IR 05000302/1973006
| ML19317G388 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/31/1973 |
| From: | Crossman W, Vallish E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19317G377 | List: |
| References | |
| 50-302-73-06, 50-302-73-6, NUDOCS 8003030798 | |
| Download: ML19317G388 (11) | |
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UNITED STATES
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DIRECTORATE OF REGULATORY OPERATIONS i
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REoioN n - suite eis 230 P E ACHT R E E ST R E ET, NORT H, EST
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RO Inspection Report No. 50-302/73-6 Licensee:
Florida Power Corporation
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320134th Street South P. O. Box 14042 St. Petersburg, Florida 33733 Facility Name: Crystal River 3 Docket No.:
50-302 License No. :
CPPR-51 Category:
A2 Location:
Crystal River, Florida Type of License B&W, PWR, 2452 Mwt
Type cf Inspection: Routine, Unannounced, Construction Dates of Inspection: July 10-13, 1973
Inspector in Charge:
T. E. Conlon, Reactor Inspector Engineering Section i
Facilities Construction Branch Accompanying Inspectors: None Other Accompanying Personnel:
J. C. Bryant, Senior Inspector Engineering Section
/cilities Construction Branch F
Principal Inspector:
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b 3 6~- 7 I E..U Vallish, Reactor Inspector Date Facilities Section Facili ies Construction Branch b-b_
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~ 7-3/-73 Reviewed By:
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W. A. qt'o'ssman, Senior 16spector Date
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Facilities Section
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Facilities Construction Branch 80030307 (
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RO'Rpt. No. 50-302/73-6-2-r SUNfARY OF FINDINGS
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I.
Enforcement Action
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A.
Violations None B.
Safety Items None II.
Licensee Action on Previously Identified Enforcement Matters A.
Violations 73-1/Al Decay Heat and Makeup and Purifications Systems Welding Welding performed was not in accordance with the qualified welding procedure. This item remains open.
73-1/A2 Decay Heat and Makeup and Purification Systems Radiography Radiography of welds was not in accordance with the pre-
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scribed procedure. This item remains open.
B.
Safety Items None
III. New Unresolved Items
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None
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IV.
Status of Previously Reported Unresolved Items
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73-5/1 Weld Material control The licensee altered the main warehouse storage area to
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ensure adequate separation and storage of weld rod
material. This item is closed. '(Details I, paragraoh 2)
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B0 Rpt. No. 50-302/73-6-3-73-5/2 Safety Valve Piping
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Assurance is required that saf[ty valve piping design criteria did include dynamic force reactions. This item remains ~open.
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73-5/3 Control Rod Drive Motor Tube Extension Discontinuities
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Verification of acceptance criteria and determination if any thin wall tubes are to be installed is required.
This item remains open.
73-5/4 Limitorque Valve Operator Failures Modification of certain models of Limitorque valve operators
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installed in safety related systems is to be accomplished.
i This item remains open.
73-5/5 Control Rod Drive (CRD) Undewoltage Trip Assembly Deficiency Deficiencies in design or manufacture of these trip assemblies resulted in a generic problem requiring subcontractor action for resolution. This item remains open.
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73-5/7 Differential Pressure (D/P) Cell Survey
The licensee has completed a survey for the use of certain models of DP cells with a history of maloperation and states that these models are not used at this facility.
This item is closed.
(Details I, paragraph 3)
73-5/9 Paddle-Type Flow Switches The applicant is determining if any of these type switches are installed in' adverse environments. This item remains
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i 73-5/12 FPC Audit of B&W The applicant directed an audit of the NSSS supplier and the report will be reviewed later. This item is open.
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RO Rpt. No. 50-302/73-6-4-73-5/14 Reactor Internals Modification.
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Modification to these internalsi'is being accomplished in the vendor shops prier to delivery to the site. This
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item remains open.
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73-5/15 Quality Assurance Audits The licensee agreed that quality assyrance audits should be closed promptly and will investigate and rectify the t
situation as to their delinquency. This item remains
open.
73-5/16 Cable Installation
A potential problem of space and circuit separation exists in the cable spreading area. The licensee agreed
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to make a detailed analysis of space needs and make an evaluation of the present capabilities of the spreading room and slot layout. This item remains open.
72-3/5 Procedures for Final Inspection cf Piping There has oeen no change in status. This item remains open.
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72-5/3 Valve Wall Thickness Requirements
There has been no change. in status. This item remains open.
73-1/2 Suspect Lack of Material control - Weld Filler Material
B&W Topical Reports BAW-1402 and BAW-1403 have been reviewed for adequacy by AEC Headquarters and it was determined that those major components involved are acceptable for their
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intended service. This item is closed (Ref: letter dated June 19, 1973, from AEC, Engelken, to B&W,. Mallay, Licensing
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Manager).
73-3/1 Radiography of Piping The licensee is reviewing M. W. Kellogg's radiographic procedure and evaluating their, radiographs with regard to the primary usage of film side penetrameters. This item 4 remains open.
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,RO Rp't. No. 50-302/73-6-5-i V.
Design Changes
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None
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_VI. Unusual Occurrences -
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None
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VII. Other Significant Findings A.
Project Status l
No significant reportable changes.
B.
Personnel Changes i
No significant changes observed.
VIII. Management Interview The attendees of the management interview included the following:
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Florida Power Corporation (FPC)
H. L. Bennett - Director, Generation Construction D. W. Pedrick - Quality Engineer Babcock and Wilcox Construction Company (BWCC)
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L. M. Watson - Project Manager T. J. Richardson - Project Engineer Discussion The scope of inspection was outlined and the inrpector informed the attendees that within the areas examined for Class I components, no deficiencies or violations were identified.
