IR 05000302/1974004
| ML19319C970 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/11/1974 |
| From: | Crossman W, Vallish E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19319C957 | List: |
| References | |
| 50-302-74-04, 50-302-74-4, NUDOCS 8003040905 | |
| Download: ML19319C970 (9) | |
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RO Inspection Report No. 50-302/74-4
FLORIDA POWER CORPORATION
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DISTRIBUTION:
H. D. Thornburg, RO
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I Ragttlatory Standards (3)
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ATOM;C ENERGY COMMISSION
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RO Inspection Report No. 50-302/74-4
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Licensee: Florida Power Corporation 320134th Street South
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P. O. Box 14042 St. Petersburg, Florida 33733
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Facility Name: Crystal River 3 Docket No.:
50-302 License No.:
CPPR-51
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Category:
A3/B1 Location:
Crystal River, Florida
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Type of License: B&W, PWR, 2560 Mwt, 885 Mwe Type of Inspection: Routine, Unannounced, Construction y/
Date of Inspection: March 1, 1974 Dates of Previous Inspection: January 31 - February 1, 1974 Inspector-in-Charge :
E. J. Vallish, Reactor Inspector Faciliti(.3 Section Facilities Construction Branch Accompanying Inspector:
F. U. Bower, Reactor Inspector Engineering Section Facilities Construction Branch Other Accompanying Personnel:
W. A. Crossman, Senior Inspector Facilities Section cilities Construction Branch
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Principal Inspector:
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,-c Date E. JVVallish, Reactor Inspector Facilities Section Facilities Construction Branch
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Y Reviewed By:
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Date W. A. Crossman, Senior Inspector FacilitiesSection I
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Facilities Construction Branch
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'R0 Rpt. No. 50-302/74-4-2-
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SUMMARY OF FINDINGS
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I.
Enforcement Action
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A.
Violations
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None
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Safety Items
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None
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Licensee Action on Previously Identified Enforcement Matters
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Violations
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None
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Safety Items None III. New Unresolved Items
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IV.
Status of Previously Reported Unresolved Items 74-1/1 Nondestructive Testing Reports The licensee agreed that nondestructive testing reports are required for specified code inspections and will investigate and rectify the situation as to their omission in the weld data quality package. This item remains open.
73-13/1 Inadequate Wiring Devices t
The subject devices have been modified and now appear adequate.
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This item is closed.
(Details I, paragraph 3)
73-13/2 Cabinet Wiring Channel Separation A corrective program has been implemented with action in i
progress. This item will remain open until the work in
progress has been completed and results evaluated by RO:II.
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(Details I, paragraph 4)
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'R0 Rpt. No. 50-302/74-4-3-
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73-5/3 Valve Wall Thickness Verification
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Work is progressing toward completion of the three
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deficient areas.
(Details II, paragraph 2)
Thickness measurements were not made of valve bonnets,
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cover plates or nozzles adjacent to the weldend preparation.
This item remains open.
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The engineering evaluation of the valves thin walls
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b.
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was not acceptable.
FPC stated the valves would be repaired by welding to meet the requirements of the original purchase order.
This item temains open.
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FPC is waiting for an engineering evaluation from c.
Babcock and Wilcox Company justifying the wall thickness at the weld joint of the pilot operated relief valve.
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This item remains open.
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73-5/14 Reactor Internals Modification Modification of the internals is being accomplished in
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the vendor shops prior to delivery to the site.
This item
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remains open.
(Details II, paragraph 3)
V.
Design Changes
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None VI.
Unusual Occurrences None
VII.
Other Significant Findings Construction Progress.
(Details II, paragraph 4)
VIII. Management Interview A management interview was held on March 1,1974, and the details
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of the inspection were discussed with H. L. Bennett, Director, Generation Construction, and others of the staf f.
They were in-formed that there were no new enforcement or unresolved items resulting from this inspection.
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RO Inspection Report No. 50-302/74-4 I-1
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DETAILS I Prepared by:
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Date F
o'wer', Jteactor Inspector
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gineering Sectio'ti Facilities Construction Branch
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Dates of Inspection: March 1, 1974
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Reviewed by:
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Date.
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. Bryanr# Senior Inspector
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gineering Section
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acilities Construction Branch *
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Persons Contacted
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Florida Power Corporation (FPC)
R. Slater - Quality Engineer R. Bonner - Electrical Engineer 2.
Electrical / Instrumentation (E/I) Construction Program Cursory discussion with those contacted indicated that the E/I construction program has continued without significant problems and is basically on schedule. Work is just commencing in the reactor building with the installation of tray and conduit in progress. Work is reported well advanced in the turbine-generator and auxiliary buildings with -punch list status no more than 3-4 weeks away.
E Local instrumentation rack installation, sensor piping and electrical connection thereto is anticipated to be started in the next 2-3 months.
