IR 05000302/1974012
| ML19319C850 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/02/1974 |
| From: | Fred Bower, Bryant J, Vallish E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19319C843 | List: |
| References | |
| 50-302-74-12, NUDOCS 8003040811 | |
| Download: ML19319C850 (7) | |
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O . . . RO Inspection Report No. 50-302/74-12 Licensto: Florida Power Corporation ,
3201 34th Street South P. O. Box 14042 . St. Petersburg, Florida 33733 - Facility Name: Crystal River 3 , ' .- Docket'No.: 50-302 License No.: CPPR-51 Category : A3/B1 Location: Crystal River, Florida ,'
Type of License: B&W, PWR, 2452 Mwt, 855 Mwe
J Type of Inspection: Routine, Unannounr:ed, Construction Dates of Inspection: September 11-13, 1974 Dates of Previous Inspection: August 13-16, 1974
Inspector-in-Charge: F. U. Bower, Reactor Inspector Engineering Section Facilities Construction Branch ' Accompanying Inspector: T. D. Gibbons, Reactor Inspector Engineering Section Facilities Construction Branch Other Accompanying Personnel: ne /8-2 ~7 V '
/ Principal Inspector: - E. J.,Vallish, Reactor Inspector Date , Facilities Section Facilities Construction Branch Reviewed By: / T7k /t r,t b v- --- - / /62 <./ J. d. Bryant, Senior Inspector',"! V / Dste / Facilities Section / . Facilities Construction Branc
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. . . . - . . . - - , A R0 Rpt. No. 50-302/74-12' -2-
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SUFDIARY OF. FINDINGS ' . 'I.
Enforcement Action . A.
Violstions ' None - ,
~ B.
Safety Items- . None -
. \\ .- II.
Licensee Action on Previous?.y Identified Enforcement Matters j . A.
Violations ~
There were no previously identified enforcement matters.
- B.
Safety Items There were no previously identified safety items.
III. New Unresolved Items None IV.
Status of Previously Reported Unresolved Items 74-10/3 Defective Westinghouse Type W-2 Control Switch Component (DROB No. 74-6) Recent inspection findings indicate a possible safety problem may exist in the plants'using Westinghouse Type W-2 control l switches. The licensee is investigating this possibility for Crystal River 3.
This-item remains open.
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74-10/4 Deficiency in ITE Molded Case Circuit Breakers, Type HE-3 (DROB No. 74-8) Deficiencies were discovered during preoperational testing of the Trojan nuclear plant, of magnetic trip elements in these circuit breakers. The licensee is investigating this possibility for l , Crystal River 3.
This item remains open.
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... 74-10/5 Deficiency in the ' General' Ele' tric-Model-4KV Magne-Blast Circuit ~ c i l Breakers (DROB No. 74-9):
. Recent information indicates that oversized trip bars and im- . proper' clearances.of related guide holes and linkages in these ' breakers could negate operation of the engineered safety system
components which-utilize'this model breaker. The' licensee is.. . '.
- investigating the possible use of this model breaker at Crystal
. River 3.
This item remains open.
- 73-5/3 Valve Wall Thickness verification , , - . t l a.
Thickness measurements were not made of valve.bonnetr, covir i plates pr nozzles adjacent to the weldend preparation.
j 'Ulis item _ remains open.
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b.
The engineering evaluation of the valves' thin' walls was not ' ^
acceptable. FPC stated that the valves would be repaired by welding to meet the requirements of the original purchase - , order. This item remains open.
c.
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.
This item f.
remains open.
i 73-5/14 Reactor Internals Modifications Modification of the internals is being accomplished in the. vendor ! shops and verification will be made after the internals are delivered to the site. This item. remains open.
V.
Design Changes None , , , VI.
Unusual Occurrences i ' l None i - .
VII. Other Significant Findings l l-None VIII. : Management Interviev
) -An_ exit interview -vas ' held 'uith H. L. Bennett, Director, Generation i
Construction, and other members of-the site staff. The inspeccors related:the results of their inspection. No violations or new unresolved ~ items were identified.
