IR 05000302/1974008
| ML19319C845 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/18/1974 |
| From: | Bryant J, Conlon T, Vallish E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19319C836 | List: |
| References | |
| 50-302-74-08, 50-302-74-8, NUDOCS 8003040805 | |
| Download: ML19319C845 (7) | |
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RO Inspection Report No. 50-302/74-8 Licensee:
Florida Power Corporation
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.3201 34th Street South P. O. Box 14042
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St. Petersburg, Florida 33733 Facility Name:
Crystal River 3 Docket No.:
50-302
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License No.:
CPPR-51 Category:
A3/B1 Iocation:
Crystal River, Florida
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Type of License: B&W, PWR, 2452 Mut, 855 Mwe
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Type of Inspection: Rourine, Unannounced. Construction Dates of Inspection: June 11-14, 1974 Dates of Previous Inspection: April 29 - May 3, 1974
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Principal Inspector: E.J.Vallish,ReactorInspect5r Facilities Section Facilities Construction Branch
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Accompanying Inspectors:
T. E. Conlon, Reactor Inspector Engineering Section J
Facilities Construction Branch Other Accompanying Personnel:
ne Principal Inspector:
7'N7V E. J4'Vallish, Reactor Inspector Date Facilities Section Facilities Construction Branch Reviewed By:
'///?/ff s #2 C.'Brysn g Se'nior Inspector
Date
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acilities Section Facilities Construction Branch DOPY 312T T0: PDR
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LPDR /
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8008040I 6
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.b RO Rpt.-No. 50-302/74-8.'
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SUFMARY OF FINDINGS
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Enforcement Action A.
Violations
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None
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Safety Items
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None
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II.
Licensee Action on Previously Identified Enforcement Matters
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A.
Violations
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B.
Safety Items None.
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III. New Unresolved Items i
None IV.
Status of Treviously Reported Unresolved Items
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74-7/2 Containment Building Dome Concrete (10 CFR 50.55(e))
Early results of concrete cylinder tests indicated low
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i strength. FPC will report as required by 10 CFR 50.55(e).
This item remains open.
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73 5/3 Valve Wall Thickness verification
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l Thickness measurements were not made of valve bonnets, a.
cover plates or nozzles adjacent to the weldend j
preparation. This item remains open.
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b.
The engineering evaluation of the valves' thin walls was not acceptable.
FPC stated the valves would be
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repaired by welding to meet the requirements of the
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original purchase order. This item remains open.
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RO Rpt. No.:50-3 2/74-8-3-
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FPC is waiting for an engineering evaluation from 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 Modifications Modifuation of the internals is being accomplished in the
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vendor shops and verification will be made after the internals are delivered to the site. This item remains.open.
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V.
Design Changes
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None
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VI.
Unusual Occurrences
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None VII. Other Significant Findings
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Personnel and Organization Changes
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J. T. Rodgers' department has been renamed " Quality and Environmental i
Departments." Under that position is M. H. Kleinman, ?'trector,
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Quality Programs Department. Parallel with the Quality and Environ-mental Departments, and also under the Senior Vice President,
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System Engineering and Operations is the new " Director, System
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Engineering" position filled by Ned Spake.
Directly under this position is the " Director, Generation Engineering" who is
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W. A. Szelistowski.
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VIII. Management Interview A management interview was held and the results'of the inspection were discussed with E. E. Froats, Manager, Site Surveillance (Nuclear), and others of t e staff. They were informed that there were no new enforcement or unresolved items resulting from this inspection.
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RO Rpt. No. 50-302/74-8 I-l 7~ /9 7Y DETAILS I Prepared By"
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y T.'E. Conlon,. Reactor Inspector
/.Date Engineering Section Facilities Construction Branch
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Dates of Inspection:
e 11-14, 1974 2 f M'
Reviewed By:
a-B. 'J. Cphran, Acting Senior Inspect >r Date Engineering Section
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Facilities Construction Branch
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Persons Contacted a.
