IR 05000302/1975003
| ML19319C715 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/04/1975 |
| From: | Bryant J, Ebneter S, Vallish E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19319C711 | List: |
| References | |
| 50-302-75-03, 50-302-75-3, NUDOCS 8003030837 | |
| Download: ML19319C715 (9) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION O\\
REGloN ll 230 PE ACHTTt CE f.TR ECT. N. W, $UITE 918 ATLANTA. GEORGI A 30333 i
l IE Inspection Report No. 50-302/75-3
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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 Facility Name:
Crystal River 3
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Docket No.:
50-302 License No.:
CPPR-51
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Category:
A3/B1
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s Location:
Crystal River, Florida Type of License:
B&W, PWR, 2452 Mwe, 855 Mwe Type of Inspection: Routine, Unannounced, Construction Dates of Inspection:
February 12-14, 1975 Dates of Previous Inspection: January 27-31, 1975 s
Principal Inspector:
E. J. Vallish, Reactor Inspector Facilities Section Facilities Construction Branch Accompanying Inspectors:
S. D. Ebneter, Reactor Inspector Engineering Section Facilities Construction Branch Other Accompanying Personne_l:g None,
Principal Inspector:
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E. J. Wallish, Reactor Inspector Date Facilities Section Facilities Construction Branch i
t, kw 8 ~ #/- 7 Reviewed By:
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J. C. Bryanrg Senior Inspector O Date Facilities Section Facilities Construction Branch M SENT TO: POR
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IE Rpt. No. 50-302/75-3-2-
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SUMMARY OF FINDINGS
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I.
Enforcement Items
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None
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II.
Licensee Action on Previously Identified Enforcement Items l
There were no previously identified enforcement items.
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III.
New Unresolved Items 75-3/1 Receiving Inspection Procedure s
Wording in the Quality Program Procedure QP No. 15.50,
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Revision 0, is vague on the subject of lack of documentation for spare parts and supplies during receiving inspection.
FPC will reconsider the wording.
(Details II, paragraph 3)
75-3/2 Instrumentation Inspection criteria There is inadequate inspection criteria for compression g
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type instrument tubing fittings and instrument line slopes.
FPC will review this item and supplement the criteria.
(Details I, paragraph 3.0)
IV.
Status of Previously Reported Unresolved Items'
74-15/1 Makeup and Purification System Letdown Orifice (10 CFR 50.55(e)
Item)
NSSS supplier investigation revealed that cavitation and subs.
quent erosion would occur in the last three stages of this let-down orifice.
Subject orifice wa.. returned to manufacturer for modification. This item remains open.
74-14/2 Seismic Qualification of the Control Rod Drive Control System AC Breaker Cabinets (10 CFR 50.55(e) Item)
A re-evalaation of the seismic qualification of the control rod drive control system AC breaker cabinets has revealed that attachment of the cabinets to the floor is inadaquate to withstand the SSE acceleration levels.
A field cha"ge will be issued by B&W to modify attachment of the AC breaker cabinets to the floor.
FPC will monitor the B&W corrective action.
This item remains open.
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IE Rpt. No. 50-302/75-3-3-
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73-5/14 Reactor Internals Modifications
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Modification of the internals was to have been accomplished in the vendor shops and verification will be made when the
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internals are assembled.
Thin 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
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VII. Other Significant Findings
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A.
Project Status Electrical and instrumentation wiring and termination continues.
Clean rooms are established and unpackaging of reactor internals is in progress.
B.
Personnel or Organizatio Changes The quality assurance function is now the responsibility of E. E. Froats, Site Surveillance Manager, who is supported by R. W. Slater, Que.lity Engineer, and his organization which includes various engineering disciplines.
The new Quality Surveillance Manager is J. C. Clapp whose Quality Engineer, J. C. Hicks, heads the functional unit. A new function named Procedure Surveillance and Training is headed by W. A. Shields.
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(Details II, paragraph 2)
VIII. Management Interview An exit interview was held with Messrs. H. L. Bennett, Director, Generation Construction; E. E. Froats, Manager, Site Surveillance (Nuclear); and others. The results of the inspection were discussed.
No noncompliances were found, but two new unresolved items were identified.
