IR 05000321/1985022

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Insp Repts 50-321/85-22 & 50-366/85-22 on 850629-0726. Violations Noted:Refs Listed Improperly in safety-related Calibr Procedures & Valve Internal Parts Found Missing from Safety Sys Valve
ML20134H450
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 08/13/1985
From: Holmesray P, Nejfelt G, Panciera V
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20134H439 List:
References
50-321-85-22, 50-366-85-22, NUDOCS 8508280420
Download: ML20134H450 (6)


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NUCLEAR REGULATORY COMMISSION

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Report Nos.: 50-321/85-22 and 50-366/85-22 Licensee: Georgia Power Company P. O. Box 4545 Atlanta, GA 30302 Docket Nos.: 50-321 and 50-366 License Nos.:

DPR-57 and NPF-5 Facility Name: Hatch 1 and 2

~ Inspection Dates: June 29 - July 26, 1985 Inspection at Hatch site near Baxley, Georgia Inspectors:3[IMdI

C P. Holme's-Ray, Senio espntInspector Date Signed W/T AA 83/&r G. N eltges)g#ft Inpfector

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Approved by:

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V.' W. Pani:fera', Cliief, Project Section 2B Bate '5fgned Division of Reactor Projects SUMMARY Scope:

This inspection involved 179 inspector-hours on site in the areas of Technical Specification compliance, operator performance, overall plant operations, quality assurance practices, station and corporate management practices, corrective and preventive maintenance activities, site security procedures, radiation control activities, and surveillance activities.

Results:

Of the areas inspected, two violations were identified:

(References listed improperly in safety-related calibration procedures, Paragraph 10; and valve internal parts found missing from a safety system valve, Paragraph 9).

8508280420 850814 PDR ADOCK 05000321

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REPORT DETAILS 1.

Persons Contacted Licensee Employees

  • H. C. Nix, Site General Manager
  • T. Greene, Deputy Site General Manager
  • H. L. Sumner, Operations Manager
  • T. Seitz, Maintenance Manager C. T. Jones, Engineering Manager R. W. Zavadoski, Health Physics and Chemistry Manager
  • P. E. Fornel, Site QA Manager
  • S. B. Tipps, Superintendent of Regulatory Compliance Other licensee employees contacted included technicians, operators, mechanics, security force members and office personnel.
  • Attended exit interview 2.

Exit Interview The inspection scope and findings were summarized on July 26, 1985, with those persons indicated in paragraph 1 above.

During the reporting period frequent discussions were held with the General Manager and/or his assistants concerning inspection findings.

The licensee acknowledged the findings and took no exception.

The licensee did not identify as pro-prietary any of the material provided to or reviewed by the inspector during this inspection.

3.

Licensee Action on Previous Inspection Findings Not inspected.

4.

Unresolved Items Unresolved items were not identified during this inspection.

5.

Plant Tours (Units 1 and 2)

The inspectors conducted plant tours periodically during the inspection interval to verify that monitoring equipment was recording as required, equipment was properly tagged, operations personnel were aware of plant conditions, and plant housekeeping efforts were adequate.

The inspectors also determined that appropriate radiation controls were properly esta-blished, critical clean areas were being controlled in accordance with procedures,. excess equipment or material was stored properly and combustible ~

material and debris were disposed of expeditiously.

During tours the inspectors looked for the existence of unusual fluid leaks, piping vibra-tions, pipe hanger and seismic restraint settings, various valve and breaker

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positions, equipment danger and caution tags, component positions, adequacy of fire fighting equipment, and instrument calibration dates.

Some tours were conducted on backshifts and weekends.

The inspectors routinely conduct partial walkdowns of ECCS systems.

Valve and breaker / switch lineups and equipment conditions are randomly verified both locally and in the control room.

During the inspection period the inspectors conducted a complete walkdown in the accessible areas of the Unit 1 core spray (CS) system to verify that the lineups were in accordance with licensee requirements for operability and equipment material conditions were satisfactory.

On July 15, 1985, during the walkdown of the Unit 1, train "A", CS system, it was noted by the resident inspector that the southeast diagonal, lowest level (87'), was in a poor state of housekeeping.

This radiological area with surface contamination (which required a radiation work permit for entry) had equipment, paper, protective clothing, and used plastic left on the floor.

There was also about 1/8 to 1/2 - inches of water covering a portion of the floor and a floor drain.

The source of this water was not known.

A supervisor from health-physics was notified of this condition and he took action to get the area cleaned up.*

Within the areas inspected, no violations or deviations were identified.

6.

Plant Operations Review (Units 1 and 2)

The inspectors periodically during the inspection interval reviewed shift logs and operations records, including data sheets, instrument traces, and records of equipment malfunctions.

This review included control room logs and auxiliary logs, operating orders, standing orders, jumper logs and equipment tagout records.

The inspectors routinely observed operator alertness and demeanor during plant tours.

During normal events, operator performance and response actions were observed and evaluated.

The inspec-tors conducted random off-hours inspections during the reporting interval to assure that operations and security remained at acceptable levels.

Shift turnovers were observed to verify that they were conducted in accordance with approved licensee procedures.

