ML20062A277
| ML20062A277 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 08/18/1978 |
| From: | Dickerson M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20062A276 | List: |
| References | |
| 50-267-78-13, NUDOCS 7810110308 | |
| Download: ML20062A277 (8) | |
See also: IR 05000267/1978013
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U. S. NUCLEAR REGULATORY COMM!SSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
IE Inspection Report No. 50-267/78-13
Docket No. 50-267
License No. DPR-34
Licensee:
Public Service Company of Colorado
P. O. Box 840
Denver, Colorado 80201
Facility Name:
Fort St. Vrain Nuclear Generating Station
Inspection At:
Fort St. Vrain Site, Platteville, Colorado
Inspection Conducted: August 7-11, 1978
Inspectors:
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M. W. Dickerson, Reactor Inspector
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Inspection Summary
Inspection on August 7-11, 1978 (Report No. 50-267/78-13)
Areas Inspected: Routine, unannounced inspection of environmental qualifi-
cation of safety related electrical equipment; records; cleanline:.;;
surveillance of pipe supports and restraints; licensee event reports; IE
Bulletins and Circulars; follow up on inspector identified and unresolved
problems and follow up on items of noncompliance. The inspection involved
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69 inspector-hours on-site by two (2) NRC inspectors.
Results: Of the eight areas inspected, one item of noncompliance was found
during the review of records (Infraction - failure to follow procedure,
paragraph 4). An additional example of the item of noncompliance for
failure to follow procedure was also found during the review of cleanliness
(Infraction - failure to follow procedure, paragraph 5).
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DETAILS
1.
Persons Contacted
Public Service Company of Colorado
M. Block, Senior Results Engineer
- L. Brey, Superintendent Operations
D. Frost, Engineer, Technical Services
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D. Harihan, Document Clerk
- E. Hill, Supervisor Operations
- W. Hillyard, Supervisor Technical Services
J. Liebelt, Supervisor Electrical Maintenance
- F. Mathie, Superintendent, Maintenance
- M. McBride, Resident Engineer
L. McInroy, Superintendent QA Services
H. Revie, QA Engineer
J. Salakaweitz, QA Engineer
L. Singleton, Shift Supervisor
F. Swart, Superintendent, Nuclear Production
- C. Tracy, Superintendent Operations QA
- D. Warembourg, Manager QA
- Attended exit interview.
2.
Licensee Action on Previous Inspection Findings
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(0 pen) Inspector Follow Up Item (IR 50-267/76-13): Records of plant
operating cycles. While the licensee appears to be maintaining
records of each cycle, fonnal administrative controls for maintaining
records has not been established. Moreover, the licensee considers
that scrams from power levels less than 100 percent as that particular
portion of a cycle (i.e., a scram from 50% power is counted as one-half
a cycle). While this appears to be conservative, the oasis for this
assumption is not based on an engineering evaluation. Because this
item has been open since November 17, 1976 with marginal progress toward
completion of the necessary corrective action, this item is upgraded
to an unresolved item.
(0 pen) Inspector Follow Up Item (IR 50-267/77-10): Surveillance of
pipe supports and restraints. Hydraulic snubber BFS 398E has been
repaired, however, corrective action for the remaining items has not
been completed.
(See paragraph 6 of this report.)
(0 pen) Inspector Follow Up Item (IR 50-267/77-09 and 77-14): Plant
operating items. The specific items noted in the two reports have
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been corrected, however, a mechanism for designating and assuring that
these panels which may be left open or alternately must be closed has
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not been formalized.
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(0 pen) Inspector Follow Up Item (IR 50-267/78-14): Pulled fuses.
While all fuse blocks have bcen checked, an outstanding Corrective
Action Report (CAR) Numt-ar 538 relative to marking or tagging of
those blocks not requiring fuses remains outstanding.
(0 pen)InspectorFollowUpItem(50-267/78-06): Modification
necessary to allow Functional Testing of level Switches. Change.
Notice 763 necessary to install test connections which would allow
functional testing of a number of level switches, i.e.: LSH-21451,
LSH-21452, LSH-21453, LSH-21385, LSH-21440, LSH-21441 has not been
completed. Because the capability to functional test the level
switches is necessary and the scheduled completion date for the
change notice has not been met, this item is upgraded to an
unresolved item.
(Closed) Inspector Follow Up Item (50-267/78-06):
Inclusion of
certain level switches in the calibration / functional test program.
The inspector has determined that those System 21 level switches
noted in the subject report have been included in the Fort St. Vrain
calibration / functional test program.
(0 pen) UnresolvedItem(50-267/78-08):
Inconsistencies in Procedure
SR 5.3.5-A, Hydraulic Power System Calibration. The inconsistencies
in the surveillance procedure remain uncorrected. The inspector
reviewed CAR 756 and two pieces of internal correspondence dated
June 4,1978 and July 1,1978 requesting that action be taken to
correct the inconsistencies.
(Closed) Item of Noncompliance - Infraction 1.a (50-267/78-08):
Failure to analyze cleaning agents. The licensee has revised
Administrative Procedure ADM-12, " Maintenance and Repair Procedure,"
to provide specific cleaning agents which may be utilized. Additionally,
an engineering study, dated June 23, 1978, by PSC concluded that the
previous cleaning of stainless steel components had not been
detrimental.
(0 pen) Item of Noncompliance - Infraction 1.b (50-267/78-08):
Failure to control weld rod. A form for weld rod control has been
developed to be utilized by plant maintenance, General Atomic and
Stearns-Rogers. Revision of the necessary procedures is expected
to be completed by August 25, 1978.