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IE Rpt. No. 50-302/75-3 I-1
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DETAILS I Prepared by:
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S. D. Ebneter, Reactor Inspector Date Engineering Section Facilities Construction Branch
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Dates of Inspection:
February 11-14, 1975
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3-4-76~
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Reviewed by:
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L. L. Beratan, Senior Inspector Date
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Engineering Section Facilities Construction Branch
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Persons Contacted Florida Power Corporation (FPC)
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R. W. Slater - Quality Enginner
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D. W. Pedrick, IV - Compliance Engineer J. E. Dawson - Special Projects Engineering M. Robinson - Instrumentatis. t Engineer 2.
Scope of Inspection
This inspec: ion included an examination of system instrumentation and an audit of the preservice inspection status. The instrumentation
' nspection included a review of installation procedures, quality i
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control activities and QC records. Instrumentation systems installations are in a very early stage which limited the inspection to those specific items detailed below.
The preservice inspection status audit was limited to program aspects since there has been a change in the contractor that will perform these
. services.
3.
Instrumentation a.
Instrument Installations The inspector chose the following instruments and systems for inspection:
Instrument Designation System RC3B-PTl Reactor Protection System RC3A-PTl
RC3A-PT3 Safeguards System RC3B-PT3
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i IE Rpt. No. 50-302/75-3 I-2
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j Very few of the instrument components were installed, wiring
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was not complete and sensor '.ines had not been run. Many of the-instruments that had been lastalled, including the above pressure,
transmitters had been removed under nonconformance NCR 1372.
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i Instrument arrangement drawings 1C-308-605 and 1C-308-604 defined the instrument locations and mountings in the containment. All
of the instruments were located at elevation 95 with one set at
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l the north station and the redundant set located at the south station, displaced by approximately 160* in azimuth thus assuring
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adequate physical separation.
Electrical conduits RCR 95 and
RCH 13 were adequately identified and color coded in accordan,ce
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l with Procedure W33.
Sensor lines for these instruments had not
been installed but iso-diagrams were availabic which detailed
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I-the installation ual routing.
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The diagrams appeared satisfactory with the exception of a
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quantitative definition of sensur lla. slepe requirements. Other documentation did contain adequate slope definitions and it appears that it is a matter of incorporating the requirement on the drawing since this is the primary installation reference.
The licensee
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i stated that this would be reviewed and incorporated as necessary.
Procedure W56, " Installation of Instrumentation," and W79, " Inspection
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Requirements for Instrumentation Systems," are the procedures
governing instrument installation and inspection.
The inspector l
noted that there was no provision for inspection of compression
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type fittings'on instrument lines in the procedures. The licensee
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stated that this would be reviewed.
This item in conjunction with the sensor line slopes is identified as an unresolved item (75-3/2).
The inspector noted that separation criteria for sensor lines had
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been incorporated in Procedure W79. This latter item was discussed in RO Report No. 50-302/74-12.
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Instrument Cables and Conduits i
i The' inspector selected several installed conduits in the contain-ment spray system for inspection. Procedure'W33, " Procedure for
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Installing Conduit, Cable Tray and Underground Duct Bank," specifies the criteria for conduit installation and W32 contains the require-
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. ments for installation of cables.
The inspector verified the installatica records, QC records and physical routing of conduits i
CAE 15, CAE 16 and CAE'24 and associated cables. No items of
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noncompliance were identified.
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{[~N IE Kpt.'No. 50-302/75-3 I-3
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c.
Noncomformance Record Review Procedure QP 15.10, "Nonconformance Control," is the basic document
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covering nonconformances and it interfaces with QP 14.50 and QP 14.11.
The inspector reviewed indepth NCR 1372 pertaining to instruments and verified compliance with procedural requirements.
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Affected instruments were tagged and all records information
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correlated.
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The inspector reviewed the NCR log and randomly selected several
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open NCR's and several closed NCR's for review. The records
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appeared satisfactory and marking requirements had been complied with. NCR 1730 was listed as open but was found to have been clo sed. The licensee made the appropriate log entry to complete the record.- No items of noncompliance were noted and the inspector had no further questiocs.
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4.
Preservice Inspection a.
Planning The licensee has contracted wit h the Babcock and Wilcox (B&W)
s-Construction Company to perform the preservice (baseline) inspection.
The baseline inspection plan is being prepared by B&W to conform to l
ASME Code Section XI,1972 editien, as specified in FPC QP 10.11.
