IR 05000302/1974015
| ML19319C816 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/30/1974 |
| From: | Bryant J, Vallish E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19319C813 | List: |
| References | |
| 50-302-74-15, NUDOCS 8003040782 | |
| Download: ML19319C816 (7) | |
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UNITED STATES Js ATOMIC ENERGY COMMISSION
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DIRECT 0 HATS OF REGULATORY OPERATIONS,
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RO Inspection Report No. 50-302/74-15
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Licensee:
Florida Power Corporation
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3201 34th Street South I
Post Office Box -14042 St. Pe.:trsburg, Florida 33733
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Facility Name: Cry..tal River 3 Docket No.:
50-302 i
t License No.:
CPPR-51 l
Category:
A3/B1 l
Location:
Crystal River, Florida Type of License: B&W, PWR, 2452 Mwt, 855 Mwe
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Type of Inspection:
Routine, Unannounced, Construction
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Dates of Inspection:
December 12-13, 1974
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Dates of Previous Inspection:
October 10-11, 1974 i
Principal Inspector:
E. J. Vallish, Reactor Inspector
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Facilities Section l
Facilities Construction Branch Accompanying Inspectors: None Other Accompanying Personnel: None Pr1ncipal Inspector:
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f E. J. Vallish, Reactor Inspedtor Dat4
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Facilities Section Facilities Construction Branch
/2[y; Reviewed by: if J. C. Bryant, SeniorInspetor dat4 Facilities Section
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Facilities Construction Branch a
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RO Rpt. No. 50-302/74-15-2-
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I.
Enforcement Action
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A.
Violations t
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Safety Items None
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II.
License Action on Previously Identified Enforcement Matters
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' A.
Violations
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There were no previously identified enforcement matters.
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Safety Items There were no previously identified safety items.
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III. New Unresolved Items
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74-15/1 Makeup and Purification System Letdown Orifice (10' CFR 50.55(e) Item)
NSSS supplier investigation revealed that cavitation and subsequent erosion would occur in the last three stages of this letdown
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orifice.
Subject orifice is being returned to manufacturer for I
modification.
(Details, paragraph 2)
IV.
Status of Previously Reported Unresolved Items 74-14/1 Reactor Internals Handling Fixture Design Deficiency
,10 CFR 50.55(e) Item)
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The design of a spherical nut capture device could have allowed
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the nut to becone unthreaded to such an extent that the weight of the internals would have sheared the threads, dropping the internals.
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Field Change Procedure No. 092 was accomplished by B&W to modify this fixture. This item is closed.. 0 Details, paragraph 3)
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RO Rpt. No. 50-302/74-15-3-
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74-14/2 Seismic Qualification of the Control Rod Drive Control System
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AC Breaker Cabinets (10 CFR 50.55(e) Item)
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A re-evaluation of the seismic qualification of the control
rod drive control system AC breaker cabinets has revealed that the attachment of the cabinets to the floor is inadequate
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to withstand the SSE acceleration lev 21s.
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A field change will be issued by B&W to modify the attachment of the AC breaker cabinets to the floor.
FPC will monitor the B&W correctiva action.
This item remains open.
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74-10/3 Defective Westinghouse Type W-2 Control Switch Component (DROB No. 74-6)
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Recent inspection findings indicate possible safety problems ~
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may exist in the plants using Westinghouse Type W-2 control
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switches.
This item is closes.
(Details, paragraph 4)
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 possi-
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bility for Crystal River 3.
This item is transferred to RO:II
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Test and Startup Branch for followup.
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73-5/3 Valve Wall Thickness Verification
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a.
Thickness measurements have been made of valve bonnets,
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cover plates or nozzles adjacent to the weldend prepa-
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ration. This item is closed.
(Details, paragraph Sa)
b.
The engineering evaluation of the valves ' thin walls are now acceptable. This item is closed.
(Details, paragraph 5b)
c.
FPC has received an engineering evaluation from Babcock and Wilcox Company justifying the wall thickness at the j
weld joint of the pilot operated relief valve.
This item is closed.
(Details, paragraph Sc)
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RO Rpt. No. 50-302/74-15-4-
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73-5/14 Reactor Internals Modifications Modification of the internals.was to have been accoglished
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in the vendor shops and verification will be made when the internals are assembled. 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 i
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None VIII. Management Interview An exit interview was held with Messrs. M. H. Kleinen, Director, Quality Standards; E. E. Froats, Manager, Sire Surveillance (Nuclear);
and R. W. Slater, Quality Engineer. The results of the inspection were discussed.
No new violations were found, but one new unre, solved item
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was identified.
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DETAILS Prepared by:
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E.[){ Vallis [,ReactgfInspector
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j Facilities Section, Tacilities
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Construction Branch
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Dates of Inspection:- December 12-13, 1974
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Reviewed by:
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J. Cffrfant,' g%iiior Inspector Dat'a '
Fac m ties Section, Facilities
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Construction Branch
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Persons Contacted
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Florida Power Corporation (FPC)
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M. R. Kleinman - Director, Quality Programs Department
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E. E. Froats - Manager, Site Surveillance (Nuclear)
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R. L. Bennett - Director, Generation Construction 1'
C. E. Jackson - Superintendent, Site Construction R. W. Slater - Quality Engineer J. E. Barrett - Engineer, Mechanical
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h J. E. Colby - Field Engineering Supervisor
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Contractor Organizations
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J. A. J a es, Construction Co. (JAJ)
J. R. Amunc.Jon - Manager, JAJ QC
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2.
