IR 05000302/1974007
| ML19319C992 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/29/1974 |
| From: | Bryant J, Vallish E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19319C972 | List: |
| References | |
| 50-302-74-07, 50-302-74-7, NUDOCS 8003040922 | |
| Download: ML19319C992 (12) | |
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Florida Power Corporation AUG.2 1974.
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50-302/74-7
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Letter from Florida Power Corporation from JTRodgers
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dated July 24, 1974
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Distribution:
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H'."D. Thornburg, RO AO:HQ,(4)
Directorate of Licensing (4)
DR Central Files PDR Local PDR s
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ATOMIC ENERGY COMMISSION
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DriG:?HATM W ;EGULATORY OPERATIGE
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RO Inspection Report No. 50-302/74-7
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Licensee: Florida Power Corporation 3201 34th Street South
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P. O. Box 14042
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St. Petersburg, Florida 33733
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Facility Name: Crystal River 3
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Docket No.:
50-302 License No.:
CPPR-51
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Category:
A3/B1 Location: Crystal River, Florida
Type of License: B&W, PWR, 2452 Mwt, 855 Mwe Type of Insp.ection: Routine, Unannounced. Construction
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Dates of Inspection: April 29 - May 3, 1974 Dates of Previous Inspection: March 12-15, 1974 Principal Inspector:
E. J. Vallish, Reactor Inspector Facilities Section Facilities Construction Branch Accompanying Inspectors:
F. U. Bower, Reactor Inspector Engineering Section Facilities Construction Branch T. E. Conlon, Reactor Inspector Engineering Section r
Facilities Construction Branch Other Accompanying Personnel: None Principal Inspector:
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A.'J. Val.Msh,ReactovInspector Date d acilities Section
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F cilities Construction Branch
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Reviewed By:
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J. C 4Bryant, Senior Inspector D,3ce
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Faciiities Section
/f Facilities Construction Branch E
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RO Rpt. No. 50-302/74-7-2-p
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SUMMARY OF FINDINGS
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Enforcement Action i
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Violations
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I, None-
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Safety Items
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II.
Licensee Actf on on Previously Identified Enforcement Matters
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Violations
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i None
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Safety Items
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None t
III. New Unresolved Items 74-7/1 Revisions to Specific Heat Curve for UO2 Fuel (50.55(e))
FPC had been notified by the B&W Company that certain revisions were required in the specific heat curve for UO2 fuel as used in some of their transient-computer codes. FPC considered this a significant deficiency and reported it as required by 10 CFR 50.55(e).
The B&W reanalyses will have generic implications and is being followed by Licensing to conclusion.
This item is considered closed from Region II's inspect. ion efforts.
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l 74-7/2 Containment Building Dome Concrete (10 CFR 50.55(e))
Early results of concrete cylinder tests indicated low strength. FPC will report as required by 10 CFR 50.55(e).
This item-is open.
(Details III, paragraph 7)
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RO'Rpt. No. 50-302/74-7
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IV.
Status of Previously Reported Unresolved Items
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i 73-13/2 Cabinet Wiring Channel Separation
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I The rework program has been completed and the inspection
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procedure amended to include this activity as an inspection
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point for all reviewing work. This item is closed.
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(Details I, paragraph 4),
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73-5/3. Valve Wall Thickness verification (Details III, paragraph 4)
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Thickness measurements were not made of valve bonnet $,
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cover plates or nozzles adjacent to the weldend preparation. This item remains open.
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b.
The engineering evaluation of the valve's thin walls
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was not acceptable.
FPC stated the valves would be l
repaired by welding to meet the requirements of the
original purchase order.
This item remains open.
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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.
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This item remains open.
73-5/14 Reactor Internals Modification Modification of the internals is being accomplished in the vendor shops and verification will be made after the
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internals are delivered to the site.
This item remains open.
(Details III, paragraph 5)
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Design Changes s
None VI.
Unusual Occurrences None
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RO Rpt. No. 50-302/74-7-4-
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VII. Other Significant Findings None
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VIII. Management Interview
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A management interview was held and the scope and results o5 the
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inspection were discussed with E. E. Froats, Manager, Site Surveillance (Nuclear), and others of the staff. They were inforn:ed that there
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were no new enforcement or unresolved items resulting from this inspection.
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RO Rpt. No. 50-302/74-7 I-l
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DETAILS 1 Prepared by:
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F. U. Bower, Reactor Inspector Date Engineering Section Facilities Construction Branch
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29 - May 3, 1974
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l Reviewed by:
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B. J.
'ran, Acting Senior
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Ins tor
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Engineering Section Facilities Construction Branch
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Persons Contacted
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Florida Power Corporation (FPC)
R. Slater. - Quality Engineer
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R. Bonner - Electrica". Engineer
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O J. Hobbs - Electrical-Mechanical Superintendent A. Gomez - Electrical Control Systems Manager
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2.