Within the inspected. areas, no violations or deviations were identified.

7.

Technical Specification Compliance (Units 1 and 2)

During this reporting interval, the inspectors verified compliance with selected limiting conditions for operations (LCOs) and results of selected surveillance tests.

These verifications were accomplished by direct obser-vation of monitorir.g instrumentation, valve positions, switch positions, and review of completed logs and records.

The licensee's compliance with selected LC0 action statements were reviewed on selected occurrences as they happened.

Within the areas inspected, no violations or deviations were identifie,.

8.

Physical Protection (Units 1 and 2)

The inspectors verified by observation and interviews during the reporting interval that measures taken to assure the physical protection of the facility met current requirements.

Areas inspected included the organi-zation of the security force, the establishment and maintenance of gates, doors and isolation zones in the proper condition, that access control and badging was proper, and procedures were fcilowed.

Within the areas inspected, no violations or deviations were identified.

9.

Review of Nonroutine Events Reported by the Licensee The following Licensee Event Reports (LERs) were reviewed for potential generic impact, to detect trends, and to determine whether corrective actions appeared appropriate.

Events which were reported immediately were also reviewed as they occurred to determine that Technical Specifications were being met and that the public health and safety were of utmost consideration. The following LER was considered closed:

Unit 2:

85-10, Rev. 1*

  • In-depth review performed.

In 1984, as part of the Unit 2 outage, residual heat removal (RHR) system check valve 2E11-F050B and its bypass valve 2E11-F122B were removed from the system and the check valve replaced.

The bypass valve was welded in place on June 15, 1984, and the actuator was installed on June 26, 1984.

On July 6, 1984, the check valve was leak tested with the valve lineup signed off showing the bypass valve shut.

No leakage was observed. On April 10, 1985, the check valve failed local leak rate testing and the bypass valve was disassembled to aid in leak path determination.

At this time the internal parts were found to be missing.

There is no record of any maintenance having been performed since the 1984 outage.

The conclusion reached is that the valve internals were left out in 1984 and the leak test of the check valve was accomplished with the bypass valve gaged.

No record of a maintenance work order (MWO) to remove the operator and internals for the purpose of gaging the bypass valve for the leak test of the newly installed check valve were found.

This failure to return the RHR system to its design configuration after maintenance is a violation (366/85-22-01).

10. Procedure Review During the review of a safety-related calibration procedure (HNP-1-5261, Revision 16, Agastat Timing Relay Calibration) the Resident Inspector was unable to obtain the vendor technical manual from the site document cor. trol room using the information provided in the procedure.

The licensee was informed of this difficulty and eventually located the vendor technical manual in question in the document control room after a three hour search.

The particular problem in this instance was that a unique document control

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number was not generated when an additional binder was added to contain

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newer vendor technical manuals.

Based on the problem encountered locating vendor technical manuals, nine other safety-related calibration procedures were randomly selected.

Of these, four. vendor technical manuals had similar discrepancies, which were:

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Procedure Number Title Comment HNP-1-5251 General Electric Type-Section G of the procedure Self Synchronizing cited "S-19238" and procedure Manual / Automatic Transfer reference section cited Station

"S-19239, GEK 9690, Vol X, Part 4."

The correct document reference number is "S-192398, GEK 9690, Vol. X, Part 4A."

HNP-2-5251 (samear,above)

Section G of the procedure cited "SX-29461" incorrectly as the document reference number for the vendor technical manual.

HNP-2-5255'

General Electric 562 Section G of the procedure Limiter Calibration cited "S-30698, GEK 9690, Vol. X, Part 3, Signal Conditioners, Tab 5.

The correct document reference number is "S-19238, GEK 9690,

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Vol. X, Part 3, Signal i

Conditioners, Tab 5."

HNP-2-5273 Model 195-4 Mercoid Section H of the procedure Level Switch cited "SX-29451, GEK 45778, Vol. X, Part 3, Switches, Tab 7" and the procedure

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reference section cited

"Part 2" for this document reference number. The correct

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document reference number is

"S-30698, GEK 45778, Vol. X,

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Part 3, Switches, Tab 6."

Therefore, five of the ten vendor technical manuals cited in the safety-

. related calibration procedures sampled were incorrect.

However, this problem appeared to be strictly administrative, because the resident inspector observed that a calibration technician was able to readily locate

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.these technical vendor manuals based on his familiarity with the equipment, i

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except for the technical vendor manual cited in HNP-1-5261, which was discussed above.

The licensee had previously identified in an internal 0A audit letter dated February 19, 1981, that five out of ten calibration procedures had not included a required reference or had an improper reference listed. This QA item was closed out June 9, 1983, by the licensee.

Also, it was noted that the title of HNP-1-5273, Revision 6, "Model 1951-4EV Mercoid and SL400 Robertshaw Level Switch," was for the Model 1951-4EV Mercoid Level Switch and did not apply to the SL400 Robertshaw Level Switch.

This lack of administrative control of technical vendor manuals, which were used in safety-related calibration procedures, is a violation (50-321, 366/85-22-02).

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