IR 05000266/1981017
| ML20032C358 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/27/1981 |
| From: | Guldemond W, Hague R, Konklin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20032C355 | List: |
| References | |
| 50-266-81-17, 50-301-81-19, IEB-80-11, IEC-81-07, IEC-81-7, NUDOCS 8111090711 | |
| Download: ML20032C358 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION-0/FICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-266/81-17; 50-301/81-19 Docket No. 50-266; 50-301 License No. DPR-24; DPR-27 Licensee:
. isconsin Electric Power Company W
231 West Michigan
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Milwaukee, WI 53203 Facility Name-Point Beach Nuclear Power Plant, UnitF 1S2 Inspection At:
Point 2aach Site, Two Rivers, WI
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Inspection Conducted: September 1-4, 8-11, 14-18, 21-25, 28-30, 1981
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Reactor Projects Section 2A
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Inspection Summary Inspection on September 1-4, 8-11, 14-18, 21-25, 28-30 1981 (Report No.
n 50-266/81-17; 50-301/81-19)
Areas Inspected: Routine resident inspection of Operational Safety Veri-fication, Monthly Maintenance Observation, Monthly Surveillance Observa-tion, Followup on Licensee Event Reports, IE Bulletin and Circular Followup, Review of Plant Observations, Foilowup or Items of Noncompliance, and Review
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of Periodic and Special Reports. The inspection involved a total of 126
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inspector-hours onsite by two NRC inspectors including 20 inspector-hours
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onsite during offshifts.
Results: Of eight areas inspected, no items of noncompliance were identified.
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I 8111090711 811027 DR ADOCK 05000266 PDR
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DETAILS 1.
Persons Contacted
- G. A. Reed, Manager, Nuclear Power Division J. J. Zach, Superintendent Technical Services T. J. Koehler, Operations Superintendent J. C. Reisenbuechler, I&C Engineer W. J. Herrman, Maintenance Superintendent R. S. Bredvad, Health Physicist
- R. E. Link, Assistant to the Manager
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- F. A. Zeman, Office Supervisor The inspectors also talked with and interviewed members of the Operations, Maintenance, Health Physics, and Instrument and Control Sections.
- Denotes personnel attending exit interviews.
2.
Operational Safety Verification The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the month of September 1981. The inspector verified the operability of selected emergency systems, reviewed tagout records and verified proper return to service of affected components. Tours of the aux-iliary building 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 maintenance.
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. During the month of September 1981, the inspector walked down the accessible portions of the emergency electrical, safety injection, containment spray, auxiliary feed, and fire protection systems to verify oper-ability. The inspector also witnessed portions of the radioactive
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waste system controls associated with radwaste shipments and barrel-
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ing.
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 were identified.
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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 follosing items were considered during this review:
the limit-ing condicions for operation were met while components or systems were renuved from service; approvals were obtained prior to initiat-ing the work; c tivities were accomplished using approved procedures and were inspected as applicable; functional testing and/or calibra-tions 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 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:
On September 2, 3, and 4, 1981, the inspector conducted spot checks of maintenance activities on the electric fire pump.
It was noted that there were no maintenance procedures or technical manuals at the job site, a bearing was not protected to preclude entry of foreign material, and open containers of solvent were left unattended.
During the week of September 14, 1981, the inspector monitored the annual maintenance on the 4D Diesel Generator.
It was noted that all lower inspection covers were removed and left off for an extended petiod. This condition can allow entry of foreign materials into the lubricating oil sump. Post-maintenance inspection prior to replacing the inspection covers is limited to the area above the oil sump level.
The inspector did not identify the observed conditions to be contrary to regulatory requirements; however, he expressed concern about the conditions increasing the possibility of entry of foreign materials into safety related equipment.
Licensee management acknowledged this concern and reaffirmed their position that post-maintenance cleanliness is established and con-trolled by the workers. The inspector will continue to follow this item.
Following completion of maintenance on the electric fire pump and the 4D diesel generator, the inspector verified that these systems had been teturned to service properly.
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4.
Monthly Surveillance Observation The inspector observed technical specifications required surveillance testing on the Unit 1 Reactor Protection System, Unit 2 Reactor Pro-tection System, and the 3D Diesel Generator and verified that testing was performed in accordance with adequate procedures, that test in-strumentation 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 personnel.
The inspector also witnessed portions of the following test activities:
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4D Diesel Generator Biweekly Testing 5.
Licensee Event Reports Followup The inspectors reviewed all outstanding licensee event reports and determined that none could be closed out during the inspection period.
6.
IE Bulletin Followup For the IE Bulletin listed below the inspector verified that the written response was within the time period stated in the bulletin, c
that the written response included the information required to be reported, that the written response included adequate corrective action commitments based on information presentation 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 written response was accurate, and that corrective action taken by the licensee was as described in the written response.
Review of licensee's evaluation and actions concerning IE Bulletin No. 80-11, Masonry Wall Design.
The July 17, 1981 letter, C. W. Fay to H. R. Denton states in response to action item 12 that the nuclear engineering section Safety Review Committee conducted an operability analysis of identified overstressed masonry walls and concluded that continued operation of the Point Beach Nuclear Plant pending repairs is justified.
The identified overstressed walls were tabulated in action item 17 of the July 17, 1981 letter. They were walls 111-1, 111-3N, 113, and 114 in the control room and wall 19 of the battery room, in meeting 81-02 of the NES Safety Review Committee held on July 15, 1981.
Continued operability for the control room walls was justified based on use of-alternate station shutdown capabilities and continued operability for
the battery room wall was based on a probabilistic study. All five of these walls were reinforced prior to August 28, 1981.
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IE Circular Followup For the IE Circular listed below, the inspector verified that the Circular was received by the licensee management, that a review for applicability was performed, and +. hat if the circular were applic-able to the facility, appropriate corrective actions were taken or were scheduled to be taken.
81-07 Control of Radioactively Contaminated Material 8.
Erview of Plant Operations On September 24, 1981, the inspector sat in on a safety review committee meeting. The inspector verified that provisions of technical specifications dealing with membership, review process, frequency, and qualifications were met. The inspector also veri-fied that decisions made were reflected in the meeting minutes and that corrective actions proposed were taken.
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Followup on Items of Noncompliance Licensee actions in response to the items of noncompliance documented in the inspection reports below were reviewed to ascertain that the actions were completed as committed and were in conformance with regulatory requirements.
Docket Number
Inspection Report
Remarks
Number
50-266
50-266/81-13
(Closed) Failure to
50-301
50-301/81-15
identify and secure
transient fire hazards
50-301
50-301/81-11
(Closed) Failure to
report reactor trip
on ENS 10.
Review of Periodic and Special Reports
The inspector reviewed the semiannual monitoring report for the ptiriod
from January I to June 30, 1981. This report was submitted in accor-
dance with Technical Specification 15.6.9.3.c.
No discrepancies were
noted.
11.
Exit Interview
The inspector met with licensee represer.tatives (denoted in Paragraph
1) throughout the month and at the conclusion of the inspection period
and summarized the scope and findings of the inspection activities.
The licensee acknowledged these findings.
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