0. Spaner, Engineer |
| | * S. Spitko, Administrative Engineer |
| | * C. Swenson, Compliance Engineer |
| | * G. Termine, Engineer |
| | * W. Ullrich, Superintendent Nuclear Generation Division T. Wilson, Site QA Supervisor 1.2 Licensee Contractors |
| | * A. Melikian, Project Engineer (EPM) |
| | * D. Brecken, Project Manager-(EPM) |
| | 1.3 Nuclear Regulatory Commission (NRC) |
| | * T. Johnson, SRI |
| | * G. Gears, Project Manager J. Williams, RI |
| | * Denotes those present at exit intervie .0 Purpose This team inspection was conducted to ascertain licensee compliance with 10 CFR 50, Appendix R, Sections III. G, J, and O. Because full compliance with the above regulations is not required until the end of the next i Unit 2 refueling outage, the team reviewed the licensee's approach to compliance, along with the plans and schedules for completing all other modifications required in this are I i |
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| 8611210440 DR 861114 ADOCK 05000277 PDR i
| | 3.0 Background 10 CFR 50.48 and 10 CFR 50, Appendix R, became effective on February 17, 198 For Peach Bottom Units 2 and 3, the applicable portions of this regulation are Sections III.G, " Fire Protection of Safe Shutdown Capa-bility," III.J, " Emergency Lighting," and III.L, " Alternative and < |
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| | Dedicated Shutdown Capability." |
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| | 10 CFR 50.48 sets forth the schedule for the completion of modifications required for compliance with the above regulations. Section III.G of Appendix R requires that fire protection features are provided to ensure ~ ~ ~~~ ~ |
| | that one train of equipment necessary to achieve and maintain safe shut-down remains available in the event of a fire at any location within a licensed operating facility. For hot shutdown conditions, one train of the systems necessary must be free of fire damage (III.G.I.a). For cold shutdown conditions, repair is allowed using in place procedures and materials available onsite with the provision that cold shutdown be achievable within 72 hours of the initiating event (III.G.1.b). Section III.G.2 lists specific options to provide adequate protection for redun-dant trains of equipment located outside of the primary containmen These options are: |
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| | Separation by a fire barrier having a three hour rating (III.G.2.a). |
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| | Separation by a horizontal distance of at least 20 feet with no in-tervening combustibles and with fire detection and automatic fire suppression installed in the fire area (III.G.2.b). |
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| DETAILS 1.0 Participants
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| 1.1 Philadelphia Electric Company (PECO)
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| W. Alden, Engineer in Charge, Licensing W. Birely, Senior Engineer, Licensing W. Boyer, Supervising Engineer W. Brady, Engineer R. Lees, Assistant Chief Electrical Engineer W. Mindick, Senior Engineer
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| G. Morely, Supervising Engineer G. Reid, Senior Engineer C. Swenson, Compliance D. Spaner, Engineer G. Termino, Engineer U.S. Nuclear Regulatory Commission (USNRC)
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| C. Anderson, Chief, Plant Systems Section J. Durr, Chief, Engineering Programs Branch
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| | Enclosure of one train in a fire barrier having a one hour rating in addition to having fire detection and automatic suppression installed in the fire area (III.G.2.c). |
| P. Eselgroth, Chief, Projects Section 2A G. Gears, NRR Project Manager T. Johnson, Senior Resident Inspector
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| , A. Krasopoulos, Reactor Engineer S. Pullani, Lead Reactor Engineer 2.0 Background The inspection of Peach Bottom Units 2 and 3 during March 17-21, 1986 for compliance with the 10CFR50, Appendix R requirements resulted in the issuance of a Conformatory Action Letter (CAL) by the Region on April 11, 1986.
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| r The CAL specified the licensee's schedule to complete the Appendix R Safe Shutdown confirmatory program and stated that they would inform the Region
| | If the protection required by Section III.G.2 is not provided or the systems of concern are subject to damage from fire suppression . |
| ; if any violations from the Appendix R requirements are identified.
| | activities, Section III.G.3 of the rule requires that an alternate or dedicated shutdown capability be provided which is independent of the area of concern. Any alternate or dedicated system requires NRC review and approval prior to implementation. |
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| l The purpose of this Management Meeting was to discuss: the Appendix R violations identified by the licensee as requested by the CAL; the interim compensatory actions taken and the long term corrective actions planned by the license .0 Presentation and Discussion Following the initial introductions, Mr. Jacque Durr, Chief of the l
| | For situations in which fire protection does not meet the requirements of-- |
| | Section III.G, however, such protection is deemed to be adequate by the licensee for the specific situation, the rule allows the licensee to request an exemption on a case-by-case basi Such exemption requests are submitted to the NRC for review and approval and must be justified by the licensee on a technical basi l Presently the licensee must comply with all of the requirements iterated |
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| Engineering Programs Branch opened the meeting by asking the licensee to describe the violations as identified by their safe shutdown re-evaluation.
| | above. One exemption from full compliance is the modification work associated with the alternative shutdown capability for Unit 2. Since some of the alternative shutdown systems are common to both units, alter- ! |
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| | native shutdown capability is not required for either unit until the end of the next Unit 2 refueling outage. Also, because the licensee is developing a more detailed fire hazards analysis, compliance with section III.G and J. could not be fully ascertained. The analysis will be completed by September 30, 198 .0 Post-Fire Safe Shutdown Capability 4.1 Systems Required for Safe Shutdown In the event of a fire concurrent with the loss of offsite power, the~ ~~ ~ |
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| | following systems are used to provide the safe shutdown capability of the plant: |
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| The licensee distributed a document titled " Appendix R Task Force Deficiency Summary" which is included as Attachment 1 to this repor The licensee proceeded to explain that their re-evaluation of the safe shutdown capability identified about 50 deficiencies in about 20 fire area The deficiencies were classified as falling into three categories: | | High Pressure Coolant Injection (HPCI) System |
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| | Reactor Core Isolation (RCIC) System |
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| | Automatic Depressurization (ADS) and non-ADS Safety Relief Valves (SRVs) |
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| | Residual Heat Removal (RHR) System-shutdown cooling mode, suppression pool cooling mode, and low pressure coolant injection (LPCI) mode |
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| | Core Spray (CS) System |
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| | High Pressure Service Water (HPSW) System |
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| | Emergency Service Water (ESW) System |
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| Changes in initial assumptions
| | Onsite AC Power Generation and Distribution System |
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| Spurious Operation
| | Onsite DC Power Generation and Distribution System |
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| Other items The licensee stated that they have established, as an interim compensatory '
| | Essantial Ventilation Systems Safe shutdown is initiated from the control room by a manual scram of the control rods or automatically by the reactor protection syste The support systems required for safe shutdown include the emergency service water system (ESW) for diesel generator cooling, high pressure service water system (HPSW) for RHR heat exchanger cooling, onsite AC emergency power system, onsite DC Emergency power system and essential ventilation system The precise methodology used for safe shutdown has not been finalized by the licensee. Currently, the following shutdown methods are under review: |
| measure, fire watches to patrol the affected areas pending their achieving full complianc The adequacy of the fire watches established by the licensee was questioned by Regional Management. The licensee indicated that they would consider enhancing their program of interim fire watche The licensee stated _that Unit 2 compliance would be given highest priorit Full compliance with Appendix R for Unit 2 is scheduled for the end of the spring 1987 refueling outag However, for Unit 3 full compliance is scheduled for the next Unit 3 refueling outage in late 1987. Regional Management stated that a I
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| justification for continued operation should be prepared for NRC review.
| | For Method A, RCIC is used to maintain reactor vessel coolant inven-tor RHR and HPSW are used for suppression pool cooling which is required for decay heat remova Heat is transferred from the vessel to the suppression pool via the ADS system and/or the RCIC steam turbine discharg _ _ _ _ - _ . |
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| | Method B For Method B, HPCI is used to maintain reactor vessel coolant inven-tory, RHR and HPSW are required as in method A for suppression pool cooling. Heat is transferred from the vessel to the suppression via the ADS system and/or the HPCI steam turbine discharg Method C For Method C, the reactor is depressurized using the ADS system to a point where either the Core Spray or the LPCI mode of the RHR' - ~ ~ - |
| | systems can be used to maintain core inventor Method D Method D, is the alternative shutdown method for a catastrophic fire in either the Control Room, Cable Spreading Room or the Emergency Shutdown Panel Are This method is described in the following sectio .2 Alternate Safe Shutdown Areas The licensee committed to and is in the process of_ establishing alternate safe shutdown capability independent of the main control room, cable spreading room and the emergency shutdown panel are The alternative shutdcwn stations are provided with circuit isolation capability using manual control switches, relays, breakers or fuse-disconnect switches, to ensure that no electrical connection exists between the alternative shutdown circuits and those affected by a fire in any one of the above-mentioned area In the event of an unmitigated fire in these areas, the operators will proceed to the alternative shutdown stations to initiate shut-down operation Communications will be established between the operators who are at the alternative shutdown stations and the coordinating operator. The alternative control stations for Peach Bottom are or will be in the following locations: |
| | 4. HPCI Alternative Control Station - This panel will be located in each unit in the MG set room at elevation 135' - 0". The-HPCI alternative control station will be equipped with pump diagnostic instrumentation and transfer switches and alternative power supplies for the HPCI turbine. This panel will be equipped - |
| | with the alternative process monitoring instrumentation which indicates reactor vessel pressure and level, suppression pool temperature, and condensate storage tank leve . Diesel Generators Alternative Control Station - These panels will be located in Unit 2 4KV emergency switchgear rooms B/D and are common to both Units 2.and 3. The panels will be equipped with transfer switches to isolate all main control room control circuits, and also diesel generator diagnostic instrumentatio _ _ |
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| | 4. KV Emergency Switchgear Alternative Controls - These controls are located in the 4KV emergency switchgear rooms in each unit. Transfer switches will provide alternative local control and status indication for the motor control centers and for the ESW, RHR and HPSW pump . ADS Transfer / Isolation Station - Alternative control capabilities for 3 ADS valves and the associated nitrogen supply isolation valves will be located on the HPCI Alternative Control Stations in the M-G Set Rooms. The transfer / isolation switches for these controls are located in the 4KV switchgear rooms. The remote locations for the transfer / isolation switches are necessary to preserve safe shutdown capability for the M-G Set Room . RHR/HPSW Suppression Pool Alternative Control Stations - |
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| | Alternative control capabilities and transfer / isolation switches for one loop of RHR/HPSW Motor Operated Valves (MOV's), needed to support Suppression Pool Cooling, will be located at the HPCI Alternative Control Stations in the M-G Set Room .3 Remaining Plant Areas The licensee indicated that all other areas of the plant not required to have an alternate safe shutdown system, comply with the requirements of Section III.G.2 of Appendix R, unless an exemption request has been approved by the staf .0 Inspection Methodology The inspection team examined the licensee's provisions for separating and protecting equipment, cabling and associated circuits necessary to achieve and maintain hot and cold shutdown conditions. This inspection sampled selected fire areas which the licensee had identified as being in compli-ance with Section II The following functional requirements were reviewed for achieving and maintaining hot and cold shutdown: |
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| Attachment 1 PHILADELPHIA ELECTRIC COMPANY APPENDIX R SAFE SHUTDOWN ANALYSIS AGENDA i
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| Introduction W. M. Alden R. J. Lees Overview of Task Force Review W. J. Boyer Deficiencies and Causes W. J. Mindick Compensatory Actions W. C. Birely Corrective Actions W. J. Boyer Implementation of Corrective Actions W. J. Boyer l
| | * Reactor coolant makeup |
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| | Process monitoring |
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| APPENDIX R TASK FORCE DEFICIENCY SUMMARY I. Changes in initial assumptions:
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| l Associated DC loads were not included in the battery calcula-tions. Calculations now include the largest credible high im-pedance fault. The effect is that batteries are depleted at a faster rat Area Parameter 13N-I Instrument power * (MOD 2085)
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| 2-III DG exciter control (MOD 2078)
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| 2-IV Reactor press, torus temp, drywe11 tem (MOD 2085, 1029E)
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| *These items also resulted from the censolidation of fire areas without proper review of instrumention concern Hot shorts and grounds on the ungrounded DC system were originally assumed to not cause undesired effect Un-grounded DC systems are new assumed to become grounded as a result of the fire and the potential for blown control fuses and spurious operation are now included in the analysi Area Effect 43II, 44I, 45I, 46I Blown control power fuse for ESW (MOD 1351D)
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| 37-II, 38-I, 39-I, 48-I, 50-II Blown control power fuse for ESW (MOD 1351D)
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| 351, 36II, 37III Tripping of RHR pump breaker (MOD 2078)
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| 6S-I Tripping of HPCI (MOD 1457)
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| turbine Previous analyses did not address putting excess inventory into the reactor vessel. The analysis now reflects the need to shut down systems which are not required for safe shutdown but which could cause the loss of the safe shutdown capabil-ity by overfilling the reacto . . ,__ . _ - - -- . -
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| Appandix R Task Force -2-
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| Deficiency Summary
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| | The inspection team examined the licensee's capability to achieve and maintain hot shutdown and the capability to bring the plant to cold shut-down conditions in the event of a fire in various areas of the plant. The examination included a review of drawings, safe shutdown procedures and other documents. Drawings were reviewed to verify electrical independence from the fire areas of concern. Procedures were reviewed for general content and feasibilit Also inspected were fire detection and suppression systems and the degree of physical separation between redundant trains of Safe Shutdown Systems (SSSs). The team review included an evaluation of the susceptibility of' - |
| | the SSSs to damage from fire suppression activities or from the rupture or inadvertent operation of fire suppression system The inspection team examined the licensee's fire protection features provided to maintain one train of equipment needed for safe shutdown free of fire damage. Included in the scope of this effort were fire area boundaries, including walls, floors and ceilings, and fire protection.of |
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| Area Effect 6S-I, 13N-III, 13S-II Inability to isolate
| | openings such as fire doors, fire dampers, and penetration seal The inspection team also examined the licensee's compliance with Section III.J, Emergency Lighting. Section III.0, Oil Collection System for Reactor Coolant Pump is not applicable to the licensee since the contain-ment is inerted during normal operations. |
| . HPCI (MOD 2080)
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| 25-IV Inability to isolate RCIC (MOD 1352A,
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| i Previous analyses did not include consideration of separation between manholes for imbedded conduit The analysis now examines the separation between redundant cables within the various compartments of the manhole Area Effect
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| 50-II Less than 3 hr. sep-Yard aration between re-dundant HPSW/ESW
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| : pumps (MOD 2078)
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| Yard Less than 3 hr. sep-aration between re-dundant DG cable (MCD 2091) Previous analyses assumed that instrument air could be es-tablished for a fire in Fire Area 13S by cross-connecting the
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| ! Unit 2 and Unit 3 headers. It has been determined that this solution is not feasible due to timing constraints and the possibility that parallel air headers may be damaged by the fire such that pressure could not be maintained. (FA-13SIII MOD 1950)
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| ; Previous Hi/Lo pressure boundary analyses did not factor the environmental effects of a Hi/Lo pressure boundary failure into the safe shutdown analysis. Fire damage to the control cables of the RPV head vent valves could result in the in-crease of drywell temperature, which has potential adverse effects on equipment operabilit I Spurious operations
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| ! Spurious operations that occur at inopportune times could re-sult in equipment damage.
