IR 05000483/1986006

Insp Rept 50-483/86-06 on 860310-14.No Violations or Deviations Noted.Major Areas Inspected:Previous Insp Findings,Program Implementation for Tests & Experiments, Measuring & Test Equipment & Calibr

ML20138C637
Person / Time
Site:	Callaway
Issue date:	03/28/1986
From:	Choules N, Hawkins F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20138C619	List: IR 05000483/1986006 ML20138C617
References
50-483-86-06, 50-483-86-6, NUDOCS 8604020548
Download: ML20138C637 (6)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Report No. 50-483/86006(DRS)

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Docket No. 50-483' License No. NPF-25 Licensee: The Union Electric Company Post Office Box 149 St. Louis, MO 63166 Facility Name: Callaway, Unit 1 Inspection At: Callaway Site, Callaway County, M0 Inspection Conducted: March 10-14, 1986 Inspector:

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N. C. Choules 3/ 76 Date

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- Approved By: F. C. Hawkins 3/26/6(o

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Quality Assurance Programs Dafe Section Inspection Summary Inspection on March'10-14, 1986 (Report No. 50-483/86006(DRS))

Areas Inspected: Routine, announced inspection by one regional inspector of licensee actions on previous inspection findings, and program implementation for tests and experiments, measuring and test equipment, and calibratio Results: Of the eight findings reviewed, seven were closed. No new violations or deviations were identified.

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DETAILS 1. Persons Contacted Union Electric Company

• G. L. Randolph, Manager, Callaway Plant

• A. D. Neuhalfen, Manager, Quality Assurance (QA)

• J. D. Blosser, Assistant Manager, Operations and Maintenance

• W. R. Robinson, Superintendent, Instrument and Control (I&C)

• R. D. Affolter, Superintendent, Engineering

• G. H. Belchik, Assistant Superintendent, Maintenance

• J. C. Gearhart, Superintendent, QA Supervising Engineer

• T. P. Sharkey, Supervisor, Compliance

• L. H. Kanackel, QA Supervising Engineer

• B. K. Stanfield, QA Assistant Engineer F. W. Hartman, I&C Foremen W. A. Norton, QA Engineer USNRC

• B. H. Little, Senior Resident Inspector C. H. Brown, Resident Inspector Other personnel were contacted as a matter of routine during the inspectio * Denotes those attending the exit interview on March 14, 1986.

2. Licensee Action on Previous Inspection Findings (Closed) Open Item (483/84011-06): Individual training records for Nuclear Engineering personnel had not been established. The inspector verified by review of selected records that the licensee had established individual training records for Nuclear Engineering personne (Closed) Open Item (483/84011-08): Lack of independent verification of Instrument and Control (I&C) valve positions. The licensee had re-revised safety-related procedures to require independent verifica-tion of I&C valve positio In addition, the licensee was revising these procedures to provide for improved verification by requiring individual sign-offs for each step. Approximately 80% of the proce-dures had been re-revised and the licensee is continuing this proces The inspector has no further concerns in this are r

. (Closed) Open Item (483/84011-23): Content and use of the vendor

' history file was not controlled by a formal procedure. The licensee had prepared and approved Procedure QAP-G0-00700, " Quality Assurance Supplier Evaluation," which included requirements for the control of vendor history information, (Closed) Unresolved Item (483/84011-25): Lack of a trending program for corrective actions. The licensee's Quality Assurance Department had identified the lack of a trending program in Request for Corrective Action (RCA) No. P8403-177. The RCA had been close Procedures QAP-22-00225, "QA Trend Analysis Report" and QDP-22-04401,

" Incident Report / Licensee Event Report Trending Program," had been prepared and approved. The licensee is presently issuing IR/LER and QA Trend Analysis reports which showed the licensee had implemented the trending progra (Closed) Unresolved Item (483/84011-26): NRC evaluation of licensee corrective action related to the smoke in the control room event on December 30, 1983. The licensee's corrective actions for the smoke in control room event were reviewed by the Division of PWR Licensing-A, NR In a letter to the Director, Division of Reactor Safety, Region III, NRR reconnended that the licensee establish operating procedures to require operators to don protective gear when high. levels of Co or CO 2 are detected or under conditions involving nose, throat or eye irritation which interfere with the ability of the operators to perform safety functions. The inspector discussed this reconnendation with the licensee. The licensee issued a change to the Alarm Procedure, OTA-RL-RK063, for high Co or Co, in control room ventilation to instruct operators to don protective gear (SCA) when conditions involve nose, throat or eye irritation. Also, Procedure OT0-22-0001, " Control Room Inaccessi-bility," requires operators to consider using respiratory devices when smoke or toxic gas is in the control roo (0 pen) Open Item (483/85013-01): Three procedures concerning s planning guides, Q-lists, and SNUPPS computer program requirements were identified by the licensee as needing either preparation or revision. The licensee had issued Procedure WEP-22-00011 on February 28, 1986. Procedure QAP-22-01830 had been prepared and was in the review cycle. Originally, the licensee planned to revise Procedure QE-343, but is now going to write another procedure. This item will remain open pending issuance of QAP-22-01830 and the new procedur (Closed) Unresolved Item (483/85013-03): A computerized schedule of calibrations was needed. The inspector verified from review of calibration reports and computer listings' that the licensee had prepared and implemented a computerized scheduling of calibration The licensee had scheduled 95% of the calibrations and was working on scheduling the remaining 5%. The inspector has no further concerns regarding this ite ..

