ML19317F189
| ML19317F189 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/15/1973 |
| From: | Peltier I US ATOMIC ENERGY COMMISSION (AEC) |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8001080903 | |
| Download: ML19317F189 (5) | |
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UNITED STATES ATOMIC ENERGY COMMISSION l 'l J
W ASHINGTON, D.C. 20545 l
NOV 151973 ir,,, e DOCKET NOS: 50-269 p.
i-APPLICANT:
DUKE POWER COMPANY FACILITY : OCONEE Unit 1 MEETING WITH DUKE AND B&W, NOVEMBER 1,1973, BETHESDA, MARYLAND, VIOLATION OF ROD WITHDRAWAL TECHNICAL SPECIFICATIONS LIMIT
Background:
Duke Power Company reported by letter an " abnormal On October 16, 1973, o::currence" involving the violation of a limiting condition for operation 1
specified in the Oconee Unit 1 Technical Specification 3.5.2, Contro _
e Rod Group and Power Distribution Limits.
Shortly af ter midnight on October 5,1973, rods were being inserted by the automatic control system and exceeded the insertion limits provided The operator reduced by Figure 3.5.2-1 of the Technical Specifications.
power from 95% to 89% in order to return the rods within limits within 15 minutes af ter discovery that the limit had been exceeded at 95% power.
The reactor was operated for about 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> at 89% power while boron was adjusted and the reactor was returned to 957. power.
Prior to the incident the plant had operated for 3 days at 73% power and was at equilibrium Zenon for that level. Shortly before the incident power was reduced to 62% to bring on an auxiliary pump and brought up to It is reasonable to assume that the 95% power in a little over an hour.
control system at the time the insertion limit was exceeded at 95%
power.was adjusting for the dif ference in Xenon equilibrium at 95% and At 89% power a boron correction of about 10 ppm van made 73% power.
to bring the rods within the correct range for returning to 95% power.
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. NOV 1 5 1973 Since the Technical Specifications which became effective for oconee Unit 1 ontNovember 6,1973, restrict the use of boron for transient Xenon adjusteent above 80% power and the Technical Specifications in effect on October 5,1973, did not.
The staff and the applicant agreed that a meeting to discuss this incident would be useful to test the nee Technical Specifications under similar circunstances. The primary concern is the adequacy of administrative controls to prevent exceeding the LOCA peaking factor limit.
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Summary Duke described the events leading up to, during and follcwing the incident and B&W made proposals for changing the current Technical Specifications to be more workable and effective under similar circumstances. As a consequence of the discussion the following agreements were reached:
1.
Duke committed to providing rod withdrawal (and insertion) limit alarms to be installed within about 2 months of completing the concept.
2.
Duke will revise the October 16, 1973, Abnormal Occurrence Report No. A0-269/73-5 " Control Rod Withdrawal Limits" to correct minor errors and add more detail essential to the incident understanding.
3.
Duke (and B&W) will provide the bases and final wording of the Technical Specifications changes being proposed for AEC review and approval in about 3 weeks.
The LPM does not feel that this matter has high urgency as a safety matter since the LOCA peaking factor limit appears to be adequately protected by the existing Technical Specifications. However, proposed changes to the Technical Specifications should be cleaned up prior to licensing y
Unit 3, at which time Technical Specifications will be issued applicable t
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ENCLOSURE 1 AGENDA FOR MEETING WITH DUKE POWER COMPANY
' Duke Power Company should discuss in detail the xenon transient
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which Oconee 1 was undergoing.
Duke Power Company should discuss in detail the actions taken to 2.
compensate for the Xenon transient.
Babcock & Wilcox and Duke Power Company should discuss the Technical 3.
Specifications 3.5.2 and 3.5.2.5-d.
Babcock & Wilcox and Duke Power Company should present their proposed modifications to the Technical Specifications for consideration by us.
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ENCLOSURE 2 MEETING ATTENDANCE LIST Atomic Energy Commission 1
A. Schwencer I
l D. Kirkpatrick, RO F. Jape, RO:II D. Pieno R. Satterfield l
M. Chatterton l
M. Dunnenfeld i
H. Riching I
I. Peltier Duke Power Company K. Canady T. Cotton P. Baxton R. Wilson G. Cage J. Hamston Babcock & Wilcox R. Steinke J. Harrison W. Brunson R. Straub 4
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s NOV 1 5 1373 to all three units. RO feels that the licensees corrective actions under the Technical Specifications effective at the tie of the incident were appropriate.
Enclosed are the meting agenda and list of attendees.
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I. A. Peltier, LPM PWR-4 DOL ~
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Enclosures:
1 1.
Meeting Agenda 2.
List of Attendees i
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