IR 05000313/1973004
| ML19320A018 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/13/1973 |
| From: | Brownlee V, Crossman W, Rausch J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19320A009 | List: |
| References | |
| 50-313-73-04, 50-313-73-4, NUDOCS 8004140638 | |
| Download: ML19320A018 (19) | |
Text
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ATOMIC ENERGY COMMISSION
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DIRECTORATE OF REGULATORY CPERATIONS e'.
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AT L ANT A. GEORGa A 30303 RO Inspection Report No. 50-313/73-4 Licensee: Arkansas Power and Light company Sixth and Pine Streets Pine Bluff, Arkansas 71601 Facility Names Arkansas Nuclear One, Unit 1 Docket No. :
50-313 License No.:
CPPR-57 Category:
A3/B1 Location: Russellville, Arkansas Type of License:
B&W, PWR-2568 Mwt, 880 Mwe Type of Inspection: Routine, Unannounced h
Dates of Inspection: March 6-9, 1973, and March 20-21, 1973 Dates of Previous Inspection: February 20-23, 1973 Principal Inspector:
V. L. Brownlee, Reactor Inspector Facilities Section Fa;:ilities Construction Branch Accompanying Inspectors:
J. K. Rausch, Reactor Inspector Facilities Section Facilities Construction Branch E. J. Vallish, Reactor Inspector Facilities Section Facilities Construction Branch Other Accompanying Personnel: None
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Principal Inspectors
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V. L. Brownlee, Reactor Inspector
' Date Facilities Section Facilities Construction Branch Reviewed By:
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W. A. Crossman, Acting Senior Inspector Date Facilities Section (O Facilities Construction Branch 8 0 0 414 0 g38
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RO Report No. 50-313/73-4-2-
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SUMMARY OF FINDINGS I.
Enforcement Action A.
Violations None B.
Safety Items None
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II.
Licensee Action on Previously Identified Enforcement Matters A.
Violations None B.
Safety Items
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None x
h III.
New Unresolved Items 73-4/1 Faulty Overcurrent Trip Delay Device on Circuit Breakers For Engineered Safety Systems (RO Bulletin 73-1, RO:II Letter, Dated February 21, 1973)
AP&L is in the process of determining whether safety related circuit breakers of the described make and models are utilized at the ANO facilities.
73-4/2 r.i=4 torque valve Operators (Region II Letter Dated December 4, 1972)
AP&L has been responsive to our letter; however, they have not finalized their evaluation. This item remains open.
IV.
Status of Previously Reported Unresalved Items 72-2/1 Incore Instrument Guide Tube Failure (Region II Letter, Dated May 23, 1972, Item 1)
Field work is completed in accordance with the new design requirements. This item is closed.
(Details II, paragraph 4)
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RO Report No. 50-313/73-4-3-
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72-4/1 Reactor Vessel 'and Reactor Vessel Interna's Modification
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(Region II Letter, July 27,1972, Item 1)
The Babcock and Wilcox Company (B&W) Topical Report BAW-10051, dated September 1972, relative to the redesign of the reactor internals and instrument nozzles was ac-
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copted by Licensing. The FSAR by Amendment 31, dated November 17, 1972, references this topical report as being applicable to ANO 1.
Field work is completed in accord.ince with the new design requirements. This itam is closed.
(Details II, paragraph I
3)
72-4/2 Cable Routing (Region II Letter, July 27,1972, Item 2)
The routing of cables under the control room removable floor may not meet safeguards and reactor protection systems separations and loading criteria.
It is our understanding that the licensee will evaluate this item D
and corrective measures will be initiated as may become necessary. This item remains open.
72-4/3 Cable Routing (Region II Letter, July 27,1972, Item 2)
i The separation of safety channel wiring inside the B&W supplied panels may not meet the requirements of the safeguards and reactor protection systems separations
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I and loading requirements.
It is our understanding that the licensee will evaluate this item and corrective measures will be initiated as may become necessary. This
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item remains open.
