IR 05000346/1980027
| ML19340D622 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/10/1980 |
| From: | Reyes L, Rogers W, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19340D621 | List: |
| References | |
| 50-346-80-27, NUDOCS 8012310482 | |
| Download: ML19340D622 (9) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGIO!. III Report No. 50-346/80-27 Docket No. 50-346 License No. NPF-3
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Licensee: Toledo Edison Company Edison Plaza, 300 Madison Avenue Toledo, Ohio 43652 Facility Na:ne: Davis-Besse Nuclear Power Station Inspection At: Davis-Besse Site, Oak liarbor, Oli Inspection Conducted:
September 22-26, 29-30, October 1-3, 6-10, 14-17, 1980 R Fu.) t b Inspectors:
L. A. Reyes g,
j g..g RFLO fer W. G. Rogers jf j
jg.,
RFu)wdeh Approved By:
R. F. Warnick, Chief, N u / d; / 9 4 '
Projects Secticn 3 n+P Inspection Summary Inspection on September 22-26, 29-30, October 1-3, 6-10, 14-17, 1980 (Heport No. 50-346/80-27)
Areas Inspected:
Routine resident inspection of Followup on Previous Inspection Findings, Monthly Maintenance Observation, Monthly Surveillance Observation, Followup of Licensee Event Reports, Followup of IE Bulletins, Inspection During Long Term Shutdown, Review of Plant Operations During Refueling Outage, Independent Inspection Effort (allegation on welder qualification, allegation on fire retardant work completion, testing of decay heat removal isolation valves), Emergency Planning and Actions Taken on TMI Lessons Learned.
The inspection involved 119 inspector-hours onsite by two NRC inspectors including 26 inspector-hours onsite during off-shifts.
Results:
No items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted T. Murray, Station Superintendent
- B. Feyer, Assistant Station Superintendent P. Carr, Maintenance Engineer S. Quennoz, Technical Engineer
- D. Huffman, Administrative Coordinator D. Miller, Operations Engineer D. Briden, Chemist and Health Physicist m u..,,
J. Hickey, Training Supervisor L. Simon, Operations Supervisor C. Daft, Operations QA Manager
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C. Byrne, QA Auditcr
- Denotes those present at the exit interview on October 10, 1980.
The inspectors also interviewed other licensee employees, including members of the technical, operations, maintenance, IEC, training and health physics staff.
2.
Licensec Actions on Previous Inspections Findines (Closed) Open Item (50-346/80-23-02) The licensee prepared procedure EP 1202.63 " Loss of NNI Power" and performed training for all license personnel.
The inspector reviewed the procedure, attended portions of the training, reviewed the training records and verified that the NNI instrumentation in the control room was properly labeled.
(Closed) Open Item (50-346/80-23-03) The licensee prepared procedure EP 1202.62 " Integrated Control System Loss of Power" and performed
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training for all license personnel. The inspector reviewed the
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procedure, attended portions of the training, reviewed the training records, and verified that the ICS instrumentation in the control room was properly labeled.
(Closed) Open Item (50-346/80-23-05) The inspector reviewed the below listed procedures and determined that appropriate guidance was included for the use of the saturation meter.
EP 1202.02, Rev. 16 " Station Blackout" EP 1202.04, Rev. 16 " Reactor / Turbine Trip" EP 1202.06, Rev. 14 " Loss of Reactor Coolant and Reactor Coolant Pressure" EP 1202.14, Rev. 8
" Loss of Reactor Coolant Flow - RCP Trip" EP 1202.26, Rev. 13 " Loss of Steam Generator Feed" AB 1203.02, Rev. 6
" Loss of All AC Power" a
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AB 1203.04, Rev. 7 "Depressurization of the RCS with only Safety Grade Equipment" AB 1203.05, Rev. 7 " Complete Loss of Main and Auxiliary Feedwater" AB 1203.06, Rev. 2 " Inadequate Core Cooling Guidelines" MC 7500.26
" Saturation Meter Post Implementation Test for FCR 79-439" (Closed) Noncompliance (50-346/80-19 Paragraph 10) Failure to log
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the position of locked valves AF 599 and AF 608.
The inspector has reviewed the locked valve log on many occasions as part of his routine daily inspections and has determined that when locked valves are repositioned their position is properly documented in the. locked valve log.
(Closed) Noncompliance (50-346/80-19 Paragraph 10) Failure to sign the monthly inspection tags of fire extinguishers. The inspector conducted tours of the containment, auxiliary and turbine buildings and determined that the monthly inspection tags are being signed for each inspection and that inspection tags that were missing were replaced.
