ML20132B605
| ML20132B605 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/11/1985 |
| From: | Debs B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20132B546 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM 50-269-85-25, 50-270-85-25, 50-287-85-25, NUDOCS 8509260246 | |
| Download: ML20132B605 (3) | |
See also: IR 05000269/1985025
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION 18
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101 MARIETTA STREET, N.W.
ATLANTA, GEORGIA 30323
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Report Nos.: 50-269/85-25, 50-270/85-25, and 50-287/85-25
Licensee: Duke Power Conpany
422 South Church Street
Charlotte, NC 28242
Docket Nos.: 50-269, 50-270, and 50-287
License Nos.: DPR-38, DPR-47, and
Facility Name: Oconee 1, 2, and 3
Inspection Conducted: April 22 - 26 1985, and July 3, 1985
Inspector:
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B. T. Debs
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Date 5 gned
Approved By:
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B. T. Debs, Acting Section Chief
Date Signed
Operational Programs Section
Division of Reactor Safety
SUMMARY
This refers to an inspection conducted on April 22 - 26, 1985, and an Enforcement
Conference held in Atlanta, Georgia, with members of Duke Power staff on July 3,
1985, to discuss the operability status of Unit I containment atmosphere hydrogen
monitors as documented in Inspection Report 50-269/85-09, 50-270/85-09, and
50-287/85-09.
The Enforcement Conference provided NRC Region II staff with a
better understanding of the past operability status of the licensee's containment
atmosphere hydrogen monitors.
The Enforcement Conference also provided Duke
Power staff with a better understanding of. the regulatory requirements which
apply to these monitors.
8509260246 850919
ADOCK 05000269
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DETAILS
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1.
Attendance at.the Duke - NRC Enforcement Conference on July 3, 1985, at the
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NRC's Region II Office included:
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Duke Power Company
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H. B. Tucker, Vice President,' Nuclear Production
K. S. Canady, Manager, Nuclear Engineering
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M. Tuckman, Station Manager, Oconee
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N. Rutherford, System Engineer, Licensing
K. R. Caraway, Supervising Design Engineer
R. Bond, Compliance Engineer
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T. Glenn, I&E Support Engineer
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Nuclear Regulatory Commission
Dr. J. Nelson Grace, Regional Administrator
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Roger D. Walker, Director, Division of Reactor Projects (DRP)
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A. F. Gibson, Acting Director, Division of Reactor Safety (DRS)
G. R. Jenkins, Director, Enforcement and Investigation Coordination Staff
C. A. Julian, Acting Chief, Operational Branch, DRS
B. T. Debs, Acting Chief, Operational Programs Section, DRS
H. C. Dance, Chief, Reactor Projects Section 2A, DRP
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W. T. Orders, Senior Resident Inspector, McGuire
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L. P. Modenos, Enforcement Specialist
K. Sasser, Resident Inspector, Oconee
A. Bill Beach, IE, Enforcement
L. Trocine, Enforcement Specialist
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2.
Exit Interview
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The inspection scope and findings were summarized on July 3,1985, with
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those persons indicated in paragraph 1 above.
The licensee did not
identify as proprietary any of the material provided to or reviewed by the
NRC.
3.
Licensee Action on Previous Enforcement Matters
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URI 269, 270, 287/85-09-03, Unit 1 Reactor Building Hydrogen Monitoring
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SystemOperability,(Closed)
On July 3, 1985, an enforcement conference was held with respresenta-
tives of the Duke Power Company and the NRC in Atlanta, Georgia, to
discuss the aforementioned item.
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Duke Power Company representatives discussed Oconee's pre-TMI and
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post-TMI containment hydrogen monitoring capability.
They also
presented a historical description of Oconee's implementation of Item
II.F.1.6 of NUREG-0737 to provide continuous indications of hydrogen
concentration in containment.
Additionally, Duke Power Company
discussed their proposed technical specifications for the post-TMI
containment hydrogen monitors and their current method of detennining
system operability. The presentation also provided a history of Oconee
Unit 1 containment hydrogen monitor perfonnance and operability.
In conclusion, Duke Power Company acknowledged that for a period of
time in early 1985, both Trains A and B of Oconee's Unit I containment
hydrogen monitoring system were technically . inoperable due to failed
calibrations, but that the system was functionally operable since there
was hydrogen concentration indication although outside the existing
calibration acceptance criteria.
Duke Power Company maintained that
the significance of having technically inoperable hydrogen monitoring
during this time is mitigated since Oconee procedures suggest that
containment hydrogen recombiners be operating shortly after an accident
to preclude an explosive hydrogen atmosphere. Since Unit I containment
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hydrogen monitor trains A and B were technically inoperable from
March 6,1985, to March 26, 1985. This condition represents a violation
of 10 CFR 50.44(b) (269, 270, 287/85-25-01).
As a result of this event, the licensee recognized the need for more
definitive actions to assure operability of TMI related equipment which
are not currently covered by existing Technical Specifications.
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b.
URI 269, 270, 287/85-09-05, Reactor Building Spray Setpoint, (Closed).
At the conference described in the aforementioned item, it was
concluded that the less than or equal to 30 psig setpoint for reactor
building spray initiation as it appears in the licensee's Technical
Specifications is technically correct for loss of coolant accidents.
Licensee representatives stated that assumptions and values regarding
this setpoint which appear in the licensee's Final Safety Analysis
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Report would be changed to accurately support the technical specifica-
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tion value.
This item is therefore considered closed with no
violations or deviations noted.
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