. (Closed) Open Item (483/85015-01): . Procedure for and full implementa-tion of the licensee's Nuclear Plant Reliability Data (NPRD) syste 'The licensee had issued Procedure PDP-22-0005, " Nuclear Plant Reli-ability Data System (NPRDS) Program." Licensee representatives indicated the NPDRS program was fully implemente ._

3. Tests and Experiments The inspector reviewed the implementation of the licensee's tests and experiments program to verify that it was being conducted in accordance with 10 CFR 50.59 and the licensee's procedur Documents Reviewed (1) Engineering Department Procedures, EDP-22-04010, "Special Test Procedures".

(2) .Three special test procedures and safety evaluation Results of Inspection The licensee had not performed any special tests and experiments, although they plan to perform several later during the current refueling outag The inspector reviewed three special test procedures which the licensee plans to perform during the current outage. The tests were reviewed for technical content and to determine if 10 CFR 50.59 safety evaluations were performed. No items of concern were identifie . Measuring and Test Equipment (M&TE)

The inspector reviewed the licensee's M&TE program to verify that the licensee had implemented a program to control safety-related equipment that is in conformance with regulatory requirements,~ industrial guides and standard Documents Reviewed (1) Administrative procedures for the control of M&T (2) Calibration records of selected M&T (3) Selected M&TE calibration procedure (4) Selected "Out of Tolerance" report (5) QA Audits of M&TE performed in 1985 and 1986.

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. Results of Inspection The inspector reviewed M&TE equipment and records in the instrument and control and the maintenance areas to verify that the instruments were calibrated at the specified frequency, calibration stickers were attached, instruments were properly stored, procedures had been prepared and used for the calibrations, standards used for calibration were traceable to the National. Bureau of Standards, and out of tolerance reports were being prepared when instruments were found out of calibratio The inspector's reviews of the records for the GAP-2115-IC Heise gauge showed that on October 10, 1985, the gauge was sent offsite to be repaired because it was defective. Procedure 10P-22-0006, "M&TE Out of Tolerance," requires a report to be generated if an instrument is suspected of being out of tolerance. It also requires a usage search be conducted, and any calibrations performed using the instrument be evaluated. No Out-of-Tolerance Report had been prepared for the Heise gauge. The licensee's reviews of the gauge's use, after the inspector identified the problem, showed the gauge had not been used to cali-brate any instruments since its last calibration on April 10, 198 The licensee also performed review of several calibration records and found no other cases where Out-0f-Tolerance Reports were not generated. The inspector's review of the licensee's Out-of-Calibra-tion Report log showed that reports are being prepared. It appears that this was an isolated event and the inspector has no further Concern The inspector reviewed four Out-of-Tolerance Reports for equipment suspected of being out of calibration. Usage reviews and evaluations were being conducted as require The inspector also verified that the licensee had conducted audits of the M&TE area. Audits had been conducted in 1985 and 1986. The audits were broad in scope and some deficiencies were identifie . Calibration The inspector reviewed the licensee's calibration program to verify that they had implemented a program to ensure that safety-related instrumenta-tion which is not specifically controlled by the Technical Specification is calibrated, Documents Reviewed (1) Selected calibration procedures (2) Selected instrument calibration records (3) QA audits of calibration performed in 1985 and 1986

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.. Results of Inspection The inspector selected instruments from the reactor systems which-

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were not specifically required to be calibrated by the Technical Specifications. The inspector verified by review of records and procedures, and from interviews that the instruments were calibrated at specified frequencies, and procedures have been prepared and used for the calibration Interviews and review of procedures' indexes indicated calibration procedures had been prepared for all safety-related instruments.not specifically covered by the Technical Specificatio . Exit Interview The inspector met with licensee representatives listed in Paragraph 1 on March 14, 1986, and summarized the purpose, scope, and findings of the inspection. The inspector discussed the likely informational content of the inspection report with regard to documents or processes reviewed by-the inspector during the inspection. The licensee did not  :

identify any such documents or processes as proprietar i

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