ML19312E813
| ML19312E813 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 04/30/1980 |
| From: | Donat T, Graham M, Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19312E810 | List: |
| References | |
| 50-369-80-03, 50-369-80-3, NUDOCS 8006090565 | |
| Download: ML19312E813 (6) | |
See also: IR 05000369/1980003
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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101 MARIETTA ST., N.W., SUITE 3100
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ATLANTA, GEORGIA 303o3
Report No. 50-369/80-03
Licensee: Duke Power Company
422 South Church Street- -
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Charlotte, NC 2B242
Facility: McGuire Nuclear Station
Docket No. 50-369
License No. CPPR-83
Inspection at McGuire Nuclear Station, near . Charlotte, NC
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Inspectors:
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. Donat
Date Signed
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H. J. Sta}im /
Date Signed
Accompanied by:
D. P. Falconer (March 31, 1980 to April 4, 1980)
Approved by:M.
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R . 1) . Martin / Section Chief, RONS Branch
Dfte Signed
SUMMARY
Inspection on March 27-29 and March 31 - April 4, 1960
Areas Inspected
This routine, unannounced inspection involved 101 inspector hours on site in the
areas of preoperational test witnessing, review of licensee response to bulletins
and circu'ars, and followup on open items from previous reports.
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Results
Of the three areas inspected, no items of noncompliance o'r deviations were
identified,
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DETAILS
1.
Persons Contacted
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Licensee Employees
- M. D. McIntosh, Plant Manager
- T. L. McConnel, Superintendent of Technical Services
- D. J. Rains, Superintendent of Maintenance
- L. Weaver, Performance Engineer
- M. E. Pacetti, Test Engineer
D. Marquis, Associate Test Engineer
J. Lukowski, Assistant Test Engineer
- L. C. Van Vynckt, Staff Engineer, Operations
- N. McCraw, Assistant Engineer, Operations
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- M. Sample, Projects and Licensing Services Engineer
E. Estep, Projects and Licensing
- D. B. Lampke, Projects and Licensing
- T. H. Heluaan, Steam Licensing
G. A. Copp, Associate Engineer Corporate Licensing Staff
Other licensee employees contacted included members of the operations,
technical services and office staffs.
- Attended exit interview
2.
Exit Interview
The inspection scope and findings were summarized on April 4,1980 with
those persons indicated in paragraph 1 above. The inspector discussed the
areas inspected and confirmed the licensee's commitments to action in these
The inspector also responded to several questions regarding the
areas.
logistics of the NRC resident inspectors' relocation to the McGuire site.
3.
Licensee Action on Previous Inspection Findings
Not inspected.
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4.
Unresolved Items
Unresolved items are matters about which more information is required to
determine whether they are acceptable or may involve noncompliance or
deviations. A new unresolved item identified during this inspection is
discussed in paragraph 5.a.
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5.
Review of Licensee Responses to Bulletins and Circulars
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In the response to IE Bulletin 79-24 on possible freezing of outdoor
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lines, the licensee committed to add heat tracing to the recirculation
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and vent lines of the refueling water storage tank by January 1, 1980.
This work was not performed, and the licensee failed to notify the NRC
of any change in his intentions. The inspector's major concern was
not with the licensee's failing to met his commitment, but with the
failure of the licensee's tracking system to adequately identify the
commitment and its required completion date.
This item (80-03-01) has been left unresolved pending further review
by the inspector of the licensee's procedures and practices for handling
of commitments to the NRC for possible items of noncompliance.
b.
IE Bulletin 79-28 addresses substandard gaskets on NAMCO Model EA180
limit switches which fail with exposure to elevated temperatures.
In
his response to the bulletin, the licensee committed to change all
affected gaskets prior to fuel loading.
The inspector was informed
that responsibility for replacing the gaskets had been assigned to the
construction group, and that a nonconforming i;em report for the work
was outstanding. Completion of the work will be verified in a future
inspection (0 pen Item 80-03-02).
IE Circular 79-04 describes loose locking nuts on limitorque valve
c.
operators.
In has response to this Circular, the licensee informed
the Commission that 40% of the limitorque valve operators in Unit 2
had been found defective and replaced. The licensee committed in his
response to inspecting and replacing as necessary defective limitorque
valve operators found in Unit 1.
The inspector was informed that this
work was being performed the week of the inspection.
Inspector followup
of the completed work is an open item (80-03-03).
d.
IE Circular 79-22 addresses porsible Power Operated Relief Valve
(PORV) inadequate closure times if the valves have not been exercised
for an extended period. Tne inspector was informed of the licensee's
intent to exercise and time the PORV's quarterly, and to achieve this
by adding the PORV's to the list of valves for PT/1/A/4151/02. This
is the periodic test procedure which quarterly checks the isolation
valves of the Pressurizer Relief Tank vent lines and nitrogen lines.
Incorporation of PORV testing into PT/1/A/4151/02 prior to issuance of
a license is an open item to be followed up at a later inspection
(80-03-04),
IECircular79-19describesalooselockingdeviceonimpellersof
e.
