IR 05000266/1980002
| ML19309D731 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/04/1980 |
| From: | Hague R, James Smith, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19309D730 | List: |
| References | |
| 50-266-80-02, 50-266-80-2, 50-301-80-01, 50-301-80-1, NUDOCS 8004110245 | |
| Download: ML19309D731 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-266/80-02: 50-301/80-01 Docket No. 50-266; 50-301 License No. DPR-24; DPR-27 Licensee: Wisconsin Electric Power Company 231 West Michigan Milwaukee, WI 53203 Facility Name:
Point Beach Nuclear Power Plant, Units 1 and 2 Inspection At:
Point Beach Site, Two Creeks, WI
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Inspection Conducted: January 22 through 24, 1980 p. EN Inspectors: J
. Smilh 3 - 4 - F4'
3 - T b'O na Approved By:
R. F. Warnick, Chief 3-4f-86 Reactor Projects Section 2 Inspection Summary Inspection on January 22, through 24, 1980 (Report No. 50-266/80-02, 50-301/80-01)
Areas Inspected: Routine unannounced inspection January 22 through 24, 1980 to review plant operations, organization and administration, quality assurance, review and audits, and records. The inspection in-volved 48 inspector-hours by two NRC inspectors.
Results:
Of the five areas inspected no items of noncompliance were identified.
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DETAILS 1.
Persons Contacted
- G. A. Reed, Manager, Nuclear Power Division
- J. Greenwood, Assistant to the Manager F. T. Rhodes, Operations Superintendent
- F. Zeman, Office Supervisor The inspectors also talked with and interviewed members of the reactor engineering and technical sections.
- Denotes those present at exit interview.
2.
Plant Operations a.
Plant Tour (1) The inspectors performed a plant tour. The housekeeping was good.
(2) Selected valve positions were verified in the auxiliary feedwater systems, safety injection systems, and residual heat removal systems for proper alignment. No discrepanc-ies were noted.
b.
Manager's Supervisory Staff Meeting Minutes The subject minutes for meetings 79-52 through 79-55 were reviewed. One item of concern was identified. This is an open item pending resolution by the licensee.
i The licensee is continuing investigation of potential sources of Tritiated water which is somehow getting into the ground water at the site. During a recent test to determine the integrity of the spent fuel pit liner the leakage collection system (leakchase channels) was filled with demineralized water.
It was planned then to add fluorescent dye to the water which would have provided indication on the spent fuel pool side of in-leakage of the dyed water. The test had to be terminated when water started flowing from cracks in the fuel transfer tube concrete structure in the facade of both Units 1 and 2, and from cracks in the spent fuel pit wall above the drumming station area. The outside temperature was below freezing so the leakage in the facade would have frozen since the facade is unheated. An isotopic analysis was performed on a sample of the leakage in the Unit 1 facade. The tritium concentration-2-
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~4 was 10 uci/cc. Another analysis was performed on the backflow
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out of thg canal leakoff valve. The tritium concentration was 1.8 X 10 uCi/cc. Concentrations of tritium found in samples from other areas in the past are listed below for comparison.
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Spent fuel pit activiyty:
10 uci/cc
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-2 South SFP leakoff:
10 uCi/cc-4 Heater Drain tank pump casings:
10 u i cc-5 Ground Water:
10 uCi/cc To date, the licensee has not formalized a plan for identifying and isolating the potential sources of tritiated water. Plan-ning and evaluation of potential options is underway.
3.
Organization and Administration The inspector reviewed the licensee's organization and qualifications of employees and determined the following:
a.
The licensee's onsite organization structure is as described in the Technical Specifications.
b.
Key management personnel of the facility meet the requirements of ANSI 18.1.
c.
Authorities and responsibilities of licensee personnel are as delineated in the Technical Specifications and as delineated in Administrative Control Procedures PBNP 3.1 through 3.12.
d.
The minimum shift crew composition is in accordance with the Technical Specifications.
e.
The makeup of the Offsite Review Committee and the Onsite Review Committee (manager's supervisory staff) are as required by the Technical Specifications.
f.
Changes in organization structure have been reported to the NRC as required by the Technical Specifications.
No items of noncompliance or deviations were identified.
4.
Review and Audits a.
Review of the minutes of the licensee's Onsite (manager's supervisory staff) and Offsite Review Committees for the past year verified that both committees are meeting the licensee's Technical Specifications requirements as follows:
(1) Meeting frequency for Onsite and Offsite Review Committee.
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(2) Meeting memberships and quorum requirements.
(3) Technical Specifications changes are reviewed as required.
(4) Reportable occurrences are reviewed as required.
(5) Violations of facility Technical Specifications are reviewed.
(6) Plant operations are reviewed for industrial and nuclear safety hazards by manager's staf f.
b.
The inspector reviewed the audits conducted by the Offsite Review Committee, the corporate Quality Assurance group, and the plant Quality Assurance Coordinator, and determined that audits are being conducted as required by the Technical Spec-ifications and the licensee's administrative instructions.
No items of noncompliance or deviations were identified.
5.
Records i
The inspector reviewed the licensee's program of control, storage, and retrieval of recordt to determine if the requirements of Techn-ical Specification 15.6.10, ANSI N 45.2.9-1974, and the licensee's administrative procedure PBNP 3.26 are being complied with.
a.
Records of the A-01 fuel assembly history.
b.
Records of CVCS system modifications for the life of the plant.
Plant radiation and contamination survey records for the period c.
February through June, 1970.
d.
Environmental survey records prior to plant startup November 2, 1967 through October 22, 1970.
Exposure records and termination reports of employees and e.
contractors for the year 1970.
f.
Waste disposal and dilution records for the year 1975.
g.
Inservice inspection records of first Unit I refueling October through December 1972 and first Unit 2 refueling November, 1974.
No items of noncompliance or deviations were identified.
6.
Quality Assurance Program The licensee's approved QA Program is Appendix H to the FSAR.
The inspector reviewed selected changes to the licensee QA imple-menting procedures which are contained in the QA Manual Volume 1, Administrative Control Policies and Procedure Manual. Most of the-4-
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changes are minor and are within the scope of Appendix H.
Proce-
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dures have been revised or new procedures prepared which implement the changes to Appendix H.
No items of noncompliance or deviations were identified.
7.
Exit Interview The inspectors met with the licensee's representatives (denoted in Paragraph 1) at the conclusion of the inspection on January 24, 1980. The inspectors summarized the scope and findings of the in-spection.
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