Electrical / Instrumentation (E/I) Progress The construction sequence of the project has caused delays for the E/I portion of the work in the reactor and intermediate buildings.
This delay has resulted in much of the E/I work in other areas to be far advanced toward ccepletion while the E/I work is just now commencing in the reactor areas. Due to this condition, the RO inspection program has not beca completed, nor will it be until appreciable progress on the safety system in the aforenentioned regions is shown.
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The E/I work is reported to be 79% complete on a project basis,
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cable pulling is 65% complete and conductor termination stands at 59%. Work is continuing with the same average craft work force of 240 electricians working a standard week.
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No special problems were reported and none are anticipated that will inhibit progress in the foreseeable future.
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Licensing Operations (LO) Personnel Field Trip The LO personnel were supported by the RO inspector during their field activities at the site.
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R0 Rpt. No. 50-302/74-7 I-2
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The LO electrical engineer examined several of the installed
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specific requirements and guidelines set forth in licensing
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documents.
Several questions of a general nature were generated
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by the L0 personnel which were discussed in depth with the licensee's
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stafi. All items impinging on the licensing activity were dealt
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with in a manner acceptable to the LO group.
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I No RO action items were generated during this phase of the inspection.
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4.
Cabinet Wiring Channel Inspection (73-13/2)
Inspection documentation and corrected wiring were examined for One several cabinets id,entified as problem areas. The work has been completed as required by the rework procedures. No deficiencies were identified.
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In addition to the foregoing, the QC inspection point program for such installations has been revised to add a requirement that assures such features will be specifically inspected for continuing work.
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There are no further questions and this itert is closed.
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R0 Rpt. No. 50-302/74-7 II-l-
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DETAILS II Prepared By:
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T. E. Conlon, Reactor Inspector
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Engineering Section Facilities Construction Branch
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Dates of Inspection:
il 29 -
3, 1974 s
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Reviewed By:
'A L// h 6 7/,
B.f.Cyran,ActingSenior
/ Da(e Inspector, Engineering Section
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Facilities Constructi.on Branch 1.
Persons Contacted
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Florida Power Corporation (FPC)
C. E Jackson - Construction Superintendent
E. E. Fronts - Manager Site Surveillance (Nuclear)
R. W. Slator - Quality Engineer L. R. We.de - !!cchanical Quality Engineer
J. C. Hobbs, Jr. - Superintendent Mechanical and Electrical Systems b.
Contractor Organizations
(1) Of.lbert Associates Incorporated (CAI)
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S. R. Buckingham - Site QA Coordinator (2) Babcock and Wilcox Construction Company (BWCC)
R. Shope - Site QA Representative r
j (3) J. A. Jones Construction Company (JAJ)
J. Amundson - Site QC Supervisor
'1 2.
Primary Coolant Piping A followup inspection was conducted on primary coolant piping with emphasis placed on post-weld heat treatment (PWHT). All
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of the 22 field weld joints for the 28 and 36-inch piping have
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RO Rpt. No. 50-302/74-7 II-2
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been completed. Of the 22 field joints, 8 of them are stainless steel and do not require PWHT.
The remaining 14 joints will be PWHT in accordance with BWCC procedure 9W-602N and sequence
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procedure BW-071. Procedure 9W-602N is of a general nature
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while procedure BW-071 is quite specific in the following areas:
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Number of thermocouples
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Location of thermocouples
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Method of attaching thermocouples
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Temperature and tolerance per thermocouple In addition to the automatic temperature recorder, a BWCC QC inspector
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i logs the temperature of each thermocouple every 30 minutes. The
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inspector examined the log sheets for 3 joints and found them complete.
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I The inspector examined the QC data packages for the 8 stainless
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joints and each package contained:
Signed copy of secuence procedure BW-045 for each joint a.
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Weld matetial issue slips
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Repair instructions i
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Weld control data sheet FPC and BWCC radiographic reports e.
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Within the areas examined, there were no deficiencies or violations identified.
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Main Steam Piping
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Welding The inspectcr performed a followup examination of field welding
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on main steam and feedwater lines inside the containment building.
A number of finished field welds were examined for veld contour,
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RO Rpt. No. 50-302/74-7-II-3
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reinforcement, undercut and arc. strikes. The visual examination
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revealed no deficiencies.
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In order to check on the completeness of QC documentation, two
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field weld joints, Nos. 21MS and 20FW, were selected for examina-
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tion of the documentation in JAJ files which consisted of the following:
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(1) Field weld data sheet
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(2) Weld rod issue slips
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(3) Issue slip.s for consumable inserts (4) Stress relief charts
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(5) NDI reports Within the areas examined, there were no deficiencies or violations identified.
