IR 05000346/1982032
| ML20028C214 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/20/1982 |
| From: | Peebles T, Reyes L, Rogers W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20028C207 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.2.1, TASK-2.B.4, TASK-TM 50-346-82-32, NUDOCS 8301070209 | |
| Download: ML20028C214 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-346/82-32(DPRP)
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Docket No. 50-346 License No. NPF-3
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Licensee: Toledo Edison-Company Edison Plaza 300 Madison Avenue Toledo, Oli 43652 Facility Name: Davis-Besse Nuclear Power Station, Unit 1 Inspection At: Oak liarbor, OH Inspection Conducte :
ve ber 1-30, 1982 Inspectors:
.A Pee
/J J8 #3
. G. R ge
/4 48 FA Approved By:
A. Reyes, ef
/4 48
'rojects Se on 2B
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Inspection Summary Inspection on November 1-30, 1982 (Report No. 30-346/82-32(DPRP))_
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Areas Inspected: Routine safety inspection of Previous Inspection Findings; Operational Safety Verification; Monthly Maintenance Observation; Monthly Surveillance Observation; Plant Trips; IE Circular Follow-up; TMI Lessons Learned; and Independent Inspection. The inspection involved 216 inspector-hours onsite by two NRC inspectors including 60 inspector-hours onsite during off-shifts.
Results: Of the eight areas inspected, no items of noncompliance or deviations were identified.
8301070209 821222 PDR ADOCK 05000346 O
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DETAILS 1.
Persons Contacted
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Murray, Station Superintendent B. Beyer, Assistant Station Superintendent S. Quennoz, Assistant Station Superintendent P. Carr, Maintenance Engineer J. Werner, Instrument Engineer D. Miller, Operations Engineer W. O'Connor, Assistant Operations Engineer D. Briden, Chemist and Health Physicist J. Hickey, Training Manager L. Simon, Operations Supervisor C. Daft, Q.A. Director
- T.
Powers, Administrative Coordinator
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Faris, Administrative Coordinator The inspectors also interviewed other licensee employees, including members of the technical, operations, maintenance, I&C, training, health physics, and security staff.
- Denotes those attending the exit interview on November 30, 1982.
2.
Action on Previous Inspection Findings:
(Closed) Open Item (346/82-31-01): The licensee's analysis of fire doors 509 and 512 indicates that they do not have the proper certification and the doors have been declared inoperable. Adequate compensatory measures are in place and the licensee is pursuing re-certification or purchase of new doors. This item is considered closed.
3.
Operations Safety Verification The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the month of November. The inspector verified the operability of selected emergency systems, reviewed tagout records and verified proper return to service of affected components. Tours of auxiliary buildings and turbine buildings were conducted to observe plant equipment conditions, including potential fi re hazards, fluid leaks, and excessive vibrations and to verify that maintenance requests had been initiated for equipment in need of main-tenance. 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 observed plant housekeeping / cleanliness conditions and verified implementation of radiation protection controls. The inspector also witnessed portions of the radioactive waste system controls associated with radwaste shipments and barreling. A cask with dewatered Powdex resin was observed being loaded for shipment.
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During the month of November, the inspector walked down the accessible portions of the:
a.
Component Cooling Water System b.
Diesel Generators c.
Batteries and Switchgear d.
Containment Fan Coolers e.
Service Water System f.
Containment Valves 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 deviat4.ons were identified.
4.
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 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; ac-tivities 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 :: cords were maintained; activities were accomplished by qualified personnel; parts and materials used were properly certified; radiological controls were imple-mented; and fire 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:
Replacement of FP-8 (gate valve at discharge of electric fire pump).
FCR 81-103 (portion for adding power from F12C for addition of F12D).
Primary demineralizer filter valves.
NI-4 (Intermediate range neutron mcnitor).
Seismic hangers on component cooling water piping.
Pressurizer heater trouble shooting (BE605 open due to ground fault).
