IR 05000528/1983028

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IE Insp Rept 50-528/83-28 on 830627-0701.No Noncompliance Noted.Major Areas Inspected:Organization & Staffing,Facility Tour,Effluent Monitor calibr,NUREG-0737 Items II.F.1 & II.B.3 & Open Item Followup
ML20024F618
Person / Time
Site: Palo Verde 
Issue date: 07/20/1983
From: Book H, Sherman C, Wenslawski F
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20024F603 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.F.1, TASK-TM 50-528-83-28, NUDOCS 8309090525
Download: ML20024F618 (4)


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U.S. NUCLEAR REGULATORY COMMISSION

REGION V

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Report No. 50-528/83-28.

Docket No. 50-528 License No. CPPR-141 Licensee: Arizona Public Service Company P. O. Box 21666 Phoenix, Arizona 85036 Facility Name: Palo Verde Nuclear Generating Station - Unit 1 Inspection at:

Palo Verde Site - Wintersburg,' Arizona i

Inspection conducted: June 27 to July l, 1983

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Inspector:

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C. She an, Radisti n Speci ist-Dite Signed Approved by:

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A 7 e70 f3 F. A.' Wenslawski,. Chief.

D(te Signed

Reacto Radiat' n Protection Section 7 20

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Approved by:

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H. E. Book, Chief

'Date Si),ned

Radiological Safety Branch Summary:

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Inspection June 27 to' July 1, 1983 (Report No. 50-528/83-12)

Areas Inspected: Organization and staffing, facility tour, effluent monitor

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calibration, NUREG-0737 items II.F.1 and II.B.3 and followup on open items.

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l The inspection involved 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> onsite by one regionally based inspector.

Results:

In the areas inspected, no items of noncompliance or deviations

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were identified.

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8309090525 830721 PDR ADOCK 05000528

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DETAILS 1.

Persons' Contacted -APS

  • J. Bynum, Manager, Nuclear Operations
  • J. Allen, Technical Support Manager
  • L. Brown, Manager Radiation Protection and Chemistry
  • T. I Bloom, Licensing Engineer B. Cederquist, Chemistry Supervisor
  • W. Fernow, Administrative Support Manager G. Hampton, Radiation Protection Technician (RPT)

M. Lantz, Lead Radiation Physicist G. Perkins, Radiation Protection Supervisor

  • W. Rogers, Acting Radiation Protection Supervisor
  • C. Russo, Operations QA/QC Manager J. Schlag, Supervising Radiation Physicist - Unit 1
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Smith, Licensing Engineer Contractor - Personnel D. Gibson, Engineer, Nuclear Environmental Group, Bechtel E. Schultz, Startup Engineer, VOLT J. Sims, Lead Radiological Engineer, Combustion Engineering

  • Denotes those attending the exit interview on July 1, 1983.

?2.

Licensee Action on Previous Inspection Findings (Open) (83-12-12) Inspector request for vendor records of calibration of RMS system.

Inspector verified that some documents are now available for review at licensee document control center. Records for selected monitors will be reviewed.

(0 pen) (83-12-15) ~ Inspector. identified item concerning main steam monitor case. Discussion with licensee and vendor representative indicated that a viewing aperture is in fact present, however, it was not possible for the' licensee to remove the monitor case during the inspection visit. The inspector still desires to view this aperture and discuss the shielding analysis with appropriate personnel.

(0 pen) (83-12-17) Inspector requested information concerning installation of the plant vent was provided. This will be discussed with the responsible engineer during a subsequent inspection. Other areas identified have not been completed by the licensee.

The inspector was shown a letter dated June 16, 1983 from W. H. Wilson (Bechtel) to Van Brunt, Subject: Response to NRC Audit / Comment on Sampling Technique. This letter addressed in part some of the concerns identified in inspection report 50-528/83-12.

In particular, estimates of iodine plateout and correction factors were provided for six radiation monitors.

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The inspector was informed that this letter was in response to an NRC emergency planning preoperational inspection conducted in April 1983.

The inspector will review line loss and related factors for the normal range and post accident monitoring systems when all related evaluations

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are completed.

3.