(Open) Noncompliance (50-346/80-15) Failure to notify the NRC Opera-tions Center as per requirement of 10 CFR 50.72.
The inspector verified that Information Notice 80-06 " Notification of Significant Events" had been distributed to the shift supervisors.
The inspector reviewed Special Order 22-4 "Use of Emergency Phones" ar.d determined that the order had been revised. The licensee is reviewing Proce-dure AD 1839.00 " Station Operations" to consolidate and simplify the instructions to shift licensed nersonnel on the reporting
' requirements of 10 CFR 50.72.
This item will remain open until
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procedure AD 1839.00 is revised.
3.
Monthly Maintenance observation Station maintenance activities of safety related systems and com-ponents 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 specifications.
The following items were considered during this review:
the limiting conditions for operation were met while components or systems were removed from service; approvalc were obtained prior-3-e~ :,- a vw-e
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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
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implemented; and, fire prevention controls were implemented.
Work requests were reviewed to determinc status of outstanding jobs and to assure that priority is assigned to safety related equipment maintenance which may affect system performance.
-- r The following maintenance activities were observed / reviewed:
Inspection and repair of valves CF-30 and DH-7G.
Following completion of maintenance on the RCS to LPI isolation check valves, the inspector verified that these systema had been returned to service properly.
No items of noncompliance or deviations were identified.
4.
Monthly Surveillance observation The inspector observed technical specifications required surveil-lance testing on the electric fire pump (ST 5016.02) 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 tech-nical 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 re-
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viewed and resolved by appropriate management personnel.
The inspector also witnessed portions of the following test activities:
RCP Coastdown Flow (PT 5163.02), Auxiliary Feedwater Pump Test (ST 5071.10).
No items of noncompliance or deviations were identified.
5.
Licensee Event Reports Followup Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to determine that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to pre-vent recurrence had been accomplished in accordance with technical specifications.
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l 79-04 " Failure to Post a Security Guard on Containment Entrance During Free Access"
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80-22 " Loss of Control Room Indication for H, Analyzer Discharge
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Valve CV5010E"
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80-24 " Inadvertent Closure of AFW Fump Turbine Main Steam Isolation Valve MS-107"
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80-25 " Control Rod 5-11 Absolute Position Indication Inoperable" 80-26 " Smoke Detector DS 8656 in Continous Alarm Condition" 80-66 " Doors on Spent Fuel Pool EVS Block Open" 80-67 " Failure of Solenoid Valve Operator for Main Steam
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Valve MS101A" No items of noncompliance or deviations were identified.
6.
IE Bulletin Followup For the IE Bulletins listed below the inspector verified that the
written response was within the time period stated in the bulletin, that the written response included the information required to be reported, that the written response included adequate corrective action commitments based on information presented in the bulle-tin and the licensee's response, that licensee management forwarded copies of the written response to the appropriate onsite management representatives, that information discussed in the licensee's
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,ritten response was accurate, and that corrective action taken by w
the licensee was as described in the written response.
78-04 " Environmental Qualification of Certain Stem Mounted Limit Switches Inside Reactor Containment." The licensee has
initiated FCR 78-426 to replace the Namco switches used for position indication on the containment purge system.
This facility change is scheduled for the 1981 refuelin2 outage.
The inspector will followup on the completion of this
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modification and closure of nonconfermance report 57-78.
(50-346/80-27-01)
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79-23 " Potential Failure of Emergency Diesel Generator Field
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Exciter Transformer."
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80-18 " Maintenance of Adequate Minimum Flow Thru Centrifugal Charging Pumps Following Secondary Side High Energy Line Rupture."
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Wo items of noncompliance or deviations were identified.
7.
Inspection Durine Long Term Shutdown
The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the period of September 22 - October 17, 1980. The inspector verified surveillance tests required during the shutdown were accomplished, reviewed tagout records, and verified applicability of containment integrity. Tours of containment, auxiliary and turbine buildings accessible areas, including exterior areas were
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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 maintenance.
The inspec-tor observed plant housekeeping / cleanliness conditions, including potential fire hazards, and verified implementation of radiation protection controls. The inspector by observation and direct interview verified that the physical security plan was being implemented in accordance with the station security plan. The inspector reviewed the licensee's jumper / bypass controls to verify
i there were no conflicts with technical specifications and verified the implementation of radioactive waste system controls.
The inspec-tor witnessed portions of the rcdioactive waste systems controls associated with radwaste shipments and barreling.