(Closed) Item of Noncompliance - Deviation (50-267/78-08): Failure
to keep records. A requirement to maintenance records of solvents
and cleaning solutions utilized on stainless steel parts has been
incorporated into Maintenance Procedure MP-04, " Administrative
Policy for Maintenance Procedures." Additionally, this require
ment has been approved for all required procedures by the Plant
Operating Review Comittee in meeting number 268, dated August 9,
1978.
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3.
Environmental Qualification of Safety Related Electrical Equipment
The inspector determined that the licensee had assigned responsi-
bility for review of those items requiring review by the licensee
in IE Circular 78-08, " Environmental Qualifications of Safety
Related Electrical Equipment at Nuclear Power Plants." Each of the
items enumerated had been compared with his plant circumstances and
resulted in a determination that no corrective action was necessary.
The status of each of the items is as follows:
a.
Connectors: Response to IE Bulletins 77-05 and 77-05A
submitted December 12, 1977 included data to support con-
clusion of adequacy.
b.
Penetrations: IE Bulletin 77-06 sent to licensee for
information only - Electrical Penetrations not utilized.
c.
Terminal Blocks: Response to IE Bulletin 78-02 submitted
February 17, 1978. No unprotected blocks of the type
specified utilized.
d.
Limit Switches: Response to IE Bulletin 78-04 submitted
March 9,1978. No NAMCO D2400X or EA-170-302 snap lock
switches utilized in any safety related equipment. NAMCO
EA-170-11100 snap lock limit switches utilized and test
data to support conclusion of adequacy contained in
submi ttal .
e.
Cable Splices:
IE Circular 78-08. No electrical penetrations
utilized and no splices are allcwed unless inside control
cabinets in accordance with Electrical Design Installation
Specification 1N2.
f.
Other Potential Problems: IE Circular 78-08.
(1)
Radiation and temperature effects on electrical cables:
No electrical cabling utilized in these types of areas.
(2)
Temperature limitations on nylon components of solenoid
valves: Detennined that nylon components are not utilized.
(3)
Adequacy of qualification testing of components by
seperate effects versus sequential testing of environ-
mental parameters and qualification of electrical
transmitters: Reviewed in 1977 and problems found were
corrected.
No items of noncompliance or deviations were identified.
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4.
Records
The inspector reviewed the licensee's program for the control,
storage, retention and retrieval of records and documents for
conformance to Technical Specification requirements.
Charts TR4637 and TR4638 were among the records selected for
retrieval and inspection. These are three-pen recorder charts
for PCRV cooling water inlet and outlet temperature and concrete
surface temperature. Concrete surface temperature was not
recorded on chart TR4637 for the period March 11-17, 1978.
Neither concrete surface temperature nor cooling water outlet
temperature was recorded on chart TR4638 for the period March 10-17,
1978. No plant trouble reports (PTR) requesting recorder maintenance
could be located for this period. The licensee's failure to properly
monitor the performance of these recorders and to initiate a PTR
for corrective action is an apparent item of noncompliance with
Fort St. Vrain procedure ADM-28, " Administrative Procedure for
Data Logs, Data Sheets, and Charts." This procedure requires
that such recorders be checked once each shift to be sure that the
recorder is inking and reading properly and that
a PTR be written
if the recorder is not working properly.
For the period of March 11-17, 1978 the data available is insuffi-
cient to document compliance with Technical Specification LC0 4.2.15.
This problem has been previously identified by the licensee for
other LCO's and the generic problem is addressed in Corrective Action
Requests 403 and 404 and in Quality Assurance Deficiency Report 375.
The inspector will monitor the licensee's progress in developing
a system of documenting compliance with LC0's. This item is
unresolved.
5.
Cleanliness
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The inspector reviewed the administrative controls that the licensee
has established to assure adequate housekeeping and cleanliness. The
inspector conducted discussions with personnel and a tour of the
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facility in order to detennine the effectiveness of these controls.
During the facility tour, housekeeping conditions were observed to
be generally satisfactory. An exception to this was the auxiliary
electrical room where the following conditions existed:
Three empty cardboard boxes were present.
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One cardboard box containing styrofoam packing was present.
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One cardboard box was being used as a trash container.
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Two partial rolls of used chart paper were observed in the
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bottom of Panel I-47.
Loose teletype paper was on the floor.
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The existence of these conditions is an apparent item of noncom-
pliance with the requirements of Fort St. Vrain Procedure ADM-30,
" Administrative Procedure for Control of Combustibles." This
procedure requires that parts, instruments and other supplies in
ccmbustible containers be unpacked and the packing safely stored
or disposed of before the part or instrument is taken into the
plant operating area.
It further provides that if the item must
be unpacked at the work area, the combustibles shall be removed
to suitable storage imediately.
The licensee took appropriate corrective action during the period
of this inspection, and no written response to this item is
required. flo other items of noncompliance or deviations were
identified in this portion of the inspection.
6.
Surveillance of Pipe Supports and Restraint Systems
The inspector reviewed the licensee's program, procedures and
schedule pertaining to pipe support and restraint systems for
conformance to the requirements of the Technical Specifications.
The inspection included a review of records, a physical inspection
of snubbers and supports during a facility tour, and a review of
open items from inspection number 77-10.
The following items noted during inspection 77-10 remain open:
The refueling interval surveillance procedures for hydraulic
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snubbers have not been prepared.
The licensee has no plans to establish a surveillance program
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for pipe restraints other than hydraulic snubbers.
The hydraulic snubber inspection program does not include an
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inspection of piston and/or reservoir vents, or sample test-
ing of hydraulic fluid.
The licensee does not have a program for lubricating the
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grease fittings of hydraulic snubbers.
The inspector identified the following new open items:
The U-clamps near V42387 and V42378 were not secured to the
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pipe support. A plant trouble report was initiated to correct
this discrepancy.
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