Cable installation of all classes is roughly estimated at 55-60%
complete with work continuing on installation and termination.
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RO Rpt. No. 50-302/74-4 I-2
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Inadequate Wiring Devices (Ref. 73-13/1)
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The subject unresolved item was examined with the following results.'
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Following the inspection wherein the potentisl deficiency was identified, the licensee's engineering unit took corrective action
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The notice by releasing an engineering change notice (No. 632).
provides a sketch and other instructions whereby the size of the
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subject wiring enclosures was increased to a capacity sufficient
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to accommodate the cable routed through them.
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Examination of the affected hardware revealed that the work specified
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by the aforementioned document had been accomplished and accepted
The wo'rk was of an acceptable order of workman-by the site QC unit.
This item is closed.
ship and no deficiencies were identified.
Cabinet Wiring Channel Separation (Ref. 73-13/2)
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In execution cf their commitment, made to RO during the last inspection
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in this area wherein the subject unresolved item was generated,
the licensee site staff has examined the several hundred conductors forming the presently installed inventory of-safety related circuits.
This examination identified all control room cabinet mounted
equipment associated with safety systems ard the relative condition
of the associated conductors as they relate to the requirements of
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i Where the subject conductors were the single-failure criteria.
located in a manner inconsistent with the physical separatioa (distances and/or barrier) as set forth-in Regulatory
requirement Guide 1.75, rework, consisting of rerouting the offending conductors,
uas stipulated.
l The results of this examination are contained in a tabulation document
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that describes the condition existing for each board mounted equipment and the related rework requirement for those areas found This document was examined at the site along with the deficient.
Although one hardware that has experienced rework action to date.
FPC inter-office letter from Engineering to the construction unit,still
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which forms a part of the documentation package for this effort,
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clings to the concept that teflon tubing provides suitable protection i
to meet any postulated event occuring within these cabinets, there were no cases observed nor is it expected that any case will arise wherein teflon tubing will form the total barrier and/or separation This is as it should be to meet medium for safety related conductors.
the minimum requirements as set forth in the referenced RO Guide.
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RO Rpt. No. 50-302/74-4 I-3
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The corrective effort was reported to be progressing satisfactorily.
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This was affirmed by the inspector during this interim sample examination. The work is projected to be completed 'within the
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next.3-4 weeks.
The work will be examined by RO at that time to
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confirm that corrective action has been appropriate.
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This item will remain open pend'ing completion and a positive finding
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regarding suitability to meet the requirements.
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RO Report No. 50-302/74-4
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k-I~ M DETAILS II Prepared by:
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J E. JV Vallish, Reactor Inspector Date
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Facilities Section Facilities Construction Branch
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Date of Inspection: Hsrch 1, 1974 d
3-#-74/
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Reviewed by:
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W. A. Crossman, Senior 4dspector Date'
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l Facilities Section Facilities Construction Branch
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Persons Contacted
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Florida Power Corporation (FPC)
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H. L. Bennett - Director, Generation Construction R. W. Slater - Quality Engineer
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L. R. Wade - Mechanical Quality Engineer
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b.
Contractor Organizations J. A. Jones-Construction Company (JAJ)
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J. R. Amundson - QC Supervisor l
Babcock and Wilcox Construction Company (B&W)
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J. R. McGill - QC Supervisor 2.
Valve' Wall Thickness Verification The contractor's representative stated that they were working-
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toward completion of the three areas which were reported deficient in RO Report No. 50-302/74-3 concerning these measurements. When complcr.ed RO:II will reinspect this item.
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3.
Reactor Internel.s Modification
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reactor internals will be shipped to the site along with the l
other internals during May 1974.
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RO Report No. 50-302/74-4 II-2
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4.
Construction Progress Backcladdiag of the primary piping joints is in progress. Fitup
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and welding of the joints in the incore instrument tubes is under-way.
Cleanup and coating of the reactor building interior rooms and finish painting of auxiliary piping and components is in
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progress. The spent fuel pits have been lined and fitting of
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the miscellaneous fuel handling hardware-is underway. Wires and cables are being pulled and terminations proceeding. The
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containment-building horizontal tendons are being installed.
Concrete is being placed in the circular lif ts in the containment dome above the ring girder. The ring girder forms have been stripped and the concrete is being finished. The reinforced
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concrete berm protection structures are being placed at the seaward side of the facility. The last circulation pump is yet to be "
installed on the intake structure.
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Letter to Florida Power Corporation from N. C. Moseley,
50-302/74 4 dated j
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DISTRIBUTION:
H. D. Thornburg, RO
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_RO:HQ (4)
L &" _- ' _ncrrte cf LI_ _ :'. M)
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DR Central Files
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cc encl. only:
- PDR
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- Local PDR
- NSIC
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- DTIE, OR
- State
- To be dispatched at a later date.
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