Organization and Staffing The licensee has filled the position of Radiation Protection Supervisor.

The individual hired has 8 years experience at an operating power reactor including previous experience in an equivalent position. Additional training and experience include two years of University technical training, six years experience as an ELT in the U.S. Navy, and technician experience at a power reactor. This background meets the qualification requirements of FSAR section 13.1.3.1.

This individual appears to be qualified to act in place of the Radiation Protection and Chemistry Manager during temporary absences.

The inspector reviewed the organizational structure of the radiation protection (RP) department including plarned organizational changes, awaiting management approval, and the experience, qualifications and responsibilities of the Radiation Protection Support Group. Experience level of personnel in this group (1 supevisor, 3 engineers) was discussed with the supervisor. Each engineer is degreed and has some health physics experience. The supervisor has a master's degree in health physics. None of these personnel have previous experience at operating nuclear reactors. This group provides technical support for environmental surveillance, emergency planning and dosimetry.

In addition, support in the area of respiratory protection programs and dosimetry is provided by Combustion Engineering personnel.

The inspector discussed his concern with licensee management that this group, while having adequate technical experience and training, does not have operating reactor experience.

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No items of noncompliance or deviations were identified.

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Facility Tour A tour of the containment, auxiliary and radwaste buildings was conducted during the inspection. The inspection included verification of radiation monitor installation and review of the PASS installation progress.

No items of noncompliance or deviations were identified.

5.

-Radiation Monitoring System (RMS)'

FSAR Chaptcr 11.5, " Process and Effluent Radiological Monitoring and

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Sampling Systems", and FSAR Section 1.8, "Conformance to NRC Regulatory Guides", commits the licensee to Regulatory Guide 1.21,

" Measuring,... Radioactivity in... Effluents from... Nuclear Power Plants",

Chapter 11.5 further commits the licensee to sample isokinetically in

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accordance with ANSI Standard N13.1-1969, " Guide to Sampling Airborne Radioactive Materials...".

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The inspector discussed the preoperational test program for the RMS with members of the Radiation Protection staff in order to determine how the test program would address the above commitments. The inspector had also discussed the preoperational test program with I&C startup engineers, the AE and Radiation Protection Management in order to determine specific involvement of various' individuals. These discussions failed to identify individuals in the APS organization who were examining the RMS and the preoperational test program to insure that the various requirements would be met.

Discussion with RP staff indicate a desire for technical expertise in the RMS area to be within the RP staff.

Specifically, the inspector attempted to discuss with station (radiation protection) personnel how the licensee will verify or validate:

sampling effectiveness

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minimum detectable activity

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media collection efficiency

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vendor provided calibration factors

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isokinetic sampling

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and related items for the RMS process and effluent monitors.

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Discussions with RP staff indicated that these items were being considered by various individuals but no clear program, plans or procedures were identified to the inspector.

In addition, the Radiation Protection and Chemistry Manager has not delegated to professional personnel, the responsibility to track progress of RMS installation, preoperational testing and procedures to insure all commitments would be met.

The apparent lack of technical management of the RMS, the apparent lack of attention to radiological details of the test program and the absence of experienced professional support for RMS within the licensee organization were brought to the attention of the Technical Support Manager.

No items of noncompliance or deviations were identified.

6.

Post Accident Sampling System (PASS)

The inspector reviewed the progress of PASS installation. Major components have been received and are in the process of installation.

The inspector was advised of the formation of a CRACS/ PASS task force reporting to the Chemistry Manager. The task force consists of personnel from chemistry, radiation protection and operations engineering. The stated purpose of this group is to ensure satisfaction of all regulatory requirements for CRACS/ PASS and to ensure capability to sustain plant activities in these areas.

No items of noncompliance or deviations were identified.

7.

Exit Interview

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- The' scope and results of the inspection were discussed with the licensee representatives denoted in paragraph (1) on July 1,1983. The licensee was informed that no items of noncompliance or deviations were identified. The inspector's concerns as identified in paragraph 5 that responsibility for the radiation monitoring system within the APS/RP organization has not been clearly defined was discussed.

In addition, the experience level of the RP technical support group, identified in paragraph 3, was discussed'with licensee management. The inspector

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