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| | ) 6.0 Inspection of Protection Provided for Safe Shutdown Systems 6.1 Protection in Various Fire Areas The team reviewed the protection prov'ided to SSSs in selected fire areas for compliance with Appendix R, Sections III.G.1, 2 and The following fire areas were inspected: |
| ! Fire damage to logic cables in the RHR system could
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| cause the RHR pump-breakers to close prior to power being available from the emergency bu If this oc-curs, the breaker logic will trip and lock up and must be cleared at the switchgear prior to restarting the pum (FA-34-III MOD 2078)
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| | The Cable Spreading Room |
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| | 'The Switch Gear Room |
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| | The Battery Room |
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| | The Intake Structure (Fire Areas 47 and 48) |
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| | The Turbine Building |
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| | The Reactor Building, Fire Areas 5, 6, 12 and 13 |
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| , Appendix R Task Force -3-Deficiency Summary 4 Fire damage to logic cables could start the RHR pumps with no minimum flow protection on the pump. The avail-able time before damage occurs to the RHR pump is con-
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| sidered to be too short for the operator to recognize the situation and to take manual action to secure the
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| ! RHR pum (FA-6S-II, 13N-II MOD 2084) Spurious operations of equipment or components that could de-feat system function that were overlooked or not included in previous analyse . Fire damage to the fire protection system cables in the diesel generator building could initiate CO, injection in individual diesel bays. Since the dieser takes com-bustion air from its room, the diesel would stop on loss of ai (FA-44II, 45II, 46II, 54II MOD 2078) Fire damage to control cables for the ESW sluice gates could cause these gates to close and block ESW flow path. (FA-25II, 39II, 50I lock open sluice gates) Fire damage to control cables for the ESW discharge valve could cause the valve to close and block the ESW flow pat This item was identified, but not installed for Alternative Shutdown and overlooked for Safe Shutdow (2-I, 25-III, 34-II, 36-III, 43-I, 54-I MOD 2079) Fire damage to logic cables for HPCI could isolate the system. (13S-I MOD 2078) Fire damage to bus current transformer cables could trip the bus and lockout the diesel generator breaker (34-I, 35-II, 36-I, 37-I MOD 2078) Fire damage to control cables for a HPCI AC valve could cause the valve to close and disable the HPCI syste (FA-25I Mod 1352A, 1353A)
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| : II Other items 1 The field walkdown of safe shutdown conduits identified that some safe shutdown conduits were inaccurately shown on de-sign drawings. (2-II MOD 2085) Fire damage in FA-30 results in the loss of both the primary and backup power sources to the RHR and HPSW flow instrument (MOD 1029E, 2085)
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| . Appendix R Task Force -4-Deficiency Summary Emergency lighting was installed for analyses submitted 9/16/83, 7/11/83, and 7/22/83. During subsequent analysis, further installations of emergency lighting was de ferred pending final design of Alternative Shutdown and completion of the Safe Shutdown reverification program. The locations have now been identified (Table A-4 of FPP) and design for installation is in progress. (MOD 2081) Fire damage results in the loss of power to a diesel genera-tor auxiliary motor control center. The diesel is used for safe shutdown in the area. (6N-II, 40-I MOD 2078) The associated circuit analysis identified one molded case circuit breaker which requires a trip setpoint change to pro-vide proper coordinatio (Associated circuit by common power source) (MCD 2083) The associated circuit analysis identified a motor control center section 20DllA separated from its main motor control center 20Dll that had no overcurrent protection. (Associated circuit by common enclosure) (MOD 13S2A, 1353A) Fire damage in Unit 3 results in the loss of a Unit 3 torus temperature loop fed from a common unit power supply. (13N-I)
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| I Previously identified items Unit 2 Process and Diagnostic Instrumentatio Previous commitment was for end of upcoming Unit 2 re-fueling outag (Mod 1029E) Frovide thermal magnetic trip devices to MCC Previous Associated Circuit Analyses identified need for thermal magnetic breaker Modification was on hold pending equipment qualification of device (Mod 1029J, K, L) Spurious closure of HPCI and RCIC steam valves The potential for these valves to defeat system operation was identified during the 3/86 audit and reported en 5/22/86. This report identified the condition on one RCIC valve and one HPCI valve. The reverification iden-tified the concern on one additional RCIC valv (Mod 2079) Unit 2 relief valve capability Previous commitment was for end of upcoming Unit 2 refueling outage (Mcd 1950)
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| . | | The Radwaste Building, Fire Areas 2 and 25 |
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| . | | Yard Area Manholes 25, 89 and 90 No unacceptable conditions were identified except as follows: |
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| | Inspection effort incomplete because of unfinished analysi The inspection team could not ascertain the licensee's compliance with Section III.G of Appendix R because the analysis identifying the shutdown methodology had not been finalized at the time of the inspection. This is an unresolved item pending completion of the analysi (50-277/86-08-01 and 50-278/86-08-01) |
| ;- . Appendix R Task Force -5-Deficiency Summary
| | 6.2 Safe Shutdown Procedures The team requested to review safe shutdown and alternative shutdown procedures to ascertain that shutdown can be achieved in a safe and orderly manne The licensee stated that these procedures have not been developed as yet but will be in effect by the end of the next Unit 2 refueling outage. This is in agreement with previous commitments made to the NR This is an unresolved item pending licensee completion of the procedure (50-277/86-08-02 and 50-278/86-08-02) |
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| | 6.3 Protection for Associated Circuits Appendix R, Section III.G requires that protection be provided for associated circuits that could prevent operation or cause malopera-tion of redundant trains of systems necessary for safe shutdow The circuits of concern are generally associated with safe shutdown circuits in one of three ways: |
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| | Common bus concern |
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| | Spurious signals concern |
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| | Common enclosure concern |
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| | The associated circuits were evaluated by the team for common bus, spurious signal, and common enclosure concerns. . Power, control, and instrumentation circuits were examined on a sampling basis for potential problem . Common Bus Concern-The common bus concern may be found in circuits, either safety related or non-safety related, where there is a common power source with shutdown equipment and the power source is not electrically protected from the circuit of concer . |
| | . 9 The team examined, on a sampling basis, protective relay coordination for 4160V and 480V buses and protection for specific instrumentation, control and power circuits. The coordination of fuses and circuit breakers was checked by examination of the licensee's fuse and breaker coordination curves. The licensee performs relay calibration during refueling outages on approximately 18 month interval No unacceptable conditions were identifie .3.2 Spurious Signals Concern ~ ~~ - |
| | The spurious signal concern is made up of 2 items: |
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| | False motor control and instrument indications can occur such as those encountered during the 1975 Browns Ferry fire. These could be caused by fire initiated grounds, short or open circuit * |
| | Spurious operation of safety related or non-safety related components can occur that would adversely affect shutdown capability (e.g., RHR/RCS isolation valves). |
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| i i Testable check equalizer valves on RHR and CS.
| | The team requested to review documents, on a sampling basis, in the following areas to ascertain that no spurious signal concern exists: |
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| | Current transformer secondaries |
| | * High/ low pressure interfaces |
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| | General fire instigated spurious signals The licensee explained that an associated circuit analysis for spurious signals is currently being developed but is not yet finishe This is an unresolved item pending the licensee's comple-tion of an associated circuits analysis for spurious signal (50-277/86-08-03 and 50-278/86-08-03). |
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| ; Previous Hi/Lo pressure boundary analysis identified
| | 6.3.3 Common Enclosure Concern The common enclosure concern may be found when redundant circuits are routed together in a raceway or enclosure and they are not electrically protected or when a ~ fire can destroy both circuits due to inadequate fire barriers. The team could not inspect this area since the licensee's analysis was incomplete. The licensee stated that this analysis is currently in proces .. |
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| | , 10 This is an unresolved item pending licensee completion of the analysis and reinspection in this are (50-277/86-08-04 and 50-278/86-08-04) |
| need to address valves. Mechanical analysis now demon-
| | 7.0 Emergency Lighting 10 CFR 50, Appendix R, Section III.J, requires that emergency lighting units with at least an 8-hour battery power supply shall be provided in all areas needed for operation of safe shutdown equipment and in access and egress routes theret ~. - _ . - -. |
| , strates failure as acceptable. | | Due to lack of safe shutdown procedures, the team was not able to inspect this area. This item remains unresolved. (50-277/86-08-05 and 50-278/86-08-05) |
| | 8.0 Oil Collection System for Reactor Coolant Pumps 10 CFR 50, Appendix R, Section III.0, requires that the reactor coolant pumps shall be equipped with an oil collection system if the containment is not inerted during normal operation. As the containment for either unit is inerted during normal operation, the above requirement does not apply to Units 2 or .0 _ Unresolved Items Unresolved items are matters for which more information is required in order to ascertain whether they are acceptable, violations, or deviation Unresolved items are discussed in Sections 6.1, 6.2, 6.3 and .0 Exit Interview The inspection team met with the licensee representatives, denoted in Section 1.0, at the conclusion of the inspection on March 21, 1986, and the team leader summarized the scope and findings of the inspection at that time. |
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| 1 Unit 2 and Common Alternative Shutdown ~
| | , The team leader also confirmed with the licensee that the report will not contain any proprietary information. The licensee agreed that the inspection report may be placed in the Public Document Room without prior licensee review for proprietary information (10 CFR 2.790). |
