IR 05000010/1981019
| ML17194A416 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 01/08/1982 |
| From: | Jordan M, Reimann F, Tongue T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17194A415 | List: |
| References | |
| 50-010-81-19, 50-10-81-19, 50-237-81-36, 50-249-81-28, NUDOCS 8201210221 | |
| Download: ML17194A416 (11) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Reports No. 50-10/81-19; 50-237/81-36; 50-249/81-28 Docket Nos. 50-10, 50~237, 50-249 Licenses No. DPR-02, DPR-19, DPR-25 Licensee:
Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name:
Dresden Nuclear Power Station, Units 1, 2, and 3 Inspection At:
Dresden Site, Morris, IL Inspection Conducted:
November 7 through December 4, 1981
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T. M. Tongue
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M. J. Jordan
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Approved By:
F. W. Reimann, ActingJC~ief, Reactor Projects Section IC Inspection Summary
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Inspection on November 7 through December 4, 1981 (Reports No. 50-10/81-19, 50-237/81-36, 50-249/81-28)
Areas Inspected:
Action on Previous Inspection Findings, Operational Safety Verification, Monthly Maintenance Observation, Monthly Surveillance Observa-tion, Licensee Event Reports Followup, Plant Trips, Receipt of New Fuel, Design Changes and Modifications, Inspection During Long Term Shutdown, and Three Mile Island Modifications - Trackin The inspection involved a total of 185 inspector-hours onsite by two NRC inspectors, including 49 inspector-hours onsite during offshift~
Results:
Of the ten areas inspected, there were no items of noncompliance.
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DETAILS SECTION I Persons Contacted
- D. Scott, Station Superintendent
- R. Ragan, Operations Assistant Superintendent J. Eenigenburg, Maintenance Assistant Superintendent
- D. Farrar, Administrative Services and Support Assistant Superintendent J. Brunner, Technical Staff Supervisor J. Wujciga, Unit 1 Operating Engineer J. Almer, Unit 2 Operating Engineer M. Wright, Unit 3 Operating Engineer J. Doyle, QC Supervisor
- D. Adam, Waste Systems Engineer G. Myrick, Rad-Chem Supervisor B. Saunders, Station Security Administrator B. Zank, Training Supervisor
- E. Wilmer, QA Coordinator
- R. Stobert, QA Engineer The inspector also talked with and interviewed several other licensee employees, including members of the technical and engineering staffs, reactor and auxiliary operators, shift engineers and foremen, electrical,
- mechanical and instrument personnel; and contract security personne *Denotes those attending one or more exit interviews conducted on November 12, 1981, and December 4, 19~.
Action on Previous Inspection Findings Open Inspection Item 50-237/80-25-02 was reviewed during the period of November 7, 1981, through December 4, 198 While observing the licensee inspections of new fuel for the upcoming Unit 3 refueling, it was found that the personnel involved were knowledgeable with regard to procedures, and a copy of the most recent approved procedures were available for referenc This open inspection item is considered close Open Inspection Item 50-10/81-07-01, was reviewed by the inspector and found that a procedure had been written and carried out for Unit l steam drum reference leg back fill and level instrument calibration. It was also found that a routine surviellance is under developmen This item will remain open until the surviellance development is complet.
Operational Safety Verification The inspector observed control room operations, reviewed applicable log~
and conducted discussions with control room operators during the period of November 7 through December 4, 198 The inspector verified the oper-ability of selected emergency systems, reviewed tagout records and
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verified proper return to service of affected component Tours of Units 2 and 3 reactor buildings and turbine buildings were conducted to observe plant equipment conditions, including potential fire hazards, fluid leaks, and excessive vibrations and to verify that maintenance requests had been initiated for equipment in need of maintenanc The inspector by observa-tion and direct interview verified that the physical security plan was being implemented in accordance with the station security pla The inspector observed plant housekeeping/cleanliness conditions and'
verified implementation of radiation protection control During the period of November 7 through December 4, 1981, the inspector walked down the accessible portions of the Unit 2.Diesel Generator, LPCI and Core Spray, Unit 3 Diesel Generator, and Unit 2/3 Diesel Generator, Standby Gas Treatment System to verify operabilit The inspector also witnessed portions of the radioactive waste system controls associated with radwaste shipments and barrelin These reviews. and observations were conducted to verify that facility operations were in conformance with the requirements established under technical specifications, 10 CFR, and administrative procedure No items of ~oncompliance were identifie.
