ML19316A122
| ML19316A122 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/18/1977 |
| From: | Jape F, Robert Lewis, Rogers R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19316A105 | List: |
| References | |
| 50-269-77-26, 50-270-77-26, 50-287-77-26, NUDOCS 7911280650 | |
| Download: ML19316A122 (9) | |
See also: IR 05000269/1977026
Text
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NUCLEAR REGULATORY COMMISSION
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230 PEACHf F4EE STREET, N W SulTE 1217
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Report Nos.:
50-269/77-26, 50-270/77-26 and 50-287/77-26
Docket Nos.:
50-269, 50-270 and 50-287
License Nos.: DPR-38, DPR-47 and DPR-55
Licensee: Duke Power Company
P. O. Box 2178
422 South Church Street
Charlotte, North Carolina 28242
Facility Name:
Oconee 1, 2 and 3
Inspection at:
Oconee Nuclear Station
Inspection conducted: October 17-20, 1977
Inspectors:
F. Jape
R. Rogers
Accompanying Personnel:
None
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Reviewed by:
6.
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R. C. Lewis, Chief
Date
Reactor Projects Section No. 2
Reactor Operations and Nuclear Support Branch
I,nspection Summary
Inspection on October 17-20, 1977 (Report Nos. 50-269/77-26,
50-270/77-26 and 50-287/77-26)
Areas Inspected:
Routine, unannounced inspection to followup on previous
inspection findings and licensee event reports.
The inspection involved
52 inspector-hours by two NRC inspectors.
Results: Of the two areas inspected one item of noncompliance (infraction -
failure to adhere to procedures paragraph 6) was identified.
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RII Rpt. Nos. 50-269/77-26,
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50-270/77-26, and 50-287/77-26
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DETAILS I
Prepared by:
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F.
ape, Reactor Tr.'
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Date
Reactor Proje .. ection No. 2
Reactor Opetations and Nuclear
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Support Branch
Dates of Inspection:
October 17-20, 1977
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Reviewed by:
R. C. Lewis, Chief
Date
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Reactor Projects Section No. 2
Reactor Operations and Nuclear
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Support Branch
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1.
Persons Contacted
Duke Poser Co. (DPC)
J. E. Smith, Station ! mager
- J. N. Pope, Superintendent of Operations
O. S. Bradham, Superintendent of Maintenance
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- R. M. Koehler, Superintendent of Technical Services
J. T. Campbell, Operating Engineer, Unit 2
W. Matthews. Tech. Specialist
W. H. Knight, Assistant Shift Supervisor
W. W.
Smiah, Control Operator
E. A. Rapp, Control Operator
J. B. Price, Assistant Shift Supervisor
R. C. Adams, Instrument and Control Engineer
R. A. Knoerr, I&E Engineering Support
E. E. Hite, I6E Engineering Support
- R.
T. Bond, Technical Services Engineer
T. E. Cribbe, Assistant E..sincer Test
R. P. Todd, Assistant Engineer Test
J. Brackett, Senior QA Engineer
- D.
C. Dukes, Audit Supervisor, QA
- Denotes those present at the exit interview.
2.
Licensee Action on Previous Ins _pection Findings
a.
Noncompliance
IC_losed)
Noncompliance (269/77-6, 270/77-6, 287/77-6 Items A
> and B in Notice __of Violation)
Instrument callbration procedures having maximum tolerances
exceeded were not recorded on the maximum tolerance exceeded
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sheet and were not reported to the supervisor.
DPC's response,
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RII Rpt. Noa. 50-269/77 ~3
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50-270/77-26, and 50-2ai/77-26
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dated June 20, 1977, stated, in part, that the importance of
completing procedures and reporting inadequate data would be
re-emphasized to the appropriate personnel.
This action was
verified by review of an Intrastation Letter to all I5E engineers
and supervisors, dated June 9, 1977, and by discussions in
these procedures.
(Closed) Noncomp1_f ance _(269/7 7-E2]_0/7 7-7, 287/ 77-7, Item B
Failure to comply with posting requirements of 10 CFR 19.11.
Licensee's corrective action to prevent recurrence was verified.
A review of 10 CFR 19 was completed and the station directive
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covering bulletin boards was revised on July 15, 1977.
The
revision covers all posting requirements delineated in 10 CFR 19.11.
b.
Unresolved Item
(Closed)_ Unresolved Item _74-14/2, " Ventilation Control Between Auxiliary
and Turbine Buildings."
Actions taken to correct the problem were reviewed and were
found to effectively resolve the problem.
Actions completed
were sealing of cracks and joints in and around the common
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doors and walls including all cable chases, increasing capacity
of exhaust fans (Nos. 17 and 18) and improved periodic fan
maintenance.
The net effect of these actions has been to
effectively eliminate the negative pressure problem.
