IR 05000267/1979006
| ML19263E419 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 04/05/1979 |
| From: | Dickerson M, Testerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19263E417 | List: |
| References | |
| 50-267-79-06, 50-267-79-6, NUDOCS 7906180137 | |
| Download: ML19263E419 (4) | |
Text
.
.
V. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
IE Inspection Report No. 50-267/79-06 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. b ain Site, Platteville, Colorado Inspection Conducted: March 19-23, 1979 Inspector:
7. I. gu d'-A
-/-m.-
g - 5 - 77 M. W. Dickerson, Reactor Inspector Date Approved By:
bN
- .f - 7f T. F. Westennan, Chief, Reactor Projects Section Date Inspection Summary Inspection on March 19-23,1979 (Report No. 50-267/79-06)
Areas Inspected:
Routine, unannounced inspection of refueling activities; and maintenance activities.
The inspection involved thirty-five (35)
inspector-hours on-site by one (1) NRC inspector.
Results:
No items of noncompliance or deviations were identified.
2355 181 7906180/37
-
.
_2_
DETAILS 1.
Persons Contacted Public Service Company of Colorado R. Bass, Special Senior Licensed Operator L. Bishard, Special Senior Licensed Operator W. Crane, Supervisor Mechanical Maintenance J. Gamm, Supervisor Technical Services
- R. Heller, Reactor Engineering, Technical Services
- E. Hill, Supervisor Operations
- W. Hillyard, Administrative Services Manager
- T. Howard, Superintendent Operations QA F. Mathie, Operations Manager
- D. Warembourg, Manager Nuclear Production General Atomic R. J. Nirschl, Fuels Representative at Site
- Attended exit interview.
2.
Refueling Activities The inspector verified by direct observation that:
a.
Monitoring of the core reactivity during refueling was in accordance with procedures and Technical Specifications; b.
Containment integrity was properly maintained; c.
The insertion and removal of fuel was conducted in accordance with established procedures; d.
Core internals, leads, studs, etc. were stored properly to protect against damage;
-
e.
Make-up and license requirements of the refueling crew on the refueling floor and in the control room were in accordance with Technical Specifications; f.
The reactor mode switch was in the position required by Technical Specifications, and; g.
Control Rod configuration was as required by procedures and the Technical Specifications.
2355 182
.
,
-3-During the refueling, portions, or all of the following activities were observed:
(1)
Reinspection of block S/N 150 and the core support blocks (Ref: IE Inspection Report 50-267/79-04). This inspection confirmed that the work on block S/N 150 and on the core support blocks were not cracks but appear to be residual stain marks.
(2) Loading of fuel handling machine (Refueling tape address 701-737) with 31 elements and reflectors from fuel storage well No. 9 for loading into region 35.
(3) Placing of a Reactor Isolation Valve in region 5.
(4) Movement of the fuel handling machine to region 35.
(5)
Insertion of 31 elements and reflector blocks into region 35 (address 750-781).
(6) Movement of the auxiliary transfer cask to region 5 (for removal of control rod).
(7) Place instrumented control rod into auxiliary transfer tank and move to region 35.
(8)
Install instrumented control rod in region 35.
(9) Unloading of 21 fuel elements (including three control rod elements) from region 5 into fuel storage well No. 9 (address 251-271).
(10)
Reactivity determination with control rod returned to region 35 and control rod removed from region 5.
(11)
Removal of 21 elements (including three control rod elements)
from region 5 (address 301-321).
No items of noncompliance or deviations were identified.
3.
Maintenance The inspector reviewed two maintenance procedures for proper approvals, inspection hold points, provisions for proper system alignment, fire watch and testing. The procedures reviewed were a) CWP 205, Rev. 1, dated March 15,1979 (Change Notice 120A) for the addition of 39 valves to the penetration interspace pressure system to facilitate leak testing 2355 183
-
.
-4-
.
of the individual penetrations, and b) CWP 238, approved September 23, 1977 (Change Notice 238), for modification of the hydraulic oil piping to level switches LSL-91145/46 to permit calibration of the level switches.
-
Each of the CWP's, CNS reviewed contained appropriate considerations for material compatability, seismic calculations, design review veri-fication, safety evaluation and material traceability, documentation, inspection and testing.
The review of CWP 238 indicated that either the CWP was incomplete or an additional CWP would have to be written to complete the work.
CWP as written included only instructions with reference to modification for LSL 91145. This was pointed out to the licensee who indicated that the CWP would be corrected to include LSL 91146 before the work was initiated. This is considered an open item.
No items of nonconformance or deviations were identified during the inspection.
4.
Exit Interview An exit interview was conducted with representatives of the licensee on March 23, 1979, at the conclusion of the inspection.
At the interview, the inspector discussed the findings indicated in the previous paragraphs. The licensee acknowledged his findings.
,
2355 184 t
....w.
.
e.
.-
e.
.
--%
e-..
.
..
=. * - - - -... -.
~..w-e----.
- - -..