Monthly Maintenance Observation Station maintenance activities of safety related systems and components listed below were observed/reviewed to ascertain that they were conducted in accordance with approved procedures, regulatory guides and industry codes or standards and in conformance with technical specification The following items were considered during this review:
the limiting conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initiating the work; activities were accomplished using approved procedures and were inspected as applicable; functional testing and/or calibrations were performed prior to returning components or systems to service; quality control records were maintained; activities were accomplished by qualified personnel; parts and materials used were properly certified; radiological controls were implemented; and, fire prevention controls were implemente Wo;rk requests were reviewed to determine status of *outstanding jobs and to assure that priority is assigned to safety related equipment maintenance which may affect system performanc The following maintenance activities were observed/reviewed:
Unit 2 Diesel Generator, 4A and 4B Core Spray Valves, Unit 3 Diesel Generator, Unit 2/3 Diesel Generator, 2A Service Water Pump
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- Following completion of maintenance on the Core Spray Valves, the inspector verified that these systems had been returned to service properl No items of noncompliance were identifie.
Monthly Surveillance Observation The inspector observed technical specifications required surveillance testing on the Unit 2 !RM Rod Block/Scram Surveil+ance Calibration rest, LPCI pump and valve operability, Core Spray pump and valve operability containment cooling service water system pump operability, Unit 3 HPCI pump and valve operability and verified that testing was performed in accordance with adequate procedures, that test instrumentation was calibrated, that limiting conditions for operation were met, that removal and restoration of the affected components were accomplished, that test results conformed with technical specifications.and procedure requirements and were reviewed by personnel other than the individual directing the test, and that any deficiencies identified during the testing were properly reviewed and resolved by appropriate management personne The inspector also witnessed portions of the following test activity:
Unit 2/3 removing moisture from the SBGTS charcoal absorbers No items of noncompliance were identifie.
License~ Event Reports Followup Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to deter-mine that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to prevent recurrence had been accomplished in accordance with technical specification LER' s UNIT 2 81-11 81-50 81-53 81-54 81-55 81-56 81-57 81-58 81-59 81-60 81-61 DESCRIPTION Unplanned Discharge to the River (Closed)
PCIV 1601-55 Failed Solenoid (Closed)
Unit 2 Fuel Pool ARM High Rad (Closed)
Turbine 1st Stage Pressure 45% Scram Bypass Switch Out of Calibration (Closed)
Leak in Fl6or Drain Collector Discharge Line (Closed)
High Drywell Pressure Switch (ECCS) Out of Calibration (Closed)
HPCI System Declared Inoperable (2-2305-10") (Closed)
"B" SBGT System Inoperable (Closed)
"A" CCSW Pump Outboard Bearing Failure (Closed)
Daily Offgas Ratio Out of Limits and Second Sample Not Taken As Soon As Possible (Open)
Damage to Horizontal Guide (1510-12) Restraining LPCI/CCSW Pipe 1510-16" (Closed)
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- DESCRIPTION Torus Water Level Greater Than Tech. Spec. Limits (Closed)
Control Rod Drive R-6 Failure to Scram (Closed)
Failure of Pressure Suppression to Rx. Bldg. Vacuum Breaker Pressure Switch to Trip at Proper Setpoin (Closed)
MSIV Clo~ure Time Out of Spec. (Open)
Unit 2 Quarterly Storage Battery Checks (Late) (Closed)
Main Steam Line High Flow Switch 261-2D Trip Above Tec. Spec. Limits (Closed)
Leak in Piping 3A Rx Water Cleanup Regen. Hx. Pipl.ng (Open)
Rx. Vessel Low Low Water Level Isolation LIS 3-263-57B Tripped Above Tech. Spec. Limits (Closed)
West East and East East Scram Discharge Header Panel Monitor High-High Level Trip greater than 2.5" (Closed)