Florida Power Corporation (FPC)
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C. E. Jackson - Construction Superintendent E. E. Froats - Manager, Site Surveillance (Nuclear)
R. W. Slater - Quality Engineer L. Wade - Mechanical Engineer, NDT (UE&C)
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Contractor Organizations Babcox and Wilcox Construction Company (BWCC)
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J. R. McGill - QC Supervisor 2.
Primary Coolant Piping A followup inspection revealed that 10 of the 14 field weld joints have been final radiographed after Post Weld Heat Treatment (PWHT).
X-ray film for five of the 10 joints have been submitted to FPC for i
review. At the time of inspection, FPC had not performed their review of these film.
The inspector selected film for joints WJ-4-
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3 and 6-3 for review.
The film appeared adequate in contrast, density, identification and quality of weld.
Radiography was done in accordance with BWCC procedure 9T-RT-200 and UT was in accordance with procedure 9T-UT-201.
.ne inspector had no further questions in the area of primary pipint,.
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Other Class I Piping
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The inspector conducted a followup inspection on installed piping
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for decay heat, core flood and makeup piping systems.
Examination
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R0 Rpt. No. 50-302/74-8 I-2
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(visual) of field welds revealed no apparent deficiencies for work performed by both BWCC and JAJ. Yht audit performed by FPC on QC
documentation submitted by BWCC revealed small errors and inconsistencies.
As a result of these findings, FPC returned the documentation to BWCC for review and corrections.
This documentation will be examined
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on a subsequent inspection.
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Pressurizer
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During the initial installation of the pressurizer, a condition of insufficient clearance was detected between the pressurizer foundation
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haunch and the pressurizer vessel.
In order to provide the required
2-inch clearance, the vessel was removed and the concrete haunch ~
s was chipped and sanded to provide the clearance, after which the vessel was reinsta'11ed.
The vessel removal, concrete chipping and reinstallation of the$
vassel was done in accordance with procedure FPC-W94.
The inspector
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had no further questions.
5.
Control Rod Drive Mechanisms (CRDM)
,_s Receipt inspection, handling, storage and installation are to be in accordance with BWCC specification FS-lll-ld.
This specification l
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references the manufacturer's manual and B&W drawings. Procedures
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will be written for detail implementation of specifics contained in FS-111-ld.
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The CRDM's were manufactured by Diamond Power Specialty Corporation under B&W~ purchase order PO-021107LP.
The purchase order references B&W engineering specification CS-3-87.
Receipt inspection and monthly storage inspection reports were on file.
The following vendor QC documentation is at the site for each CRDM:
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Material identification and heat numbers.
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NDT reports.
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Hydrostatic tests results.
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Acceptance test results.
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ASME data reports.
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Certification of conformance.
The inspector examined the documentation and had no further questions.
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Rpt. No. 50-302/74-8 II-1
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DETAILS II Prepared By:
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E. J.fsVa111sh, Reactor Inspector Date
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Facilitics Section Facilitics Construction Branch
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Dates of Inspection: June 13-14, 1974'
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Reviewed By:
uw Jy;CVBryantft' Senior Inspector Date'
facilities Section
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Facilities Construction Branch
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Persons Contacted
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Florida Power Corporation (FPC)
C. E. Jackson - Construction Superintendent
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E. E. Froats - Manager, Site Surveillance (Nuclear)
R. W. Slater - Quality Engineer 2.
Nonconformance Reports (NCR)
The machine output compilation of NCR's was reviewed. This compilstion relates the history and status of all NCR's that were written.
No deficiencies were identified concerning the processing, control and follow-up actions on these NCR's.
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RO Inspection Report No. 50-302/74-8
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FLORIDA POWER CORPORATION JUL 2 31974, Crystal' River 3
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DISTRIBUTION:
H. D. Thornburg, RO RO:HO (
DR Ce'ntral Files
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Regulatory Standards (3)
Directorate of Licensing (13)
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cc enc 1. only:
- PDR
- Local PDR
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- NSIC
- S'cate
- To be dispatched at a later date.
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