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RO Rpt. No. 50-302/73-6 I-1
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DETAILS I Prepared b &
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7 77 T. E. Conlon, Reactor Inspector
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Engineeririg Section-Facilities Construction Branch
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Dates of Inspect n:
uly 10-13, 1973
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7/73 Reviewed by?
J. C. Bryant, Senior Inspector Date Engineering Section Facilities Construction Branch
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Persons Contacted j
Florida Power Corporation (FPC)
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D. W. Pedrick - QA Engineer 2.
Weld Material Control The licensee informed the inspector that provisions had been made for physical separation of acceptable welding material from nonacceptable material.
A visual inspection of the main warehouse storage area revealed a wire cage with locked entry for acceptable welding material.
Nonacceptable material is stored in the warehouse with " HOLD" tags attached.
The acceptable welding material is withdrawn from the cage as required to supply the central issue station.
The inspector had no further questione and the item is closed.
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Differential Pressure Cell Survey
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The licensee was requested to conduct a survey for the possible
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use of Barton D/P cells models 368, 384 and 386 in safety related
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systems. The licensee informed the inspector that the above-listed models utilize a strain gage sensing element and will not be used at Crystal River Unit No. 3.
However, a Barton model 224 bellows type
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will be used. The inspector had no further questions and the item is closed.
4.
Reactor Vessel (RV)
The Babcock and Wilcox Construction Company- (BWCC) installed the react;or vessel in accordance with field construction procedure (FCP)
- 007, Revision 3, entitled " Erection 'of Reactor Vessel."
This procedure is a 32-step sequence for moving the reactor vessel from storage to final positioning on the soleplate inside the containment building.
The leveling and alignment of the RV was in accordance with BWCC
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RO Rpt". No. 50-302/73-6 I-2 procedure #012,' Revision 1.
This procedure required the RV principal-centerline to be level within 0.125 inch of true position and the
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final documented deviation was less than.093 inch.
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At the present time, the RV holddown studs have been made wrench
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tight; however, final tensioning of the studs will be done in accordance with FPC construction procedure W43, Revision 2, dated February 26, 1973.
This procedure will require eight SR-4 strain gages to be placed on predetermined studs and the readings from these strain gages will be used to verify accuracy of the stress-strain load curves.
All studs, including those with strain gages attached, will be tensioned and then measured with a calibrated, direct reading dial indicator.
Final acceptance of tensioning will be based on elongation as measured by the dial indicator.
In-place inspection of the RV is done every 30 days.
The inspection is limited to visual observation for cleanliness, surface damage and to see that all nozzles are properly covered.
Within the above areas, there wera no deficiencies or violations identified.
5.
Other Class I components The inspector reviewed the documentation for receipt inspection and storage of the following components:
a.
Reactor Coolant Pumps These pumps were supplied by Byron Jackson under purchase order
- 80215Z and in accordance with B&W specifications CS-3-9 and
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CS-3-36.
Both of these documents were available at the site.
Additional records were available for pump internals. (shaft, impeller and cover) and casings such as:
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(1) Certification of compliance.
(2) Certification of chemical and physical properties.
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(3) Heat treatment.
(4) Radiography reports.
(5) Certification of cleanliness.
Monthly inspection sheets were in the file and dated for each
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month since-initial. receipt inspection.
b.
HP and LP Injection Pumps The HP injection pumps were purchased from Bingham Pump s
Company under purchase order #81549LW and the LP injection
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RO Rpt. No.- 50-302/73-6 I-3 pumps were purchased from Worthington Corporation under purchase order 81551LW. Both purchase orders invoke B&W specifications CS-3-30 for pump end and CS-3-34 for motor end.
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The above documents were at the site and available for review.
Additienal records in the file included:
(1) Quality release from B&W.
(2) Mill certifications and associated heat numbers for impe11ers, shafts and casings.
(3) Vendor's certificate of cleanliness.
(4) Vendor's manuals.
(5) Receipt inspection data.
Both the HP and LP injection pumps are stored in enclosed warehouses.
The motor ends have strip heaters for moisture control and the monthly G
inspection sheets indicate that hand rotation is performed every month.
c.
Pressurizer Relief Valves A total of four valves were purchased from Dresser Industries under purchase order #81395LS.
This included two safety valves, one power actuated relief valve and one relief isolation valve.
The safety valves were furnished in accordance with B&W specification CS-3-28 and the power actuated relief valve to B&W specification CS-3-79.
The above documents were at the site and available for review.
The licensee's files contained the folJowing additional records:
(1) Vendor's certificate of compliance.
(2) Mill certifications and heat numbers.
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(3) Initial receipt inspection.
At the present time, the valves are in wooden boxes and stored in a BWCC warehouse.
Periodic storage inspection is done every month and consists of a visual inspection for external damage.
- Insta11ation and post-installation inspection criteria are q
contained in BWCC procedure FS-III-9.
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'R0 Rpt'. No. 50-302/73-6 I-4
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Letdown Coolers
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The inspector reviewed the purchase order-and B&W specification
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for the letdown coolers. The file also contained:
(1) Vendor certificate of compliance.
(2) Mill certifications for shell and tubes.
(3) Radiography reports.
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(4) Certificate of cleanliness.
Within the above areas, there were no deficiencies or violations identified.
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