(Closed)
Unresolved Item 76-1/2, " Electrical Equipment Calibration."
This subject is related to enforcement item I.A.2 identified
in Report 269/76-6, 270/76-6 and 287/77-6 and will be resolved
in conjunction with followup of the items of noncompliance.
3.
Unresolved Items
Unresolved items are matters about which more information is required
in order to ascertain whether they are acceptable items, items of
noncompliance, or deviations. One unresolved item was identified
during the inspection which is discussed in Details II, paragraph 5.
4.
_Managemy t Exit Meeting
The inspectors met with R. M. Koehler, Acting Station Manager, on
October 20, 1977, to discuss the inspection findings.
Licensee
management acknowledged the inspection findings without significant
comment.
Licensee was notified on November 15, by phone, of the item
of noncompliance involving failure to follow procedures and resulting
in the loss of a 125 VDC battery required by TS 3.7.2(e).
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RII Rpt. Nos. 50-269/77-26,
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V.)
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5.
Followup _ on Inspector ident ified Problems
Follevup was conducted on the following items which were identified
by the inspector during a previous inspection.
a.
Surveillance Scheduling
During inspection 50-269/77-6, 50-270/77-6 and 50-287/77-6,
the inspector found that in some cases surveillances were
scheduled based on the date the preceeding surveillance was
completed; whereas, the data sheets were completed as much as
five months earlier.
The inspector stated that this method
could result in noncompliance with the Technical Specification
periodic testing requirements.
Followup on this item revealed
that all future surveillance schedules will be based on the
starting date rather than completion date.
This item is
closed.
b.
As Found Data on String Checks
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In inspection report 50-269/77-6, 50-270/77-6 and 50-287/77-6
a problem was discussed that involved the lack of as-found
data on periodic calibrations.
Followup revealed that as-found
data are now required to be recorded prior to c.:aking any
adjustments for the calibration.
This item is closed.
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c.
Calibration Procedure Details
In report 50-269/77-6, 50-270/77 6 and 50-287/77-6, the inspector
identified a situation where se.eral procedures had been
changed to type A procedures from type B (as defined in Administrative
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Policy Manual 4.2), but did not contain the detailed instructions
required for type A procedures.
The licensee has reviewed
this problem and revised the appropriate procedures to confor=
with the administrative instruction.
This item is closed.
d.
Licensee Internal Audits
During inspection 50-269/77-6, 50-270/77-6 and 50-287/77-6, a
review of licensee internal audits revealed that these audits
did not include a review of the technical adequacy of procedures
and their acceptance criteria.
Followup was completed by
reviewing recent licensee internal audits and comparing these
with those previously reviewed.
The recent audits were found
to contata details regarding technical adequacy and acceptance
criteria.
Thie item is closed.
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1]ousek_e_eping in _U_ nit _2 West Penetrat_ ion Room
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In inspection report 50-269/77-15, 50-270/77-15 and 50-287/77-
15, the inspector reported that the housekeeping in the Unit 2
West Penetration Room presented a personnel safety hazard in
that oil was present on the floor and miscellaneous debris
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were present.
A tour was conducted in this area and was found
to be clear of debris. Also, the oil had been cleaned from
the floor.
This item is closed.
6.
Review of Licensee Event Reports
The inspector performed an in-office review of the nonroutine event
reports listed below to verify that the report details met license
requirements, identified the cause of the event, described corrective
actions appropriate for the identified cause and adequately assessed
the event and any generic implications.
In addition, for those
reports marked with an asterick, the inspector examined selected
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operating and maintenance logs and records, and internal incident
investigation reports.
Selected personnel were interviewed to
verify that the report accurately reflected the circumstances of
the event, that the corrective action had been taken and/or responsibility
assigned to assure completion, and that the event was reviewed by
the licensee as stipulated in the technical specifications.
The
following event reports were reviewed:
- 269/77-15, BWST Level Channel Inoperable
- 269/77-17, Inadvertent Isolation of Emergency Power Source
269/77-18, Error in ECCS Analysis
- 269/77-19, IFDW-108 Discovered Inoperable
269/77-20, 125 VDC Battery Charger Failure
270/77-11, Primary to Atmosphere Leak From 2B SG
In event report 269/77-20, the licensee identified noncompliance
with TS 3.7.2(e).
The event resulted in loss of a 125 VDC battery
in excess of the time permitted by T.S. due to failure to follow
procedures.
The corrective actions presented in the licensee's
event report were verified by the inspector and no additional
response is requested.
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DETAILS II
Prepared by:
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R. F. Rogers, R .ctor Inspector
Date
Reactor Projects Section No. 2
Reactor Operations and Nuclear
Support Branch
Dates of Inspection:
October 17-20, 1977
Revieued by:
$ $=
//kg/]]
R. C. Lewis, Chief
Date
Reactor Projects Section No. 2
Reactor Operations and Nuclear
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Support Branch
1.