Following completion of maintenance on the electrical switchgear powering Service Water Train 2 and RPS Channel 4 trouble shooting, the inspector verified that these systems had been returned to service properly.
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The licensee's review of capped containment integrity valves has been completed with no discrepancies outstanding.
No items of noncompliance or deviations were identified.
5.
Monthly Surveillance Observation The inspector observed technical specifications required surveillance testing on the Diesel Generators and Service Water Pump and verified that testing was performed in accordance with adequate procedures, that test instrumentation was calibrated, that limiting conditions for operation were mot, 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 personnel.
The inspector also witnessed portions of the following test activities:
ST 5030.7 Containment Pressure Monthly Functional ST 5071.01 Auxiliary Feedwater Pump No. 2 Functional ST 3031.01 SFAS Monthly
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No items of noncompliance or deviations were identified.
6.
Plant Trips Following the plant trip on November 8, 1982, the inspector ascertained the status of the reactor and safety systems by observation of control room indicators and discussions 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 licensee.
All systems responded as expected, and the plant was returned to operation on November 9, 1982, following replacement of the moisture (
separator reheater Invel switch.
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_I_E 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 scheduled to be taken.
(Closed) IEC 81-13 Torque Switch Electric Bypass Circuit for Safeguard Service Valve Motors.
No items of noncompliance or deviations were identified.
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8.
Implementation of TMI Lessons Learned Item I.A.2.1 (Closed): Upgrade of Reactor Operator (RO) and Senior Reactor Operator (SRO) Training)
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i The inspector reviewed the revised administrative procedures for SR0 and
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R0 training and found good agreement between the criteria of NUREG-0737 i
and the licensee's program as delineated in administrative procedures.
The licensee requires three months of shift work for prospective SR0's
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and R0's.
The licensee's training program has been modified to include heat transfer, fluid flow and thermodynamics. The licensee requires mitigation of core damage training for all SRO's and RO's.
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licensee has increased the number and frequency of control manipulation to that required by Enclosure 4 of the March 28, 1980 Denton Letter.
The inspector verified that all SRO's and RO's had met the control
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manipulation criteria for 1980 and 1981. This item is considered closed.
i Item II.B.4. (0 pen): Training for Mitigating Core Damage The lhspector reviewed training certificates on mitigation of core j
damage given by Babcock and Wilcox and found that all STA's, SRO's and RO's had successfully completed the training.
It should be noted that NUREG-0737 states that "STA's and operating personnel from the plant manager through the operations chain to the licensed operators shall receive all the training indicated in Enclosure 3 to H.R. Denton's March 28, 1980 letter." The Station Manager has not attended the mitigation of core damage training. However, the licensee only I
committed in their correspondence to training STA's, SRO's and RO's and
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as such the licensee has met their commitment on Item II.B.4 as of
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November 30, 1982.
In a December 3, 1982, letter NRR requested the
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licensee to address the difference between NUREG-0737 and the licensee's
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commitment and to respond to NRC Region III for evaluation. This item will be reviewed further following completion of the Region III
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evaluation of the licensee's response.
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No items of noncompliance or deviations were identified.
9.
Independent Inspection Effort i.
I The inspectors routinely attended meetings with licensee management
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and various shift turnovers between shift supervisors and licensed /non-l licensed operators. These meetings and discussions provided a daily j
status of plant operating and testing activities as well as discussion of significant problems or incidents.
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An INPO evaluation team arrived on site November 29, 1982, for their annual audit.
The inspector inquired into the status of the incorporation of drawing change notices into the station drawings and was informed that the effort was to begin by December 15, 1982, and be complete within two months.
i The inspectors will follow this progress.
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10.
Exit Interview
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The inspector met with licensee representatives (denoted in Paragraph 1)
throughout the month and at the conclusion of the inspection on November 30
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and summarized the scope and findings of the inspection activities. The
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licensee acknowledged the findings.
Also, the inspectors acknowledge the licensee's action to permit the j
resident inspectors to. sign out keys. This allows expedited inspections
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and access to areas equivalent to that of Toledo Edison employees.
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