IR 05000010/1981017
| ML17194A382 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 12/17/1981 |
| From: | Jordan M, Reimann F, Tongue T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17194A381 | List: |
| References | |
| TASK-2.E.4.1, TASK-2.E.4.2, TASK-2.K.3.15, TASK-2.K.3.27, TASK-TM 50-010-81-17, 50-10-81-17, 50-237-81-32, 50-249-81-24, NUDOCS 8112310385 | |
| Download: ML17194A382 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Reports No. 50-010/81-17; 50~237/81-32; 50-249/81-24 Docket Nos.50-010; 50-237; 50-249 Licenses No. DPR-02; DPR-19; DPR-25 Licensee:
Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facilit.Y Name:
Dresden Nuclear Power Station, Units 1, 2, and 3 Inspection At:
Dresden Site, Morris, IL Inspection Conducted:
October 3 through November 6, 1981 Inspectors: ~~
T. M. To~ue
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M. J. Jordan
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- Approved By:
F. W. Re~~~~n /"**A~~ihg I Chi~f Reactor Projects Section IC Inspection Summary I
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- *: / i,1 Inspection on October 3 through November 6, 1981 (Reports No. 50-010/81-17; 50-237/81-32; and 50-249/81-24)
Areas Inspected:
Routine unannounced resident inspection of Operational Safety Verification, Monthly Maintenance Observation, Monthly Surveillance Observation, Licensee Event Reports Follow-up, Plant Trips, Receipt of New Fuel, Inspection During Long Term Shutdown, and Three Mile Island Modifi-cation The inspection involved a total of 200 inspector-hours onsite by two NRC inspectors including 49 inspector-hours onsite during offshif Results:
Of the eight areas inspected, there were no items of noncompliance identifie a112301003c~50~b6~~lo PDR A n
PDR G
- DETAILS 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. Rybak, Technical Staff Group Leader
- P. Holland, Technical Staff Engineer
- Denotes those attending one or more exit interviews conducted on October 16, 1981, October 30, 1981, and November 6, 198 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.
Operational Safety Verification The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators during thev period of October 3 through November 6, 198 The inspector verified the operability of selected emergency systems, reviewed tagout records and verified proper return to service of affected component Tours of the 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 observation and direct interview verified that the physical
. security plan was being implemented in accordance with the station security pla The inspectors observed plant housekeeping/cleanliness conditions and verified implementation of radiation protection control During the period of October 3 through November 6, 1981, the inspector walked down the accessible portions of the Unit 2 Diesel Generator, HPCI, LPCI, CS, Unit 3 Diesel Generator, LPCI, CS, Unit 2/3 Diesel Generator systems to verify operabilit The inspector also witnessed*portions of the radio-active 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 noncompliance 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 Work requests were reviewed to determine status of outstanding jobs and to assure that prio~ity is assigned to safety related equipment maintenance which may affect system performanc The following maintenance activities were observed/reviewed:
Unit 2 Diesel Generator Unit 3 Diesel Generator, Spent Fuel Pool Rack installation - Mandrel and Neutron Testing, S/R Valve Acoustical Monitor repai Unit 2/3 Diesel Generator Following completion.of maintenance on the Unit 2, 3, and 2/3 Diesel Generator, 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 diesel generator cooling water pump 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 activities:
Unit 2 A.R.M. Calibration, and the Unit 3 Group I Containment Isolation
~n Hi Steam Flo No items of noncompliance were identifie.
Licensee Event Reports Followup The.licensee reported finding the Unit 3 diesel generator emergency fuel cut-off valve.in the shut position, which placed the diesel generator in an inoperable conditio The discovery was made at about 9:30 a.m., on October 14, 1981 by an equipment operator while conducting routine system check The licensee will be submitting a 30 day letter (LER) describing the even The licensee immediately corrected the condition by opening the emergency fuel cut-off valve and verified that the same valves were open on the Units 2 and 2/3 diesel generator The licensee has added these valves to the equipment operators routine check lists to verify that they are in the open positio The licensee has also placed locking devices on other valves that are essential for diesel operatio As an added measure, the locks on the doors to the diesel generator have been modified to assure that they will self-lock when the doors are shu This matter is close On October 23, 1981, a routine operational surveillance check of Units 2/3, and 3 diesel generators was performe During this surveillance Unit 2/3 tripped on overtemperature (Unit 3 was tripped manually to avoid over-heating).
Various tests have been performed in an effort to determine the caus It ~as been determined that the cause of the overheating was due to lack of cooling water to the diesel generator heat exchange Addi-tional testing is taking place to determine the cause of inadequate water flow to the heat exchange Preliminary notifications have been written, and Region III personnel are following this problem closel Results of current testing will.be reported in subsequent report The licensee reported finding a damaged seismic pipe hanger on the 2A Containment Cooling Service Water (CCSW) system on October 6, 198 The hanger's anchor bolts were completely pulled out of the concrete along with a sizeable segment of concret In addition, approximately 12 addi-tional hangers were found to be in questionable conditio The licensee declared this system inoperable, and tested the 2B CCSW subsystem as required by Technical Specification Walk down and visual tests of the*
2B, 3A and 3B CCSW subsystems revealed no additional damag The damaged hangers on the 2A CCSW subsystem were repaired, the system tested and returned to servic The licensee has revised procedures to prevent recurrence and has committed to an engineering study to determine the caus This matter is the subject of a special inspection by Region III piping specialis The inspection results will be forth coming in Inspection Report No. 50-237/81-3 No items of noncompliance were identifie,.. Plant Trips Following the plant trips of Unit 3 on October 18, 1981, and Unit 2 on November 3, 1981, the inspector ascertained the status of the reactor and safety systems by observation of control room indicators and dis-cussions with licensee personnel concerning plant parameters, emergency system status and reactor coolant chemistry. The inspector verified the establishment of proper communications and reviewed the corrective actions taken by the license All systems responded as expected, and the plants were returned to operation on October 20, 1981 and November 7, 1981, respectivel No items of noncompliance were identifie.
