IR 05000302/1975017
| ML19317G326 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/01/1975 |
| From: | Fred Bower, Bryant J, Vallish E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19317G324 | List: |
| References | |
| 50-302-75-17, NUDOCS 8002280933 | |
| Download: ML19317G326 (7) | |
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UNITE 3 STATES
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NUCLEAR REGULATORY COMMISSION f\\
REGION !!
g 230 PEACHTREE STREET N. W.
SUITE St 8 ATI.ANTA. GEo RGI A 30303
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IE Inspection Report No. 50-302/75-17
Licensee:
Florida Power Corporation 3201 34th Street South
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l P. O. Box 14042 St. Petersburg, Florida 33733
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i Facility Name: Crystal River 3
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Docket No.:
50-302
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I License No.:
CPPR-51
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Category:
A3/B1
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Location:
Crystal River, Florida l
Type of License:
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Type of Inspection: Routine, Unannounced, Construction i
Dates of Inspection: Fovember 5-7, 1975 Dates of Previous Inspection:
September 29-30 - October 1, 1975 Inspector-in-Charge:
T. E. Conlon, Reactor Inspector Engineering Support Section Reactor Construction and Engineering Support Branch
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l Accompanying Inspectors:
F. U. Bower, Reactor Inspector Engineering Support Section Reactor Construction and 5'ngineering Support Branch Other Accompanying Personnel:
None
Principal Inspector:
M- / 'I E. J/ Vallish, Reactor Inspector Date Projects Section
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Reactor Construction and Engineering Support Branch Ybx M'/- 7I Reviewed by:
J. C. )lfyant,~Sfotion Leader Date
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Project's Section
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Reactor Construction and Engineering
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(m gC Support Branch
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IE Report No. 50-302/75-17-2-
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SUMMARY OF FINDINGS
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I.
Enforcement Items None
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II.
Licensee Action on Previously Identified Enforcement Items
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Infractions il 75-12-Al(II)
Control of Special Processes
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This noncompliance item is deleted from the Reac't'or Construction and Engineering Support Branch reports and will be added to the Reactor Operations and. Nuclear Support Branch reports.
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III. New Unresolved Items None i
IV.
Status of Previously Reported Unresolved Items
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73-12/1 Hanger and Support Documentation Documentation and controi of deviations to hanger and support installations is now defined.
This item is closed.
(Details I, paragraph 2)
74-14/2 Seismic Qualification of the Control Rod Drive Control System AC Breaker Cabinets (10 CFR 50.55(e) Item)
Field work and QC documentation is complete and acceptable.
This item is closed.
(Details II, paragraph 2)
75-7/1 Procurement Records for Control Rod Drive AC Breaker Cabinet Required documents have been provided and approved.
This item is closed.
(Details II, paragraph 3)
V.
Design Changes None
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VI.
Unusual Occurrences None
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IE Report No. 50-302/75-17-3-
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VII.
Other Significant Findings,
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None I
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l VIII. Management Interview
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An exit interview was held with Mr. E. E. Froats, Manager, Site Surveillance (Nuclear), and other members of the staff to discuss
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the inspection findings as reported herein.
The licensee was informed that no noncompliances or new unresolved items resulted from this inspection. The licensee acknowledged the findings.
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.IE,Rpt. No. 50-302/75-17 I-l
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" DETAILS I Prepared by e*y& M
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T. E. Conlon, Reactor Inspector
'Date Engineering Support Section Reactor Construction and Engineering
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Support Branch Dates of Inspection: November 5-7, 1975
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/2~/~ I Reviewed by:
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L. L. Beratan, Section Leader Data
Engineering Support Section l
Reactor Construction and Engineering Support Branch
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Persons Contacted'
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Florida Power Corporation (FPC)
E. E. Froats - Manager, Site Surveillance D. Bienkowski - QA Engineer
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J. Alberdi - Project Manager b.