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72-4/4 Control Rod Drive Motor Tube Defect Analysis (Region II Letter, July 27,1972, Item 3)
Upon arrival of documentation onsite, AP&L will audit the 4 -
NDT records to verify that tubes meet acceptance criteria of BAW 10047, Rev. 1, and identify physical location of installed minimum wall tubes. This item remains open.
(Details II, paragraph 5)
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RO Report No. 50-313/73-4-4-
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72-7/1 Pressurizer Safety'and Relief Valve Mounting and Connecting Piping (Region II Letter, August 21, 1972, Item 1)
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It is our understanding that the licensee will evaluate the pressurizer safety and relief valve mountings and connecting piping to assure that these have been analyzed for dynamic reaction forces during blowdown. This item remains open.
72-11/1 Paddle-Type Flow Switches (Region II Letter, December 19, 1972, Item 1)
It is our understanding that the licensee will obtain in 6rmation regarding the extent to which paddle-type l
flow switches are utilized within the nuclear piping systems. This item remains open.
72-11/2 B&W Safety Cabinets - Internal Panel Wiring (Region II Letter, December 19, 1972, Item 2) (See Item 72-4/3.)
It is our understanding that the licensee will require that B&W perform an engineering evaluation of all safety cabinets regarding conformance to the separations criteria for internal cabinet wiring. This item remains open.
72-11/3 Cable Installation in Control Room and Computer Room False Floor and Floor of Main Control Panels (Region II Letter, December 19, '1972, Item 3) (See Item 72-4/2. )
It is our understanding that the licensee will require Bechtel Engineering Corporation (Bechtel) to evaluate cable installation under the control room and computer room false floor regarding separations, loading and quality
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workmanship criteria. This item remains open.
72-11/4 Aluminum Instrumentation Housings Located Inside Containment (Region II Letter, December 19, 1972, Item 4)
i AP&L confirmed that environmental testing had been performed and that the instruments located within containment did have protective coatings that were compatible with environmental conditions. This item is closed.
(Details I, paragraph 4)
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RO Report No. 50-313/73-4-5-
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72-11/5 Storage and Inspection Program for Installed or' Stored
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In-Place Equignent (Region II ' Letter, December 19, 1972, Item 5)
Evamination of Bechtel's revised FIM procedure and site
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inspection records and discussion with AP&L/Bechtel QA/QC
personnel close this item.
(Details I, paragraph 5)
72-11/6 General Electric Company (G-E) Reactor Trip Breakers (Region II Letter, December 19, 1972, Item 6)
G-E supplied relays do not require the type of calibration for which test data was requested; therefore, this item is closed.
(Details I, paragraph 6)
r 72-11/7 Qualification of Containment Instrumentation (Region II
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Letter, December 19, 1972, Item 7)
AP&L confirmed that instrumentation located within con-tainment is qualified to function following the DBA.
This item is closed.
(Details I, paragraph 7)
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72-12/1 Discrepancies Between Piping and Control Systems Field work is completed in accordance with engineering instructions. This item is closed.
(Details I, paragraph 8)
72-12/2 Valve Wall Thickness Verification (Region II Letter, June 30, 1972)
J is our understanding that AP&L will develop ard implement a verification program when AEC defines the requirements regarding their letter of exception, July 28, 1972. This
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item remains open.
73-2/1 Reactor Building Service Water Cooling System Drawing Error (RO Inquiry Report No. 50-313/72-30/CDR)
Field work is completed in accordance with engineering
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instructions. This item is closed.
(Details T,
-paragraph 9)
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RO' Report No. 50-313/73-4-6-
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73-2/2 Lack of Material Control Weld Filler Material (RO' Inquiry Report No. 50-313/73-10/CDR)
This item is being evaluated by Headquarters staff. This item remains open.
j V.
Design Changes
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Core Flood Modificatior.s.
(Details III, paragraph 2)
VI.
Unusual Occurrences None VII.
Other Significant Findings A.
Project Status See Details I, Item 2, " General."
B.
Personnel or Organizational Changes None C.