| i Previous commitment was for end of upcoming Unit 2 re-j fueling outage (Mod 1351,1352) -
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| | At no time during this inspection was written material provided to the licensee by the team. |
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Category:INSPECTION REPORT
MONTHYEARIR 05000277/19990071999-10-19019 October 1999 Insp Rept 50-277/99-07 & 50-278/99-07 on 990810-0922.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000277/19990051999-07-27027 July 1999 Insp Repts 50-277/99-05 & 50-278/99-05 on 990518-0628. Non-cited Violations Noted.Major Areas Inspected:Operations, Surveillances & Maintenance,Engineering & Technical Support & Plant Support Areas IR 05000277/19990041999-06-11011 June 1999 Insp Repts 50-277/99-04 & 50-278/99-04 on 990405-0517. Non-cited Violation Noted.Major Areas Inspected:Operations, Surveillances & Maintenance,Engineering & Technical Support & Plant Support Areas IR 05000277/19990011999-03-25025 March 1999 Insp Repts 50-277/99-01 & 50-278/99-01 on 990105-0215.No Violations Noted.Major Areas Inspected:Operations, Surveillances & Maint,Engineering & Technical Support & Plant Support Including Security & Safeguards Activities IR 05000277/19980111999-02-0101 February 1999 Insp Repts 50-277/98-11 & 50-278/98-11 on 981110-990104. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000277/19980091999-02-0101 February 1999 Insp Repts 50-277/98-09 & 50-278/98-09 on 981116-1204. Violations Noted.Major Areas Inspected:Reactor Core Isolation Cooling & 4kV Electrical Distribution Sys Operation Under Normal & Emergency Operating Conditions IR 05000277/19980121998-12-16016 December 1998 Insp Repts 50-277/98-12 & 50-278/98-12 on 981116-19.No Violations Noted.Major Areas Inspected:Emergency Preparedness full-participation Exercise Evaluation IR 05000277/19980101998-12-11011 December 1998 Insp Repts 50-277/98-10 & 50-278/98-10 on 980922-1109. Violations Noted.Major Areas Inspected:Licensee Operations, Surveillances & Maint,Engineering & Technical Support & Plant Support ML20155D4571998-10-28028 October 1998 Insp Repts 50-277/98-08 & 50-278/98-08 on 980811-0921. Violations Noted.Major Areas Inspected:Operations, Surveillances & Maintenance,Engineering & Technical Support & Plant Support Areas IR 05000277/19980071998-09-15015 September 1998 Insp Repts 50-277/98-07 & 50-278/98-07 on 980623-0810.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000171/19980011998-08-0707 August 1998 Insp Rept 50-171/98-01 on 980612.No Violations Noted. Major Areas Inspected:Review of Facility Mgt & Control, Decommissioning Support Activities,Radiological Safety & Independent Measurements by Inspector ML20236R7661998-07-16016 July 1998 Insp Repts 50-277/98-06 & 50-278/98-06 on 980505-0622. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000277/19980021998-06-0909 June 1998 Insp Repts 50-277/98-02 & 50-278/98-02 on 980315-0504. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000277/19970041998-05-14014 May 1998 Insp Repts 50-277/97-04 & 50-278/98-04 on 980309-13 & 0330-0403 (Onsite) & 980314-0429 (Inoffice).Violation Noted. Major Areas Inspected:Licensed Operator Requalification Training & Evaluation & Maint Rule Implementation Areas IR 05000278/19980051998-05-0707 May 1998 Insp Rept 50-278/98-05 on 980330-0424.Violations Noted. Major Areas Inspected:Events Re Discovery of Foreign Matl in 3A Core Spray Pump on 980324 IR 05000277/19980011998-05-0101 May 1998 Insp Repts 50-277/98-01 & 50-278/98-01 on 980118-0314. Violations Noted.Major Areas Inspected:Licensee Operations, Surveillance & Maint,Engineering & Technical Support & Plant Support Areas ML20217N3771998-03-30030 March 1998 Insp Rept 50-277/98-03 on 980212-0303.Violations Noted.Major Areas Inspected:Reviewed Events,Significance,Reportability & CAs for 2 'A' RFP Turbine High Level Trip Events Involving 3 1997 Failures & 1 Trip on 980206 ML20203E3701998-02-20020 February 1998 Insp Repts 50-277/97-08 & 50-278/97-08 on 971123-980117. Violations Noted.Major Areas Inspected:Plant Operations, Maint,Engineering & Plant Support IR 05000277/19970071997-12-16016 December 1997 Insp Repts 50-277/97-07 & 50-278/97-07 on 970921-1122. Violations Noted.Major Areas Inspected:Operations, Surveillance & Maintenance,Engineering & Technical Support & Plant Support Areas IR 05000277/19970061997-10-15015 October 1997 Insp Repts 50-277/97-06 & 50-278/97-06 on 970810-0920.No Violations Noted.Major Areas Inspected:Plant Operations, Maint,Engineering & Plant Support IR 05000277/19970051997-09-12012 September 1997 Insp Repts 50-277/97-05 & 50-278/97-05 on 970608-0809. Violations Noted.Major Areas Inspected:Operations, Surveillance & Maint,Engineering & Technical Support & Plant Support Areas ML20149L2951997-07-24024 July 1997 Insp Repts 50-277/97-04 & 50-278/97-04 on 970504-0607. Violations Noted.Major Areas Inspected:Operations, Surveillance & Maintenance,Engineering & Technical Support & Plant Support ML20140D2051997-06-0404 June 1997 Integrated Insp Repts 50-277/97-02 & 50-278/97-02 on 970308-0503.Violations Noted.Major Areas Inspected: Operations,Surveillance,Maint,Engineering,Technical Support & Plant Support IR 05000277/19970011997-04-14014 April 1997 Insp Repts 50-277/97-01 & 50-278/97-01 on 970112-0308.No Violations Noted.Major Areas Inspected:Operations, Surveillance & Maint,Engineering & Technical Support & Plant Support ML20138P2661997-02-10010 February 1997 Insp Repts 50-277/97-03 & 50-278/97-03 on 961209-970131. Violations Noted.Major Areas Inspected:Areas Involving Radiological Environ Monitoring Programs ML20134K2821997-02-0707 February 1997 Insp Repts 50-277/96-09 & 50-278/96-09 on 961110-970111.No Violations Noted.Major Areas Inspected:Operations, Surveillance & Maintenance,Engineering & Technical Support & Plant Support IR 05000277/19960121996-12-20020 December 1996 Insp Repts 50-277/96-12 & 50-278/96-12 on 961119-21.No Violations Noted.Major Areas Inspected:Erf Staffing, Procedure Implementation,Effectiveness of Mitigation Actions,Communications & Command & Control ML20132G4901996-12-20020 December 1996 Insp Repts 50-277/96-11,50-278/96-11,50-352/96-08 & 50-353/96-08 on 961003-1127.No Violations Noted.Major Areas Inspected:Documentations Containing Safeguards Info ML20132E9271996-12-18018 December 1996 Insp Repts 50-277/96-08 & 50-278/96-08 on 960908-1109. Violations Noted.Major Areas Inspected:Operations, Surveillance & Maintenance,Engineering & Technical Support & Plant Support ML20138G2791996-09-0707 September 1996 Insp Repts 50-277/96-06 & 50-278/96-06 on 960707-960907. Violations Noted.Major Areas Inspected:Operations, Surveillance & Maintenance,Engineering & Technical Support & Plant Support IR 05000277/19940101994-08-0404 August 1994 Insp Repts 50-277/94-10 & 50-278/94-10 on 940605-0716.No Violations Noted.Major Areas Inspected:Plant Operations, Maint,Surveillance,Engineering & Technical Support ML20059C7791993-12-20020 December 1993 Enforcement Conference Repts 50-277/93-27 & 50-278/93-27 on 931210.Areas Discussed:Safety Significance of Three Events Re Entry Into Controlled Areas W/O Satisfying Radiological Safety Requirements During Period of 931027-29 IR 05000277/19930281993-12-20020 December 1993 Insp Repts 50-277/93-28 & 50-278/93-28 on 931115-19.No Violations Noted.Major Areas Inspected:Licensee Main Steam Safety Valve & Safety/Relief Valve Related Activities ML20058D3431993-11-23023 November 1993 Insp Repts 50-277/93-27 & 50-278/93-27 on 931004-10.No Violations Noted.Major Areas Inspected:Alara,Planning for Radiological Work,Radiation Worker Practices,Training & Qualifications & Shipping of LLW for Disposal IR 05000277/19930241993-11-22022 November 1993 Insp Repts 50-277/93-24 & 50-278/93-24 on 930914-1030. Violation Noted.Major Areas Inspected:Operations,Refueling Maint,Surveillance,Engineering & Technical Support IR 05000277/19930261993-11-0808 November 1993 Insp Repts 50-277/93-26 & 50-278/93-26 on 930920-30.Major Areas Inspected:Isi Program & Related Activities IR 05000277/19930301993-11-0808 November 1993 Insp Repts 50-277/93-30 & 50-278/93-30 on 931018-22.No Violations Noted.Major Areas Inspected:Radioactive Liquid & Gaseous Effluent Control Programs IR 05000277/19930291993-11-0101 November 1993 Insp Repts 50-277/93-29 & 50-278/93-29 on 931012-15.No Violations Noted.Major Areas Inspected:Review of Pims Interface W/Maintenance Including Work Order Development & Maintenance trending,Unit-3 Arts/Mell Mod Training ML20058M2461993-10-19019 October 1993 Insp Repts 50-277/PA-93-02 & 50-278/PA-93-02 on 930913-14. No Violations Noted.Major Areas Inspected:Llrw Shipment to Burial Site Including,Shipping Documentation,Package Insp, Labeling,Marking,Placarding,Vehicle Insp IR 05000277/19930231993-10-13013 October 1993 Insp Repts 50-277/93-23 & 50-278/93-23 on 930913-17.No Violations Noted.Major Areas Inspected:Security Audits, Detection & Assessment Aids,Access Control of Personnel, Packages & Vehicles,Vital Key Area Control & Alarm Stations ML20057E7921993-10-0101 October 1993 Insp Repts 50-277/93-19 & 50-278/93-19 on 930802-06.No Violations Noted.Major Areas Inspected:Alara,External Dosimetry,Nuclear Quality Assurance Audits & Shipping of low-level Wastes for Disposal ML20057E2731993-09-27027 September 1993 Insp Repts 50-277/93-18 & 50-278/93-18 on 930802-06.No Violations Noted.Major Areas Inspected:Operational Objectives & Goals,Effectiveness of Performance & Self Assessment ML20057C2281993-09-22022 September 1993 Insp Repts 50-277/93-17 & 50-278/93-17 on 930803-0913.No Violations Noted.Major Areas Inspected:Util Staff & Mgt Response to Plant Events to Verify Proper Identification of Root Causes ML20057C1121993-09-16016 September 1993 Insp Repts 50-277/93-10 & 50-278/93-10 on 930628-30.Onsite Response to Exercise Scenario Very Good.Major Areas inspected:annual,partial-participation Emergency Preparedness Exercise IR 05000277/19930161993-08-0505 August 1993 Insp Repts 50-277/93-16 & 50-278/93-16 on 930712-15.Actions Taken to Strengthen Perceived Weaknesses Noted.Major Areas Inspected:Erosion/Corrosion Program,Per GL 89-08 ML20127N6521993-01-25025 January 1993 Insp Repts 50-277/92-32 & 50-278/92-32 on 921215-930118.No Violations Noted.Major Areas Inspected:Plant Operations, Maint & Surveillance,Engineering & Technical Support, Qa,Radiological Controls & Physical Security IR 05000277/19920321993-01-25025 January 1993 Insp Repts 50-277/92-32 & 50-278/92-32 on 921215-930118.No Violations Noted.Major Areas Inspected:Plant Operations, Maint & Surveillance,Engineering & Technical Support, Qa,Radiological Controls & Physical Security IR 05000277/19920821993-01-11011 January 1993 Insp Repts 50-277/92-82 & 50-278/92-82 on 921019-23 & 1130. Violations Noted.Major Areas Inspected:Licensee GL 89-10 Program & Walkdown IR 05000277/19920291992-12-24024 December 1992 Insp Repts 50-277/92-29 & 50-278/92-29 on 921101-1214.Minor Safety Significance Noted.Major Areas Inspected:Plant Operations,Maint & Surveillance,Engineering & Technical Support & Assurance of Quality IR 05000277/19920311992-12-15015 December 1992 Insp Repts 50-277/92-31 & 50-278/92-31 on 921116-20.No Violations Noted.Major Areas Inspected:Design & Procedures Used to Mitigate Consequences of Cable Spreading Room Fire 1999-07-27