Receipt of New Fuel Prior to receipt of new fuel the inspectors verified that technically adequate and approved procedures were available covering the receipt, inspection, and storage of new fuel; the inspectors also observed preliminary receipt inspections and storage of new fuel elements and verified that these activities were performed in accordance with the licensee's procedure.
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 October 3 through November 6, 198 The inspector verified surveillance tests required during the shutdown were accomplished, reviewed tagout records, and verified applicability of containment integrit Tours of the Unit 1 accessible areas, including exterior
- areas were made to make.independent assessments of equipment condi-tions, 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, including potential fire hazards, and verified implementation of radiation protection con-trol The inspector by observation and direct interview verified that the physical security plan was being implemented in accordance with th 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 corre-spondence, CECo stated that since Unit 1 is undergoing an extended chemical cleaning, refueling and back fit outage, the issues of 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 Requirements - 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 to review 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 verify that licensee actions on the Task Action Items in this T The design changes were reviewed and approved in accordance with technical specifications and established QA/QC control The design changes were controlled by established procedure 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 detected., Operating procedure modifications were made and approved in accordance with technical specifications for such design changes/
modification As-built drawings were changed to reflect the modificatio Applicable licensee personnel have received training relating to the modificatio TI 2515/52, TASK II.E.4.1, Dedicated Hydrogen Penetrations NUREG-0737 Item 2 Dresden Units 2 and 3 make use of the Containment Atmosphere Dilution (CAD) technique to meet this requiremen The inspector verified that the CAD portion of the CAD/CAM systems was installed, tested, made ~perational, and personnel were train~d in it's us This item remains open pending further review by the resident inspecto /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 This item concerning containment purge and vent isolation valves isolat-ing on a drywell high radiation signal was made operational on Unit 2 in June 198 The inspectors reviewed this matter against the criteria listed, with the exception of item f, which was not completed as the inspectors were required to review other matter The installation was
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found to be acceptable and to meet the requirements of NUREG-0737 position The remaining review will be completed during a subsequent resident inspectio The licensee is planning to complete this modi-fication during the refueling and maintenance outage in January 198 The inspection will be completed on Unit 3 when the modification is complete CECo letter dated July 1, 1981, references a December 15, 1980, CECo letter from J. S. Abel to D. G. Eisenhut, and BWR Owners Group Study under cover letter by Mr. T. J. Dente's letter to Mr. D. G. Eisenhut dated June 29, 1981, that this isolation signal is not neede This matter is under evaluation by NR In the same document, the licensee stated that the operability of this trip will not be made a Technical Specification requiremen Item II.K.3, Sub Item 15-HPCI Break Detection Logic The licensee has installed the 3 second time delay relay in Units and 3, as committed to in the licensees' July 1, 1981, letter to the NR Inspection items a thru f, as described above for Unit 2 and 3 were satisfie However, the Aperature card showing the as-built modification drawing for Unit 2 has not been returned to the sit The licensee has on site a copy of the drawings marked-up showing the as-built condition, and this is considered acceptable to complete above item The licensee is to address the concerns identified in the letter from Thomas A. Ippolito of NRC dated October 21, 1981, in order to close this ite The inspector reviewed the functional test for the time delay/relay and found that the verificatio~ initials were not filled in according to the procedur The test procedure required a verification initial for each ste The data sheet was initialed after the first step with an arrow down the side of the page through the remaining blanks that required initials, indicating that all steps had been accomplishe The intent of the procedure was-to initial each step as it was accom-plishe This was brought to the attention of management and is being reviewed to determine if it was a result of inadequate knowledge by the individual, or if the individual knew how to make the proper signature but did no This is an open item pending the licensee's corrective action to prevent recurrenc This is an open inspection ite (No. 50-249/81-24-01)
Item II.K.3, Sub Item 27 - Provide Common Reference Level for Vessel Level Instrumentation The licensee has modified the control room reactor water level indicators for both Units 2 and 3, such that the instruments now use the bottom of the separator skirt as a common zer This is as committed to by the licensees' December 31, 1980, and July 1, 1981, letters to the NR The inspection items a thru f as described above for Unit 2 and 3 were satisfie *
In addition to this commitment, the licensee is adding a new transmitter and changing the control room indication for the Wide Range A~cident Yarways so that it is temperature compensate Marked-up drawings are being used to close this ite Final as-built drawings will be completed after the modification is complet.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) throughout the month and at the conclusion of the inspection on November 6, 1981 and summarized the scope and findings of the inspection activitie The licensee acknowledged the findings of the inspectio