Inquiry Reports None
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VIII.
Management Interview Arkansas Power and Light Company (AP&L)
N. A. Moore - Chief QA Coordinator A. C. Bland - QA Engineer (Civil)
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C. L. Bean - QA Engineer (Mechanical)
E. Quattlebaum - QA Engineer (Electrical)
L. W. Humphrey - QA Engineer (General)
Bechtel Engineering Corporation (Bechtel)
C. G. Beckham - Iead QA Engineer (Mechanical)
P. W. Sly - QC Engineer (Records)
The inspectors apprised the attendees of the general areas of inspection and findings.
No enforcement action items were identified.
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B0 Report No. 50-313/73-4-7-i i
l The licensee was informed that RO II had no further questions regarding previously identified unresolved items 72-2/1, 72-4/1,
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72-11/4, 72-11/5, 72-11/6, 72-11/7, 72-12/1, and 73-2/1.
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RO Report No. 50-313/73-4 I-1
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DETAILS I Prepared By:
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V. L. Brownlee, Reactor Date Inspector, Facilities Section, Facilities Construction Branch s
Dates of Inspection: March 6-9, 1973, and March 20-21, 1973 Reviewed By:
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9 5 / 73 W. A. Crossman, Acting Senior Date Inspector, Facilities Section Facilities Construction Branch i
'l 1.
Individuals contacted a.
Arkansas Power and Light Company (AP&L)
N. A. Moore - Chief QA Coordinator A. C. Bland - QC Inspector (Civil)
C. L. Bean - QC Inspector (Mechanical)
E. Quattlebaum - QC Inspector (Electrical)
L. Humphrey - QC Inspector (General)
J. W. Anderson - Plant Superintendent J. H. Woodward - Director of Power Production Department W. Cavanaugh III - Project Manager D. N. Bennett - QC Engineer (Operations)
b.
Contractor Organizations Bechtel Engineering Corporation (Bichtel)
W. T. Stubblefield - Project Superintendent C. G. Beckham - Lead QA Engineer G. Stewart - Construction /Startup Coordinator P. W. Sly - QC Engineer A. Nispeling - QC Engineer (Electrical)
2.
General This inspection encompassed two site visits, March 6-9, and March 20-21, 1973. The inspector was accompanied by F. J. Long, Chief, Facilities Construction Branch, RO:II, during the second site inspection. The
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RO' Report No. 50-313/73-4 I-2
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Director of Regulatory Operations.
F. Kruesi, and the Deputy Director of Field Operations, D. Knuth, met,with AP&L management personnel on March 20, 1973, and toured the construction site.
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Progress of Construction: Physical Construction is estimated to be i
964 complete. Piping systems installation is considered 99% complete.
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Electrical systems installation is estimated to be 984 complete.
Bechtel personnel onsite for Unit 1 is 536 with 53 st:bcontractor personnel. AP&L personnel is 92 including 5 QA.
Bechtel construction forces have decreased approximately 25% within the past 90 days.
Labor problems, none.
3.
Work Stannary and Schedule AP&L has announced a revised startup schedule. They have requested
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that the construction permit be extended from July 1,1973, to
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January 1, 1974. Fuel loading is scheduled for November 1973 with commercial operation estimated March 1974.
l Rannining piping systems installation wrk consists of installation of a small number of pipe hangers, pipe systems flushing and closing of
pipe loops. The containment post-tension systen stressing and greasing operations have been completed. Two tendons have not been installed (31-H-12 and 32-H-8).
Spent fuel pool work is scheduled for completion by the end of March. Deep cleaning and painting of the contaim.2ent building and other facilities has ccmanenced.
Systems turnover to operations is expected to be complete by the end of April. Forty-three systems have been completly turned over,
' fourteen systor.s have been partially (excess of 50%) turned over and eleven systems have no release.
4.
