IR 05000313/1973009
| ML19309D977 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/24/1973 |
| From: | Brownlee V, Crossman W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19309D936 | List: |
| References | |
| 50-313-73-09, 50-313-73-9, NUDOCS 8004110763 | |
| Download: ML19309D977 (10) | |
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UNITED STATES ATOMid ENERGY COMMISSION o
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DIRECTORATE OF REGULATORY OPERATIONS i
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REGloNll - SUIT E 810
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RO Inspection Report No. 50-313/73-9 Licensee: Arkansas Power and Light Company Sixth and Pine Streets Pine Bluff, Arkansas 71601 Facility Name: Arkansas Nuclear One, Unit 1 Docket No.:
50-313 License No.:
CPPR-57 Category:
A3/B1 Location: Russellville, Arkansas Type of Licensee: B&W, PWR-2568 Mwt, 880 Mwe Type of Inspection: Routine, Unannounced, Construction Dates of Inspection: July 5-6,1973 Dates of Previous Inspection: June 12-15,1973 Principal Inspector: Y', /.h G CT 7/27/77
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V. L. Brownlee, Reactor Inspector Date Facilities Section Facilities Construction Branch Accompanying Inspectors: None
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Other Accompanying Personnel: None Reviewed by:
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W. A. Crossman, Senior Inspector Date Facilities Section Facilities Construction Branch E
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RO Rpt. No. 50-313/73-9-2-
SID9fARY OF FINDINGS
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I.
Enforcement Action A.
Violations None
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B.
Safety Items None
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II.
Licensee Action on Previously Identified Enforcement Matters A.
Violations 73-6-Al Lack of Documentation and Effecting Followun of Corrective Action Regarding Possible Nonconforming Materials, Parts or Components Nm Contrary to Criteria IV and XVI, the inspection revealed that AP&L's program for handling of signifi-cant construction deficiencies failed to document and effect followup evaluation of an apparent significant construction deficiency regarding the control rod drive trip breaker undervoltage trip assembly problem identified at the Oconee nuclear facility. This item remains open.
73-6-A2 Documentation of Nonconforming Materials, Parts or
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Components Contrary to Criterion IV, the inspection revealed that AP&L's constructor, Bechtel, has been lax in implementing in a timely manner nonconformance reports for the purpose.
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of reporting, controlling, processing and documenting resolution of nonconformances identified during inspection.
This was evidenced by the several months span between identifying the mechanical interlock problems associated with the Allis-Chalmers motor control centers and initiating the nonconformance report. This item remains open.
B.
Safety Itsms None
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RO'Rpt. No. 50-313/73-9-3-
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III. New Unresolved Items
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None IV.
Status of Previousiv Reported Unresolved Items 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
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understanding that the licensee will evaluate this item 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 I
supplied panels may not meet the requirements of the safeguards and reactor protection systems separations 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 item remains open.
72-7/1 Pressurizer Safety and Relief Valve Mounting and Connecting Piping (Region II Letter, August 21,19 72, Item 1)
It is our understanding that the licensee will evaluate the J
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.
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72-11/2 B&W Safety cabinets - Internal Panel Wiring (Region II Letter, December 19,1972, Item 2) (See Item 72-4/3)
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This item is resolved.
(Details I, paragraph 9)
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 bur understanding that the licensee will require Bechtel
to evaluate cable installation under the control room and computer room false floor regarding separations, loading
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and quality worknanship criteria. This item remains open.
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RO Rpt. No. 50-313/73-9-4-72-12/2 valve Wall Thickness Verification (Region II Letters.
June 30.1972 and February 16. 1973)
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AP&L (Bechtel) has completed the UT measurement program.
RO:II will examine the verification program on July 18-20, 1973.
(Details I, paragraph 3)
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73-2/2 Lack of Material Control-Weld Filler Material (R0 Inquiry Report No. 50-313/73-lQ/CDR)
Regulatory staff (Headquarters) has reviewed and accepted B&W Reports BAR-1402 and 1403 regarding steam generator, reactor vessel and vessel head weld material records.
This item is resolved.
(Details I, paragraph 4)
V.
Design Changes None VI.
Unusual Occurrences None
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VII.
Other Significant Findings A.
Project Status
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See Details I, paragraph 2, " General," and paragraph 8, " Mixing of Fuel Pellets."
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B.
Personnel or Organizational Changes J. D. Phillips is now designated as Senior Vice President.
l D. N. Bennett, AP&L Operations QC Engineer, is being transferred l
to San Francisco as AP&L contact at Bechtel. Bennett will be
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replaced by J. L. Orlicek, Staff Engineer, Little Rock. Orlicek has been a member of the QA committee.
B. F. Allen, Bechtel Welding Engineer, is leaving the site. He will be replaced by W. D. Schweter, the present Welding QC Engineer.
C.