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000277/19990071999-10-19019 October 1999 Insp Rept 50-277/99-07 & 50-278/99-07 on 990810-0922.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000277/19990051999-07-27027 July 1999 Insp Repts 50-277/99-05 & 50-278/99-05 on 990518-0628. Non-cited Violations Noted.Major Areas Inspected:Operations, Surveillances & Maintenance,Engineering & Technical Support & Plant Support Areas IR 05000277/19990041999-06-11011 June 1999 Insp Repts 50-277/99-04 & 50-278/99-04 on 990405-0517. Non-cited Violation Noted.Major Areas Inspected:Operations, Surveillances & Maintenance,Engineering & Technical Support & Plant Support Areas IR 05000277/19990011999-03-25025 March 1999 Insp Repts 50-277/99-01 & 50-278/99-01 on 990105-0215.No Violations Noted.Major Areas Inspected:Operations, Surveillances & Maint,Engineering & Technical Support & Plant Support Including Security & Safeguards Activities IR 05000277/19980111999-02-0101 February 1999 Insp Repts 50-277/98-11 & 50-278/98-11 on 981110-990104. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000277/19980091999-02-0101 February 1999 Insp Repts 50-277/98-09 & 50-278/98-09 on 981116-1204. Violations Noted.Major Areas Inspected:Reactor Core Isolation Cooling & 4kV Electrical Distribution Sys Operation Under Normal & Emergency Operating Conditions IR 05000277/19980121998-12-16016 December 1998 Insp Repts 50-277/98-12 & 50-278/98-12 on 981116-19.No Violations Noted.Major Areas Inspected:Emergency Preparedness full-participation Exercise Evaluation IR 05000277/19980101998-12-11011 December 1998 Insp Repts 50-277/98-10 & 50-278/98-10 on 980922-1109. Violations Noted.Major Areas Inspected:Licensee Operations, Surveillances & Maint,Engineering & Technical Support & Plant Support ML20155D4571998-10-28028 October 1998 Insp Repts 50-277/98-08 & 50-278/98-08 on 980811-0921. Violations Noted.Major Areas Inspected:Operations, Surveillances & Maintenance,Engineering & Technical Support & Plant Support Areas IR 05000277/19980071998-09-15015 September 1998 Insp Repts 50-277/98-07 & 50-278/98-07 on 980623-0810.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000171/19980011998-08-0707 August 1998 Insp Rept 50-171/98-01 on 980612.No Violations Noted. Major Areas Inspected:Review of Facility Mgt & Control, Decommissioning Support Activities,Radiological Safety & Independent Measurements by Inspector ML20236R7661998-07-16016 July 1998 Insp Repts 50-277/98-06 & 50-278/98-06 on 980505-0622. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000277/19980021998-06-0909 June 1998 Insp Repts 50-277/98-02 & 50-278/98-02 on 980315-0504. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000277/19970041998-05-14014 May 1998 Insp Repts 50-277/97-04 & 50-278/98-04 on 980309-13 & 0330-0403 (Onsite) & 980314-0429 (Inoffice).Violation Noted. Major Areas Inspected:Licensed Operator Requalification Training & Evaluation & Maint Rule Implementation Areas IR 05000278/19980051998-05-0707 May 1998 Insp Rept 50-278/98-05 on 980330-0424.Violations Noted. Major Areas Inspected:Events Re Discovery of Foreign Matl in 3A Core Spray Pump on 980324 IR 05000277/19980011998-05-0101 May 1998 Insp Repts 50-277/98-01 & 50-278/98-01 on 980118-0314. Violations Noted.Major Areas Inspected:Licensee Operations, Surveillance & Maint,Engineering & Technical Support & Plant Support Areas ML20217N3771998-03-30030 March 1998 Insp Rept 50-277/98-03 on 980212-0303.Violations Noted.Major Areas Inspected:Reviewed Events,Significance,Reportability & CAs for 2 'A' RFP Turbine High Level Trip Events Involving 3 1997 Failures & 1 Trip on 980206 ML20203E3701998-02-20020 February 1998 Insp Repts 50-277/97-08 & 50-278/97-08 on 971123-980117. Violations Noted.Major Areas Inspected:Plant Operations, Maint,Engineering & Plant Support IR 05000277/19970071997-12-16016 December 1997 Insp Repts 50-277/97-07 & 50-278/97-07 on 970921-1122. Violations Noted.Major Areas Inspected:Operations, Surveillance & Maintenance,Engineering & Technical Support & Plant Support Areas IR 05000277/19970061997-10-15015 October 1997 Insp Repts 50-277/97-06 & 50-278/97-06 on 970810-0920.No Violations Noted.Major Areas Inspected:Plant Operations, Maint,Engineering & Plant Support IR 05000277/19970051997-09-12012 September 1997 Insp Repts 50-277/97-05 & 50-278/97-05 on 970608-0809. Violations Noted.Major Areas Inspected:Operations, Surveillance & Maint,Engineering & Technical Support & Plant Support Areas ML20149L2951997-07-24024 July 1997 Insp Repts 50-277/97-04 & 50-278/97-04 on 970504-0607. Violations Noted.Major Areas Inspected:Operations, Surveillance & Maintenance,Engineering & Technical Support & Plant Support ML20140D2051997-06-0404 June 1997 Integrated Insp Repts 50-277/97-02 & 50-278/97-02 on 970308-0503.Violations Noted.Major Areas Inspected: Operations,Surveillance,Maint,Engineering,Technical Support & Plant Support IR 05000277/19970011997-04-14014 April 1997 Insp Repts 50-277/97-01 & 50-278/97-01 on 970112-0308.No Violations Noted.Major Areas Inspected:Operations, Surveillance & Maint,Engineering & Technical Support & Plant Support ML20138P2661997-02-10010 February 1997 Insp Repts 50-277/97-03 & 50-278/97-03 on 961209-970131. Violations Noted.Major Areas Inspected:Areas Involving Radiological Environ Monitoring Programs ML20134K2821997-02-0707 February 1997 Insp Repts 50-277/96-09 & 50-278/96-09 on 961110-970111.No Violations Noted.Major Areas Inspected:Operations, Surveillance & Maintenance,Engineering & Technical Support & Plant Support IR 05000277/19960121996-12-20020 December 1996 Insp Repts 50-277/96-12 & 50-278/96-12 on 961119-21.No Violations Noted.Major Areas Inspected:Erf Staffing, Procedure Implementation,Effectiveness of Mitigation Actions,Communications & Command & Control ML20132G4901996-12-20020 December 1996 Insp Repts 50-277/96-11,50-278/96-11,50-352/96-08 & 50-353/96-08 on 961003-1127.No Violations Noted.Major Areas Inspected:Documentations Containing Safeguards Info ML20132E9271996-12-18018 December 1996 Insp Repts 50-277/96-08 & 50-278/96-08 on 960908-1109. Violations Noted.Major Areas Inspected:Operations, Surveillance & Maintenance,Engineering & Technical Support & Plant Support ML20138G2791996-09-0707 September 1996 Insp Repts 50-277/96-06 & 50-278/96-06 on 960707-960907. Violations Noted.Major Areas Inspected:Operations, Surveillance & Maintenance,Engineering & Technical Support & Plant Support IR 05000277/19940101994-08-0404 August 1994 Insp Repts 50-277/94-10 & 50-278/94-10 on 940605-0716.No Violations Noted.Major Areas Inspected:Plant Operations, Maint,Surveillance,Engineering & Technical Support ML20059C7791993-12-20020 December 1993 Enforcement Conference Repts 50-277/93-27 & 50-278/93-27 on 931210.Areas Discussed:Safety Significance of Three Events Re Entry Into Controlled Areas W/O Satisfying Radiological Safety Requirements During Period of 931027-29 IR 05000277/19930281993-12-20020 December 1993 Insp Repts 50-277/93-28 & 50-278/93-28 on 931115-19.No Violations Noted.Major Areas Inspected:Licensee Main Steam Safety Valve & Safety/Relief Valve Related Activities ML20058D3431993-11-23023 November 1993 Insp Repts 50-277/93-27 & 50-278/93-27 on 931004-10.No Violations Noted.Major Areas Inspected:Alara,Planning for Radiological Work,Radiation Worker Practices,Training & Qualifications & Shipping of LLW for Disposal IR 05000277/19930241993-11-22022 November 1993 Insp Repts 50-277/93-24 & 50-278/93-24 on 930914-1030. Violation Noted.Major Areas Inspected:Operations,Refueling Maint,Surveillance,Engineering & Technical Support IR 05000277/19930261993-11-0808 November 1993 Insp Repts 50-277/93-26 & 50-278/93-26 on 930920-30.Major Areas Inspected:Isi Program & Related Activities IR 05000277/19930301993-11-0808 November 1993 Insp Repts 50-277/93-30 & 50-278/93-30 on 931018-22.No Violations Noted.Major Areas Inspected:Radioactive Liquid & Gaseous Effluent Control Programs IR 05000277/19930291993-11-0101 November 1993 Insp Repts 50-277/93-29 & 50-278/93-29 on 931012-15.No Violations Noted.Major Areas Inspected:Review of Pims Interface W/Maintenance Including Work Order Development & Maintenance trending,Unit-3 Arts/Mell Mod Training ML20058M2461993-10-19019 October 1993 Insp Repts 50-277/PA-93-02 & 50-278/PA-93-02 on 930913-14. No Violations Noted.Major Areas Inspected:Llrw Shipment to Burial Site Including,Shipping Documentation,Package Insp, Labeling,Marking,Placarding,Vehicle Insp IR 05000277/19930231993-10-13013 October 1993 Insp Repts 50-277/93-23 & 50-278/93-23 on 930913-17.No Violations Noted.Major Areas Inspected:Security Audits, Detection & Assessment Aids,Access Control of Personnel, Packages & Vehicles,Vital Key Area Control & Alarm Stations ML20057E7921993-10-0101 October 1993 Insp Repts 50-277/93-19 & 50-278/93-19 on 930802-06.No Violations Noted.Major Areas Inspected:Alara,External Dosimetry,Nuclear Quality Assurance Audits & Shipping of low-level Wastes for Disposal ML20057E2731993-09-27027 September 1993 Insp Repts 50-277/93-18 & 50-278/93-18 on 930802-06.No Violations Noted.Major Areas Inspected:Operational Objectives & Goals,Effectiveness of Performance & Self Assessment ML20057C2281993-09-22022 September 1993 Insp Repts 50-277/93-17 & 50-278/93-17 on 930803-0913.No Violations Noted.Major Areas Inspected:Util Staff & Mgt Response to Plant Events to Verify Proper Identification of Root Causes ML20057C1121993-09-16016 September 1993 Insp Repts 50-277/93-10 & 50-278/93-10 on 930628-30.Onsite Response to Exercise Scenario Very Good.Major Areas inspected:annual,partial-participation Emergency Preparedness Exercise IR 05000277/19930161993-08-0505 August 1993 Insp Repts 50-277/93-16 & 50-278/93-16 on 930712-15.Actions Taken to Strengthen Perceived Weaknesses Noted.Major Areas Inspected:Erosion/Corrosion Program,Per GL 89-08 ML20127N6521993-01-25025 January 1993 Insp Repts 50-277/92-32 & 50-278/92-32 on 921215-930118.No Violations Noted.Major Areas Inspected:Plant Operations, Maint & Surveillance,Engineering & Technical Support, Qa,Radiological Controls & Physical Security IR 05000277/19920321993-01-25025 January 1993 Insp Repts 50-277/92-32 & 50-278/92-32 on 921215-930118.No Violations Noted.Major Areas Inspected:Plant Operations, Maint & Surveillance,Engineering & Technical Support, Qa,Radiological Controls & Physical Security IR 05000277/19920821993-01-11011 January 1993 Insp Repts 50-277/92-82 & 50-278/92-82 on 921019-23 & 1130. Violations Noted.Major Areas Inspected:Licensee GL 89-10 Program & Walkdown IR 05000277/19920291992-12-24024 December 1992 Insp Repts 50-277/92-29 & 50-278/92-29 on 921101-1214.Minor Safety Significance Noted.Major Areas Inspected:Plant Operations,Maint & Surveillance,Engineering & Technical Support & Assurance of Quality IR 05000277/19920311992-12-15015 December 1992 Insp Repts 50-277/92-31 & 50-278/92-31 on 921116-20.No Violations Noted.Major Areas Inspected:Design & Procedures Used to Mitigate Consequences of Cable Spreading Room Fire 1999-07-27
[Table view] Category:INSPECTION REPORT