Aluminum Instrumentation Housings Iocated Inside Containment (Region II Letter, December 9, 1972)
The B&W Topical Repcrt, BAW-10017, Section 7, " Materials Compatibility,"
was presented for RO review. The tests did demonstrate that B&W sup-plied instrument protective coatings were compatible with the contain-ment environmental conditions.
It was reported that Bechtel supplied components do not have aluminum
housings. The purchasp specifications specify stainless or carbon steel housings.
RO has no further questions.
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Storage and Inspection Program for Installed or Stored In-Place Equizmient (Region II Letter, December 19, 1972, Item 5)
Bechtel FIM Procedure No. E-3, Rev. 4, February 7, 1973, has been revised to more specilically define storage and storage inspection requirements. Motor shaft rotation frequency is specified to be
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performed in accordance with manufacturer's instructions: however, site policy is to rotate on a quarterly frequency unless manufac-turer's requirements specify a shorter frequency.
(Primary coolant pump motors are rotated weekly.)
Examination of site magger and rotation records and discussion with AP&L/Bechtel QA/QC personnel indicate that RO:II hasno further questions regarding this item.
6.
General Electric Company (G-E) Reactor Trip Breakers (Region II Letter, December 19, 1972)
B&W reports that the circuit breakers (two a.c. and four d.c.) have no overcurrent devices or other such devices requiring calibration.
There are overvoltage and undervoltage setpoints in the CRDCS which
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" turn off" the system by opening the a.c. circuit breakers when an overvoltage or undervoltage condition is sensed within the system.
The procedure for their calibration is in the CR"r Instruction Manual, Vol. 1, Section 7.2.6.
These functions n identified as
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not being part of an NSS safety system.
RO has no further questions.
7.
Qualification of Containment Instrumentation (Region II Letter, December 19, 1972, Item 7)
AP&L confirmed that instrumentation and control components supplied t
by both B&W and Bechtel, which are required to operate following DBA, are qualified to function in the environmental pressure, temperature, humidity and radiation existing following DBA.
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RO:II has no further questions.
8.
Discrepancies Between Piping and Control Systems System modification to corract the deficiency consisted of:
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RO Report No. 50-313/73-4 I-4
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a.
Swap the feedwater piping between the reheaters and the reactor building penetrations. The pipe change eliminated the necessity to reconnect the instruments associated with the primary steam loop and brings the design in compliance with the B&W piping and instrument drawings.
'b.
Because the instruments on the steam generator shell (associated with the secondary steam loop) were associated with the incorrect steam generator number, their electrical cables to the ICS cabinets and in the computer had to be reconnected to their proper terminals. -
The output side of the ICS and the control panel wiring is unaf-
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fected since the control panel design basically followed the B&W patter as they relate to loop designation in the ICS design.
c.
For certain instruments located on the steam generator shells, the instrument index and data sheets and instruments tags vere changed.
d.
The main steam block and turbine stop valve nameplates and control
cables required changes.
e.
Safety evaluation - One case was identified as a " borderline" area which could be classified as affecting safety related equipnent.
The emergency feedwater valves as designed before this change would be inconsistent with respect to their redundant power supply and control switch location on the control panels. The power and control cables, as well as the electrical raceways, were interchanged.
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Bechtel has identified engineering and construction changes to effect resolution to the steam generator / loop A versus B problem.
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Physical examination of system changes did not identify deviations to design changes or field QA/QC program procedures. RO:II has no further questione.
9.
Reactor Bui.~i. ding Service Water Cooling System Drawing Error (RO Inquiry Report No. E9-313/72-3Q/CDR)
System modification to correct the deficiency consisted of:
a.
The service water supply header (HBD-46-10") supplying cooling water to VCC 2 A and B was disconnected from service water loop II (HBD-20-14") supply line and connected to the service water loop I (HBD-14-14") supply line.
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RO' Report No. 50-313/73-4 I-5 b.
The service water supply header -(HBD-45-10") supplying cooling water to VCC 2 C and D was disconnected from service s.+.er loop I (HBD-14-14") supply line and connected to the service rater loop (HB-20-14") supply line.