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Hangers, Supports and Restraints The inspector made a-followup examination on the implementation of FPC field procedure Q-23, entitled, " Inspection of Piping Support Assemblies," and Q-35, entitled, " Inspection of Piping j
Support Locations." The QC documentation on file was in agreement with the requirements of the above listed procedures.
The final. QC documentation consists of a log sheet with initials and dates for the nine areas of inspection. However, if deficiencies are found then a " Hanger Checklist" is issued identifying the condition and issued to the craf ts for correction.
After correction and signoff by the craf t foraman, a reinspection is made for verification and the log sheet is, then signed off r
by the JAJ QC inspector.
In the current procedures there is no j
requirement to retain the hanger checklist as documentary j
j evidence of deficiency correction. Upon inquiry by the inspector
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concerning retention of these daecklists, the licensee stated
that the procedure would be revised to require retention of the subject checklists.
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Within the areas examined, there were.no deficiencies or violations
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identified.
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V RO Rpt. No. 50-302/74-7 III-1
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[-M/~Y DETAILS III Prepared by:
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Date E. 7/ fallish, Reactor Inspector Facilities Section Facilities Construction Branch
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Dates ot Inspection:
April 29 - May 3, 1974 d!St/79 Reviewed by:
['.1md I
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J JC. Brfan27 Senior Inspector y
Edcilities Section
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Facilities Construction Branch
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1.
Persons Contacted Florida Power Corporatim (FPd a.
C. E. Jackson - Construction Superintendent E. E. Froats - Manager, Site Surveillance (Nuclear)
R. W. Slater - Quality Engineer
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Contractor Organizations J. A. Jones Construction Company (JAJ)
J. R. Amundson - Site Quality Control Supervisor
2.
Defective Hydraulic Shock Suppressors and Restraints (ROB No. 73-4)
A particular brand of hydraulic shock suppressors and restraints exhibited generic failures in use. Inspection of File 15.4.11 documentation in the field indicates that none of this make of unit is to be used at Crystal River 3.
Appropriate action was taken to preclude a similar occurrence in the shock suppressors and restraints being used. The schedule for future inspections of these units was examined and no deficiencies were indicated. This item is closed.
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Malfunction of Safety Related Westinghouse W-2 Switches ~ (ROB No. 74-6)
Westinghouse Nuclear Services Division has prepared a technical
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bullatin regardi tg the W-2 switch malfunction. This bulletin is
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ideatified as NSD-TB-73-26. Documentati.on was examined at the site which confirmed the fact that no W-2 type switches were used, or
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will be usec. iri the safety related systems at Crystal River 3.
This
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item is closed.
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RO Rot. No. 50-302/74-7 III-2
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4.
Valve Wall Thickness Requirements (73-5/3)
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Statua of the valve wall thickness measurement program was discussed with the JAJ site quality control supervisor, and a copy of the
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compilation of data was obtained for information and detailed review by the Engineering Section of th'e Region II Facilities Construction r
Branch.
There is no change in the status of. dtis item pending review of the aforementioned data.
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5.
Reactor Internals Modification (73-5/14)
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A report of the audit of Babcock and Wilcox Company, (B&W), Barberton,-
Ohio, shops was reviewed.
This audit was conducted by W. G. Warnick, Project Manager of Nuclear and Industrial Systems, of the GE Apollo and Ground Systems Company, which serves under contract to FPC for quality assurance functions. The audit concerned the status of 'the
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reactor system interum1.s modifications records and the backup records, concerning the internals, which will not be part of dae vendor's package, but will be retained for record by B&W.
There is no change in the status of this item, and it remaAns open.
6.
Reactor Building Tendons g
Inspection was conducted of the buttonheading operation on the hocp tendon wires. A go-no-go gage was used to qualify the size of the buttonhead. Visual inspection with optical aids revealed no cracks exceeding specifications on the heads during the upsetting operation.
Dies used were accurate and smooth, resulting in proper shoulder Contours.
The start of pulling of the dome tendons into the structure commenced on schedule, May 1, 1974.
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Containment Building Dome Concrete (10 CFR 50.55(e)) (74-7/2)
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Early results of concrete test cylinder compression breaks, indicapa low strength of a 160 cubic yard annulus of the containment buildiu
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dome.
FPC considered this reportable under the requirements of 10 CFR 50.55(e).
FPC notified the AEC and will submit a full report after the 28-day cylinders are tested and the architect-engineer
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analyzes the results.
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Letter to Florida Power Corporation from N. C. Moseley dated JUN 3 81974 50-302/74-7
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DISTRIBUTION:
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H. D. Thornburg, RO
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Directorate of Licensing (4)
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DR Central Files
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cc encl. only:
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- PDR
- Local PDR
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- NSIC
- DTIE, OR
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- State
- To be dispatched at a later date.
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