ML20027E399
| ML20027E399 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 10/08/1982 |
| From: | Felton J NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Audin L AFFILIATION NOT ASSIGNED |
| Shared Package | |
| ML20027E400 | List: |
| References | |
| FOIA-82-428 NUDOCS 8211150170 | |
| Download: ML20027E399 (2) | |
Text
PD(L-olb
[
'o UNITED STAT Es E"
N NUCLEAR REGULATORY COMMISSION
.,E WASHINGTON, D. C. 20555 t,
a
%, ' ' * * * /
October 8,1982 Mr. Lindsey Audin One Everett Avenue IN RESPONSE REFER Ossining, NY 10562 TO F01A-82-428
Dear Mr. Audin:
This is in partial response to your letter dated September 6,1982, it which you requested, pursuant to the Freedom of Information Act, copies of eight classes of documents as described in your letter.
In partial response to your request, we are providing you with copies of the documents listed on Appendix A.
Document 4 of Appendix A answers your item 1, and it is the only informaiton we have located on this subject.
locument 8 of Appendix A relates to your item 2.
You will note that the extensive index list included with document 8 identifies documents on file in the NRC's Public Document Room (PDR) located at 1717 H Street, N.W., Washington, D.C. 20555.
Any of these indexed documents can be ordered directly from the PDR as stated in document 8.
With respect to your item 3 concerning the LWR Hydrogen Manual produced by General Physics Corporation, the final draft is not yet available, and the report will not be publicly available until 1983.
Documents 2 and 3 of Appendix A relate to your item 6.
Documents 1, 5, 6, and 7 of Appendix A all relate to your item 7.
NUREG-0923(Cost: $2.50 per copy) can be ordered directly from the Government Printing Office Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555.
Payment in advance is required for documents ordered from this source.
Our search for documents which may be subject to your request is continuing, and we will communicate with you again when our search efforts are completed.
Sinc 6r ly, Y
b' J
. Felton, Director Division of Rules and Records Office of Administration
Enclosures:
As stated
~
I ~821T1150170 821008
Re: FOIA-82-428 Appendix A
- l.
5/18/82 NRC Inspection Report No. 50-267/82-09 (9 pages) 2.
6/23/82 Excerpt from Weekly Report - paragraph 4 - LOFT (1/2 page) 3.
6/29/82 Excerpt from Weekly Report - paragraph 8 - LOFT (1/2 page) 4, 6/30/82 List of Selected References (2 pages) 5.
7/8/82 Memo for H. Denton et. al. from Geor Highlight - Fort St. Vrain'(1 page) ge Kuzmycz re: Daily 6.
7/19/82 Note for R. J. Mattson from Michael Tokar re: Comment on FSV Cracked Fuel Elements (1 page) 7.
9/15/82 Letter to George Kuzmycz from H.- L. Brey re: Status of Cracked Fuel Elenent Webs w/ attached Figure 1 - Core Position of Flements (5 pages) 8.
7/30/82 Letter to Ms. Andrea L. Kronzek, from J. M. Felton, NRC (4 pages) i i
- A copy of this report is available in.the NRC Public Document Room
i APPENDIX B U. S. NUCLEAR REGULATORY COMMISSION REGION IV NRC Inspection Report:
50-267/82-09 License:
DPR-34 Docket:
50-267 Category:
5 Licensee:
Public Service. Company of Colorado P. O. Box 840 Denver, Colorado 8,0201 Facility Name:
Fort St. Vrain Nuclear Generation Station Inspection at:
Fort St. Vrain Site, Platteville, Colorado Inspection Conducted:
April 1-30,1982
. N.
Inspectors:
SJg r M. W. Dickerson, Senior Resident Reactor Inspector Date h
5l3 *U G. L. Plumlee III, Re'sident Reactor Inspector Date IN
[-li-?
- Approved:
T. F. Westerm,an, Chief, Reactor Project Section A Date Inspection Summary Inspection conducted April 1-30.1982 (Report:
50-267/82-09)
Areas Inspected:
Routine, announced inspection of Surveillance; Maintenance; Operational Safety Verification; Follow Up of Previous Inspection Findings; and Review of Periodic and Special Reports.
The inspection involved 126 inspection-hours onsite by two NRC inspectors.
Results:
Within the five areas inspected, one violation was identified (Failure to adhere to Procedural Requirements, Paragraphs 3a and 3b).