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Most of the welds that are to be examined have been identified as the result of previous efforts. These are being incorporated in the plan by B&W. The licensee is planning to perform the piping baseline in mid-1975 prior to actual system cold hydro based on a recent ASME code interpretation dated December 18, 1974.
i The reactor vessel will be examined in early 1976 by the B&W
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j Automated Reactor Inspection System (ARIS) after the system's cold hydro test has been completed.
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The licensee ia presently studying the need to perform an eddy current inspection of the steam generator tubes as described in Regulatory Guide 1.83.
This will be performed by someone other than the baseline contractor.
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- i IE Rpt. No. 50-302/75-3-I-4
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b.
Examinations Completed Some of the examinations required by ASME Section XI have been performed by Southwest Research Institute as the result of
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l a previous contract arrangement.
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The control rod drive tube-to-head welds have been examined
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l ultrasonically and visual inspections of the reactor coolant pump
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internals and casings have been completed.
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IE Rpt. No. 50-302/75-3 II-1 V
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DETAILS II Prepared By:
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E. J. Vallish, Reactor Inspector
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Facilities Section
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I Facilities Construction Branch
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Dates of Inspection: - b ry ;12-le, 1975 N' M /M '/hA/
Z 9/~,7M Reviewed By:
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J. 6. $yant, Senior Insp'eetor-
/r pag, Facilities Section
Facilities Construction Branch 0-e
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1.
Persons Contacted
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a.
Florida Power Corporation (FPC)
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M. H. Kleinman - Director, Quality Programs Department
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E. E. Froats - Manager, Site Surveillance (Nuclear)
H. L. Bennett - Director, Generation Construction
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C. E. Jackson - Superintendent, Site Construction
R. W. Slater - Quality Engineer i
J. C. Clapp-- Quality Surveillance Manager J. C. Hicks - Quality Engineer W. A. Shields - Procedure Surveillance and Training
D. W. Bienkowski - Engineer II T. L. Baker - Records Supervisor b.
Contractor Organization
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Babcock and Wilcox Construction Company (B&WCC)
i J. McGill - QC Supervisor
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2.
QA Organization and-Program A followup indepth inspection was conducted of the FPC total program
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covering the adequacy of development and implementation of the QA I
organization and program.
Significant changes were made to the FPC
.QA and QS functions as a result of the. transfer of direct QA respon-
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L sibilities from Gilbert Associates,. Incorporated to the FPC Quality Programs Department.
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The following documents were examined:
i Crystal River Unit No. 3 Quality Organization Chart - 1/17/75 a.
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Florida Power Corporation. Quality Programs Department Administra-tive Procedures-
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s, Florida Power Corporation, Quality Manual, Volumes I 'and II c.
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I E ".p t. no. 50-302/75-3 II-2 v
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Quality Assurance Review, dated 1-29-75, file code ARCS-006 d.
B&W Procedure for Installation of Reactor Internals, B&W FPC
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No. 090 R2 FPC audit of B&W Internals Records during April 1974
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Amendment 44 of'the Crystal River Unit 3 FSAR
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g.
Inspection on the site indicated that the QS/0A organizations are
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functioning as described in the application.
To test the functioning
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of the quality program, the reactor internals were used as a sample item and basis of audit. Examples of performance were observed of all B&W Construction organizations relating to quality of the internals.
Company has erected clean-room type enclosures in the reactor building in which tF i are unloading the internals components from their shipping containers. The procedures for this activity were reviewed by FPC QA and approved. B&W QC is inspecting the unloading and assembly operations.
FPC QA reviews and audits procedures and hardware related to the internals inspection and assembly. FPC Q Surveillance audits the function of QA O
to assure adequate implementation of the approved programs and to determine the viability of the overall quality program.
No inconsistances with
i the application were identified.
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Receiving Inspection Procedure FPC Quality Program Procedure QP No. 7.52 Rev. O, paragraph 4.2 (3)
describes the processing of safety related items needed for use before final acceptance according to receiving inspection procedures.
It gives an example of an item being held for documentation. This QP references QP No.15.50, which implies that the engineer may use the item as is.
This action would be contrary to the intent of Appendix B, Criterion VII, which requires, " Documentary evidence that the material and equipment conform to the procurement requirements shall be available st the nuclear power plant site prior to installation or use...."
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(emphasis added).
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QP No. 7.52 and QP No. 15.50 are designated as operating status procedures hence have not been implemented; this removes the item from the noncompliance category and places it in the unresolved item
. category, wherein additional information is required for disposition.
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