IR 05000302/1973002
| ML19319C871 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/13/1973 |
| From: | Crossman W, Vallish E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19319C858 | List: |
| References | |
| 50-302-73-02, 50-302-73-2, NUDOCS 8003040829 | |
| Download: ML19319C871 (11) | |
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UNITED STATES ATOMIC ENERGY COMMISSION
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e-DIRECTORATE OF REGULATORY OPERATIONS
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AT L. A N T A. GEORGI A 30303 RO Inspection Report No. 50-302/73-2 Licensee: Florida Power Corporation 3201 34th Street South P. O. Box 14042 St. Petersburg, Florida 33733 FaciJity Name: Crystal River Unit 3 Docket No.:
50-302 Licanse No.:
CPPR-51 Lccation: Crystal River, Florida Type of License: B&W FWR; 2425 Mwt
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Type of Inspection: Routine, Unannounced D.ates of Inspection: March 13-16, 1973 Dates of Previous Inspection: January 23-25, 1973 Inspector-in-Charge:
T. E. Conlon, Reactor Ins; ctor Engineering Section Facilities Construction Branch Acu.mpanying Inspector:
D. H. Danielson, Reactor Inspector Facflities Section Facilities Construction Branch Other Accompanying Perso g :
e Principal Inspector:
k-f-73 E. f. Vallish, Reactor Inspector Date Facilities Section, Facilities Construction Branch
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Reviewed by:
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W. A. Crossman, Acting Senior Inspector, Facilities Date Section, Facilities Construction Branch
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RO Rpt. No. 50-302/73-2-2-SUMMARY OF FINDINGS I.
Enforcement Action A.
Violations None
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B.
Safety Items
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None
II.
Licensee Action On Previously Identified Enforcement Matters A.
Violations 73-1-Al Decay Heat and Makeup and Purification Systems Welding Contrary to Criterion IX of Appendix B to 10 CFR 50, welding performed on the makeup and purification system was not in accordance with the qualified welding procedure, SS-1-TIG, in that larger diameter filler metal than that prescribed was in use.
This item remains open.
73-1-A2 Decay Heat and Makeup and Purification Systems Radiographs
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Contrary to Criterion IX of Appendix B to 10 CFR 50, radiography of welds on the decay heat removal system
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were not in accordance with the prescribed Pitt'sburgh Testing Laboratory procedure (PTL Q-7, paragraph 4.6)
i concerning placement of penetrameters.
This item remains open.
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B.
Safety Items
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i None III.
New Unresolved Items None j
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RO Rpt. No. 50-302/73-2-3-
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IV.
Status of Previously Reported Unresolved Items 73-1/1 Missing Radiographs
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Radiographs for the final acceptance of weld 42-DH could not be located. This item remains open.
73-1/2 Lack of Material Control - Weld Filler Material
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The licensee has received notification from the Babcock and Wilcox Company (B&W) that steam generators contain unqualified weld filler material.
This item remains open.
72-5/1 Radiographs / Code Case 7'
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The senaitivity level and penetrameter thickness used in M. W. Kellogg's radiograph procedure is in accordance with USAS B31.7, Code Case 72.
The item to be resolved is the acceptability of the deviation in sensitivity and penetrameter require-i ments for that code case. This item remains open.
72-5/3 Valve Wall Thichness Requirements Verification of valve wall thickness to meet construction requirements. This item remains open.
72-3/5 Procedures for Final Inspection of Piping Develop procedures for the final inspection of piping installation prior to hydrotest and insulating.
This item remains open.
71-5/5 Cleanliness Proced'res for Piping and Compo*2ents a
Develop procedures for internal and externhi cleanliness of stainless steel valves, piping and components. This item remains open.
V.
Design Changes None VI.
Unusual Occurrences None
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Ro Rpt.~No. 50-302/73-2-4-
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VII.
Other Significant Findings =
A.
Project Status A licenses representative reported' construction was considered 68% complete as of March 1, 1973.
B.
Personnel or Organization Changes t
There were no reportable personnel or_ organizational changes identified.
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C.
Inquiry Reports There were no inquiry reports to be considered.
I VIII.
Management Interview The scope and results of this inspection were discussed with H. L. Bennett, Director, Generation Construction, C. E. Jackson, Construction Superintendent, E. E. Froats, Supervisor, Quality and Standards, D. W. Pedrick, Supervisor, Quality Surveillance, and other members of the plant staff.
