IR 05000255/1982012
| ML20053C379 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 05/19/1982 |
| From: | Boyd D, Jorgensen B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20053C378 | List: |
| References | |
| 50-255-82-12, NUDOCS 8206020029 | |
| Download: ML20053C379 (4) | |
Text
U.S. NUCLEAR REGULATORY COTIISSION
REGION III
Report No. 50-255/82-12(DPRP)
Docket No. 50-255 License No. DPR-20
Licensee: Consumers Power Company 212 West Michigan Avenue Jackson, MI 49201 Facility Name: Palisades Nuclear Generating Plant Inspection At: Palisades Site, Covert, MI Inspection Conducted: April 1-30 1982 a c (d, &
f - / 9 4 2-Inspector:
B. L. Jorgensen SC ugh
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Approved By:
D. C. Boyd, Chief 7 'l
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Reactor Project Section 1A
Inspection Sumwary
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Inspection during April 1-30, 1982 (Report No. 50-255/82-12(DPRP))
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Areas Inspected: Routine resident inspection program activities including actions during long-term shutdown; surveillance; maintenance; and overview of steam generator tube examination and leak repair. The inspection in-volved a total of 54 inspector-hours onsite by one NRC inspector including 16 inspector-hours onsite during off-shifts.
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Results: No items of noncompliance or deviations sere identified in any of the areas inspected.
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DETAILS 1.
Persons Contacted
- R. W. Montross, General Manager J. S. Rang, Operations / Maintenance-Superintendent H. J. Palmer, Technical Superintendent
- G.
H. R. Petitjean, Technical Engineer W. S. Skibitsky, Operations Superintendent B. L. Schater, Operations Supervisor R. P. Margol, Senior Engineer D. W. Langschwager, Shift Supervisor A. F. Brookhouse, Shift Supervisor S. Ghidotti, Shift Supervisor D. W. Kcupa, Shift Supervisor E. I. Thompson, Shift Supervisor S. F. Pierce, Radioactive Materials Control Supervisor
- D. G. Malone, QA Engineer
- Denotes those present at the Management Interview on May 4, 1982.
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A number of other members of the plant Operations / Maintenance, Technical
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or Chemistry / Health Physics staffs were also contacted briefly.
2.
General The plant remained in a cold shutdown condition throughout the month of April 1982, for identification and repair of steam generator tube leakage and associated tube surveillance and testing.
3.
Activities During Shutdown
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The inspector made frequent control room observations, reviewed applic-able logs and conducted discussions with control room operators.
The inspector verified operability of selected systems, reviewed tagout j
records, and verified proper return to service of affected components.
Additional tours and observations were made in the turbine building; auxiliary building; service water structure; and the emergency power
cnd control facilities.
The inspector verified implementation of radiation protection controls, station security plan, and housekeeping /
cleanliness controls; observed plant equipment conditions including potential hazards; and verified maintenance orders had been initiated for equipment requiring repair.
The inspector independently surveyed one radwaste truck awaiting shipment.
These observations and reviews were conducted to verify licensee compliance to Technical Specifications, 10 CFR, and controlling procedures.
No items of noncompliance or deviations were identified.
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l 4.
Maintenance
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The inspector observed / reviewed maintenance activities on the systems or components listed below to ascertain they were conducted in conformance to applicable requirements.
a.
Containment ventilation pipe segment replacement b.
Tank T-90 - replace leaky taps c.
Main steam spring can - remove pins and reset d.
"C" service water pump - shaft' overhaul The following were considered during the review:
approvals obtained prior to start of work; compliance to limiting conditions for opera-tion; use of approved procedures where applicable; use of qualified personnel; maintenance of required records; functional or calibration testing for return-to-service; and implementation of radiological or fire protection controls, as appropriate.
Following completion of maintenance on the containment ventilation and service water systems, the inspector verified the systems were returned to service properly.
No items of noncompliance or deviations were identified.
5.
Surveillance The inspector obsarved testing as listed below and verified: utilization
of adequate procedures; use of calibrated instrumentation; compliance to i
operability requirements; and independent review of test results, a.
Steam generator eddy current testing (see also Paragraph 6)
b.
Electrical verification testing for new NSSS sample panel i
I c.
Calibration test of containment hi-rad monitor
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d.
Calibration test of main steam hi-rad monitor No items of noncompliance ~ or deviations were identified.
6.
Steam Generator Tube Examination / Repair Two leaking tubes were identified in the hot leg of the "A" steam
generator.
Initial identification was by observation of secondary-to-
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primary leakage with a slightly elevated secondary pressure (about
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180 psi) and a drained primary side. Verification consisted of j
independent identification, using at least two different types of probe in each case, by eddy-current test (ECT).
In each case, through-wall indications were found associated with tube supports and previously i
identified small " dents." The inspector followed the inspection effort, l
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including observation of ECT work in progress. The licensee kept the NRC Office of Nuclear Reactor Regulation (RR) informed on progress, j
findings, and plans.
Following identification of the leaky tubes, the licensee performed sampling ECT program concurred in by NRR. Ultimately, over 600 tubes in the "A" steam generator hot leg and almost 300 tubes in the cold leg were tested. No further indications of similar tube problems were identified.
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One leaky weld was identified on a tube plug instc11ed in 1974. This plug was removed and replaced.
The two tubes found leaking were plugged.
The licensee surveyed both steam generators to verify proper records and maps of plugged tubes. The net result of reconciling discrepancies among various records and the "as-found" conditions was the gain of a dozen tubes in the "A" generator, which were deplugged when it was determined they had been plugged at one end only; and that no plugging
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was required.
In the "B" steam generator a parallel verification review resulted in the installation of two plugs.
On completion and verbal reporting of ECT program results, the licensee
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agreed to an NRR request that a more restrictive primary-to-secondary leakrate limit be implemented through the remainder of the current operating cycle. The licensee, with NRR concurrence, has implemented
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a plant " Standing Order" imposing a steady-state limit of 0.1 gpm and a transient limit of 0.6 gpm.
This " Order" was reviewed by the inspector and found to parallel the language of the Technical Specifications while imposing the agreed-upon restrictions.
The licensee's detailed re-evaluation of the data on which the plant i
shutdown was originally based; i.e., which had yielded a calculated 0.32 gpm leak; established the leak had reached only approximately 0.2 gpm.
Thus, the action level of the Tecnnical Specifications
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(0.3 gpm) had not been reached or exceeded at the time of plant shut-
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down. This difference in findings is apparently due to conservatisms in the original calculations, which the licensee may decide to
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eliminate from his procedures.
No items of noncompliance or deviations were identified.
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7.
Management Interview A management interview was conducted following completion of the inspection, on May 4, 1982. The scope and findings of the inspection, as documented in these Details, were discussed with the licensee representatives (see Paragraph 1).
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