IR 05000346/1981015
| ML20031F305 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/28/1981 |
| From: | Mcgregor L, Reyes L, Rogers W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20031F304 | List: |
| References | |
| 50-346-81-15, NUDOCS 8110190513 | |
| Download: ML20031F305 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-346/81-15 Docket No. 50-346 License No. NPF-3
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Licensee: Toledo Edison Company Edison Plaza, 300 Madison Avenue Toledo, OH 43652 Facility Name: Davis-Besse Nuclear Power Station, Unit 1 l
Inspection At: Oak Harbor, OH Inspection Conducted: August 3-7, 10-14, 17-21, 24-28, and 31, 1981 Inspectors:
Y2.B[S)
2S[8)
G ge s
%h.1 Pee Approved By:
L. G. MtGregor, Acting Chief 2.8 /81 Reactor Projects Section 2B Inspection Summary i
Inspection on August 3-7, 10-14, 17-21, 24-28, and 31, 1981 (Report
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No. 50-346/81-15)
Areas Inspected: Routine, unannounced Inspection of followup on previous Inspection Findings, Operational Safety Verification, Monthly Maintenance Observation, Monthly Surveillance observation, Licensee Event Reports fol-lowup, IE Circular followup, Receipt of Neu Fuel, Implementation of TMI lessons learned, Public Meeting on August 24, 1981, Relocation of the local Public Document Room and Requalification training. The inspection involved a total of 190 inspector-hours onsite by two NRC inspectors including 54 inspector-hours onsite during offshifts.
Results: No items of noncompliance or deviations were identified.
n110190513 810929
- PDR ADOCK 05000346 WJ PDR
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DETAILS 1.
Persons Contacted T. Murray, Station Superintendent B. Beyer, Assistant Station Superintendent P. Carr, Maintenance Engineer
- S. Quennoz, Assistant Station Superintendent
- J. Werner, Administrative Coordinator D. Miller, Operations Engineer D. Briden, Chemist and Health Physicist J. Hickey, Training Supervisor L. Simon, Operations Supervisor C. Daft, Operations QA Manager C. J. Greer, QC Supervisor J. Lingenfelter, Technical Engineer
- Denotes those attending the exit interview on August 20, 1981.
The inspectors also interviewed other licensee employees, including members of the technical, operations, maintenance, I&C, training and physics staff.
2.
Followup on Previous Inspection Findings (0 pen) Unresolved Item (50-346/79-13-04): Omissions on procedures verifications checklists. While conducting a valve lineup of the Containment !!ydrogen Dilution System Train No. 2, the inspector noticed that Valves CV-199 and SW-193 were not included in Procedure SP 1104.55. However, all valves were found to be in the correct position.
(0 pen) Open Item (50-346/80-27-03):
Identification tags for safety related valves. While conducting a valve lineup of the Containment Hydrogen Dilution System Train No. 2, the inspector found nine valves (26% of the total system) with no identification tags.
3.
Operational Safety Verification The inspector observed control room operations, revi6wed applicable logs and conducted discussions with control room operators during the month of August. The inspector verified the operability of selected emergency systems, reviewed tagout records and verified proper return to service of affected components. Tours of containment building, auxiliary building and turbine building 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 ecuipment in need of maintenance. The inspector by observation and direct interview verified that the physical security plan was being implemented in accordance with the station security plan.
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The inspector observed plant housekeeping / cleanliness conditions and verified implementation of radiation protection controls. During the month of August, the inspector walked down the accessible portions of the Containment Hydrogen Dilution System Trains 1 and 2 to verify operability. The inspector also witnessed portions of the radioactive waste system controls associated with radwaste shipments and barreling.
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 procedures.
No items of noncompliance or deviations were identified.
4.
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; 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 contro]* were implemented; and, fire prevention controls were implemented.
Work 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 performance.
The following maintenance activities were observed / reviewed:
Low Pressure Injection Pump No. 1. outboard bearing replacement.
Following completion of' maintenance on the Low Pressure Injection Pump No. 1,'the inspector verified that these systems had been returned to'
service properly.
No items of noncompliance or deviations were identified.
5.
Monthly Surveillance Observation The inspector observed technical specifications required surveillance testing'on the ECCS Quarterly Valve Test (ST 5051.13) and CCW Pump No. 1 Monthly Test (ST 5074.01) and verified that testing was performed in accordance with adequate procedures, that test instrumentation was cal-ibrated, that limiting conditions ' for operation were met,.that removal-3-
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'and restoration of the affected components were accomplished, that test results conformed with technical specifications and procedure require-ments 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 personnel.
'The inspector also witnessed portions of the following test activities:
SFAS Monthly Test (ST 5031.01)
i DH/LPI Pump and Check Valve Test (ST 5051.10)
ECCS Verification'of Flowpath (ST 5051.12)
No items of noncompliance or deviations were identified.