The areas inspected were pertinent to the reactor coolant pressure boundary piping and included: (1) the quality control system related to welding and welding material control; (2) verification that the licensee-contractor is meeting the construction requirements for QC inspection; (3) implementa-tion of the quality assurance program; and (4) the quality control system relating to shipping, receipt inspection, storage, and issue of these permanent construction items.
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There were no enforcement matters identified.
The inspector observed that the weldor's name and identifying number did not appear on the field weld control record form used for welding in progress. The licensee stated that current procedures did not require this information to be filled in until the weld was complete. However, the licensee agreed to
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revise the procedure and immediately implement the requirement that all weldors sign their name'and identifying number prior to start of welding for each joint.
t The inspector inquired about the lack of indicating' lights on portable ovens used for weld rod storage. The licensee stated
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that this would be looked into.
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RO Report No. 50-302/73-2 I-1
DETAILS I Prepared By:
S/75 i
i T. E. Conlon, Reactor
' Ddte Inspector, Engineering
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i Section, Facilities
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Construction Branch Dates of Inspection: March 13-16, 1973
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Reviewed By:
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C. BrystW, Senior.
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Inspector, Engineering Section, Facilities Construction Branch
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Persons Contacted Florida Power Corporation (FPC)
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C. E. Jackson - Construction Superintendent D. W. Pedrick - Supervisor, Quality Surveillance b.
Contractor Organizations
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Babcox and Wilcox Construction Company (BWCC)
J. R. McGill - Supervisor, Quality Control 2.
Reactor Coolant Pressure Boundary Piping (RCPB)
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Organization Installation and field welding of the reactor coolant pressure boundary piping will involve two organizations.
The division of RCPB piping between. the two organizations is as follows:
(1) Babcox and Wilcox Construction Company (BWCC)
i (a) Reactor Coolant Piping (all)
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(b) Decay Heat (inside reactor building)
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RO Rpt.'No. 50-302/73-2 I-2
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(c) Makeup and Purification (inside reactor building)-
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i (d) Core Flood (specific portions)
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(2) J. A. Jones Construction Company (JAJ)
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(a) Main Steam and Feedwater j
(b) Balance of all other RCPB piping i
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b.
Welding i
(1) Review of Quality Control System The inspector performed a review of the following documentation
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as verification that quality control procedures, work procedures, and record keeping requirements have been established for the Welding program by FPC, BWCC, and JAJ.
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(a) FPC - QCP 5.1.1.2, " Liquid Penetrant Inspection"
(b) FPC - QCP 5.1.1.4, " Radiographic Inspection" (c) FPC - QCP 5.1.1.3, " Magnetic Particle Inspection"
(d) FPC - QCP 8.1.1.1, " Inspection of. Quality Characteristics j
and Record Requirements" (e) FPC - QCP 9.1.1.1, "Nonconformance Reporting and Implementation of Corrective Action" (f) FPC - W14, " Field Weld Data Sheet"
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(g) FPC - W21, " Withdrawal and Handling of Weld Rod" (h) FPC - W41, " Procedure for Weld Repair" (1) BWCC - 9A-120," Qualification of Weldors and Welding i
Operators" (j) BWCC - 9A-158, " Storage Handling and Issuing of Welding Materials" i '
(k) BWCC - 9A-140, " Procedure for Completing Weld Control Record Forms"
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RO Rpt. No. 50-302/73-2 I-3 (1) BWCC - 9T-102A, " Radiographic Methods and Acceptance Standards" (m) BWCC - 9T-102F, " Magnetic Particle Inspection and Acceptance Standards" (n) BWCC - 9A-167, 9A-168, 9A-169, and 9A-170, " Nondestructive Testing Personnel Qualifications" (o) BWCC - 9T-102H, " Liquid Penetrant Inspection and Acceptance Standards" (p) JAJ - W4, " Receiving, Storage, and Issuing" There were no deficiencies or violations identified in this area.
(2) Followup Record Review Several field welds were selected from the decay heat, core
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flood and makeup and purification systems for record review in order to test and verify the implementation of the quality control system. The following weld joints were selected:
(a) Makeup and Purification System Joint Nos. 416, 417, and 442 (b) Core Flood System Joint Nos.17,18, and 19 (c) Decay Heat System Joint Nos.174 and 175
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Records for these joints are filed by joint number and each record folder contained a field weld data sheet, weld control record form, weld rod issue slip, NDT results and material certificacions for consumable inserts and weld rod.
Thcre were no deficiencies or violations identified in this area.
(3) Followup Observations of Work Welding of the large diameter primary coolant loop piping is presently scheduled to commence on or about May 1973.
Therefore, observation of work performance was limited to welding currently
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underway on the decay heat (DH) system.