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__ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___.. _ _. .- q - . , - ,-m i ! R0 Rpt. No. 50-302/74-12 I-1 , . . 'i '. / ' - '7 "' DETAILS I Prepared By: ./., T. D. Gibbons, Reactor Inspector Date Engineering Section
Facilitica Construction Branch ' I s .,..<a i s .' - } 4, F. U. Bower, Reactor Inspector Date Engineering Section , Facilities Construction Branch Dates of Inspection: September 10-13, 1974 - , /h'[[" Reviewed By: 67M., Mk_.
d_/ ' L. L.~Beratan, Senior Insp,ector Date Engineering Sec' tion ' Facilities Construction Branch
1.
Persons Contacted /) Florida Power Corporation (FPC) (/ P. King - Quality Surveillance Auditor M. Robinson - Instrument Engineer R. Slater - Quality Engineer 2.
Scope This inspection was conducted to review the implementation of the Quality Program for the receipt, inspection and installation of the reactor instrumentation.
3.
Progress of Electrical and Instrumentation Installation The licensee reported that 79% of the cabling has been completed ' and cable termination was approximately 72% completed.
There are 300+ electricians working.
The reactor building was re-ported to have about-33% of the cables pulled and the tray system almost 100% complete.
The conduit in the reactor building is estimated to be 75% complete.
The RCP motors are the only major electrical equipment yet to be installed.
About 400 circuits on the project are still undefined.
No Class I circuits have been pulled in the reactor building. Most of the instruments in - the reactor building have been stored in place.
None of the sensing lines have been inscalled to the instruments.
The s ( ) penetrations have been installed.
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Perrennc1 Actions A new employee has been hired as a quality surveillance auditor.. . The man is a retired chief petty officer electrician with 20 years service.
His service has been on nuclear submarines.
. . 5.
Inspecticn Findings . The following pressure transmitters were examined as a representive '. sample of the engineered safety features.
The P/T were selected af ter review of drawings ESA03 and ESB03 (block diagrams of the - engineered safety features), ' a.
RC-3 APT 3 b.
RC-3 APT 4 . c.
RC-3BPT4 . . In-place storage of the PT's was inspected.
The QC documentation was reviewed for compliance with the procurement specifications, source inspections, receiving inspection and the prelmininary ] installation.
The sensing lines and the electrical cables were not installed.
Inspection of the sensing lines and the cable installation y will be performed at a subscquent inspection.
The review of the records of procurement, source inspection, and receiving inspection did not reveal any discrepancies.
The inspectors discussed the installation of the instrumentation
sensing lines.
It was pointed out that field routing of sensing lines without specific separation requirements and procedures had resulted in problems regarding the single failure criterion.
It was noted that existing procedures do not specifically refer to the requirements f for sensing line separation.
The licensee stated that drawings and , procedures will be developed to provide assurance that the instrument lines will be installed to meet the separation requirements.
The inspectors discussed the out-of-core nuclear instrumentation.
The inspectors were shown drawings and vendor manuals on in- ! stallation. The licensee assured the inspectors that procedures would incorporate the necessary requirements.
The inspectors stated that they would review the procedures and installation , on a subsequent inspection.
! The inspectors discussed the installation and testing of the Triax ' l I Cable for the nuclear instrumentation.
The licensee was informad l that on other cites the Tria:: Ccble was a major problem.
The b inspectors stated that they will reviou the installation of this \\ item en a later inspection.
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s; ' . A valk-through of the instrucent varehouse tras conducted.
No discrepancies I.
_ vere noted.. The inspectors. examined.the storage of the reactor - ' j
i coolant pump motorc. No descrepancias vere.noted.
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e_ , I j Letter to N. C. Moseley from Florida Power Corporation dated October 21, 1974.
i 50-302/74-12 , i ! , ! DISTRIBUTION: ' l-H. D. Thornburg, RO l RO:HQ (4) C ~ g . l Directorate'of. Lice 71 sing (4) ' '-1 ) , DR Central-Files < , l-PDR . l' NSIC Local ~ PDR . i- . TIC- .. .- . STATE - - i i
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