IR 05000302/1975007
| ML19317G399 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/30/1975 |
| From: | Fred Bower, Bryant J, Vallish E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19317G394 | List: |
| References | |
| 50-302-75-07, 50-302-75-7, NUDOCS 8003030807 | |
| Download: ML19317G399 (8) | |
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UNITED STATES i
NUCLEAR REGULATORY COMMISSION j
REGION 11 230 PEACHTREE STREEr, N. W. SUITE BIS
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IE Inspection Report No. 50-3J2/75-7 Licensee:
Florida Power Corporation
,r 320134th Street South P. O. Box 14042
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l St. Petersburg, Florida 33733
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Facility Name: Crystal River 3 Docket No.:
50-302 License No.:
CPPR-51
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Category:
A3/B1 i
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Location:
Crystal River, Florida
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i Type of License:
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Type of Inspection: Routine, Unannounced, Construction
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Dates of Inspection:
June 4-6, 1975 Dates of Previous Inspection:
April 8 1, 1975
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Inspector-in-Charge:
F. U. Bower, Reactor Inspector Engineering Section i
Facilities Construction Branch Accompanying Inspectors:
T. E. Conlon, Reactor Inspector Engineering Section
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Facilities Construction Branch Other Accompanying Personnel:
J. C. Bryant, Senior Inspector
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Facilities Section-acilities Construction Branch
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Principal Inspector:
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'[C E. J U Tallish, Reactor Inspector Date Facilities Section Fa ilities Construction Branch
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Reviewed by:
~ ' ant, 'Senfor Inspector Date
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Af, J. C
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Faci es Section OJTroy d
Facilities Construction Branch e
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2-IE Rpt. No. 50-302/75-7
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StRC4ARY OF FINDINGS
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I.
Enforcement Items
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None-t
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'II Licensee Action on Previously Identified Enforcement Items
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j There were no previously identified enforcement iteus.
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III.
New Unresolved Items
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75-7/1 Procurement Records for Control Rod Drive AC i
Breaker Cabinets
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It could not be determined from records available at the i
site that the cabinets had been manufactured to the
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required quality level. The licensee is investigating this
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matter.
(Details I, paragraph 4)
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IV.
Status of Previously Reported Unresolved Items
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i 75-3/1 Receiving Inspection Procedure i
Quality Program Procedure QP No. 15.50, Revision 1, was reviewed and found to satisfactorily provide guidance for
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the control of nonconformance at receiving inspections for i
spare parts and supplies. This item is closed.
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75-3/2 Instrumentation Inspection criteria
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l Revision to Procedures FPC-W56 and FPC-W79 provide QC
control on tightening tube fittings and slope of both
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tubing and pipe. This item is closed.
(Details II, l
paragraph 2) -
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l 74-15/1 Makeup and Purification System Letdown Orifice (10 CFR i
50.55(e) Item)_
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The licensee has reinstalled the modified orifice. This item.is closed.
(Details II, paragraph 3)
74-14/2 Seismic Qualification of the Control Rod Drive Control l
System AC Breaker Cabinets (10 CFR 50.55(e) Item)
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l A re-evaluation of the seismic qualification of the control
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rod' drive control system AC breaker cabinets has revealed
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O IE Rpt. No. 50-302/75-7-3-
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that attachment of the cabinets to the floor is inadequate to withstand the SEE acceleration levels.
Design work is reported to be in progress.
FPC will monitor
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the B&W corrective action. This item remains open.
(Details I, paragraph 3)
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V.
Design Changes
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None
VI.
Unusual Occurrences
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None
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VII.
Other Significant Findings None VIII.
Management Interview An exit interview was held with Mr. C. E. Jackson, Construction Superintendent and others. The results of the inspection were discussed and the Licensee was informed that no noncompliances or deviations were identified as a result of this inspection.
