IR 05000302/1971003
| ML19308D422 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/17/1971 |
| From: | Fred Bower, Kelley W, Long F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II), US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19308D409 | List: |
| References | |
| 50-302-71-03, 50-302-71-3, NUDOCS 8002280726 | |
| Download: ML19308D422 (10) | |
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UNITED STATES h
ATOMIC ENERGY COMMISSION
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i DIVISION OF CO94Pt.IANCE 526-4503 REGION ll - SulTE 818 230 PEACHTREE STREET. NORTHWEST The MM5h AT LANT A. GEORGI A 30303
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CONSTRUCTION INSPECTION REPORT COMPLIANCE REPORT NO:
71-03 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 Crystal River, Florida
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License No..
CPPR-51 Docket No.:
50-302 Category:
A Type of Licensee:
B&W PWR - 855 Mwe Type of Inspection:
Routine - Announced O(]
Date of Inspection:
July 12-15, 1971
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Date of Previous Inspection:
May 11 4, 1971 Principal Inspector:
[ /7/7/
o W. D. Kelley, R getor Date'
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l Inspector (Condtruction)
Accompanying Inspector:
W bpu/A
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F. U. Bower, Reactor Date Inspector (Construction)
Other Accompanying Personnel:
None Reviewed By:
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F. J. Lon6, SerY1or Reactor Inspector Dat'e
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Proprietary Information:
None
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FPC 50-302/71-03-2-
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SECTION I
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ENFORCEMENT ACTION:
None LICFNSEE ACTION ON PREVIOUSLY IDENTIFIED ENFORCEMENT MATTERS:
None UNRESOLVED ITEMS
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A.
The fabricator of the nuclear service heat. exchanger substituted etching of weld runout tab section in lieu of radiography of the longitudinal weld.
(See Section II, paragraph 1. )
B.
The fabricator of the tendons for the containment has not resolved how the tendons will be greased before installation.
(See Section II, paragraph 2. )
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C.
The fabricated pipe spool pieces for Class I systems m
paragraph 3.) pplicable code requirements.
(See Section II, did not meet a D.
The NSSS supplier has not furnished information on the ultrasonic examination of the main coolant pump flywheels.
(See Section II, paragraph 4. )
STATUS OF PREVIOUSLY REPORTED UNRESOLVED ITEMS:
None DESIGN CHANGES:
None
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UNUSUAL OCCURRENCES:
None PERSONS CONTACTED FPC
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H. L. Bennett - Director, Generation Construction M. H. Kleinman - Manager, Generation Quality and Standards Department E. E. Froats - Engineer, Quality Program B. W. Pedrick - Quality Engineer J. Hobbs - Electrical and Mechanical Construction Supervisor O
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FPC 50-302/71-03-3-
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MANAGEMENT lhTEMV.Lbd
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The management interview was held on July 15, 1971, at 3:00 p.m. in the FPC corporate office in St. Petersburg, Florida.
The meeting was attended by the following FPC personnel:
J. T. Rodgers - Assistant Vice President J. Dawson - Manager, Special Projects Department M. H. Kleinman - Manager, Ge,neration Quality and Standards Department H. L. Bennett - Menager, Power Construction A'.
FPC presented the inspector with the new organizational charts and stated they would be included in their next revision of the FSAR.
B.
The inspector stated that the work order form issued to correct deficiencies did nob identify the company who initiated it.
FPC stated the company who issued the work order would be identified.
e C.
The inspector stated that sectioned and etched weld runout tabs had been rubstituted for radiographic examination of the longitudinal weld of the nuclear service heat exchanger.
FPC stated ths the weld was nonradiographical, and that drawings of the design would be available to the inspector for audit on his next inspection.
D.
The inspector inquired if FPC would have a program for valve wall thickness evaluation.
FPC stated that valves would be examined on the basis of one each for a manufacturer's pattern,.and if a thin wall was discovered the entire lot world be examined.
E.
FPC informed the inspector that the tendon supp1k r had not resolved the method of progreasing the tendons.
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F.