6.
Licensee 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 specifications.
78-78 Failure to Conduct Testing of ASME Code Passive Valves.
79-39 Post. Accident Radiation Monitor RE 5029 Inoperable.
79-33 Post Accident Radiation Monitor RE 5030 Inoperable.
79-32 Main Steam Safety Relief Valve Lifted below Technical Specification Setpoint.
79-46 Emergency Diesel Generator 1-1 Turbo Charger Bearing Failure.
79-49-Main. Steam Safety Relief Valve Lifted Below Technical Specification Setpoint.
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80-56 Loss of SFAS Channel'3 Power and Radiation Monitor 2006.
j 80-64 Loss of Essential Instrument. Panel Y2.
-80-81 Loss of Essential Instrument Panel Y2 and Reactor Trip.
80-86 Loss of Essential Instrument Panel Y3.
81-36 Containment Radiation Post Accident Monitor 5030 Inoperable.
Due To Disconnect Bypass Hose.
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No items of noncompliance or deviations were identified.
7.
IE Circular Followup For the IE Circulars listed below, the inspector verified that the Circular was received by the licensee management, that a review for applicability.was performed, and that -if the circular were applicable to the' facility, appropriate corrective actions.were' taken or were
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78-18'
' Underwriters Laboratory Fire Test.
i 81-09.
Containment Effluent Water That Bypasses Radioactivity Monitor.
81-12.
Inade'quate Periodic. Test ~ Procedure of PWR Protection System.
'No items'of noncompliance or deviations wereLidentified.
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8.
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 eleme..s and verified these activities were per-formed in accordance with.the licensee's procederes; and, followed up resolutions of deficiencies as found during new fuel inspections.
Fuel Element Inspected Date NJ02QL 8/12/81 NJ02QM 8/12/81 NJ02R1 8/19/81 NJ02R0 8/19/81 NJ02R8 8/25/81 No items of noncompliance or deviations were identified.
9.
Implementation of TMI Lessons Learned Item I.A.1.1 STA Training Licensee Administrative Procedure AD 1839.04, " Shift Technical Advisor Administrative Procedure" and the licensee's training records were found in good agreement with Criteria NUREG-0737, pages 3-3 through 3-5.
A description of the long term STA training was submitted in TECo's letter of December 31, 1980 and July 6, 1981 (Serial No. 730). Reviewed the procedure requirements with several STA's and determined they were know-ledgeable in these procedure requirements.
In addition of the STA training requirements, one STA has obtained a Reactor Lperators license and another is currently under training to obtain one.
Item I.A.2.1 Upgrade of Reactor Operator (RO) and Senior Reactor Operator (SRO) Training The licensee's training program for RO's and SRO's was found in good agreement with Criteria NUREG-0737, pages 3-16 through 3-35.
The licensee's administrative porcedures for operator training AD 1828.09 and AD 1828.10 are currently under review to reflect the upgraded training program.
Item II.B.4 Training for Mitigation of Core Damage The program for this training is being handled on a B&W owners group level. The training will be offered at the B&W facility in Lynchburg, V,
TECo personnel are currently scheduled to attend this training 'n the months of October 'and November 1981.
10.
Meeting with Local Officials On August 24, 1981, the inspector attended a meeting with Ottawa County.
officials and members of the public. The subject of the meeting was the-5-
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. change in implementation date for the Early Warning System (sirens).
The inspector answered questions from me_' r:s of.the public regarding this subject.
11.
Relocation of Local Public Document Room The Local Public Document Room was relocated from the Ida Rupp Public Library in Port Clinton, Ohio, to the Library of the Univecaity of Toledo in Toledo, Ohio. The inspector visited the library on August 31, 1981. The documents were well organized and easily accessible to the public. The inspector provided his busicuss phone number and address to the library representative in charge of government documents.
12.
Requalification Training The inspector verified that the licensee has instituted a -requalifica-tion program for licensed operators that encompasses the nine categories of 10 CFR 55, Appendix A, Section 2.
The inspector reviewed records of requalification tests, quizzes and evaluations for three Reactor Operators and two Senior Reacter Operators and found them to be in order.
Additionally, records regarding reactivity manipulations were reviewed and found in order. The. inspector also attended one and a half sessions of the radiation control and safet.y lecture and found said lecture to be in accordance with the lecture schedule and lesson plan.
No items of noncompliance or deviations were identified.
13.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)
throughout the month..The inspector informed the licensee that while conducting a valve. lineup of the containment Hydrogen Dilution system Train No. 2, nine valves (26% of the total system) did not have ident-ification tags. The inspector also noticed-that valves CV-199 and l
SW-193 were not included in the lineup procedure. This item remains
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as an unresolved open item with inspector followup.
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