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RO Rpt. No. 50-302/73-2L I-4
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l The inspector observed welding in progress on two DE piping
joints. Both joints were being welded by the manual gas
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tungsten are method.
Field weld control record forms and weld data sheets were available and enclosed in plastic jackets. All forms were properly filled out except for.
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the weldor's name and identifying number. Each weldor had only one type of weld rod in his possession and the rod was identifiable.
The QC portion of the weld control record form contained sufficient line items and corresponding
signoffs for inspection results.
t The inspector acknowledged that existing procedures did not require the weldot's name and identifying number to be added to the field weld control record form until completion of the weld.
In view of the foregoing, the inspector asked j
the licensee about the possibility of more than one weldor performing work on the same joint, but only one name and
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j identifying number appearing on the completed weld control record form. The licensee stated that this would be possible under the present method of documentation.
After further discussion, the licensee agreed to revise the procedure and
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immediately implement the requirement that all weldors sign their name and identifying number prior to start of welding for each joint.
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There were no deficiencies or violations identified in this area.
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(4) Welding Material control
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The inspector performed a walk-through inspection of JAJ and BWCC weld rod storage areas. BWCC draws its weld rod from JAJ in large quantities for use on systems other than the primary loop. Weld material for the primary loop will be
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furnished and controlled by BWCC.
The inspector did not i
observe any open cans of coated electrodes and all electrodes were stored up off the floor.
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Ovens were maintained between 150 and 3000F and each oven contained only one type and size of electrode. Portable
ovens are not equipped with indicator lights; therefore, it is necessary to lif t each cover to determine if the oven l
1s plugged in.
The licensee stated that he would look into the possibility of installing indicating lights.
Issue
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slips were being used and duplicate copies were maintained
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in the storage areas.
s There were no deficiencies or violations identified in this area.
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R0 Rpt. No. 50-302/73-2 II-1 y
DETAILS II Prepared by:
tatt/ V M M '/$
D. H. Danielson D4td Reactor Inspector Facilities Section Facilities Construction Branch Dates of Inspection: March 13-16, 1973 Reviewed by: N#32[e Y-N 73 W. A. Crossman Date Acting Senior Inspector Facilities Section Facilities Construction Branch 1.
Individuals Contacted a.
Florida Power Corporation (FPC)
O C. E. Jackson - Construction Superintendent D. W. Pedrick - Supervisor, Quality Surveillance b.
Babcock and Wilcox Construction Company (B&W)
J. McGill - Supervisor, Quality Control
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2.
Documents Examined a.
FSAR - Section 1, " Introduction and Summary"
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FPC Quality Organization, Rev. 7 of March 15, 1973 d.
FPC Quality Program - Lines of Responsibility, Figure 1-22 e.
B&W Receipt Inspection and Procedure For Tagging - Quality Control Specification No. 9A-107-1 f.
B&W Procedure for Handling Nonconformities - Quality Control Specification No. 9A-112
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B&W Storage Requirements - Quality Control Specification No. 9A-117
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RO Rpt. No. 50-302/73-2 II-2 G
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B&W Materials Control - Quality Control Specification No. 9A-117-1 1.
Responsibilities of the B&W Construction Company to the Authorized Inspector - Quality Control Specification No.
9A-176 i
j. B&W Handling of Field Construction Procedures - Quality Control Specification No. 9A-178 3.
Quality Assurance Program
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l Review of the applicable documents listed in paragraph 2 above, as they pertain to the licensee-contractor line and quality control organizations for reactor coolant pressure boundary piping, identified no deficiencies and indicated FPC's intent to meet the requirements of Appendix B of 10 CFR 50. The site and QC organization meet the intent of Criteria I and X and the organizational / functional alignment for the surveillance of the QA/QC agency meet the intent of Criteria I and IVIII, 4.
Quality control System Review of the quality control specifications listed in paragraph 2 above, as they pertain to the reactor coolant pressure boundary piping, identified no deficiencies and indicated FPC's intent to meet the requirements of Appendix B of 10 CFR 50 for shipping, receipt inspection, storage and issue. Areas observed for shipping and receipt inspection were marking and identification, protective coating, closures and packaging, cleanliness at time of receipt, and handling of nonconforming material. Areas observed that are pertinent to storage and issue were identification and control, and protection.
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APR 171973
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Ltr to Florida Power Corporation dtd APR 171973 cc v/ enc 1:
J. B. Henderson, R0 RO:HQ (4)
Directorate of Licensing (h)
DR Central Files cc v/o enc 1:
PDR Local PDR NSIC IYfIE, OR State
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