IR 05000302/1974001
| ML19319D071 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 01/23/1974 |
| From: | Crossman W, Vallish E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19319D066 | List: |
| References | |
| 50-302-74-01, 50-302-74-1, NUDOCS 8003041005 | |
| Download: ML19319D071 (8) | |
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UNITED STATES i
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ATOMIC ENERGY COMMISSION
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DIRECTORATE OF REGULATORY OPERATIONS l
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REcson is - suit E eis
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230 PE AC HT M E E ST R ECT. NORT HwE ST Ud.rgg O'
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RO Inspection Report No. 50-302/74-1
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Licensee:
Florida Power Corporation
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3201 34th Street South P. O. Box 14042
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St. Petersburg, Florida 33733
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Facility Name: Crystal River 3 Docket No.:
50-302
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License No.:
CPPR-51 Category:
A3/B1 Location:
Crystal River, Florida
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Type of License: B&W, PWR, 2560 Mwt, 885 Mwe
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Type of Inspection: Routine, Unannounced, Construction T
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Dates of Inspection: January 8-11, 1974 Dates of Previous In% tetion: Decenber 10-14, 1973 Inspector-in-Charge:
A. R. Herdt, Reactor Inspector Engineering Section, Facilities Construction Branch Accompanying Inspector: None Other Accompanying Personnel: None Principal Inspector:
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E. J. Vallish, Reactor Inspect 6t, Facilities Date
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Section, Facilities Construction Branch Reviewed by:
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W. A. Crossman, Senior Inspector, Facilities Section
' Date Facilities Construction Branch m
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RO Rpt. No. 50-302/74-1-2-O.
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SUMMARY OF FINDINGS
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Enforcement Action-
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Violations
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None l.
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Safety Items
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None
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II.
Licensee Action on Previously Identified Enforcement Matters l
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A.
Violations 73-1/A2 Decay Heat and Makeup and Purification Systems Radiography
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The licensee has fully identified the deficiencies in radio-
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graphic inspection. A corrective action program has been satisfactorily implemented. This item is closed. ' (Details I,
paragraph 2)
B.
Safety Items None III. New Unresolved Items 74-1/1 Nondestructive Testin's Reports The licensee agreed that nondestructive testing reports are reqtiired for specified code inspections and will investigate and rectify the situation as to their omission in the weld data quality package.
(Details I, paragraph Sa)
IV.
Status of Previously Reported Unresolved Items 73-13/1 Inadequate Wiring Devices
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The wiring gutters associated with control room entry ports 54A & 54B appear inadequate for the intended purpose.
This
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item remains open.
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73-13/2 Cabinet Wiring Channel separation
Redundant channel separation techniques for "in-cabinet" wiring appears-inadequate. This item remains open.
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-RO Rpt. No. 50-302/74-1-3-j
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73-11/1 Sea-Water Discharge Pipe Joints
The architect engineer has performed an engineering analysis
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on the design of these joints to determine if an omitted weld
bead will effect safety. This report is being reviewed for
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adequacy by the AEC.
This item remains open.
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73-5/2 Safety Valve Piping r
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The licensee has provided assurance that safety val e piping
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design criteria did include dynamic force reactions. This item is closed.
(Details I, paragraph 1)
i 73-5/3 Valve Wall Thickness Requirements
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In response to'the RO:II letters of June 30, 1972, and
February 16, 1973, the licensee has developed a valve wall thickness verification program. This item remains open',
73-5/14 Reactor Internals Modification
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Modification to these internals is being accomplished in the s
vendor shops prior to delivery to the site.
This item remains open.
V.
Design Changes
None VI.