Discovery of Water in HPCI Steam Supply Line (Closed)
Failure of 3B Electromatic Relief Valve to Open (Open)
Rod Worth Minimizer Failure During Shutdown (Closed)
Unit 3 Diesel Generator Failed To Start During Monthly Surveillance (Closed)
MSIV Closure Times Greater Than 5.0 Sec (Closed)
Scram Discharge Volume East Bank Level Monitor Inoperable (Closed)
Unit 3 Diesel Generator Inoperable (Open)
SRM 23 Rod Block Calibration - Failure to Trip (Closed)
APRM Gain Adjustment Factors Out of Specification (Open)
3 Diesel Generator Declared Inoperable (Open)
Failure of Channel 21 and 22 SRM's to Trip at Required Setpoint (Closed)
Rx. Bldg. to Torus Vacuum Breaker 3-1601-20B Failure to Open (Open)
Auto Blowdown Permissive Press. Sw. 3-1554E Out of Calibration (Closed)
Regarding LER 50-237/81-1 the licensee completed installation and
. tested a modification (M-12-2/3-81-7) in the rad waste Floor Drain Sample Tank (FDST) system that prevents opening the FDST inlet and discharge valves simultaneousl This modification was reviewed by the inspectors and found to be an excellant means of preventing reoccuranc This LER is considered close LER With Respect to LER ~0-237/81-57, this was reviewed in part and addressed in IE Inspection Reports No. 50-237/81-24 and 50-237/81-28, and was the full topic of a special inspection and report No. 50-237/81-25 by a Region III piping specialis Since open inspection items are identified in report No. 50-237/81-25, this LER is closed.
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- With respect to LER 50-237/81-60; this has been referred to Region III Radiation Specialist for final review and analysis.. This LER remains ope With respect to LER 50-237/81-61, this was the topic of a special inspection by a Region III piping specialist and is documented in report No. 50-237/81-3 This LER is close With respect to LER 50-237/81-62, this matt~r was the subject of LER 50-237/81-23 which resulted in a citatio The licensee presently
--h<fsaTech. Spec. change request under review with NRR that will allow a time period for correction of Torus water level when it exceeds it's normal limit This LER is close With respect to LER 50-237/81-65, the licensee committed to develop a repair manual on MSIV's to insure proper assembly in the futur This LER remains open until the manual is complet With respect to LER 50-249/81-21, the licensee has committed to a supplemental LER when the cause of the pipe break is determine This LER remains open until the supplemental LER is submitted and reviewe LER 50-249/81-25, states a supplemental report'will be submitted upon determination of the failure of the 3B electro-matic safety relief valv This LER will be closed upon receipt and acceptance of that repor Regarding LER 50-249/81-30, this matter was addressed in the previous Resident Inspectors report No. 50-249/81-2 The LER describes the event adequately however, it does not describe the extensive licensee corrective action In a discussion with the Operating Engineer, it was agreed that the licensee would submit a revised report to document all corrective action This LER remains opened until the revised LER is submitte Regarding LER 50-249/81-32, ~he licensee committed to make a procedure change to check APRM gains and m.ake adjustments between 10 to 50% power during startup This LER remains open until the procedure change is implimente Regarding LER 50-249/81-33, this matter was the subject of a special inspection/investigation report No. 50-237/81-35 and 50-249/81-27 and was also discussed briefly in inspection report No. 50-249/81-2 In the LER, the licensee committed. to a supplemental LER when the cause of this event is identifie This LER remains open until the supplemental report is submitted and accepte Regarding LER 50-249/81-35, the licensee corrective action of replacing the solenoid appeared adequate, however, the cause of the solenoid failure was not explaine In a discussion with the Unit 3 Operating Engineer, he agreed to pursue the cause of the solenoid failure and submit a supplemental LE This LER remains open until the supple-mental LER is submitted and accepted.