MONTHYEARIR 05000277/19990071999-10-19019 October 1999 Insp Rept 50-277/99-07 & 50-278/99-07 on 990810-0922.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000277/19990051999-07-27027 July 1999 Insp Repts 50-277/99-05 & 50-278/99-05 on 990518-0628. Non-cited Violations Noted.Major Areas Inspected:Operations, Surveillances & Maintenance,Engineering & Technical Support & Plant Support Areas IR 05000277/19990041999-06-11011 June 1999 Insp Repts 50-277/99-04 & 50-278/99-04 on 990405-0517. Non-cited Violation Noted.Major Areas Inspected:Operations, Surveillances & Maintenance,Engineering & Technical Support & Plant Support Areas IR 05000277/19990011999-03-25025 March 1999 Insp Repts 50-277/99-01 & 50-278/99-01 on 990105-0215.No Violations Noted.Major Areas Inspected:Operations, Surveillances & Maint,Engineering & Technical Support & Plant Support Including Security & Safeguards Activities IR 05000277/19980111999-02-0101 February 1999 Insp Repts 50-277/98-11 & 50-278/98-11 on 981110-990104. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000277/19980091999-02-0101 February 1999 Insp Repts 50-277/98-09 & 50-278/98-09 on 981116-1204. Violations Noted.Major Areas Inspected:Reactor Core Isolation Cooling & 4kV Electrical Distribution Sys Operation Under Normal & Emergency Operating Conditions IR 05000277/19980121998-12-16016 December 1998 Insp Repts 50-277/98-12 & 50-278/98-12 on 981116-19.No Violations Noted.Major Areas Inspected:Emergency Preparedness full-participation Exercise Evaluation IR 05000277/19980101998-12-11011 December 1998 Insp Repts 50-277/98-10 & 50-278/98-10 on 980922-1109. Violations Noted.Major Areas Inspected:Licensee Operations, Surveillances & Maint,Engineering & Technical Support & Plant Support ML20155D4571998-10-28028 October 1998 Insp Repts 50-277/98-08 & 50-278/98-08 on 980811-0921. Violations Noted.Major Areas Inspected:Operations, Surveillances & Maintenance,Engineering & Technical Support & Plant Support Areas IR 05000277/19980071998-09-15015 September 1998 Insp Repts 50-277/98-07 & 50-278/98-07 on 980623-0810.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000171/19980011998-08-0707 August 1998 Insp Rept 50-171/98-01 on 980612.No Violations Noted. Major Areas Inspected:Review of Facility Mgt & Control, Decommissioning Support Activities,Radiological Safety & Independent Measurements by Inspector ML20236R7661998-07-16016 July 1998 Insp Repts 50-277/98-06 & 50-278/98-06 on 980505-0622. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000277/19980021998-06-0909 June 1998 Insp Repts 50-277/98-02 & 50-278/98-02 on 980315-0504. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000277/19970041998-05-14014 May 1998 Insp Repts 50-277/97-04 & 50-278/98-04 on 980309-13 & 0330-0403 (Onsite) & 980314-0429 (Inoffice).Violation Noted. Major Areas Inspected:Licensed Operator Requalification Training & Evaluation & Maint Rule Implementation Areas IR 05000278/19980051998-05-0707 May 1998 Insp Rept 50-278/98-05 on 980330-0424.Violations Noted. Major Areas Inspected:Events Re Discovery of Foreign Matl in 3A Core Spray Pump on 980324 IR 05000277/19980011998-05-0101 May 1998 Insp Repts 50-277/98-01 & 50-278/98-01 on 980118-0314. Violations Noted.Major Areas Inspected:Licensee Operations, Surveillance & Maint,Engineering & Technical Support & Plant Support Areas ML20217N3771998-03-30030 March 1998 Insp Rept 50-277/98-03 on 980212-0303.Violations Noted.Major Areas Inspected:Reviewed Events,Significance,Reportability & CAs for 2 'A' RFP Turbine High Level Trip Events Involving 3 1997 Failures & 1 Trip on 980206 ML20203E3701998-02-20020 February 1998 Insp Repts 50-277/97-08 & 50-278/97-08 on 971123-980117. Violations Noted.Major Areas Inspected:Plant Operations, Maint,Engineering & Plant Support IR 05000277/19970071997-12-16016 December 1997 Insp Repts 50-277/97-07 & 50-278/97-07 on 970921-1122. Violations Noted.Major Areas Inspected:Operations, Surveillance & Maintenance,Engineering & Technical Support & Plant Support Areas IR 05000277/19970061997-10-15015 October 1997 Insp Repts 50-277/97-06 & 50-278/97-06 on 970810-0920.No Violations Noted.Major Areas Inspected:Plant Operations, Maint,Engineering & Plant Support IR 05000277/19970051997-09-12012 September 1997 Insp Repts 50-277/97-05 & 50-278/97-05 on 970608-0809. Violations Noted.Major Areas Inspected:Operations, Surveillance & Maint,Engineering & Technical Support & Plant Support Areas ML20149L2951997-07-24024 July 1997 Insp Repts 50-277/97-04 & 50-278/97-04 on 970504-0607. Violations Noted.Major Areas Inspected:Operations, Surveillance & Maintenance,Engineering & Technical Support & Plant Support ML20140D2051997-06-0404 June 1997 Integrated Insp Repts 50-277/97-02 & 50-278/97-02 on 970308-0503.Violations Noted.Major Areas Inspected: Operations,Surveillance,Maint,Engineering,Technical Support & Plant Support IR 05000277/19970011997-04-14014 April 1997 Insp Repts 50-277/97-01 & 50-278/97-01 on 970112-0308.No Violations Noted.Major Areas Inspected:Operations, Surveillance & Maint,Engineering & Technical Support & Plant Support ML20138P2661997-02-10010 February 1997 Insp Repts 50-277/97-03 & 50-278/97-03 on 961209-970131. Violations Noted.Major Areas Inspected:Areas Involving Radiological Environ Monitoring Programs ML20134K2821997-02-0707 February 1997 Insp Repts 50-277/96-09 & 50-278/96-09 on 961110-970111.No Violations Noted.Major Areas Inspected:Operations, Surveillance & Maintenance,Engineering & Technical Support & Plant Support IR 05000277/19960121996-12-20020 December 1996 Insp Repts 50-277/96-12 & 50-278/96-12 on 961119-21.No Violations Noted.Major Areas Inspected:Erf Staffing, Procedure Implementation,Effectiveness of Mitigation Actions,Communications & Command & Control ML20132G4901996-12-20020 December 1996 Insp Repts 50-277/96-11,50-278/96-11,50-352/96-08 & 50-353/96-08 on 961003-1127.No Violations Noted.Major Areas Inspected:Documentations Containing Safeguards Info ML20132E9271996-12-18018 December 1996 Insp Repts 50-277/96-08 & 50-278/96-08 on 960908-1109. Violations Noted.Major Areas Inspected:Operations, Surveillance & Maintenance,Engineering & Technical Support & Plant Support ML20138G2791996-09-0707 September 1996 Insp Repts 50-277/96-06 & 50-278/96-06 on 960707-960907. Violations Noted.Major Areas Inspected:Operations, Surveillance & Maintenance,Engineering & Technical Support & Plant Support IR 05000277/19940101994-08-0404 August 1994 Insp Repts 50-277/94-10 & 50-278/94-10 on 940605-0716.No Violations Noted.Major Areas Inspected:Plant Operations, Maint,Surveillance,Engineering & Technical Support ML20059C7791993-12-20020 December 1993 Enforcement Conference Repts 50-277/93-27 & 50-278/93-27 on 931210.Areas Discussed:Safety Significance of Three Events Re Entry Into Controlled Areas W/O Satisfying Radiological Safety Requirements During Period of 931027-29 IR 05000277/19930281993-12-20020 December 1993 Insp Repts 50-277/93-28 & 50-278/93-28 on 931115-19.No Violations Noted.Major Areas Inspected:Licensee Main Steam Safety Valve & Safety/Relief Valve Related Activities ML20058D3431993-11-23023 November 1993 Insp Repts 50-277/93-27 & 50-278/93-27 on 931004-10.No Violations Noted.Major Areas Inspected:Alara,Planning for Radiological Work,Radiation Worker Practices,Training & Qualifications & Shipping of LLW for Disposal IR 05000277/19930241993-11-22022 November 1993 Insp Repts 50-277/93-24 & 50-278/93-24 on 930914-1030. Violation Noted.Major Areas Inspected:Operations,Refueling Maint,Surveillance,Engineering & Technical Support IR 05000277/19930261993-11-0808 November 1993 Insp Repts 50-277/93-26 & 50-278/93-26 on 930920-30.Major Areas Inspected:Isi Program & Related Activities IR 05000277/19930301993-11-0808 November 1993 Insp Repts 50-277/93-30 & 50-278/93-30 on 931018-22.No Violations Noted.Major Areas Inspected:Radioactive Liquid & Gaseous Effluent Control Programs IR 05000277/19930291993-11-0101 November 1993 Insp Repts 50-277/93-29 & 50-278/93-29 on 931012-15.No Violations Noted.Major Areas Inspected:Review of Pims Interface W/Maintenance Including Work Order Development & Maintenance trending,Unit-3 Arts/Mell Mod Training ML20058M2461993-10-19019 October 1993 Insp Repts 50-277/PA-93-02 & 50-278/PA-93-02 on 930913-14. No Violations Noted.Major Areas Inspected:Llrw Shipment to Burial Site Including,Shipping Documentation,Package Insp, Labeling,Marking,Placarding,Vehicle Insp IR 05000277/19930231993-10-13013 October 1993 Insp Repts 50-277/93-23 & 50-278/93-23 on 930913-17.No Violations Noted.Major Areas Inspected:Security Audits, Detection & Assessment Aids,Access Control of Personnel, Packages & Vehicles,Vital Key Area Control & Alarm Stations ML20057E7921993-10-0101 October 1993 Insp Repts 50-277/93-19 & 50-278/93-19 on 930802-06.No Violations Noted.Major Areas Inspected:Alara,External Dosimetry,Nuclear Quality Assurance Audits & Shipping of low-level Wastes for Disposal ML20057E2731993-09-27027 September 1993 Insp Repts 50-277/93-18 & 50-278/93-18 on 930802-06.No Violations Noted.Major Areas Inspected:Operational Objectives & Goals,Effectiveness of Performance & Self Assessment ML20057C2281993-09-22022 September 1993 Insp Repts 50-277/93-17 & 50-278/93-17 on 930803-0913.No Violations Noted.Major Areas Inspected:Util Staff & Mgt Response to Plant Events to Verify Proper Identification of Root Causes ML20057C1121993-09-16016 September 1993 Insp Repts 50-277/93-10 & 50-278/93-10 on 930628-30.Onsite Response to Exercise Scenario Very Good.Major Areas inspected:annual,partial-participation Emergency Preparedness Exercise IR 05000277/19930161993-08-0505 August 1993 Insp Repts 50-277/93-16 & 50-278/93-16 on 930712-15.Actions Taken to Strengthen Perceived Weaknesses Noted.Major Areas Inspected:Erosion/Corrosion Program,Per GL 89-08 ML20127N6521993-01-25025 January 1993 Insp Repts 50-277/92-32 & 50-278/92-32 on 921215-930118.No Violations Noted.Major Areas Inspected:Plant Operations, Maint & Surveillance,Engineering & Technical Support, Qa,Radiological Controls & Physical Security IR 05000277/19920321993-01-25025 January 1993 Insp Repts 50-277/92-32 & 50-278/92-32 on 921215-930118.No Violations Noted.Major Areas Inspected:Plant Operations, Maint & Surveillance,Engineering & Technical Support, Qa,Radiological Controls & Physical Security IR 05000277/19920821993-01-11011 January 1993 Insp Repts 50-277/92-82 & 50-278/92-82 on 921019-23 & 1130. Violations Noted.Major Areas Inspected:Licensee GL 89-10 Program & Walkdown IR 05000277/19920291992-12-24024 December 1992 Insp Repts 50-277/92-29 & 50-278/92-29 on 921101-1214.Minor Safety Significance Noted.Major Areas Inspected:Plant Operations,Maint & Surveillance,Engineering & Technical Support & Assurance of Quality IR 05000277/19920311992-12-15015 December 1992 Insp Repts 50-277/92-31 & 50-278/92-31 on 921116-20.No Violations Noted.Major Areas Inspected:Design & Procedures Used to Mitigate Consequences of Cable Spreading Room Fire 1999-07-27
[Table view] Category:UTILITY
MONTHYEARIR 05000277/19900801990-11-0909 November 1990 SSFI Rept 50-277/90-80 & 50-278/90-80 on 900917-1003. Significant Weaknesses Identified.Major Areas Inspected: Adequacy of Licensee Corrective Actions Implemented IR 05000277/19900171990-10-0505 October 1990 Insp Repts 50-277/90-17 & 50-278/90-17 on 900814-0924.No Violations Noted.Major Areas Inspected:Operational Safety, Radiation Protection,Physical Security,Control Room Activities & Surveillance Testing IR 05000277/19900151990-09-0606 September 1990 Insp Repts 50-277/90-15 & 50-278/90-15 on 900723-27. Violations Noted.Major Areas Inspected:Cleaning & Testing of Both Diesel Engine & Generator ML20056A5061990-07-30030 July 1990 Insp Repts 50-277/90-13 & 50-278/90-13 on 900516-0702. Violations Noted.Major Areas Inspected:Operational Safety, Radiation Protection,Physical Security,Control Room Activities,Licensee Events & Maint IR 05000277/19900101990-06-15015 June 1990 Insp Repts 50-277/90-10 & 50-278/90-10 on 900403-0515.No Violations Noted.Major Areas Inspected:Operational Safety, Radiation Protection,Physical Security,Licensee Events, Control Room Activities,Surveillance Testing & Maint IR 05000277/19890211989-09-27027 September 1989 Insp Repts 50-277/89-21 & 50-278/89-21 on 890828-0901.No Violations Noted.Major Areas Inspected:Posting & Labeling, Organization & Staffing,Radiation Work Permits,Abandoned Radwaste Sys & Auditing IR 05000277/19890201989-09-21021 September 1989 Insp Repts 50-277/89-20 & 50-278/89-20 on 890730-0902.No Violations Noted.Major Areas Inspected:Onsite Regular, Backshift Insp (236 H Unit 2,135 H Unit 3) of Accessible Portions of Unit 2 & 3,operational Safety & Security IR 05000277/19890191989-08-22022 August 1989 Onsite Regular,Backshift & Deep Backshift Special Power Ascension & Restart Insps 50-277/89-19 & 50-278/89-19 on 890618-0729.No Violations Noted.Major Areas Inspected: Accessible Portions of Units 2 & 3 & Physical Security IR 05000277/19890171989-06-27027 June 1989 Insp Repts 50-277/89-17 & 50-278/89-17 on 890613-15.No Violations Noted.Major Areas Inspected:Licensee Partial Participation in Annual Emergency Preparedness Exercise on 890614 IR 05000277/19890161989-06-22022 June 1989 Restart Safety Insp Repts 50-277/89-16 & 50-278/89-16 on 890507-0617.Major Areas Inspected:Unit 2 Power Ascension Transient Testing & steady-state Operation at 35% Power Plateau,Radiation Protection & Physical Security IR 05000277/19890121989-05-25025 May 1989 Insp Repts 50-277/89-12 & 50-278/89-12 on 890410-13.No Violations Noted.Major Areas Inspected:Changes to Emergency Preparedness Program,Emergency Facilities,Independent/ Reviews/Audits & Notifications & Communications IR 05000277/19890151989-05-18018 