Bechtel is' ued Significant Deficiency Report No. 40, December 7,1972,
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s and Nonconformance Report No. M-692, January 16, 1972. NCR M-692 cleared the discrepancy indicating final inspection and acceptance on March 6, 1973.
This modification did not require changes to the physical system other than piping changes.
Examination of P&ID revisions (P&ID M-210, Rev. 6, Engineering Drawings M-38 and M-45) and visual examination of piping change close this item.
10. Post-Tensioning System Stressing and greasing of tendons has been completed. Cleaning operations to remove grease from the containment exterior was in progress during
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the inspection.
RO will continue to perform surveillance inspection of the containment external surfaces for indications of additional grease escaping from the tendon sheaths through hairline cracks in the concrete. The licensee and his contractor expects the hairline cracks to close after tensioning of tendons, thereby stopping grease flow.
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RO Report No. 50-313/73-4 II-l
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DETAILS II Prepared By:
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N O E.g.Vallish, Reactor Date Inspector, Facilities Section, Facilities Construction Branch Dates of Inspection: March 6-9, 1973 Reviewed By:
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Y*I*/3 W. A. Crossman, Acting Senior Date j
Inspector, Facilities Section i
Facilities Construction Branch
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Individuals contacted a.
Licensee' Organization - Arkansas Power and Light Company (AP&L)
- N. Moore - Chief QA Coordinator
- C. Bean - QC Inspector (Mechanical)
- A. Bland - QC Inspector (Civil)
- Present at Management Interview.
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b.
Contractor Organization - Babcock and Wilcox Company (B&W)
R. Moore - Site Engineer 2.
Organizational Changes R. Moore 'N replaced W. Hickson who has retired from B&W.
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3.
Reactor Vessel Internals Modification The react.or vessel and the reactor vessel internals are presently contained in the same enclosed area, namely the reactor pool volume.
This space is closed over the top and side by plastic shaeting and will
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be maintained to provide a Class B clean room in accordance with B&W Nuclear Standard FS -III-ld.
To gain access to this work area for in-spection of the intercals, it was necessary to " check-in" with a uni-formed guard in a change-room facility located at the side of the pool space where the internals are located. To enter the work areas, justi-fication was required; then all nonessential objects had to be checked-Jin at the change-room and clothes pockets emptied. Lintless coveralls and shoe covers were donned then the guard would permit entry.
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RO Report No. 50-313/73-4 II-2 Rwamination of the internals was conducted to verify completion of the
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modifications as described in topic 1 report BAW-10051. The modified lower grid and flow distributor containing the new incore instrument guide tubes was housed and supported by the installed lower grid
support rack. The core barrel and modified thermal shield were fastened to the lower grid by the permanent means of welded keepers
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over the machine screw heads. Craftsmen were drilling the pin holes for the dowels which secure the permanent location of the lower grid support guide blocks to the lower grid. Workers were putting the finishing touches on the revised surveillance specimen holder tubes.
Inside the core support shield workers were putting the final torque on the screws connecting the core support shield to the core barrel.
Torquing was being accomplished as precribed in the procedures, requiring increasing steps of torque force being applied in a pat-tern successively crossing the diameter of the bolt circle. Findings of the inspection are that the QA of the modification of these in-ternals is proceeding to the point where there are no further questions
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4.
Reactor Vessel Incore Instrument Guide Tube Failure The reactor vessel was entered under the same conditions described above. Inspection indicated that work was completed on the replace-
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ment of the modified incore instrument nozzles. These nozzles mate with the newly installed incore instrument guide tubes as the inter-nals are placed in the vessel. There are no further questions concerning the modifications of these tubes and the item is closed.
5.
Control Rod Drive Motor Tube Defect Analysis
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Inspection indicates that all the reexamined control rod drive motor tube extensions have been returned to the ANO site. All but two have been reinstalled on the closure head nozzle flanges. Vendor's documen-
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tation has not arrived on the site,,
AP&L intends to qualify the inspec-l tion results with regard to the acceptance limits as prescribed in Topical Report BAW-10047, after the documentation arrives onsite, This item remains open.