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The licensee reported finding a steam/water leak in the 2Dl feed heater drain line, which was isolated and drained for an investigation into the caus The leak was found to be from a crack in the junction of the drain and spill lines, which was repaire All water leakage was col-lected via the floor drain system and routed to the rad waste system for normal processin Ventilation in that room is monitored, filtered, and exhausted via the Unit 2/3 chimne No evidence of an offsite release was detected from this even This is a non-safety related system, however, the lines contained radioactive material and there was the possibility of an offsite release, the licensee has committed to submit a thirty day repor The licensee reported.an automatic initiation of the Unit 3 HPCI room fire sprinklers while testing the HPCI, during a startup of the Unit 3 reactor on November 29, 198 The HPCI test was immediately secured, the sprinkler system secured and an orderly reactor shutdown was carried ou The results of the licensee's investigation were negative in finding a cause of the sprinkler system startu The water deluge resulted in the HPCI room sump pumps, the Gland Seal Leakoff (GSLO) pump and the 2301-3 HPCI steam valve motor operator would not operate or had abnormal indication plus evidence of water in the HPCI lube oil was foun The affected equipment was repaired and the unit returned to servic The licensee will submit a report per Technical Specification A Unit 3 Reactor Scram occured on December 1, 1981, when a.malfunction occured resulting in a double notch withdrawal of a control rod when a single notch withdrawal was intende The unit tripped on an IRM HiHi signal and simultaneously a short period (less than 5 seconds) alarm sounde The licensee investigation revealed no evidence of fuel damag The apparent cause of the control rod double notch was rod speed or sequence time The licensee used the services of several consultants and conducted an onsite review prior to restarting the reacto The reactor was started up on December 3, 198 This matter was immediately reviewed on December 1, 1981, by a Region III Core Physics inspecto This everit will be identified as LER 50-249/81-40, which will be sub-mitted as a 14 day repor When the licensee submits the final report, it will be reviewed along with the onsite review by the Region III Reactor Core Physics inspecto The findings and documentation will be traceable to the LER numbe The licensee reported occurance on November 19, 1981, where the Unit 3 diesel generator overheated in a similar manner as in the event of October 23, 198 In the earlier event, the Unit 2/3 and Unit 3 diesel generators tripped automatically or had to be tripped manually due to overheatin The event of October 23, was addressed in inspection reports No.50-10/81-17, No. 50-237/81-32, and No. 50-249/81-2 The Resident Inspectors participated in the followup.of the November 19, 1981 event along with continued review by two Regional Engineering specialists and an investigato The licensee subsequently found all three diesel generator cooling water pump discharge check valves with the discs and/or flappers *broken and laying loose in the valve body or wedged in the valve outle These check valves were replaced along with the Unit 2/3 diesel generator cooling water pump after it showed evidence of degradatio A review of licensee corrective action to retain operability of the diesel generator resulted in Confirmatory Action Letters dated November 25, 1981 and December 2, 198 These events and their complete review will be documented in Inspection Reports No. 50-237/81-35 and No. 50-249/81-2 Off-Site Event The licensee reported to the SRI, that a young person (Teenager) had fallen off a public roadway into the cooling lake and was presumed drowned on November 29, 198 The licensee shifted the station cooling water to the lake bypass mode to aid in search for the bod The body was recovered the following day by local fire department rescue and recovery team Although this had no effect on the safety of the plant, it is addressed here as the incident created considerable local media interes No items of noncompliance were identifie.
Plant Trips Following the plant trips of Unit 2 on December 3, 1981; and Unit 3 on October 11 and on December 1, 1981, the inspector ascertained the status of the reactor and safety systems by observation of co.ntrol room indica-tors and discussions with licensee personnel concerning plant parameters, emergency system status and reactor coolant chemistry. The inspector verified the establishment of proper communicat1ons and reviewed the corrective actions taken* by the license All systems responded as expected, and the units were returned to operation on December 4, November 12 and December 3, 1981, respectivel No items of noncompliance were identifie.
Receipt of New Fuel The inspector verified prior to receipt of new fuel that technically adequate, approved procedures were available covering the *receipt, inspection, and storage of new fuel; observed receipt inspections and storage of new fuel elements and verified these activities were per-formed in accordance with the licensee's procedures; and, followed up resolutions of deficiencies found during new fuel inspection No items of noncompliance were identifie.