May 1989 Insp Repts 50-277/89-15 & 50-278/89-15 on 890402-0506.No Violations Noted.Major Areas Inspected:Operational Safety, Unit 2 Prestartup Activities & Power Ascension & Testing, Radiation Protection & Physical Security IR 05000277/19890131989-05-10010 May 1989 Insp Repts 50-277/89-13 & 50-278/89-13 on 890405-07.No Violations or Deviations Noted.Major Areas Inspected: Licensee Action on Previously Noted Insp Findings in Electrical Area IR 05000277/19890111989-04-20020 April 1989 Insp Repts 50-277/89-11 & 50-278/89-11 on 890405-11.No Violations Noted.Major Areas Inspected:Implementation of Unit 2 Restart Power Testing Program,Including Review of Program & Verification Re in-plant Program IR 05000277/19890061989-04-12012 April 1989 Safety Insp Repts 50-277/89-06 & 50-278/89-06 on 890227-0307.No Violations or Deviations Noted.Major Areas Inspected:Previously Identified Open Items in Inservice Testing & Local Leak Rate Testing Areas IR 05000277/19890141989-04-11011 April 1989 Physical Security Insp Repts 50-277/89-14 & 278/89-14 on 890405.All Commitments Made to Resolve Open Items Met.Major Areas Inspected:Progress to Date on Open Items in Insp Repts 50-277/89-80 & 50-278/89-80 ML20248D6151989-03-28028 March 1989 Insp Repts 50-277/89-04 & 50-278/89-04 on 890109-14.No Violations Noted.Major Areas Inspected:Licensee Actions in Response to NRC Ltr to Pepco Re Allegations on motor- Operated Valve Refurbishment IR 05000277/19890071989-03-21021 March 1989 Insp Repts 50-277/89-07 & 50-278/89-07 on 890130-0210. Violations Noted.Major Areas Inspected:Electrical Power Sys Including Verification of as-built Drawings,Adequacy of Breaker & Fuse Coordination & Plant Mods IR 05000277/19890801989-03-16016 March 1989 Physical Security Insp Repts 50-277/89-80 & 50-278/89-80 on 890105-27.Major Areas Inspected:Security Program Mgt & Effectiveness,Personnel Experience & Qualifications,Testing & Maint & Licensee self-assessments & Audits IR 05000277/19890811989-03-0606 March 1989 Integrated Assessment Team Insp Repts 50-277/89-81 & 50-278/89-81 on 890203-17.Major Areas Inspected: Effectiveness of Restart Plan Corrective Actions & Degree of Readiness of Licensee Mgt Controls IR 05000277/19880411988-11-0808 November 1988 Insp Repts 50-277/88-41 & 50-278/88-41 on 881003-07.No Violations Noted.Major Areas Inspected:Fire Protection/ Prevention Program IR 05000277/19880351988-11-0303 November 1988 Insp Repts 50-277/88-35 & 50-278/88-35 on 880926-30.No Violations Noted.Major Areas Inspected:Licensee Performance in Areas of Maint Surveillance Procedures & Records That Verify Component Availability,Per Tech Spec Requirements IR 05000277/19880371988-11-0303 November 1988 Insp Repts 50-277/88-37 & 50-278/88-37 on 880926-30.No Violations Noted.Major Areas Inspected:Radiation Safety Program,Including Status of Previously Identified Items & post-project Reviews of Unit 3 Pipe Replacement ML20206L4251988-11-0101 November 1988 Insp Repts 50-277/88-38 & 50-278/88-38 on 880926-30. Violations Noted.Major Areas Inspected:Licensee Corrective Actions for Previous Environ Qualification (EQ) Findings & Licensee EQ Documentation Re Cable Splices Qualificability ML20206D3121988-10-27027 October 1988 Insp Repts 50-277/88-32 & 50-278/88-32 on 880831-0929.No Violations or Deviations Noted.Major Areas Inspected: Licensed Operator Requalification Training Program. Weaknesses in Requalification Program Identified IR 05000277/19880341988-10-25025 October 1988 Insp Repts 50-277/88-34 & 50-278/88-34 on 880903-1014.No Violations Noted.Major Areas Inspected:Accessible Portions of Units 2 & 3 Operational Safety,Radiation Protection, Physical Security,Control Room Activities & Licensee Events IR 05000277/19880281988-10-18018 October 1988 Insp Repts 50-277/88-28 & 50-278/88-28 on 880829-0902.No Violations Noted.Major Areas Inspected:Review of Licensee Operating procedures,non-licensed Operators Training & on Site & Offsite Review Committees IR 05000277/19880361988-10-12012 October 1988 Insp Repts 50-277/88-36 & 50-278/88-36 on 880926-28.No Violations Noted.Major Areas Inspected:Annual full-participation Emergency Exercise Performed on 880927 IR 05000277/19880171988-10-0606 October 1988 In-Depth Team Insp Repts 50-277/88-17 & 50-278/88-17 on 880711-22.Violations Noted.Major Areas Inspected:Facility Maint Program & Program Implementation IR 05000277/19880331988-10-0404 October 1988 Insp Repts 50-277/88-33 & 50-278/88-33 on 880906-09.No Violations Noted.Unresolved Item Noted.Major Areas Inspected:Radioactive Effluent Controls Program,Including Releases,Radiation Monitoring Sys Calibr & Surveillances IR 05000277/19880291988-09-19019 September 1988 Insp Repts 50-277/88-29 & 50-278/88-29 on 880805 & 08-12.No Violations Noted.Major Areas Inspected:Replacement of Unit 2 & 3 Emergency Water sys,errosion-corrosion Program in Unit 2 & 3 & Radiographic Condition of Unit 3 Recirculation Pump IR 05000277/19880241988-09-16016 September 1988 Insp Repts 50-277/88-24 & 50-278/88-24 on 880716-0902.No Violations Noted.Major Areas Inspected:Operational Safety, Radiation Protection,Physical Security,Control Room Activities & Surveillance Testing IR 05000277/19880311988-09-0808 September 1988 Partially Deleted Insp Repts 50-277/88-31 & 50-278/88-31 on 880827-29 (Ref 10CFR73.21).Violation Noted.Major Areas Inspected:Mgt Effectiveness,Assessment Aids - Protected Area & Access Control - Personnel ML20154L1751988-09-0808 September 1988 Partially Deleted Insp Repts 50-277/88-26 & 50-278/88-26 on 880725-29 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Assessment Aids - Protected Area & Access Control - Personnel & Mgt Effectiveness ML20153D0741988-08-25025 August 1988 Insp Repts 50-277/88-30 & 50-278/88-30 on 880815-19. Violations Noted.Major Areas Inspected:Adequacy of Licensee Actions in Response to IE Bulletin 80-11 & Adequacy of Corrective Actions in Response to Violation 87-16-01 IR 05000277/19880231988-08-23023 August 1988 Physical Security Insp Repts 50-277/88-23 & 50-278/88-23 on 880627-30.No Violations Observed.Major Areas Inspected: Followup on Licensee Implementation of Commitments Identified in Util 880603,13,17 & 24 Ltrs IR 05000277/19880271988-08-15015 August 1988 Insp Repts 50-277/88-27 & 50-278/88-27 on 880802-04.No Violations Noted.Major Areas Inspected:Emergency Response Facilities,Public Info Program,Changes to Emergency Prearedness Program & Followup of Previously Noted Issues IR 05000277/19880251988-08-11011 August 1988 Insp Repts 50-277/88-25 & 50-278/88-25 on 880718-22.No Violations or Deviations Noted.Major Areas Inspected:Util Licensed Operator Requalification Program W/Respect to Program Effectiveness IR 05000277/19880181988-07-26026 July 1988 Insp Repts 50-277/88-18 & 50-278/88-18 on 880604-0715.No Violations Noted.Major Areas Inspected:Accessible Portions of Unit 2 & 3,operational Safety,Radiation Protection, Physical Security,Control Room Activities & Maint IR 05000277/19880211988-07-21021 July 1988 Mgt Meeting Insp Repts 50-277/88-21 & 50-278/88-21 on 880609 Re Security Concerns at Plant Reported in Annual Security Audit & Findings of Util Investigation Into Allegations by Members of Plant Security Force IR 05000278/19880141988-07-20020 July 1988 Insp Rept 50-278/88-14 on 880509-20.Unresolved Items & Concerns Noted.Major Areas inspected:safety-related Piping Weldments Selected from Plant Replacement Piping Program Insp Plan,Including Welding & Preservice Insp IR 05000277/19880191988-07-18018 July 1988 Insp Repts 50-277/88-19 & 50-278/88-19 on 880606-10.No Violations Noted.Major Areas Inspected:Implementation & Effectiveness of Corrective Actions in QA Program for Procurement of Commercial Grade Items IR 05000277/19880201988-07-12012 July 1988 Insp Repts 50-277/88-20 & 50-278/88-20 on 880613-17.No Violations Noted.Major Areas Inspected:Nonradiological Chemistry Program in Measurement Control & Analytical Procedure Evaluations IR 05000277/19880221988-07-0707 July 1988 Insp Repts 50-277/88-22 & 50-278/88-22 on 880623.No Violations Noted.Major Areas Inspected:Emergency Preparedness Annual Emergency Drill & Followup of Corrective Actions on Previously Identified Issues IR 05000277/19880131988-06-0808 June 1988 Insp Repts 50-277/88-13 & 50-278/88-13 on 880423-0603.Four Violations Noted by Licensee.Major Areas Inspected: Operational Safety,Radiation Protection,Physical Security, Refueling Activities,Maint,Outstanding Items & Events IR 05000277/19870351988-06-0101 June 1988 Insp Repts 50-277/87-35 & 50-277/87-35 on 871113-880114.No Violations Noted.Major Areas Inspected:Overall Crew Interaction,Knowledge & Use of Plant Procedures,Knowledge & Use of Tech Specs & Crew Communication IR 05000277/19880111988-05-18018 May 1988 Insp Repts 50-277/88-11 & 50-278/88-11 on 880411-15.No Violations Noted.Major Areas Inspected:Status of Previously Identified Items,Air Sampling Program,Alara,Worker Allegation & Pipe Replacement Project Changes IR 05000277/19880121988-05-11011 May 1988 Safety Insp Repts 50-277/88-12 & 50-278/88-12 on 880419-20. No Violations Noted.Deficiencies Found in Emergency Action Level Scheme & Personnel Response.Major Areas Inspected: Emergency Preparedness Training Program ML20153B8831988-04-28028 April 1988 Insp Repts 50-277/88-04 & 50-278/88-04 on 880201-11.No Violations Noted.Major Areas Inspected:Review of Licensee Action in Response to USI A-7, Mark I Containment Program IR 05000277/19880081988-04-21021 April 1988 Insp Repts 50-277/88-08 & 50-278/88-08 on 880314-18. Violations Noted.Major Areas Inspected:Replacement of Recirculation Sys Piping on Unit 3 & Detection of IGSCC in Shroud Support Access Cover Plates of Unit 3 1990-09-06
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000277/19990071999-10-19019 October 1999 Insp Rept 50-277/99-07 & 50-278/99-07 on 990810-0922.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000277/19993021999-10-13013 October 1999 NRC Operator Licensing Exam Repts 50-277/99-302OL & 50-278/99-302OL (Including Completed & Graded Tests) for Tests Administered on 990913-16.All Applicants Passed All Portions of Exams IR 05000277/19993011999-08-0404 August 1999 NRC Operator Licensing Exam Repts 50-277/99-301 & 50-278/99-301 Administered on 990702-14 (Administration) & 990715-22 (Grading).Six of Six Limited SROs Passed All Portions of Exams IR 05000277/19990051999-07-27027 July 1999 Insp Repts 50-277/99-05 & 50-278/99-05 on 990518-0628. Non-cited Violations Noted.Major Areas Inspected:Operations, Surveillances & Maintenance,Engineering & Technical Support & Plant Support Areas IR 05000277/19990041999-06-11011 June 1999 Insp Repts 50-277/99-04 & 50-278/99-04 on 990405-0517. Non-cited Violation Noted.Major Areas Inspected:Operations, Surveillances & Maintenance,Engineering & Technical Support & Plant Support Areas IR 05000277/19990011999-03-25025 March 1999 Insp Repts 50-277/99-01 & 50-278/99-01 on 990105-0215.No Violations Noted.Major Areas Inspected:Operations, Surveillances & Maint,Engineering & Technical Support & Plant Support Including Security & Safeguards Activities PNO-I-99-011, on 990208,operators Experienced lock-up of Unit 2 Plant Monitoring Sys Computers While Performing Testing for Y2K Mod of Rod Worth Minimizer Sys.Region I Public Affairs Prepared to Respond to Media Inquiries1999-03-0303 March 1999 PNO-I-99-011:on 990208,operators Experienced lock-up of Unit 2 Plant Monitoring Sys Computers While Performing Testing for Y2K Mod of Rod Worth Minimizer Sys.Region I Public Affairs Prepared to Respond to Media Inquiries ML20202J8241999-02-0101 February 1999 Notice of Violation from Insp on 981116-1204.Violation Noted:On 981204 There Were Two Instances Where PECO Had Failed to Properly Translate Design Info Into Procedures Used for safety-related Activities IR 05000277/19980091999-02-0101 February 1999 Insp Repts 50-277/98-09 & 50-278/98-09 on 981116-1204. Violations Noted.Major Areas Inspected:Reactor Core Isolation Cooling & 4kV Electrical Distribution Sys Operation Under Normal & Emergency Operating Conditions IR 05000277/19980111999-02-0101 February 1999 Insp Repts 50-277/98-11 & 50-278/98-11 on 981110-990104. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20202J5361999-01-29029 January 1999 Notice of Violation from Insp on 980309-1222.Violation Noted:Three Licensee Operators Failed to Successfully Complete Requalification Program for Facility for Which License Being Sought IR 05000277/19980121998-12-16016 December 1998 Insp Repts 50-277/98-12 & 50-278/98-12 on 981116-19.No Violations Noted.Major Areas Inspected:Emergency Preparedness full-participation Exercise Evaluation IR 05000277/19980101998-12-11011 December 1998 Insp Repts 50-277/98-10 & 50-278/98-10 on 980922-1109. Violations Noted.Major Areas Inspected:Licensee Operations, Surveillances & Maint,Engineering & Technical Support & Plant Support ML20206N6821998-12-11011 December 1998 Notice of Violation from Insp on 980922-1109.Violation Noted:On 980810,chemistry Technicians Failed to Properly Perform Required Actions of Step 4.4.3 When D Detector, RIS-2-17-458D Went Downscale During Test ML20155F7571998-10-30030 October 1998 NRC Operator Licensing Exam Repts 50-277/98-301OL & 50-278/98-301(OL) (Including Completed & Graded Tests) for Exams Administered on 980914-22.All Applicants Passed Exam ML20155D4141998-10-28028 October 1998 Notice of Violation from Insp on 980811-0921.Violation Noted:Prior to 980912,PECO Failed to Properly Maintain Sys Operation Procedure 12.1.A-3,rev 19,resulting in Two RWCU Sys Events in August 1998 ML20155D4571998-10-28028 October 1998 Insp Repts 50-277/98-08 & 50-278/98-08 on 980811-0921. Violations Noted.Major Areas Inspected:Operations, Surveillances & Maintenance,Engineering & Technical Support & Plant Support Areas IR 05000277/19980071998-09-15015 September 1998 Insp Repts 50-277/98-07 & 50-278/98-07 on 980623-0810.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000171/19980011998-08-0707 August 1998 Insp Rept 50-171/98-01 on 980612.No Violations Noted. Major Areas Inspected:Review of Facility Mgt & Control, Decommissioning Support Activities,Radiological Safety & Independent Measurements by Inspector ML20236R7661998-07-16016 July 1998 Insp Repts 50-277/98-06 & 50-278/98-06 on 980505-0622. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20236R7511998-07-16016 July 1998 Notice of Violations from Insp on 980505-0622.Violations Noted:On 980515,inoperable B Channel Had Not Been Placed in Tripped Condition for Approx 28 H ML20249A4841998-06-11011 June 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:During Eecs Suction Strainer Replacement Mod in Oct 1997,licensee Did Not Establish Instructions & Procedures to Prevent Foreign Matl IR 05000277/19980021998-06-0909 June 1998 Insp Repts 50-277/98-02 & 50-278/98-02 on 980315-0504. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20249A0781998-06-0909 June 1998 Notice of Violation from Insp on 980315-0504.Violation Noted:Radiation Area Signs Were Not Visible Nor Conspicuous ML20237E6931998-06-0808 June 1998 EN-98-045:on 980611,notice of Proposed Imposition of Civil Penalty in Amount of $55,000 Issued to Licensee.Action Based on Two Violations Re Failure to Implement Adequate Foreign Matls Exclusion Program at Facility,Which Led to Debris ML20247L2791998-05-14014 May 1998 Notice of Violation from Insp on 980309-13 & 0330-0403. Violation Noted:From January 1998 to 980313,facility Licensee Administered Annual Operating Test to Operators in Manner That Sample Not Sufficiently Comprehensive IR 05000277/19970041998-05-14014 May 1998 Insp Repts 50-277/97-04 & 50-278/98-04 on 980309-13 & 0330-0403 (Onsite) & 980314-0429 (Inoffice).Violation Noted. Major Areas Inspected:Licensed Operator Requalification Training & Evaluation & Maint Rule Implementation Areas IR 05000278/19980051998-05-0707 May 1998 Insp Rept 50-278/98-05 on 980330-0424.Violations Noted. Major Areas Inspected:Events Re Discovery of Foreign Matl in 3A Core Spray Pump on 980324 IR 05000277/19980011998-05-0101 May 1998 Insp Repts 50-277/98-01 & 50-278/98-01 on 980118-0314. Violations Noted.Major Areas Inspected:Licensee Operations, Surveillance & Maint,Engineering & Technical Support & Plant Support Areas ML20217P7281998-05-0101 May 1998 Notice of Violation from Insp on 980118-0314.Violation Noted:Nrc Identified That Control Room Supervisor Did Not Visually or Verbally Communicate Alarm Ack of an Expected Alarm That Come in on Unit 3 ML20217N3771998-03-30030 March 1998 Insp Rept 50-277/98-03 on 980212-0303.Violations Noted.Major Areas Inspected:Reviewed Events,Significance,Reportability & CAs for 2 'A' RFP Turbine High Level Trip Events Involving 3 1997 Failures & 1 Trip on 980206 ML20217N3651998-03-30030 March 1998 Notice of Violation from Insp on 980212-0303.Violation Noted:Nrc Identified That as of 980303,LER Had Not Been Submitted for Event of 970401,involving Condition Prohibited by TS Section 3.3.2.2 IR 05000277/19970091998-02-26026 February 1998 NRC Operator Licensing Exam Repts 50-277/97-09OL & 50-278/97-09OL Conducted on 970922-26.Exam Results:Two RO & Seven SRO Applicants Passed Exam.One SRO Applicant Failed Operating Portion of Exam ML20203E3701998-02-20020 February 1998 Insp Repts 50-277/97-08 & 50-278/97-08 on 971123-980117. Violations Noted.Major Areas Inspected:Plant Operations, Maint,Engineering & Plant Support ML20203E3601998-02-20020 February 1998 Notice of Violation from Insp on 971123-980117.Violation Noted:In Nov 1997,operations Personnel Did Not Fully Adhere to Routine Test Procedure RT-O-040-620-2,Rev 4, Outstanding HVAC & Outer Screen Insp for Winter Operation ML20197H0431997-12-16016 December 1997 Notice of Violation from Insp on 970921-1122.Violation Noted:Peco Did Not Properly Implement Written Procedures on Three Separate Occasions.Specifically,Between July 1997 & 0922,personnel Did Not Follow Instructions for Work Order IR 05000277/19970071997-12-16016 December 1997 Insp Repts 50-277/97-07 & 50-278/97-07 on 970921-1122. Violations Noted.Major Areas Inspected:Operations, Surveillance & Maintenance,Engineering & Technical Support & Plant Support Areas IR 05000277/19970061997-10-15015 October 1997 Insp Repts 50-277/97-06 & 50-278/97-06 on 970810-0920.No Violations Noted.Major Areas Inspected:Plant Operations, Maint,Engineering & Plant Support ML20217A6461997-09-12012 September 1997 Notice of Violation from Insp on 970608-0809.Violation Noted:Licensee Did Not Properly Maintain Written Procedures for Bypass of MCR Ventilation Sys When Div 1 MCR Radiation Monitor Was Inoperable IR 05000277/19970051997-09-12012 September 1997 Insp Repts 50-277/97-05 & 50-278/97-05 on 970608-0809. Violations Noted.Major Areas Inspected:Operations, Surveillance & Maint,Engineering & Technical Support & Plant Support Areas ML20149L2951997-07-24024 July 1997 Insp Repts 50-277/97-04 & 50-278/97-04 on 970504-0607. Violations Noted.Major Areas Inspected:Operations, Surveillance & Maintenance,Engineering & Technical Support & Plant Support ML20149L2911997-07-24024 July 1997 Notice of Violation from Insp on 970504-0607.Violation Noted:Between mid-1993 & Nov 1996,grand Master Keys That Could Be Used to Open Locked High Radiation Areas Not Maintained Under Administrative Control ML20149H1931997-07-17017 July 1997 SALP Repts 50-277/97-99 & 50-278/97-99 for 951015-970607 ML20140D2051997-06-0404 June 1997 Integrated Insp Repts 50-277/97-02 & 50-278/97-02 on 970308-0503.Violations Noted.Major Areas Inspected: Operations,Surveillance,Maint,Engineering,Technical Support & Plant Support ML20140D1841997-06-0404 June 1997 Notice of Violation from Insp on 970308-0503.Violation Noted:Between 970321-26,PECO Failed to Maintain Measures to Assure That Design Quality Std Deviations for safety-related Rhr,Hpci & HPSW Were Controlled IR 05000277/19970011997-04-14014 April 1997 Insp Repts 50-277/97-01 & 50-278/97-01 on 970112-0308.No Violations Noted.Major Areas Inspected:Operations, Surveillance & Maint,Engineering & Technical Support & Plant Support ML20138P2571997-02-10010 February 1997 Notice of Violation from Insp on 961208-970131.Violation Noted:From 960718-29,during Mod to Turbine Bldg,Licensee Did Not Assure That Turbine Bldg Atmosphere Exhausted Through Penetrations in Bldg Wall ML20138P2661997-02-10010 February 1997 Insp Repts 50-277/97-03 & 50-278/97-03 on 961209-970131. Violations Noted.Major Areas Inspected:Areas Involving Radiological Environ Monitoring Programs ML20134K2821997-02-0707 February 1997 Insp Repts 50-277/96-09 & 50-278/96-09 on 961110-970111.No Violations Noted.Major Areas Inspected:Operations, Surveillance & Maintenance,Engineering & Technical Support & Plant Support ML20134F9051997-02-0303 February 1997 Notice of Violation from Insp on 960305 & 0506 & Between 1003 & 1127.Violation Noted:Electronic Copy of Limerick Physical Security Plan,Located on PECO Nuclear Local Area Network & Document Not Under Control 1999-08-04
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report N /86-08 and 50-278/86-08 Docket N /50-278 License No. DPR-44 and DPR-56 Priority -
Category C Licensee: Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101 Facility Name: Peach Bottom Atomic Power Station Units 2 and 3 Inspection At: Delta, Pennsylvania Inspection Conducted: March 17-21, 1986 Inspector: ie Nf Nac4- Y _ /9/6 A. Krasopoul'os, Re%ctor Engineer, DRS
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Also participating in the inspection and contributing to the report were:
J. Stang, Fire Protection Specialist, NRR K. Parkinson, Electrical System Specialist, BNL A. Coppola, Mechanical Systems Specialist, BNL
, Approved by: ~ St2A,A >>44/ //9 f/o 3 3d*DRS ElSection, "' " '"T* ' "' * "'V It** ' '
Inspection Summary: Inspection on March 17-21, 1986 (Combined Report N /86-08 and 50-278/86-08)
Areas Inspected: Special, announced team inspection of the licensee's efforts to comply with the requirements of 10 CFR 50, Appendix R, Sections III. G, J and L, concerning fire protection features to ensure the ability to achieve and maintain safe shutdown in the event of a fir Results: No violations were identifie Five items remained unresolved at the end of the inspectio , PDR ADOCK.0500 e -
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DETAILS 1.0 Persons Contacted 1.1 Philadelphia Electric Company (PECO)
- H. Abendroth, Co-owner Site Representative
- W. Birely, St. Licensing Engineer
- W. Boyer, Electrical Supervising Engineer
- G. Brecht, Jr., Chief Electrical Engineer
- G. Cambell, Senior Designer
- R. Fleischmann, Plant Manager
- C. Gerdes, Mechanical Engineer
- M. Lohr, Electrical Engineer R. Lonabaugh, Fire Marshal
- J. McCawley, Electrical Engineer
- W. Mindick, Sr. Electrical Engineer
- G. Morley, Supervising Engineer J. Pizzolo, QA Engineer
- G. Reid, Sr. Mechanical Engineer
- M. Ryan, Compliance Engineer
- S. Spitko, Administrative Engineer
- C. Swenson, Compliance Engineer
- W. Ullrich, Superintendent Nuclear Generation Division T. Wilson, Site QA Supervisor 1.2 Licensee Contractors
- A. Melikian, Project Engineer (EPM)
- D. Brecken, Project Manager-(EPM)
1.3 Nuclear Regulatory Commission (NRC)
- G. Gears, Project Manager J. Williams, RI
- Denotes those present at exit intervie .0 Purpose This team inspection was conducted to ascertain licensee compliance with 10 CFR 50, Appendix R, Sections III. G, J, and O. Because full compliance with the above regulations is not required until the end of the next i Unit 2 refueling outage, the team reviewed the licensee's approach to compliance, along with the plans and schedules for completing all other modifications required in this are I i
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3.0 Background 10 CFR 50.48 and 10 CFR 50, Appendix R, became effective on February 17, 198 For Peach Bottom Units 2 and 3, the applicable portions of this regulation are Sections III.G, " Fire Protection of Safe Shutdown Capa-bility," III.J, " Emergency Lighting," and III.L, " Alternative and <
Dedicated Shutdown Capability."