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IE Report No. 50-302/75-7 I-1
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DETAILS I Prepared by:
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F. U. Bower, Reactor Inspector Date Engineering Section Facilities Construction Branch
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Dates of Inspection: June 4-6, 1975
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Reviewed by:
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Nub 4-JP 75" L. L. Beratan, Senior Inspector Date Engineering Section Facilities Construction Branch
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1.
Persons Contacted Florida Power Corporation (FPC)
R. W. Slater - Quality Engineer R. C. Bonner - Supervisor, Electrical Construction C. Snipes - Electrical Engineer-QA fx l
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E. E. Froats - Manager, Site Surv111ance
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2.
Electrical / Instrumentation (E/I) Construction Progress Since initiation of the stretched out construction schedule, the electrical craft force has averaged 64 men. This is down # rom an average electrical craf t force of 240 men prior to this tine.
Additionally, 23 of this number are assigned to the test and startup activity. With only an average of 40 electricians available to the construction activity, the modest progress reported is understandable.
Cable pulling is going forward with one crew assigned to this activity.
It is estimated that this work is 85 percent complete.
One problem encountered in this area during this inspection is that none of the instrument cable from the primary systems have been installed as yet.
This work is reported to be scheduled for the near future. Most of the E/I equipment has been set in position and anchored. Hook up work is well advanced and is continuing. Work is reportedly going forward efficiently, but slowly due to the small work force.
3.
Seismic Qualification of the control Rod Drive Control System AC Breaker Cabinets (10 CFR 50.55(e) Item) (Ref. 74-14/2)
The site staff reports that no progress has been made towards modifying f'~')
the subject cabinet physical attachments to the floor.
A field modification
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number has reportedly been assigned to cover the anticipated work and.
i the consultant A&E is in the design process. No schedule for the work was available for examination.
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The final form of the modification is not presently known, however,
it will not take the shape shown in the sketch forming part of the i
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original identification of the deficiency.
Since the present installation does not include a pedestal or concrete anchor angles as shown therein
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accepted.
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4.
Procurement Records for Control Rod Drive AC Breaker Cabinet (Ref. 75-7/1)
I An examination of procurement QC records for the subject assembly revealed only a, " blanket type certificate of compliance," that is considered inadequate to meet present commitments.
Indications existed within the
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general QC file on this and other related equipment, that additional QC records were on file at the vendor's Headquarters. The staff has agreed to obtain suitable documentation frota the supplier and have it available for examination on the site during a future inspection.
This reference alludes to the B&W Specification No. 1085/0569 which provides general classification of the plant equipment.
In this specification it is the clear intent that the subject equipent is classified as safety equipment, procured to meet a relatively high quality level.
Conversely, a letter from B&W management (3/4/74 - FPC-1366) to Mr. M. J. Kleinman, FPC QA management, lists the subject equipment in the Level III category.
The Level III category requirements are not consistent with the requirements l
imposed upon safety equipment.
This item will be considered unresolved until information is made available to allow a further evaluation.
5.
'Out-of-Core Nuclear Instrument Tube Coating It was noted that the subject tubes were coated with a material known by the trade name of "Plasite." A brochure on this material, that was examined by the inspector, does not list its radiation characteristics nor does it recommend it for use in regions of high radiation levels.
Since the tubes in question are located in a zone where high radiation fields can be expected, a possibility of future problems with this material may exist. The problem was discussed with the staff during the
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inspection and was presented at the closeout meeting.
A commitment was solicited and the licensee representative agreed to study the scea of the inspector's concern and take any action indicated by the results of the study.
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5.
Inspection Results l
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The following listed cables were examined as representative samples of installed safety related systems. This equipment and QC documentation
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was inspected for such features as workmenship, handling techniques, protection of installed equipment, cleanliness, QC inspection and docu-
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mentation and requirements of licensing such as redundancy, physical
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separation, structural integrity, material certification, testing,'use of proper materials and the suitable implementation of the QA/QC problem.
