IR 05000302/1972004
| ML19308D206 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/26/1972 |
| From: | Beratan L, Rob Parker, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19308D165 | List: |
| References | |
| FOIA-80-250 50-302-72-04, 50-302-72-4, NUDOCS 8002270669 | |
| Download: ML19308D206 (3) | |
Text
{{#Wiki_filter:O - . . ' .~ em 0'f '*,,k UNITED STATES /[ M E9 )*1 /N ATOMIC ENERGY COMMISSION li 8MMOG0GDONDMEC i/- REGICN ti - Su t T E 818 230 P E AC HT R E E ST r4 E ET, NORT HWEST
AT w A NT A. GECRG6 A 30303 . DIRECTORATE OF REGULATORY OPERATIONS . RO Inspection Report No. 50-302/72-4 Licensee: Florida Power Corporation 3201 34th Street South P. O. Box 14042 St. Petersburg, Florida 33733 Crystal River Unit 3 Docket No.
50-302 Crystal River, Florida License No. CPPR-51 Category A2 Type of Licensee: B&W, PWR, 855 Mw(e) Type of Inspection: Special, Announced Date of Inspection: September 25, 1972 Dates of Previous Inspection: August 15-17 and 28-31, 1972 M!26!72.
Inspector In Charge: GA . , R. C. Parker, Reactor Inspector D&te- ' Reactor Test and Startup Branch Accompanying Inspector: [/ 4,w fo r- /o/MM92 L. L. Beratan, Senior Structural Dite ' Engineer, Technical Assistance Branch, RO:HQ Other Accompanying Personnel: None Reviewed By: [[ /b /d/at/?d R. F. Warnick, Reactor Inspector, Reactor Test Date and Startup B auch f4 aj l nbd,v C. E. Murphy ( AotinjpCliief, Reactor Test and Da'te ' Startup Branch nU 8002270 k .
^ g f , t
s ' d ',' ,RO Report No. 50-302/72-4-2- , SUMMARY OF FINDINGS Enforcement Action None Licensee Action on Previously Identified Enforcement Items Review of previously identified enforcement items was not within the scope of this inspection.
Design Changes None Unusual Occurrences None New Unresolved Items None
Status of Previously Reported Unresolved Items No change.
! Management Interview No formal management exit interview was held due to the special nature of the inspection. However, the inspectors discussed their findings with licensee representatives during the course of the inspection.
In discussions with license representatives, the inspectors stated - that.they were disappointed that the repair concrete placement procedure was not available for review.
FPC representatives stated that they considered that they were at a holdpoint in construction until RO had inspected the work done to date.
, The inspectors stated that RO would want to see a copy of the repair concrete placement procedure when it is available and that RO would want , to inspect the concrete reinforcement, tendon conduit, and reactor building i liner repair work prior to concrete placement.
FPC's representatives ' stated that a copy of the repair concrete placement procedure would be forwarded to-Region II as soon as it is finalized and that Region II would be notified before the concrete forms are buttoned up so that RO O, can inspect the repair of concrete reinforcement, tendon conduits, and reactor building liner prior to concrete placement.
. -
, _ _ _ _ . _.
_ _ .... - - ,, , , ( '. . RO Report No. 50-302/72-4-3-
DETAILS Prepared By: R. C. Parker, Reactor Inspector L. L. Beratan, Senior j Structural Engineer i 1.
Persons Contacted ,. H. L. Bennett - FPC, Director, Generation Construction l C. E. Jackson - FPC, Construction Superintendent ! M. H. Kleinman - FPC, Manager, Generation Quality and Standards
E. E. Froats - FPC, Quality Engineer { R. S. Dorrie - FPC, Engineer G. Pachos - FPC, Structural Superintendent
2.
Reactor Building Cylindrical Concrete Structure i
The objectives of the inspection were to examine the reactor building ' cylindrical concrete structure remaining after demolition of concrete i placed during pour No. 535RB and to review repair procedures associated j with placement of new concrete.
} The concrete placed in pour No. 535RB has been removed.
Considerable ' damage was done to the reinforcing steel. A major portion of it will have to be cut out and new bars Cadwelded into place. Damage . to tendon conduits was noted and will be repaired in accordance with FPC repair procedures. There was some gouging of the liner by the jack hammers and Chicago Bridge and Iron Company (CB&I) was asked by ~ J I FPC to evaluate the damage.
The CB&I evaluation was not available i during the inspection. The CB&I procedures provide for the required repairs but, to date, none of the repairs have been made.
No noticeable
damage was done to the equipment hatch itself, i r I
'I l
- l
} s
l ! , - ,_,._ __.. _,.... - - _ - - - - - _ - -. - - -. ... . . ..... - ~ - - - . ... - }}