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6.
Control Rod Drive Mechanisms (CRDM)
An initial document review was made which determined that QA procedures, worle performance procedures and recordkeeping requirements were es-tablished for the receipt and site storage of these CRDM's.
The following documents were reviewed:
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RO Report No. 50-313/73-4 II-3
" Instruction Manual for Shim Safety Control Red Drive Mechanism,"
by Diamond Power Company.
" Receipt, Inspection, Handling Storage and Installation of the Control Rod Drive Mechanisms," FS-III-ld, a B&W Erection Department Nuclear Standard.
These documents provided adequate information to guide the receipt inspection and handling of these units and also provided information pertinent to the disposition of nonconforming components. These documents also provided specific instructions and requirements for unpacking the CRDM's, inspection, cleaning, placement, setting, alignment, hookup and final adjustment during the installation of these units. Bechtel Corporation's (Bechtel) journeymen mechanics assembled these CRDM's under the consultation and guidance of the B&W engineer provided for that purpose. After installation is completed, FS-III-ld, paragraph 9.8, requires completion of an NSS Component Installation Inscection Report (PDS-31581) in accordance with the Inspection Reporting Specification FS-IV-1 and that discrepant items be reported on PDS-31582 in accordance with FS-IV-2.
This will assure that the installation meets the construction requirements.
Inspection was performed of the work performance in the field for the
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assembly of the CRDM components. Final assembly and lubrication is taking place in an enclosed area in the containment building. This enclosed area is being maintained es a Class B clean area as required by B&W Nuclear Standard FS-III-ld.
Detailed examination of the assembled portion indicated that proper techniques of handling, placing and installation were used. Personnel were observed who continually used vacuum cleaners in the clean rooms to maintain the level of cicanliness.
7.
Reactor Vessel Internals An initial document review was made which determined that QC procedures, work performance procedures and recordkeeping requirements were established for the receipt and site storage of these reactor vessel
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internals. The following document was reviewed:
" Receipt, Inspection, Handling, Storage and Installation of the Reactor Vessel Internals,"
FS-III-le, a B&W Erection Department Nuclear Standard. This document provides adequate information to guide the construction forces during the receipt inspection and handling of these components.
Specification FS-III-le requires performance of receiving inspections and their docu-mentation on PDS-31581 forms in accordance with Specification FS-IV-1.
Deficiencies and nonconformance are to be reported on PDS-31582 forms
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l in accordance with Specification FS-IV-2.
The reviewed document pro-vided special handling requirements for each of the internals.
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i also includes instructions pertinent to unpacking, inspection, cleaning, placement and final adjustment.
Instructions were written and sup-(q plemented with pictures and sketches.
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Rd Report No. 50-313/73-4 II-4 Assembly and installation work on these internals were accontplished by Bechtel journeymen craftmen using consultation service from the B&W engineers.. Specification FS-III-le states requirements for the completion of Installation Inspection Report PDS-31581 after assembled installation
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is completed. Discrepant findings are to be reported on NSS Cceponent Deviation Report PDS-31582.
l Detailed inspection of the assembled internals and discussion with the
mechanics in the field provided sufficient evidence that the techniques used for handling and assembly of these internals was indeed in ac-cordance with the construction requirements. Examination in the field of the enclosure of the area, in which the work on these internals was
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being performed, revealed that provisions were established for the i
j protection and maintenance of cleanliness of these internals.
In-
spection also revealed that although there were no nonconforming parts
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resulting freat the assembly of these internals, Specification FS-III-le
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did provide measures to prohibit the use of any components found to be in nonconformance.
8.
Primary Coolant Pump Installation
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An initial document review was made which determined that QC procedures, work performance procedures and recordkeeping requirements were established for the receipt and site storage of the primary coolant
- pumps. The following B&W Erection Department nuclear standards were reviewed: " Receipt Inspection, Handling, Storage and Installation
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i Specifications for Reactor Coolant Piping," FS-III-3, " Receipt Inspection, Handling, Storage and Installation Specifications for
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Reactor Coolant Pump Internals and Motors," FS-III-4.