Nuclear Instrument Cables Nos. N1R-65, N1R-41, N1R-23 and N1R-3 were examined.
These cables represent all four channels of nuclear instrumen-tation and are each routed in a conduit common with all remaining cables of the respective channel. The examination did not reveal variations from the requirements.
It was noted that the four conduits containing the cables were routed in close proximity to each other for a major portion of the total routing path.
The inspector discussed the similarity of this routing geometry to that of another project in which a recent fire caused the loss of all nuclear instrument signals.
The discussion was intended to be for information only to induce a greater degree of awareness on the part of the licensee's management.
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IE Rpt. No. 50-302/75-7 II-l
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DETAILS II Prepared b
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T. E. Conlon, Reactor Inspector
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Engineering Section
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Facilities Construction Branch
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Dates of Inspection:
June 4-6, 1975
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4.70 - 7f'
Reviewed by:
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L. L. Beratan, Senior Inspector I
Engineering Section Facilities Construction Branch
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Persons Contacted
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Florida Power Corporation (FPC)
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R. W. Slater - Quality Engincar i
E. E. Froats - Manager Site Surveillance
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i D. W. Bienkowski - Mechanical Engineer i
2.
Instrumentation Inspection criteria (75-3/2)
The licensee revised Procedure FPC-W56 (Revision 2) to control tightening
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of swagelok fittings to 1-1/4 turns as recommended by the manufacturer.
Procedure FPC-79 was completely rewritten and a QC checklist was added to verify proper installation of system and to specifically verify adequate slope to instrument tubing and pipe. This item is closed.
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3.
Makeup and Purification System Letdown Orifice (74-15/1)
The potential for cavitation and subsequent erosion in the last three stages of the letdown orifice was first identified to FPC by B&W in a letter dated September 23, 1974. The licensee generated a noncon-formance (No. 1647) on October 7, 1974. The orifice unit was removed and shipped to Bingham Willamette for modification. The orifice unit has been reinstalled and signed off by QC on April 18, 1975. This item
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is closed.
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Resctor Vessel Internals - (Plenum Assembly)
The plenum assembly is complete and at the present time is stored in the l
containment on the refueling pool floor.
The trial fitup with the core support assembly has been completed. The entire plenum assembly has been cleaned to a grade B level as defined by FS-II-2 and surface chlorides were verified to be within acceptab'le limits. The unit is currently h
sealed with a polyethylene sheet.
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IE Rpt. No.-50-302/75-7 II-2
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The' inspector reviewed QC documentation for fabrication of the plenum assembly which consisted of:
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BW 1etter of certification b.
BW QA data' sheet i
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Listing of weld procedures, RT reports, electrode heat numbers, piece heat' numbers and weld joint identification.
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The QA data sheets were signed by cognizant BW personnel and indicate j
that a' complete set of documentation exists at the BW Barbertown plant.
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Assembly of the plenum unit was done in accordance with BW Proced'ure
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No. 090, Revision 2.
A review of the master copy of this procedure revealed,QC signoff for each sequential step. Within the areas examined, there were no items of noncompliance identified.
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5.
Pressurizer Valves and Piping The two relief valves and one air cperated vent valve were temporarily
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installed to facilitato ficup of discharge piping, after which they I
were removed and stored in the BW warehouse pending final installation.
The inlet and outlet openings are capped and BW is performing a weekly
inspection.
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Final installation will be done in accordance with BW Procedure No. 081 and final QC documentation will consist of signoffs against the line
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items of this procedure.
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The pressurizer relief valve. discharge piping is seismic Class I and code class III. USAS B31.7 (1969) class III piping requires only random
radiography. The inspector examined the RT film for field weld joints i
10 RC, 11 RC, 13 RC, 17 RC and-18 RC.
The inspector did not identify
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any_ deficiencies with respect to these film. Three weldors participated in the welding of these joints and were qualified to weld procedure
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The weld data. sheets were in order and visual inspection of
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