Unusual Occurrences None VII. Other Significant Findings None VIII. Management Interview The inspectors met with H. L. Bennett, Director, Generation Construction, and others of the staff, and discussed the scope and results of the inspection s
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RO Rpt. No. 50-302//4-1 I-1
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- DETAILS I Prepared by:
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/h/[7pf A. R. Herdt, Metallurgical Engineer (Date Engineering Section, r.wiliM --
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Construction Branch Dates of Inspection: January 8-11, 1974
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Reviewed by:
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/ / [f f',r J. C. Bryant, Senior. Inspector Date
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Engineering Section, Facilities
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Construction Branch
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Persons Contacted
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Florida Power Corporation (FPC)
I H. L. Bennatt - Director Generation Construction C. E. Jackson - Construction Superintendent
R. W. Slater - Quality Engineer L. R. Wade - Mechanical Quality Engineer
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E. E. Froats - Manager Site-Surveillance (Nuclear)
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Contractor Organizations (1) Pittsburgh Testing Laboratory (PTL)
J. F. Artuso - Assistant to the President i
G. W. Martin - NDE General Supervisor (2) Babcock and Wilcox Construction Company (BWCC)
L. M. Watson - Site Manager R. Shope - Site QA Representative J. R. McGill - Quality Control Supervisor 2.
Decay Heat and Makeup and Purification System Radiography
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The inspector reviewed the action taken on this previous violation (73-1/A2). The licensee has fully identified the deficiencies in radiographic inspection. The licensee stated that the corrective action program previously described in R0 Report No. 50-302/73-7 has been fully implemented. The licensee is still requiring Gilbert Associates, Inc. to audit 25%.of PTL acceptable radiographs and FPC j
to review 100% of all completed radiographs from both PTL and BWCC.
l PTL is also performing its own internal audits. Also, radiographic
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procedure, PTL-Q-7, has been revised (Revision I, dated August 8, 1973)
to include detailed radiographic procedure techniques with essential O'
variables and shooting sketches. -Personnel qualification requirements and training programs are also included.
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RO Rpt. No. 50-302/74-1 I-2 J
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The inspector reviewed the following areas: (a)'the implementation'of the corrective action program including PTL. radiographs and field,
weld data sheets of decay heat and makeup and purification system
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welds mentioned,in_ paragraph 5; (b) PTL radiographic-shooting techniques;
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(c) radiographic procedure, PTL-Q-7 Revision I; (d) NDE personnel qualification records and documentation; (e) status of PTL radiographic.
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film review.
The inspector found no violations'or deficiencies during this review except in the area of personnel qualifications.
Documentation showing
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satisfactory passing of color vision requirements could not be produced.
PTL stated that these inspectors had satisfactorily passed the color
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vision requirements, but the doctor omitted the notation on-the appropriate medical form.
This discrepancy was immediately corrected.-
As of January 3,1974, the status of PTL's radiographic review is that j
eleven (11) welds still need to be reviewed and approximately 255 welds
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are in a repair status.
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Based on the satisfactory program implementation, which includes NDE and radiographic revisv/ performance, current performance and corrective
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quality assurance actions instituted by FPC, the inspector considers j
this item closed.
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3.
Ssfety Valve Piping In a letter to FPC dated December 14, 1973, Gilbert Associates, Inc. has assurred FPC that in the stress analysis of.the main steam safety valve header and associated escape piping, the dynamic force reactions were taken into account. The inspector reviewed this letter.
This item is
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closed.
4.
Reactor Pressure Boundary Piping l
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Followup Observation of Welding i
The inspector observed the welding by BWCC of-the reactor pressure boundary piping. The welds examined were on the steam generator connections designated as field welds: WJ 6-1, 6-2, 5-1, 5-2, 5-3, 5-4, along with the field weld documentation, weldor qualification and weld rod material control identification.
The weld procedure
was available at the work site and appropriate visual inspections were performed and signed off.
i The inspector visually exar'.ned the partially completed welds for weld profile, are strikes, veld splatter, contour and uniformity of weave. The welds appe W ed of adequate quality; however, porosity
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was later found by nondest.uctive examination on some of the above listed' welds which is to be removed.