FPC informed the inspector that all Class I pipe fabricated spool pieces that had been received onsite were being inspected and those that did not meet the applicable code requirements were being quarantined.
The inspector stated he would audit the final inspection report on those l
spool pieces that were quarantined.
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FPC informed the inspector that the GAI specifications and FPC purchase orders were being revised to have the rubber l
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Oe FPC 50-302/71-03-4-
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lining of the three carbon steel radioactive gas decay tanks done in the field.
FPC also stated that the tanks were in
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place and had a hold tag on them awaiting GAI and FPC approval of a repair procedure and documentation audit.
The inspector stated he would audit the final procedures and repairs.
H.
FPC informed the inspector that a procedure would be written for final inspection of piping systems prior to hydrostatic test and applying insulation, to include inspection of hangers, restraints, damage, and are strikes.
I.
FPC informed the inspector that the plant was 31%
complete and criticality was now scheduled for July 14, 1973, with commercial operation starting on September 14, 1973 J.
FPC informed the inspector that they had not received the final recommendation from their NSSS supplier on ultrasonic testing of the main coolant pump motor flywheel.
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The inspector discussed as improved, but not complete,
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the electrical and instrumentation systems QA/QC program and procedures.
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The inspector urged that the planning of the electrical and instrumentation work be escalated in anticipation of impending needs.
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FPC 50-302/71-03-5-
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SECTION II
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ADDITIONAL SUBJECTS INSPECTED NOT IDENTIFIED IN SECTION I, WHERE NO DEFICIENCIES OR UNRESOLVED ITEMS WERE FOUND 1.
GENERAL j
FPC (Rodgers) stated that Unit 3 is estimated at 31% complete and tha criticality was now scheduled for July 14, 1973, and commercial operation to commence on September 14, 1973 Erection of the containment liner has been completed to the
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spring line and the dome plates are being welded into section i
on the ground.
Placement of reinforcing steel and concrete continues in the auxiliary building, turbine building, and
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reactor building.
The reactor vessel has been received onsite and unloaded from the barge.
/N The Power Engineering and Construction under Rodgers, t
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Assistant Vice President, had been reorganized into Generation d
Engineering and Construction consisting of the following five departments:
Generation Construction - H. L. Bennett, Director Generation Services - R. B. McKnight, Manager
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Generation Engineering - W. A. Szelistowski, Manager Generation Quality and Standards - M. H. Kleinman,
Manager Generation Environmental and Regulatory Affairs -
J. A. Hancock, Manager
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W. May, formerly Manager of Power Engineering Department, has
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been made assistant to the Vice President of Research and
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Planning.
B&W Construction Company's project manager, L. Watson,
'I project engineer, T. Richard 3on, and quality control engineer, J. McGill, are onsite full-time and have assumed
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all of their receiving and inspection functions from J. A. Jones Company.
PTL is scheduled to increase their staff of quality control inspectors onsite to 33 by July 16, 1971, and 40 by October 16, 1971.
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FPC 50-302/71-03-6-
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2.
REACTOR. VESSEL The reactor vessel was received onsite on July 7, 1971, suul
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was unloaded by B&W Construction Company.
The vessel is stored on the modified Manitowoc Model 4600 crawlers that offloaded it from the barge.
No special storage protection is required because the vessel was protected for intra-coastal waterway shipment.
The B&W receiving report states that there were no unsatisfactory conditions or causes for
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rejection.
v DETAILS OF SUBJECTS DISCUSSED IN SECTION I i
1.
NUCLEAR SERVICE HEAT EXCHANGER
'A letter from SW-Qulfport Inc. (E. M. Miller) to FPC
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(J. E. Dawson) dated June 1,1971, stated that the nuclear service heat exchanger's shell longitudinal seam had not
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been radiographed as required by the specification.
The reason given was the longitudinal pass plate served as a
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backing bar for the welding of the longitudinal seam making the butt joint unradiographical.
The letter stated it was agreed that etched coupons of runout tabs of the weld would be used in lieu of radiographs.
The etched samples are at Crystal River.
