IR 05000369/1980023

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IE Insp Rept 50-369/80-23 on 800728-0801.No Noncompliance Noted.Major Areas Inspected:Preoperational Testing Observation & Review & Followup on Open Items
ML19338F759
Person / Time
Site: McGuire Duke Energy icon.png
Issue date: 09/11/1980
From: Graham M, Martin R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML19338F755 List:
References
50-369-80-23, NUDOCS 8010270186
Download: ML19338F759 (4)


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Report No. 50-369/80-23 Licensee: Duke Power Corporation 422 South Church Street Charlotte, NC 28242 Facility Name: McGuire Nuclear Station Docket No. 50-369 License No. CPPR-83 Inspection at McGuire Site near Charlotte, North Carolina Inspector: h(LW 0W

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D' ate / Signed Approved 'oy:

9 //[fo R. D.~' Martin, Section Chief, RONS Branch at( Signed SUMMARY Inspected on July 28 - August 1, 1980 Areas Inspected This routine, announced inspection involved 32 inspector-hours on site in the of preoperational testing observation and review and followup on open areas items.

Results Of the two areas inspected, no items of noncompliance or deviations were identi-fied.

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DETAILS

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1.

Persons Contacted Licensee Employees M. McIntosh, Plant Manager T. L. McConnel, Superintendent of Technical Services L. Weaver, Performance Engineer

  • M. E. Pacetti, Test Engineer
  • R. Wilkerson, Superintendent of Administrative Services
  • M. Sample, Projects and Licensing Services Engineer D. Lampke, Projects and Licensing Other licensee employees contacted included engineers.
  • Attended exit interview 2.

Exit Interview The inspection scope and findings were summarized on August 1, 1980 with those persons indicated in paragraph I above.

3.

Licensee Action on Previous Inspection Findings Unresolved Item (80-03-01). The inspector noted that work was completed on heat tracing of the recirculation and vent lines of the reactor water storage tank. This work was identified by the inspector as incomplete in inspection 80-03 despite a licensee commitment in response to IE Bulletin 79-24 to make this modification by January 1, 1980. This item remains unresolved pending inspector review of the licensee's system for tracking conuitments.

4.

Unresolved Items Unresolved items were not identified during this inspection.

5.

Followup on Open Item (78-05-01)

The inspector reviewed the licensee's control of jumpers and temporary modifications with respect to concerns discussed in inspection 80-03, and originally raised as an open item (78-05-01). The changes made to Station Directive 4.4.0 reflect those discussed in inspection 80-03.

Therefore, this item is closed.

6.

Hot Functional Testing The inspector witnessed portions of the hot functional testing under way and observed the licensee's evaluation and resolution of problems which arose during testing. Licensee activities observed are described below.

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a.

Reactor Building Hatch Inflatable Seals

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A vendor representativa was on site to discuss with the licensee a recent inflatable seal failure involving separation of the ply at a pressure less than design. The inspector discussed possible reporta-bility of the failure under Part 21 or 10 CFR 50.55e. The licensee's review for reportability will be inspected at a later date (Inspector Followup Item 80-23-01).

The vendor also pointed out to the licensee several problems in design and operation of the personnel hatch.

The inspector briefed the resident inspector on these matters for his continued monitoring.

b.

Boron Thermal Regeneration System (BTRS)

The inspector reviewed procedure TP/1/B/1200/09 Boron Thermal Regener-ation System and observed followup to problems in implementing the procedure. The inspector has no further questions in this area.

c.

Auxiliary Feedwater System The inspector reviewed portions of TP/1/A/1250/04 Auxiliary Feedwater System (CA) and observed the licensee's efforts to troubleshoot problems with the CA pump turbine. The turbine was not able to maintain design speed. When the inspector left the site, the governor valve was being replaced as it needed to be cleaned and rebuilt. The inspector briefed the resident inspector on the status of CA testing for his continued monitoring.

d.

Lower Containment Ventilation System (VL)

The inspector continued to monitor licensee followup to the discovered overheating of the pressurizer space.

This problem was discussed previously in Inspection Report 80-22. Licensee efforts fell into the following areas.

(1) Monitoring of steam generator spaces for similar problems.

At the time of the inspection, the licensee identified overheating problems in the steam generator spaces as well as the pressurizer.

Temporary thermocouples were installed in the areas, with licensee actions to be dependent on the readings.

(2) Evaluation of Heat Damage to Components During the inspection, the licensee was attempting to evaluate damage, if any, to, snubbers and electrical cable in the hottest area of the pressurizer space.

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(3) Identification of a Configuration to Meet Temperature Require-Bents

The purpose of the preoperational test was to identify a working configuration for the Lower Containment Ventilation System (VL).

At the time of the inspection, the licensee was collecting data at various flow configurations by altering both fan speed and damper positions.

In addition, efforts were under way to locate and insulate areas of inadequate or temporarily removed insulation.

(4)

Identification of Possible Design Modifications If the measures described in paragraph (3) did not provide adequate cooling with backup fans available, the licensee was considering possible design modifications to provide more flow to the pressur-izer space.

At the time of the inspection, installation of booster fans in the vent to the pressurizer space was being discussed.

The inspector briefed the incoming resident inspector on all licensee activities on the VL system for his continued monitoring through completion of the test.

e.

Steam Dump (SB) System On July 31 the licensee opened the MSIVs in preparation for functional testing of the steam dump valves, and experienced a drop in primary system temperature. The cause of the temperature drop was found to be steam leakage through the drain valves to the condenser. The total temperature loss was about 26'F over one and one half hours, slowly enough that there was no thermal shock to the vessel and components.

The steam leakage occurred because the locked shut drain valves were, in reality, partially open.

The control room indication of valve position showed closed.

Apparently the valve limit switches were incorrectly calibrated, or had been in some way altered since cali-bration.

The inspector expressed a concern that the limit switch calibration problem could extend to safety-related valves. The licensee acknowl-edged the inspector's remarks and indicated that calibration histories of the drain valves would be made available for further inspector review.

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