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During the review of the safety tagging log and the lifted wire log the inspector noticed that the safety tag log listed "Do Not Operate" (DNO) tags dated from 1974 and that the lifted wire log listed lifted wire tags dated from 1975 and 1976. The inspector requested that the logs be reviewed and evaluation made on these old outstanding log entries.
(50-346/80-27-02)
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No items of noncompliance or deviations were identified.
8.
Review of Plant Operations The inspector verified that prior to plant startup the below listed systems had been returned to service in accordance with approved procedures.
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High Pressure Injection System b.
Low Pressure Injection System c.
Makeup and Purification System d.
Emergency Diesel Generators-6-
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Containment Spray System The inspector reviewed the mode checklist, the safety tag log, and lifted wire log and determined that systems disturbed or tested during the refueling outage were returned to operating status prior to plant startup.
During the inspector walkdown of the above mentioned system the inspector identified several locked valves that were identxfied with temporary tags.
The inspector requested that all locked valves be permanently tagged. The inspector will verify that perma-
nent tags are being installed to the locked valves in a future inspection.
(50-346/80-27-03)
9.
A11ecations on welder Qualifications The resident inspector was contacted by a contractor employee that made allegations regarding the welders' qualifications for the work performed on Facility Change 79-079 and 80-088.
The inspector reviewed the records for Facility Change 79-079, which installed a guard rail on the auxiliary building roof, and determined that welder qualification was not necessary since the job was rat covered by welding code requirements.
T The inspector reviewed the velder qualification records for Facility Change 80-088 and determined that they were adequate. The welds in question were inspected by the contractor's Quality Control inspec-tor and by a TcCo Quality inspector.
Both welding inspectors found the welds to be acceptable.
These findings were discussed with RIII personnel. A RIII welding specialist will review these findings in the next scheduled inspec-
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tion.
(50-346/80-27-04)
The inspector has not yet been successful in contacting the alleger to communicate the findings. However, the findings will be discussed with the alleger.
No items of noncompliance or deviations were identified.
10.
Allegations on Fire Retardant Work Completion The resident inspector received a message from an individual who stated that he was a representative from the Cleveland Plain Dealer who had received a phone call in which allegations were made that the Davis-Besse Plant was going to startup prior to the completion of the application of fire retardant seals.
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The inspector conducted tours of the plant, interviewed TcCo and U E C C personnel and reviewed the records of the work completed.
The inspector determined that the balance of the work to be completed was not a requirement prior to the unit startup.
The inspector has not yet been successful in contacting the alleger to communicate the findings.
Efforts will be continued to contact the alleger to discuss the findings.
No items of noncompliance or deviations were identified.
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11.
Testing of Decay Heat Removal Isolation Valves While conducting tests prior to returning to power operation from the current refueling outage the licensee identified excessive leakage through decay heat removal system check valve CF-30.
This is one of the two in-series check valves isolating the reactor coolant system (RCS) to the low pressure decay heat removal system.
Radiography of the valve was not successful and the licensee pro-l ceeded to cooldown the unit and drain the RCS to perform repairs.
Upon opening the salve the licensee found that the two bolts and locking bracket that hold the disc to the body of the valve were missing. The licensee was not able to locate the missing bolts and bracket and has prepared an evaluation for operation with the loose parts. The licensee repaired the valve and inspected the re-maining similar valves CF-28, CF-29 and CF-31.
All the other valves were found to have their bolts in place secured by the locking bracket.
The inspector witnessed the maintenance activities related to the inspection and repair of these valves. The inspector contacted the
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NRR Licensing Project Manager and Region III and informed them of
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his findings.
No items of noncompliance or deviations were identified.
12.
Emergency Planning The inspector attended a meeting on September 30, 1980, sponsored by the Ohio Disaster Service Agency. Representatives from FEMA, Ottawa County and TeCo participated in the discussions and planning of the Davis-Besse Nuclear Power Station exercise that will be held before the end of calendar year 1980.
13.
Implementation of TMI Lessons Learned Item 2.1.8.a Post Accident Sampling (TAP Item II.B.3)
The inspector reviewed procedure AD 1850.04, " Post Accident-8-
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.9 Radiological Sampling and Counting" and determined that the procedure is adequate for sampling ani analyses of samples during post accident operations. The inspector accompanied the Chemistry and Health Physicist in a walkdown of the procedure and determined that all the equipment necessary was
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available, calibrated and properly labeled.
The licensee has initiated Facility Change Request 80-147 to install a permanent RCS sampling system.
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14.
Exit Interview
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The inspector met with licensee representatives (denoted in Paragraph 1) throughout the period of September 22 through October 17, 1980, and summarized the scope and findings of the inspection activities.
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