6 j) $
\\
f v
pf)F
l
(-
2 DETAIL 1.
Persons Contacted M. Block, Superintendent of Operations T. Borst, Radiation Protection Manager B. Burchfield, Results Engineering Supervisor W.~ Franek, Nuclear Site Engineering !'anager C. Fuller, Technical Services Engineering Supervisor J. Gahm, QA Manager E. Hill, Operations Manager D. Hood, Shift Supervisor J. Liebelt, Senior Maintenance Supervisor M. McBride, Technical / Administrative Services Manager l'
V. McGaffic, Radiochemistry Supervisor H. O'Hagan, Shift Supervisor G. Reigel, Shift Supervisor L. Singleton, Superintendent Operations QA J. Van Dyke, Shift Supervisor D. Warembourg, Manager Nuclear Production R. Webb, Maintenance Supervisor W. Woodard, Health Physicist 7
The NRC inspectors also contacted other plant personnel including reactor operators, maintenance men, electricans, technicians, and -
administrative personnel.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (50-267/8116-01):
Documentation of Service Water Spacer Block.
The licensee returned the valve LCV-4218-3 to its original condition and revised the 50P to include this valve.
3.
Operational Safety Verification The NRC inspector reviewed licensee activities to ascertain that the facility is being operated safely and in conformance with regulatory requirements, and the licensee's management control system is effectively discharging its responsibilities for continued safe operation.
The review was conducted by direct observation of activities, tours of the facility, interviews and discussion with licensee personnel, independent verification of safety system status and limiting condition for operations, and review of facility records.
Included in the inspection were observation of control room activities, review of operational legs, records, and tours of accessible areas.
s
\\
3 Logs and records reviewed included:
Shift Supervisor Logs Reactor Operator Logs Equipment Operator Logs Auxiliary Operator Logs Technical Specification Compliance Logs Operations Order Book Operations Deviations Reports Clearance Log Temporary Configuration Reports Plant Trouble Reports During tours of accessible areas, particular attention was directed to the following:
Monitoring Instrumentation Radiation Controls Housekeeping Fluid Leaks Piping Vibrations Hanger / Seismic Restraints Clearance Tags Fire Hazards Control Room Manning Annunciators The operability of selected systems or portions of systems were verified by walkdown of tne accessible portions.
The NRC inspector verified the operability of the Turbine Lube Oil Purification System.
No problems were identified during the system walkdown.
t
(
4 Procedures were also reviewed and implementation observed for Gaseous Effluent Release No. 599 and Liquid Waste Releases No. 543 and 550.
The releases appeared to have been made in a satisfactory manner.
a.
During a tour of the reactor building on April 15, 1982, at 9:55 a.m. MST, with reactor power at 32%, the NRC
. inspector determined that V-6361, " Gas Waste Vacuum Tank to Liquid Drain Tank," was not sealed and appeared to be closed.
The licensee verified that V-6361 was closed, then opened, and resealed the valve.
Overall Plant Operating Procedure OPOP III requires that while reactor power is
>2%, the sealed valves shall be sealed and positioned in accordance with SR-0P-12-M.
SR-0P-12-M ' required V-6361 to be sealed open.
The licensee informed the NRC inspector
' that draining of the core support vent filters had been performed the previous day and required repositioning of V-6361.
A review by the NRC inspector of the procedure in 50P 63 for draining the core supoort vent filters indi-cated that the restoration step failed to address reopening and resealing V-6361.
The NRC inspector informed the licensee that the failure to follow procedeces, which are required by Technical Specifications. is considered a violation.
(8209-01) b.
During a tour of the reactor building on April 28, 1982, at 1:15 p.m. MDT, the NRC inspector observed that there were no clearance tag numbers entered'on the auxiliary tags placed on valves V-11119 and V-ll319.
The tags were placed in accordance with Clearance Number 3155 for System 12, Control Rods and Drives, on April 28, 1982, in preparation for work on Control Rod 19 and the associated Reserve Shutdown System.
The NRC insoector subsequently determined that the other two valves, V-ll269 and V-ll419, denoted on the clearance were also tagged with unnumbered auxiliary tags.
A check of the valve positions indicated the valves to be in the position required by the clearance.
Procedure P-2, in Section 4.1.3, requires that the Reactor Operator place the number of the clearance on each of the auxiliary tags.
The licensee was informed that failure to comply with requirements of the Procedure was considered a violation.
(8209-01)
.