Also reviewed was the Byron Jackson Punip Division's document titled, " Reactor Coolant Pump Technical Manual, Part II for Arkansas."
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The reviewed documents provided adequate information to the construction forces for guidance during the receipt inspection and handling operations.
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The documents also provided adequate means of disposition of noncon-
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forming items found during these inspections. These documents prescribed i
special handling and storage requirements for those items requiring it.
The crane capacity requirements stated were not anything requiring special
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type crane service for either receipt handling or installation.
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The documents reviewed provided instructions pertinent to handling,
- unpacking, inspection, cleaning, placement, setting, leveling, hookup and final adjustment of the primary pump casing and internals. These documents were made available to the Bechtel journeymen installing these pumps.
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RO Report No. 50-313/73-4 II-5
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I In document FS-III-4a, the requirement for a final inspection of the
t completed installation is stated. This inspection is to be documented
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on the form PDS-31581 in accordance with the Inspection Reporting Specification FS-IV-1.
The Byron-Jackson Pump Division Technical
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Manual was reviewed and contained the necessary inspection criteria for the final adjustments of these pumps.
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Observations and inspection at the site indicated that proper methods and acceptable techniques of handling, placing, and installation were used during the installation of rhese pumps. Present activity on these unitz consist of mounting the three-inch diameter steel cable pipe l
whip restraints on the pump casing and on the cold leg below tha pumps.
Fitup and installation of the small diameter, bearing coolant and lubrication pipes are aisc being accomplished at this time. Couplings are not yet installed between the motors and the pumps.
Observations at the construction locations of the work being performed indicated that adequate protectic,n and maintenance of cleanliness is being accomplished for these pumps above, around and below these units f
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RO Report No. 50-313/73-4 III-l
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DETAILS III Prepared By:
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J.' K. 'Rausch, ' Reactor Date
/ Inspector Facilities Section Facilities Construction Branch Dates of Inspection: Ma ch 6-9, 1973 Reviewed By:
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W. A. Crossman, Acting Date Senior Inspector Facilities Section Facilities Construction Branch 1.
Individuals Contacted a.
Arkansas Power and Light Company (AP&L)
N.- A. Moore - Chief QA Coordinator A. C. Bland - QA Engineer (Civil)
C. L. Bean - QA Engineer (Mechanical)
L. W. Humphrey - QA Engineer (General)
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Contractor Organizations (1) Bechtel Engineering Corporation (Bechtel)
K. Higgins - QC Engineer (Mechanical)
(2) Babcock and Wilcox Company (B&W)
R. Moore - Consultant Engineer 2.
Core-Flood Modification Consisting of Welding Flow Restricting Orifices in the Core Flood Piping at the Reactor Vessel The field change procedure, FC No. 52 to Dwg No. 139681E, was reviewed and found to be satisfactory. AP&L was asked to clarify terminology in reference to identifying the restricting orifice
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device. In some cases, the procedure referenced " sleeves" and in
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other instances " inserts". AP&L insured through B&W that just one piece was involved and that Bechtel understood.
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RO Report No. 50-313/73-4 III-2
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f Work completed on the modification at the time of the inspection included welding in the \\-inch weld and the h-inch tacking ring in each core nozzle of the reactor vessel. Required machining of weld buildup was complete.
Work is progress consisted of grinding to complete backside of ring buildup and deburring of machined areas.
Work remaining to be done includes PT of buildup areas, removal of defects, weld repair, if necessary, and installation of venturi
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inserts with TIG weld. In addition, there are system piping ad-ditions that are to be done at a later date. RO:II will document later modifications.
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A physical inspection of the work area showed that procedures were being followed. Travelers being used were not properly identified as to core flood nozzle location. The north nozzle was identified as south and the south as north. Technically, there was no problem since the work to either nozzle is required to be identical. The corrective action was to change nozzle location identification.
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