IR 05000302/1977015
| ML19319C923 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/23/1977 |
| From: | Dance H, Epps T, Hinckley D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19319C921 | List: |
| References | |
| 50-302-77-15, NUDOCS 8003040868 | |
| Download: ML19319C923 (3) | |
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UNITED STATES
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,o, NUCLEAR REGULATORY COMMISSION
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230 PEACHTREE STREET N.W.SUlTE 1217
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Report No.: 50-302/77-15
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Docket No.: 50-302, License No.: DPR-72
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Licensee: Florida Power Corporation 320134th Street, South P. O. Box 14042 St. Petersburg, Florida 33733 i
Facility Name:
Crystal River 3 j
Inspection at:
Crystal River, Florida Inspection conductsd: August 30-31, 1977
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Inspectors:
T. N. Epps D. G. Hinckley i
Accompanying Personnel: None i
Reviewed by:
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H.' C. Dance, Chief Date
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Reactor Projects Section No.1 Reactor Operations and Nuclear Support Branch Inspection Summaary
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Inspection on August 30-31, 1977 (Report No. 50-302/77-15)
Areas Inspected: Plant tour and LER followup. The inspection involved 18 inspector-hours on site by two inspectors.
Results: Of the two areas inspected, no items of noncompliance or deviations were found.
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RII Rpt. No. 50-302/77-15 I-l
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DETAILS I Prepared by:
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D.'G. Hinckley, Reaktor Inspector
' Date Reactor Projects Section No.1
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Reactor Operations and Nuclear Support Branch
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Dates of Inspection: August 30-31, 1977 b
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Reviewed by:
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H. C. Dance, Chief
'Date Reactor Projects Section No. 1 Reactor Operations and Nuclear
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Support Branch
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1.
Persons Contacted
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Florida Power Corporation (FPC)
I G. P. Beatty, Jr Nuclear Plant Mancger
- D W. Pedrick, IV, Compliance Engineer
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- J. Cooper, Compliance Auditor i
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Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items
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No new unresolved items,
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Exit Interview
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- A meeting was held by Messrs. T. N. Epps and D. G. Hinckley with Mr. D.
W.- Pedrick on August 31, 1977. The scope and results of the
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inspection were discussed. The licensee was also informed that Mr. T. N. Epps was no longer the NRC inspector for Crystal River 3 and that Mr. D. G. Hinckley would be the NRC inspector.until further
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notice.
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5.
Plant Tour
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A tour was made of t'he turbine" building and reactor control, room,.
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. Attention was given to plant cleanliness, annunciators, and control ~
l room operators,. The reactor was operating at'appror.imately 70
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percent power. No problems were identified.
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RII Rpt. No.
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6.
LER Followup The following is a list of LERs' reviewed during this inspection and the status of each:
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LERs 77-32 and 77-34 involves failure of a control rod to move and dropping of a control rod into the core. The corrective action taken by the licanee to preclude future occurrences of this ' type was to
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replace all control rod drive stators. The inspector verified that all stators have been replaced. These items are closed.
L'ERs 77-37, 77-56 and 77-92 invol'ed overspeed tripping of the v
Steam Driven Emergency Feed Pump (EFP-2). The licensee determined
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the trips to be caused by condensation buildup in the -steam inlet lines.- The corrective action taken by the licensee as described in
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-LER 77-92 was reviewed by the inspector. These items are closed.
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7.
Steam Driven Emergency Feed Pump Test
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The licensee performed a test of the emergency feed pump on
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August 15, 1977, to demonstrate the automatic start capability of the pump at the elevated steam pressure (1000-1050 psi) which would be present immediately following a turbine trip. The test was performed by procedure SP349(B), Emergency Feedwater System
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Operability Demonstration. The inspector reviewed the results of the test. No problems were identified.
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Decay Heat Pumps (DHP)
On December.21, 1976, the shaft failed on Decay Heat Pump DHP-3A.
As a result of the failure, the shafts were replaced on both pumps
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DHP-3A and DHP-3B. Babcock and Wilcox notified the licensee by
letter dated July 12, 1977, that these decay heat pumps are still l-susceptible to fatigue failure if the pumps are operated for l
extended times at the recirculation orifice flow. The operational I
limits for the new shafts has been established as 30 minutes continuously and 60 minutes total in any 12 month period.
The. licensee has committed to not operate at this m.inimum recircula-
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tion flow condition during normal operation and testing. The licensee's procedures reflect this commitment.
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