Individuals Contacted
Duke Power Company
J. E. Smith, Station Manager
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N. Pope, Superintendent of Operations
R. Koehler, Superintendent of Technical Services
R. Bond, Technical Services Engineer
R. Knoerr, Assistant Engineer
R. Adams, Maintenance Engineer (I6E)
H. Lowery, Operating Engineer
W Campbell, Reactor Engineer
2.
Licensee _ Action on Previous Inspection Findings
a.
Noncomfliance
(Closed) Noncompliance (77-4):
Failure to complete reactor
operator performance evaluations.
The inspector found that
performance evaluations were now being documented and reviewed
as required and discussed in the licensee response dated
June 20, 1977.
(Closed) Noncompliance (77-7):
Failure to follow plant
procedures in allowing contaminated steam generator we er to
drain to the hotwell.
The inspector found that the procedural
revisions discussed in the licensee response dated July 13,
1977, had been implemented and provide needed additional
administrative controls.
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b.
Deviation
(Closed)
Deviation (77-6):
Ilydrogen gas analyzer calibration
tolerance exceeded FSAR commitment.
The inspector found that
the gas analyzer calibration procedure, IP/0/A/210/4, had been
revised to reflect the FSAR commitment tolerance as described
in the IIcensee's response dated June 28, 1977.
c.
Unr_e_ solved Items
(Closed)
(76-7/4):
Lack of a written description of duties
and responsibilities of utility operators.
The inspector
reviewed a position guide which described the function, qualifications,
duties, responsibilities, and organizational relationships of
the utility operator which became effective August 1, 1977.
This item is considered resolved.
(C.c'ed)
(77-1/1):
Lack of a minimum value limit on moderator
te.perature coefficient (MTC) in test procedures conducted
su'asequent to refueling.
Thg inspector noted that the minimum
1) nit in the FSAR is 3.0x10
dk/F based on a steam line
break accident. The licensee agreed to add this limit to
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TT1 1/A/811/02, " Power Escalation Test," currently being
conducted on Unit 1 and to add the limit to all subsequent
test procedures (individually approved for each re-load).
This item is considered resolved.
(Closed) (77-6/I-1):
Adequacy of surveillance requirements
for status indicators.
The inspector reviewed audit results,
interviewed licensee representatives, and conducted a tour of
the plant to ascertain that progress had been made in th;
identification and correction of failed status indicator
lights.
Based upon the licensce's increased emphasis upon
improving in this area as a continuing concern, this item is
considered resolved.
3.
Unresolved Items
Unresolved items are matters about which more information is required
in order to ascertain whether they are acceptable items, items of
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noncompliance, or deviations.
One unresolved item disclosed during
the inspection is discussed in Paragraph 5 of this report.
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4.
Exit Inte_rview
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A discussion of the exit interview held on October 20, 1977, is
contained in Details I of this report.
5.
Open Item Followpp - Reportable Occurrence - 287/76-15 Power
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Range Adjustments
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This item cpncerning the setting of power range excore nuclear
instrumentation 9% of full power lower than actual reactor power
due to erroneous data input to the computer is elevated to an
unresolved status.
The licensee stated that no controls had yet
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been implemented to preclude recurrence.
It was also noted that
licensee procedures do not require verification of the computer
calculated heat balance or to re-calculate values prior to adjustment
when the correction is large.
This item is designated as unresolved
item 77-26/II-1.
6.
Open Item Followup - Reportable Occurrence - 287/76-12 Motor
Control Center Bus Change
This item involved completion of a station medification, NSM-650,
" Reactor Building Cooling Unit Motor Control Center," which reroutes
bus connections from Motor Control Centers XS1 and SX2 to Load
Centers X8 and X9.
The modification has been completed on Units 1
and 2.
Unit 3 will be completed by approximately January 1, 1978.
This item remains open.
7.
Open Item Followup - Steam Cenerator Tube Leaks
The s,ecific cause of the tube failures experienced has not yet
been determined and is under active investigation by DPC, B&k', and
NRR.
Regional inspectcrs will evaluate the licensee's progress
towards a solution on a continuing basis.
Since this matter is
presently under the cognizance of NRR, it will be administrative 1y
closed.
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Follogup_of Licensee Event Reports __(LERsl
Events selected were evaluated to assure that the event occurred as
described, licensee stated corrective actions were completed, the
event was reviewed and evaluated as required, and generic implications
were assessed.
The inspector conducted onsits followup review of
the following reportable occurrences at the station:
Oconee_ _1
R0-269/77-21, Dated July 13, 1977
R0-269/77-22, Dated July 21, 1977
R0-269/77-23, Dated August 5, 1977
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Implementation of the licensee's corrective action for
reports R0-269/77-22 and 23 will be reviewed on a
subsequent inspection.
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