Ingersol-Rand pumps. The licensee indicated that the locking nuts of
his Residual Heat Removal and Containment Spray Pump had been torqued
to 250 pounds rather than 215 pounds as previously required by procedure
to deal with this problem. The licensee also stated that consideration
would be given at a later time to purchase of a diffe' rent locking
device should operational experience show the increased torque to
be an inadequate fix. After discussion with the inspector, the
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licensee revised the maintenance procedure for these pumps,
MP/0/A/7150/11, to require retorquing the locking nut to 250 pounds
after pump maintenance.
6.
Observation of ESF Testing
Inspectors were present to witness performance of portions of the last
three sections of the Engineered .;afeguards Features functional test
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TP/1/A/1300/03A. These sectiac included simultaneous actuation of both
trains of safety injection, actuation of safety injection immediately after
loss of off-site power, and station blackout after a twenty-four hour
diesel run.
The inspectors have no questions or comments on the manner in which the
test procedure was implemented or on the test controls. The resolution of
several of the technical problems which arose during testing will, however,
be followed up in subsequent inspections.
Operation of the diesel generator under test conditions identified
a.
several inadequacies in the logic of the load sequencer and the diesel
generator start circuit, and in the voltage regulator. The inspector
expressed his intent to review the resultant circuitry changes at a
later date, including the licensee's consideration of these items for
50.55e reportability (0 pen Item 80-03-05).
b.
Relay chatter in the test defeat circuit of the iiesel generator load
sequencer led to failure of a relay, preventing ilosure of diesel
generator IA output breaker onto its bus. The Cutler Hammer 3 amp
relay failed open during rapid cycling when the small springs in the
top deck unit (B26-MF) bound up away from the contacts rather than
holding them closed. The circuitry changes necessary to prevent the
relay chatter problem are among those noted for follow up in 6.a.
In
addition, the inspector intends to review the licensee's consideration
of this component failbre as a generic problem for possible Part 21
reporting (Open Item 80-03-06).
In his investigation of failure of the diesel generator to restart
c.
immediately after being tripped while off-site power remained unavail-
able, the licensee found a mechanical interlock preventing restart
until diesel speed had coasted down below 50% of nominal. At the time
of the exit interview, the inspector had left an item open for licensee
and NRC review of the requirements of the Technical Specifications for
diesel generator surveillance.
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Subsequently, in a phone conversation with the inspector, the licensee
indicated that the diesel manufacturer had agreed to permit overriditg
of the mechanical interlock. Therefore, this open item is now closed.
The circuitry changes necessary to defeat the interlock-are among
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those noteJ for followup in 6.a.
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d.
Observation of the performance of the ESF functional test led to the
opening of two additional items.
(1) The inspector noted that FSAR Table 8.3.1 does not reflect current
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diesel generator load sequencing. The Nuclear Spray Pumps are
shown to actuate with Group 4 at all times, rather than Group 4
or Group 7, depending upon containment pressure. The licensee
has indicated that the FSAR will be updated prior to licensing,
with Table 8.3.1 to be included in that update (open Item 80-03-07).
(2) It was observed that containment isolation valves IRV-33B, -77B,
-80B, and -108B reopened immediately after the " Safety Injection
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Reset" was actuated. In accordance with the requirements of IEB 80-06, a)1 equipment actuated by a Safety Injection signal should
remain in its S. I. position / condition upon receipt of a " Safety
Injection Reset" signal until individually repositioned at the
control board. Subsequent discussions with the licensee identified
DCAO MC-1-346 which modifies the valve circuitry in the BB, KC,
NF, RF, RN, RV, and VQ systems to require a separate main control
board action in addition to the " Safety Injection Reset" to cause
valve repositioning. However, this DCA has not been completed
and does not modify the MSIV's or the CF isolation valves. The
need to modify the circuity of all of the S.I. affected equipment
and
its
subsequent retesting will be followed up in a future
inspection (0 pen Item 80-03-08).
7.
Followup on Open Item (78-05-01)
The inspector reviewed the licensee's control of jumpers and temporary
modifications with respect to concerns raised in a previous inspection
(0 pen Item 78-05-01):
tracking of short term temporary modifications, and
testing of modified equipment before return to normal operation.
In reviewing Station Directive 4.4.0 (Rev. 8) Temporary Modifications, the
inspector found that only a temporary modification or jumper remaining in
place for more than one shift is tracked by the temporary modifications
log. Short-tern jumpers are procedurally required by the Maintenance
Manual to be recorded at placement and removal on the work request.
How-
ever, no documentation of the work request itself, or description of the
scope of the work to be performed, is required to be retained for operator
reference.
The inspector expressed concern that after a work request is reviewed and
approved for action, total reliance is placed on the memory,of the approving
operator that a particular system or component has the potential of behaving
in an atypical manner. In discussion with the inspector, the licensee
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stated that, in general, systems and components affected by a temporary
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modification are formally removed from service in ac'cordance with Operating
Procedure OP/0/A/6100/09 Removal and Restoration of Equipment, and agreed
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to change his procedures to reflect this practice. The licensee stated
.that by April 18, 1980, Station Directive 4.4.0 would be changed to require
completion of Removal and Restoration forms for all temporary modifications
of systems turned over t<
operations by construction, and that OP/0/A/
6100/09 would include a statement of its purpose to track temporary modi-
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fications.
Performance of OP/0/A/6100/09 requires testing of equipment before return
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to service. Thus, the second concern of the open item is also addressed in
the changes above.
This item remains open pending completion of these changes.
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