Contractor Organizations (1)
J. A. Jones Construction Company (JAJ)
J. Amundson - QC Supervisor (2) Babecek and Wilcox construction company (BWCC)
J. R. McGill - QC Supervisor
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2.
Hanger and Supports Documentation (75-12/1)
l The inspector reviewed Procedure FPC-W-48 to verify that a method I
for control of field deviations to har.ger/ support design sketches were incorpora,ted. The revision included instructions for identifying,
documenting and approval.
This item is closed.
3.
Primary Loop Drain Line These drain lines attach to the primary loop at the low point in the hot and cold legs to each of the two steam generators.
Each drain line is equipped with two (1 1/2-inch manually operated, j
series mounted) valves.
The valves were purchased from Velan Valve
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Corporation on Purchase Order PR3-1390 which invokes Gilbert Associates, Inc., (GAI) Specification R0-2951.
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IE Rpt. No. 50-302/75-17 I-2
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The inspector examined the vendor QC documentation at the site and
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compared these records with the requirements of Specification RO-2951.
The recor.ds contained:
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Chemical and physical certifications e
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ASME NPV-1 data sheet
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d.
Vendor certification of compliance
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e.
Hydrostatic test reports
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The inspector conducted a visual examination of the drain line installation and selected one open butt joint in each of the four,
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lines for review of weld data she,ets, isometric drawings and radiog-raphy. The joints selected were:
Isometric Field Weld O
CR3-P-8064-RC-1 No. 9 8065 No. 11 8066 No. 7 8067 No. 8 Within the areas examined, there were no items of noncompliance identified.
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IE'Ept. No.' 50-302/75-17 II-1 DETAILS II Prepared by:
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F. U. Bower, Reactor Inspector Date Engineering Support Section Reactor Construction and Engineering Support Branch
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Dates of Inspection: November 5-7, 1975
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Reviewed by: o
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L. L. Beratan, Section Leader Date Engineering Support Section Reactor Construction and i
Engineering Support Branch
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1.
Persons Contacted
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Florida Power Corporation (FPC)
E. E. Froats - Manager, Site Surveillance D. Olsen - QA Auditor, Instrumentation P. King - QA Auditor, Electrical R. C. Bonner - Supervisor, Electrical Construction l
R. Huesman - Supervisor, Instrument Engineer 2.
Seismic Qualification of the Control Rod Drive Control System AC Breaker Cabinets (10 CFR 50.55(e) Item) (Ref. 74-14/2)
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Examination of the completed modification work and related QC records has shown that the installed components now meet all requirements identified as applicable. This item is closed.
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I 3.
Procurement Records for Control Rod Drive AC Breaker Cabinet (Ref. 75-7/1)
The licensee's A&E consultant re-examined the safety category classification of the subject equipment and determined that it was more correctly classified as Level II than Level III.
The equip-ment was then ijualified to the new safety level by confirming.that
identical equipment had been analyzed and certified by a third party testing agency (Alliance Research Center). The QC record is j
now complete and this item is closed.
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4.
Primary System Pressure Instrument Sensor Lines The sensor lines for pressure transmitters 3A-PTI and 3B-PT1 were
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armnined as installed to determine the degree of adherence to the l
applicable QC procedure and the construction drawings.
Several
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.IE Xpt. No. 50-302/75-17 II-2
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deviations from the construction drawing were noted that were found
i necessary due to field conditions.
Di::cussion with tt3 staff indicated.that the installation drawings for the subject lines would be revised to represent the "as-built" conditions. These revised drawings would be checked to confirm that all requirements
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were met.
This engineering work was reported to be in progress but was lagging behind the installation program.
During the interim
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period, QC inspection and resultant documentation was being post-
.poned since a meaningful inspection could not be performed until
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the prior activities were complete.
The staff indicated that this inspection sample was representative-of the status of all-safety related sensor lines which means that-none of those system of interest to IE:II is complete. Due to this
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incomplete status these items will be the subject of a future inspection.
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