FPC did not have
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drawings of the heat exchanger onsite but agreed to make them available to the inspector on his next inspection.
2.
CONTAINMENT TENDONS The fabricated tendons to be supplied by Prescon Corporation are required to be greased prior to shipment.
The specification requires each individual wire in a tendon to be greased independently.
Prescon is studying a method of greasing the wires and is being assisted by FPC; however, the method has"not been formally resolved.
Prescon has reviewed the
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possible problem of the pulling grigpers slipping off the pregreased tendons and has stated they do not anticipate any greater precentage of the grippers slipping off of the pregreased tendons than those coated with their rust inhibitor.
CLASS I PIPING - FABRICATED BY M. W. KELLOGG COMPANY r
FPC has reinspected all MWK fabricated spool pieces for Class I systems delivered onsite as a result of the
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FPc 50-302/71-03-7-
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inspector's observation.
A total of 36 spool pieces had been quarantined as of July 12, 1971, which represents a l
rejection rate of approximately 15%.
MWK and GAI shop inspectors were onsite the latter part of June and both agreed that some of the welds were questionable as to their meeting the applicable code requirements.
FPC stated that the last two shipments of pipe fabrication received had been originally rejected by the GAI inspector and were reworked and seem to be of better quality.
4.
MAIN COOLANT PUMP MOTOR FLYWHEEL The main coolant pump was supplied by B&W as part of their NSSS package.
They are to supply a procedure for the ultrasonic testing of the motor flywheels and they will have the procedure reviewed by their consultant.
After the procedure is approved by the consultant and FPC, it
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will be made available to the inspector for audit, e
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FPc 50-302/71-03-8-
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SECTION III Prepared By:
F. U. Bower Reactor-
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Inspector'
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(Construction)
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ADDITIONAL SUBJECTS INSPECTED NOT IDENTIFIED IN SECTION I, WHERE NO DEFICIENCIES OR UNRESOLVED ITEMS WERE FOUND
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GENERAL
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Since the E/I work completed or in process at the time of
this inspection was not of prime importance to Compliance, the work procedures developed to regulate this effort
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are considered adequate.
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l Serious staffing efforts have not started for the E/I QC group.
Discussions with FPC site QC engineer (Pedrick)
i indicate that some basic decisions still need to be made
in this regard.
For the present effort, the site QC group is adequate.
m DETAILS OF SUBJECTS DISCUSSED IN SECTION I 2.
The QA/QC program planning effort has been escalated since the last inspection with greater detail and more meaningful results.
Although the program of procedure development is admittedly far from complete, some of the previously-prepared sketching procedures have been
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revised and/or z ewritten entirely and new procedures are in the early development stage.
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One work procedure, presented to the inspector for review l
that Hobb; stated would be the format for all such procedures,
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was FPC-W30.
This draft' procedure was being circulated for
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comment and approval and dealt with receiving, handling, i
j installing and testing penetration assemblies.-
Other work procedures recently revised include FPC-W16 and FPC-W24.
FPC-W32 for overall control of cables is in the predraft stage and will constitute a major milestone
when successfully completed.
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FPC 50-302/71-03
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The meeting in the St. Petersburg FPC office was selected as an opportune time to expound on the merit of
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preplanning for such work as the E/I installation at Crystal River.
Genuine pr;blems plagueing the industry
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were discussed (without specific project reference) as cases in point that could have been avoided by good
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planning.
i The FPC vice president, present at the meeting, agreed with the inspector's st.atements and stated that they had i
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every intention of meeting their commitments.
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.s DIVISION OF COMPLIANCE s
MONTHLY REPORT FOR JULY 1971
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i Florida Power Corporation (Crystal River 3) - A CO insp.ecti_on was
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t coaducted on July 1R-1.5., to observe the progress of work Ynd verify corrective action relative to previously identified outstand-ing items.
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Two outstanding items remain unresolved - the UT of the main cooliiit pump flywheel and the use of. sectioning and etching of runoff welding tabs in lieu of spot radiography due to joint geometry of the nuclear service water heat exchanger.
No new problems were detected.
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