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RO Rpt. No. 50-302/74-1 I-3
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There.were no deficiencies or violations noted except on records, documentation and record keeping ahich is described below.
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Followup Record Review of' Welding The inspector reviewed the in-progress weld documentation,for the
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above mentioned w d ds.-'The inspector observed that the records for each weld were difficult to locate and assemble chronologically to
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asc.re all the required inspections were performed. ' Records for all
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the welds were in one folder and it appeared during this' review that
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the required deviation authorizations for weld WJ 6-l'was not at the
work site.and could not be located.
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BWCC innediately corrected this situation by establishing separate.
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folders for each veld joint and chronologically assembling the weld'
data in each folder. Deviations were required for WJ 6-1 which were
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immediately written and placed at the work site. The. licensee assured the inspector that a constant monitoring of these records arid welding
would be performed.
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No completed weld documentation package of reactor pressure boundary piping was reviewed since at this time no welds are complete.
5.
Piping and Welding Other Systems Than Reactor Pressure Boundary System
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Followup Record Review of Welding
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j The inspector reviewed the weld record documentation records for l
field welds made by Livsey and Company on the decay heat system
(DH) Nos. 8, 11, 32, 130; makeup and purification system (MU)
Nos. 65, 66, 68, 94, 100, 111, 295 and for the field welds made by BWCC:
DH-148, 165, MiJ-416, 418.
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For the above listed welds, the licensee produced records and
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documentation which included weld data sheets, radiographs, radiographic evaluation reports and weld rod material control receipts. The weld data sheets contain information such as weld procedures, weldor's name and identification, weld material identification and components to be welded.
In addition, there were inspector signoffs for ficup, visual, liquid penetrant-and radiographic test results as required.
Radiographs of the joints
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listed above were reviewed for joint identification, date, size
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of penetrameter, quality of radiograph, density and apparent quality of weld.
- There were no violations or deficiencies identified associated with Livsey and Company field welds identified during this O
inspec However, during.the review of BWCC field welds and documen, tion.
tation, the inspector observed:that no detailed reports
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by ANSI B 31.7 performed on MU 418, DH 14C and DH 165. Weld.%.
MU 416 did have a detailed written report for the PT inspectiop rcluired by ANSI B 31.7.
I; is to be noted that the radiographic reporting results were satisfat'ery to the Code requirements.
BWCC stated that they no longer complete an inspection report for
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liquid penetrant or magnetic particle inspection and just note on the field weld data sheet oc sequence of events, the date of the r
inspection, the inspector's initials and acceptance if the weld
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meets the Code acceptance criteria. The inspector disagreed with
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BWCC's documentation method as it appears not to meet ANSI B 31.7 reporting requirements for nondestructive examination.
The licensee and BWCC stated that they will investigate this matter further; how -
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ever, while this investigation is being performed BWCC will.now prepare detailed written inspection reports for all Code required nondestructive inspections.
The licensee will also examine the records of BWCC completed welds for acceptability.
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The inspector informed the licensee that this is considered 'an unresolved item and will be reviewed during subsequent inspections.
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Followup Observation of Welding i
There was no actual welding being performed on the main steam system welds; however, the inspector reviewed in-process weld documentation on main steam system (MS) Nos. 12, 23, 24, 35.
The inspector visually inspected welds 23 MS and 35 MS for weld profile, are strikes, weld splatter, contour and uniformity of The welds appeared of adequate quality with no evidence weave.
of are strikes. Weld documentation for the current status of welding was excctined.
There were no deficiencies or violations identified.
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Letter to Florida Power Corporation
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50-302/74-1 dated JAN a,4 m
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DISTRIBUTION:
D. Thornburg, RO RO:HQ (4)
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Directorate of Licensing (h)
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DR Central Files
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- PDR
- Local PDR
- NSIC
- DTIE, OR
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" State
- To be dispatched at a later date.
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