Makeup and Purification System Letdown Orifice (10 CFR 50.55(e) Item)
Design review indicated that cavitation would result in.the last three stages of these orifices which would eventually either erode the orifice shell and then cause a leak or reduce the effectiveness of the orifice i
to reduce pressure.
The erosion resulting from the cavitation could cause a release of reactor coolant outside the reactor building. This orifice system has been redesigned and field change packages are being prepared by the B&W Company to implement the correction of this deficiency.
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FPC 'is monitoring-this corrective action. This item remains open.
3.
Reactor Internals Handling Fixture Design Deficiency - (10 CFR 50.55(e) Item)
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B&W Field Change Procedure No. 092 was issued to the field to modify this
i fixture in accordance with the new improved design. The records of the rework were inspected and evid.ence of completion was determined. The
handling fixture was inspected; however, the actual modified parts could t
not be observed because disassembly would be required of the housing
j that enclosed the modified parts. This item is closed.
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)1 RO Rpt. No. 50-302/74-15 I-2
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4.
Defective Westinghouse Type W-2 Control Switch Component (DROB N'. 74-6)
o The licensee has reviewed their list of control switches and have'
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determined that they do not have Westinghouse Type W-2 control switches
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at the Crystal River 3 facility.
This item is closed.
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5.
Valve Wall Thickness Verification
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The following documents were reviewed at the site:
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"FPC Quality Program Book A, Valve Minimum Wall Thickness Program"
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" Book A, Attachment 7, Valve Minimum Wall Thickness Program"
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" Valve Minimum Wall Thickness Program, Engineering Justificatioh',' Book B" l
" Book B, Appendix 1, Minimum Wall Thickness Program, Engineering Justifica-
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tion, Repair Procedures"
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During a conference with the FPC field engineering supervisor and the JAJ QC manager all the remaining questions concerning this program were resolved to the inspectors satisfaction.
In recap; this valve wall thickness verification program detected 19 valves which were rejected as not. meeting the minimum criteria. All of these rejected valves were designated as nonconforming and Nonconformance
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and Corrective Action (NCR) forms were processed which provides quality con-trol thru the final disposition of the valve.
It was observed during review of the documeatation that the architect-engineer, Gilbert Associa'tes, t
Incorporated, FPC and the Crane Company were able to reach agreement on the technical aspects of the nonconforming valves such that repair on the i
site could be accomplished where such repair was required.
The repair procedures specify that the J. A. Jones site quality control manager is responsible for coordination and assuring that all work is performed in
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accordance with those approved procedures.
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Thickness measurements were made of the valve bonnets and cover plates a.
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and were extensively increased in quantity around the nozzles near the
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weldend preparation.
The ASME Boiler and Pressure Vessel Code,Section VIII and ANSI B16.5 were used to determine the required thickness for the-cover plates.
Data was reviewed and is contained in Attachments VII and VIII of Book A, " Valve Minimum Wall Thickness Program."
There are no further questions on this item and it is closed.
b.
Those valves requiring repair and re-evaluation have been documented l
on the appropriate NCR data sheets. Repair procedures have been prepared and coordinated as applicable with FPC, GAI, B&W and Crane.
These procedures are contained in Appendix 1 to Book B, titled, " Minimum Wall ~ Thickness Program, Engineering Justification, Repair Procedures." The evaluation is considered technically ade-
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quate and there are no further questions.
This item is closed.
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RO Rpt. No. 50-302/74-15 I-3
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1he wall thickness at the weld joint on this electromatic valve
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l (RC-RV2), B&W Purchase Order No. 81395LS and Dresser Industries, Order No. 30-54524-1, was analyzed using a prototype joint fabri-cated to the requirements of the purchase order for identical
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valves used in the_0conee plants.
Dresser has stated that the
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controlling instruction number OS-126. included identical approved procedures for welding, testing, and other actions that were imple-mented to build the Oconee, Crystal River, and other identical
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valves.
R0 Report N. 50-270/74-4 resolved the use of this o
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particular valve on the three Oconee units which are sister
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units to the Crystal River 3 unit.
This item is herewith con-sidered resolved and closed.
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6.
' General A walk-through inspection of the general construction areas was
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The new construction schedule which was reviewed calls for fuel loading May 27, 1976.
The stretch-out impact was discussed wit" Bennett and Kleinman.
Also discussed with Kleinman was the plan wherein FPC would assume the full responsibilities for the. construction quality I
assurance which is now performed by Gilbert Associates, Incorporated; Quality Assurance, who will soon vacate the site.
The inspector informed Kleinman that Regulatory' Operations will audit the new FPC QA functional organization and programs to insure continued compliance with 10 CFR 50, Appendix B.
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