Design Changes and Modifications
'Through record review that inspector verified for the design changes listed below that design changes were made in accordance with 10 CFR 50.59; that design changes were reviewed in accordance with technical specifications and the established Quality Assurance program; that design changes were conducted in accordance with written procedures which included identification of inspections required by codes or standards, and acceptance test procedures which defined acceptance values or acceptance standards; that test records verified performance of equipment modified to technical specifications/FSAR requirements and performance of modified equipment was reviewed and approve.d; that opera-ting procedures modifications were made and approved in accordance with technical specifications; that installation procedures were adequate for the identified function; that as-built drawings were changed to reflect the modifications; and that records of design changes were maintained as described in 10 CFR 50.59b and the established QA progra Unit 2 Modification (M12-2-81-5) TMI Containment Purge and Vent Valves to Close on a High Radiation Signa Modification (M12-2-75-43) ACAD/CAM Unit 3 Modification (M12-3-75-33) ACAD/CAM Unit 2/3 Modification (M12-2/3-81-07) Rad Waste Floor Drain Sample Tank Inlet and Outlet Valve Interlock No items of noncompliance were identifie.
Inspection During Long Term Shutdown The inspector observed *control room operations, reviewed applicable logs and conducted discussions with control room operators during the period of November 7 through December 4, 198 The inspector verified surveil-lance tests required during the shutdown were accomplished, reviewed tagout records, and verified applicability of containment integrit Tours of Unit 1 accessible areas, including exterior areas were made to make independent assessments of equipment conditions, plant conditions, radiological controls, safety, and adherence to regulatory requirements and to verify that maintenance requests had been initiated for equipment in need of maintenanc The inspector observed plant housekeeping/
cleanliness conditions, iricluding potential fire hazards, and verified implementation of radiation protection control Th'e inspector by obser-vation and direct.interview verified that the physical security plan was being implemented in accordance with the station security pla No items of noncompliance were identifie.
Three Mile Island Modifications - Tracking Note:
NUREG-0737 is the latest summary of all requirements related to TMI and is the classification and basis for modifications and corrective action By letter dated July 1, 1981, and other cor-respondence, CECo stated that all responses address Units 2 and 3
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onl CECo also stated that since Unit 1 is undergoing an extended chemical cleaning, refueling and back fit outage, the issues o NUREG-0737 would be addressed prior to unit startup which is not scheduled until mid 198 Temporary Instruction TI 2515/52 - TMI Action Plan Inspection Require-ments - Hardware Changes This TI is to provide a partial listing of inspection requirements for operating reactors emanating from NUREG-0737, clarification of TMI Action Plan Requirement The inspections under this TI are of licensee actions regarding plant system modifications or additions in response to Action Plan requirements due on July 1, 198 The inspectors used the following criteria to review licensee actions on the Task Action Items in this T Verify that the design changes were reviewed and approved in accordance with technical specifications and established QA/QC control * Verify that the design changes were controlled by established procedure Verify that test results were reviewed and evaluated by the licensee and that test results were within previously established acceptance criteria with retesting accomplished for those cases where test deviations were detecte Verify that operating procedure modifications were made and approved in accordance with technical specifications for such design changes/
modification Verify that as-built drawings were changed to reflect the modificatio Verify that applicable licensee personnel have received trainin~
relating to the modificatio Task Action Plan T.A.P. II.E.4.1., Item 2 of NUREG-0737 By letter dated July 1, 1981, the licensee stated that the Containment Atmosphere Dilution (CAD) portion of the Containment Atmosphere Dilution/
Containment Atmosphere Monitorin9 System (CAD/CAM) has been installed and is operational on Dresden Units 2 and This was reviewed by the inspectors against the criteria listed abov The inspection consisted of a representative sampling of the voluminous amount of material on this subject and was found to be acceptable and as stated by the license Since the CAM portion is not due for completion until 1/1/82, and is part of the total CAD/CAM modification, the package has not reached it's final close out at this tim This item will remain open until the modification is finalized by the licensee and closed out be a later inspectio.....
2515/52 TASK Action Plan T.A.P. II.E. Containment Isolation Dependability Position 7 - containment purge and vent valves must close on a high radiation signa The inspector completed the review of this item with respect to criteria 2 for Unit 2 and found it to be acceptable and as state.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)
throughout the month and at the conclusion of the inspection on December 4, 1981, and summarized the scope and findings of the inspection