10 CFR 50.48 sets forth the schedule for the completion of modifications required for compliance with the above regulations.Section III.G of Appendix R requires that fire protection features are provided to ensure ~ ~ ~~~ ~
that one train of equipment necessary to achieve and maintain safe shut-down remains available in the event of a fire at any location within a licensed operating facility. For hot shutdown conditions, one train of the systems necessary must be free of fire damage (III.G.I.a). For cold shutdown conditions, repair is allowed using in place procedures and materials available onsite with the provision that cold shutdown be achievable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the initiating event (III.G.1.b).Section III.G.2 lists specific options to provide adequate protection for redun-dant trains of equipment located outside of the primary containmen These options are:
Separation by a fire barrier having a three hour rating (III.G.2.a).
Separation by a horizontal distance of at least 20 feet with no in-tervening combustibles and with fire detection and automatic fire suppression installed in the fire area (III.G.2.b).
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Enclosure of one train in a fire barrier having a one hour rating in addition to having fire detection and automatic suppression installed in the fire area (III.G.2.c).
If the protection required by Section III.G.2 is not provided or the systems of concern are subject to damage from fire suppression .
activities,Section III.G.3 of the rule requires that an alternate or dedicated shutdown capability be provided which is independent of the area of concern. Any alternate or dedicated system requires NRC review and approval prior to implementation.
For situations in which fire protection does not meet the requirements of--
Section III.G, however, such protection is deemed to be adequate by the licensee for the specific situation, the rule allows the licensee to request an exemption on a case-by-case basi Such exemption requests are submitted to the NRC for review and approval and must be justified by the licensee on a technical basi l Presently the licensee must comply with all of the requirements iterated
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above. One exemption from full compliance is the modification work associated with the alternative shutdown capability for Unit 2. Since some of the alternative shutdown systems are common to both units, alter- !
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native shutdown capability is not required for either unit until the end of the next Unit 2 refueling outage. Also, because the licensee is developing a more detailed fire hazards analysis, compliance with section III.G and J. could not be fully ascertained. The analysis will be completed by September 30, 198 .0 Post-Fire Safe Shutdown Capability 4.1 Systems Required for Safe Shutdown In the event of a fire concurrent with the loss of offsite power, the~ ~~ ~
following systems are used to provide the safe shutdown capability of the plant:
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High Pressure Coolant Injection (HPCI) System
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Reactor Core Isolation (RCIC) System
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Automatic Depressurization (ADS) and non-ADS Safety Relief Valves (SRVs)
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Residual Heat Removal (RHR) System-shutdown cooling mode, suppression pool cooling mode, and low pressure coolant injection (LPCI) mode
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Core Spray (CS) System
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High Pressure Service Water (HPSW) System
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Emergency Service Water (ESW) System
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Onsite AC Power Generation and Distribution System
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Onsite DC Power Generation and Distribution System
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Essantial Ventilation Systems Safe shutdown is initiated from the control room by a manual scram of the control rods or automatically by the reactor protection syste The support systems required for safe shutdown include the emergency service water system (ESW) for diesel generator cooling, high pressure service water system (HPSW) for RHR heat exchanger cooling, onsite AC emergency power system, onsite DC Emergency power system and essential ventilation system The precise methodology used for safe shutdown has not been finalized by the licensee. Currently, the following shutdown methods are under review:
Method-A l
For Method A, RCIC is used to maintain reactor vessel coolant inven-tor RHR and HPSW are used for suppression pool cooling which is required for decay heat remova Heat is transferred from the vessel to the suppression pool via the ADS system and/or the RCIC steam turbine discharg _ _ _ _ - _ .
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Method B For Method B, HPCI is used to maintain reactor vessel coolant inven-tory, RHR and HPSW are required as in method A for suppression pool cooling. Heat is transferred from the vessel to the suppression via the ADS system and/or the HPCI steam turbine discharg Method C For Method C, the reactor is depressurized using the ADS system to a point where either the Core Spray or the LPCI mode of the RHR' - ~ ~ -
systems can be used to maintain core inventor Method D Method D, is the alternative shutdown method for a catastrophic fire in either the Control Room, Cable Spreading Room or the Emergency Shutdown Panel Are This method is described in the following sectio .2 Alternate Safe Shutdown Areas The licensee committed to and is in the process of_ establishing alternate safe shutdown capability independent of the main control room, cable spreading room and the emergency shutdown panel are The alternative shutdcwn stations are provided with circuit isolation capability using manual control switches, relays, breakers or fuse-disconnect switches, to ensure that no electrical connection exists between the alternative shutdown circuits and those affected by a fire in any one of the above-mentioned area In the event of an unmitigated fire in these areas, the operators will proceed to the alternative shutdown stations to initiate shut-down operation Communications will be established between the operators who are at the alternative shutdown stations and the coordinating operator. The alternative control stations for Peach Bottom are or will be in the following locations:
4. HPCI Alternative Control Station - This panel will be located in each unit in the MG set room at elevation 135' - 0". The-HPCI alternative control station will be equipped with pump diagnostic instrumentation and transfer switches and alternative power supplies for the HPCI turbine. This panel will be equipped -
with the alternative process monitoring instrumentation which indicates reactor vessel pressure and level, suppression pool temperature, and condensate storage tank leve . Diesel Generators Alternative Control Station - These panels will be located in Unit 2 4KV emergency switchgear rooms B/D and are common to both Units 2.and 3. The panels will be equipped with transfer switches to isolate all main control room control circuits, and also diesel generator diagnostic instrumentatio _ _
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4. KV Emergency Switchgear Alternative Controls - These controls are located in the 4KV emergency switchgear rooms in each unit. Transfer switches will provide alternative local control and status indication for the motor control centers and for the ESW, RHR and HPSW pump . ADS Transfer / Isolation Station - Alternative control capabilities for 3 ADS valves and the associated nitrogen supply isolation valves will be located on the HPCI Alternative Control Stations in the M-G Set Rooms. The transfer / isolation switches for these controls are located in the 4KV switchgear rooms. The remote locations for the transfer / isolation switches are necessary to preserve safe shutdown capability for the M-G Set Room . RHR/HPSW Suppression Pool Alternative Control Stations -
Alternative control capabilities and transfer / isolation switches for one loop of RHR/HPSW Motor Operated Valves (MOV's), needed to support Suppression Pool Cooling, will be located at the HPCI Alternative Control Stations in the M-G Set Room .3 Remaining Plant Areas The licensee indicated that all other areas of the plant not required to have an alternate safe shutdown system, comply with the requirements of Section III.G.2 of Appendix R, unless an exemption request has been approved by the staf .0 Inspection Methodology The inspection team examined the licensee's provisions for separating and protecting equipment, cabling and associated circuits necessary to achieve and maintain hot and cold shutdown conditions. This inspection sampled selected fire areas which the licensee had identified as being in compli-ance with Section II The following functional requirements were reviewed for achieving and maintaining hot and cold shutdown:
Pressure control
Process monitoring
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The inspection team examined the licensee's capability to achieve and maintain hot shutdown and the capability to bring the plant to cold shut-down conditions in the event of a fire in various areas of the plant. The examination included a review of drawings, safe shutdown procedures and other documents. Drawings were reviewed to verify electrical independence from the fire areas of concern. Procedures were reviewed for general content and feasibilit Also inspected were fire detection and suppression systems and the degree of physical separation between redundant trains of Safe Shutdown Systems (SSSs). The team review included an evaluation of the susceptibility of' -
the SSSs to damage from fire suppression activities or from the rupture or inadvertent operation of fire suppression system The inspection team examined the licensee's fire protection features provided to maintain one train of equipment needed for safe shutdown free of fire damage. Included in the scope of this effort were fire area boundaries, including walls, floors and ceilings, and fire protection.of
openings such as fire doors, fire dampers, and penetration seal The inspection team also examined the licensee's compliance with Section III.J, Emergency Lighting.Section III.0, Oil Collection System for Reactor Coolant Pump is not applicable to the licensee since the contain-ment is inerted during normal operations.
) 6.0 Inspection of Protection Provided for Safe Shutdown Systems 6.1 Protection in Various Fire Areas The team reviewed the protection prov'ided to SSSs in selected fire areas for compliance with Appendix R, Sections III.G.1, 2 and The following fire areas were inspected:
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The Control Room
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The Cable Spreading Room
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'The Switch Gear Room
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The Battery Room
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The Intake Structure (Fire Areas 47 and 48)
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The Turbine Building
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The Reactor Building, Fire Areas 5, 6, 12 and 13
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The Radwaste Building, Fire Areas 2 and 25
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Yard Area Manholes 25, 89 and 90 No unacceptable conditions were identified except as follows:
Inspection effort incomplete because of unfinished analysi The inspection team could not ascertain the licensee's compliance with Section III.G of Appendix R because the analysis identifying the shutdown methodology had not been finalized at the time of the inspection. This is an unresolved item pending completion of the analysi (50-277/86-08-01 and 50-278/86-08-01)
6.2 Safe Shutdown Procedures The team requested to review safe shutdown and alternative shutdown procedures to ascertain that shutdown can be achieved in a safe and orderly manne The licensee stated that these procedures have not been developed as yet but will be in effect by the end of the next Unit 2 refueling outage. This is in agreement with previous commitments made to the NR This is an unresolved item pending licensee completion of the procedure (50-277/86-08-02 and 50-278/86-08-02)
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6.3 Protection for Associated Circuits Appendix R,Section III.G requires that protection be provided for associated circuits that could prevent operation or cause malopera-tion of redundant trains of systems necessary for safe shutdow The circuits of concern are generally associated with safe shutdown circuits in one of three ways:
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Common bus concern
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Spurious signals concern
Common enclosure concern
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The associated circuits were evaluated by the team for common bus, spurious signal, and common enclosure concerns. . Power, control, and instrumentation circuits were examined on a sampling basis for potential problem . Common Bus Concern-The common bus concern may be found in circuits, either safety related or non-safety related, where there is a common power source with shutdown equipment and the power source is not electrically protected from the circuit of concer .
. 9 The team examined, on a sampling basis, protective relay coordination for 4160V and 480V buses and protection for specific instrumentation, control and power circuits. The coordination of fuses and circuit breakers was checked by examination of the licensee's fuse and breaker coordination curves. The licensee performs relay calibration during refueling outages on approximately 18 month interval No unacceptable conditions were identifie .3.2 Spurious Signals Concern ~ ~~ -
The spurious signal concern is made up of 2 items:
False motor control and instrument indications can occur such as those encountered during the 1975 Browns Ferry fire. These could be caused by fire initiated grounds, short or open circuit *
Spurious operation of safety related or non-safety related components can occur that would adversely affect shutdown capability (e.g., RHR/RCS isolation valves).
The team requested to review documents, on a sampling basis, in the following areas to ascertain that no spurious signal concern exists:
Current transformer secondaries
- High/ low pressure interfaces
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General fire instigated spurious signals The licensee explained that an associated circuit analysis for spurious signals is currently being developed but is not yet finishe This is an unresolved item pending the licensee's comple-tion of an associated circuits analysis for spurious signal (50-277/86-08-03 and 50-278/86-08-03).
6.3.3 Common Enclosure Concern The common enclosure concern may be found when redundant circuits are routed together in a raceway or enclosure and they are not electrically protected or when a ~ fire can destroy both circuits due to inadequate fire barriers. The team could not inspect this area since the licensee's analysis was incomplete. The licensee stated that this analysis is currently in proces ..
, 10 This is an unresolved item pending licensee completion of the analysis and reinspection in this are (50-277/86-08-04 and 50-278/86-08-04)
7.0 Emergency Lighting 10 CFR 50, Appendix R, Section III.J, requires that emergency lighting units with at least an 8-hour battery power supply shall be provided in all areas needed for operation of safe shutdown equipment and in access and egress routes theret ~. - _ . - -.
Due to lack of safe shutdown procedures, the team was not able to inspect this area. This item remains unresolved. (50-277/86-08-05 and 50-278/86-08-05)
8.0 Oil Collection System for Reactor Coolant Pumps 10 CFR 50, Appendix R, Section III.0, requires that the reactor coolant pumps shall be equipped with an oil collection system if the containment is not inerted during normal operation. As the containment for either unit is inerted during normal operation, the above requirement does not apply to Units 2 or .0 _ Unresolved Items Unresolved items are matters for which more information is required in order to ascertain whether they are acceptable, violations, or deviation Unresolved items are discussed in Sections 6.1, 6.2, 6.3 and .0 Exit Interview The inspection team met with the licensee representatives, denoted in Section 1.0, at the conclusion of the inspection on March 21, 1986, and the team leader summarized the scope and findings of the inspection at that time.
, The team leader also confirmed with the licensee that the report will not contain any proprietary information. The licensee agreed that the inspection report may be placed in the Public Document Room without prior licensee review for proprietary information (10 CFR 2.790).
At no time during this inspection was written material provided to the licensee by the team.