Inquiry Reports
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IMAGE EVALUATION NNNN TEST TARGET (MT-3)
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MICROCOPY RESOLUTION YdST CHART
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R0 Rpt. No. 50-313/73-9-5-VIII. Management Interview
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The inspector met with Moore, Bland, Bean, Quattlebaum and Humphrey of AP&L' and Beckham and Sly of Bechtel.
The attendees were apprised of the scope and findings of the
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inspection. No major areas of concern were discussed.
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RO Rpt. No. 50-313/73-9 I-l
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DETAILS I Prepared by: l/b /.MtL VdLL-7/1v / 77 o
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f V. L. Brownlee, Reactor
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Inspector, Facilities Section Facilities Construction Branch Dates of Inspection: July 5-6, 1973 Reviewed by:
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7/29 !23
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U W. A. Crossman, Senior Inspector Date 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 - QC Inspector (Civil)
C. L. Bean - QC Inspector (Mechanical)
,e E. Quattlebaum - QC Inspector (Electrical)
L. Humphrey - QC Inspector (General)
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Contractor Organizations Bechtel Engineering Corporation (Bechtel)
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W. J. Stubblefield - Project Superintendent C. G. Beckham - Lead QA Engineer
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P. W. Sly - QC Engineer R. McKinnon - Lead Mechanical Engineer W. D. Schuster - QC Engineer (Welding)
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2.
General
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Progress of Construction: Total personnel onsite, 816. Total construction personnel assigned to Unit 1, 445. Approxima;.ely 32 construction personnel continue to work on original scope of contract work. Remaining personnel are on rework and modi-fication. No labor problems exist. Operations and test personnel total approximately 150.
3.
Valie Wall Thickness Verification p
AP&L has directed Bechtel to evaluate the ANO-1 verification (b)
program to insure that it meets the AEC letter of February 16, 1973, requirements. Bechtel recommended measurement of fifteen i
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RO Rpt. No. 50-313/73-9 I-2 valves, three inches and larger and provided engineering evaluation for forged valves 2-1/2 inches and smaller.
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Bechtel has completed the UT measurement program and concluded that three relief valves, two 10-inch and one 12-inch gate valves, are acceptable. Other valves (nine), three B&W and six Bechtel supplied, had at least ont measurement less than specified minimum.
AP&L notified RO:II on June 1, 1973, of the valve wall thickness deficiency and submitted a significant deficiency report to RO dated July 2, 1973.
RO:II has made arrangements to examine the ANO-1, two-valve wall thickness verification programs Iuly 18-20,1973.
4.
Lack of Weld Material Control-Weld Filler Material The matters regarding lack of weld filler material control (records) as described in B&W reports BAW-1402, " Investigation of Steam Generator Weld Records," And BAW-1403, " Investigation of Major Component Weld Records" (reactor vessel and head), have been reviewed by regulatory 3O staff (Headquarters) and accepted. Review and acceptance of these reports is as noted in AEC letters to B&W dated April 24, 1973, and June 19, 1973.
AP&L notified RO:II of January 5,1973, of the steam generator weld record deficiency and submitted a significant deficiency report to RO dated February 3,1973, regarding B&W Report BAW-1402. Notification of the reactor vessel and head weld record deficiency was received by RO:II on May 18, 1973, and the significant deficiency report was submitted May 23, 1973.
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B&W has informed AP&L that equipment data packages will reflect the deficiencies and j ustification. The data packages will be reviewed by AP&L to determine the adequacy of the information.
RO:II has no further questions regarding these items.
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5.
Main Steam Line Repair AP&L notified RO:II on May 14, 1973, tha~t a major repair to the main steam line from "A" steam generator must be performed.
During the process of removing a 36" x 24" reducing ell, the weldor's cutting torch cut into the weld prep area of weld No. EBB-3-4.
AP&L evaluated the repair and did not consider it a significant deficiency.
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RO Rpt. No. 50-313/73-9 I-3 A special repair procedure was developed. The deficiency and repair is documented by NCR #M863 and field QC records.
Exam-ination of ald area and repair records identified no areas of
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departure from normal QA/QC practices and field program.
RO:II has no further questions regarding this item.
6.
Control Rod Drive (CRD) Breaker Undervoltage Trip Assembly On June 5, 1973, R. S. Eckerd, Senior Engineer, Diamond Power j
Speciality Group, supervised and inspected the removal and replacement of the undervoltage trip devices, G-E Part No.
269C282, in Trip A, Trip B and d.c. circuit breakers in the l
CRD's.
The pull in and drop out voltages were checked and found to be 74-80v pull in and 50-55 drop out.
D.C. resistance of all six
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coils was checked and found to be nominally 25 ohms. Spring l
tension was not adjusted since the pull in and drop out voltages are normal. Fuses were to be installed for overcurrent protection.
RO:II has no further questions regarding this item.
7.
Small Valve Damage AP&L info'rmed RO:II, June 4, 1972, that six 1/2-inch to one-inch motor operated valves in the sampling system were found to have.
damaged wedges.
j It has been determined that cause of damage was excessive manual
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induced torque.
Handwheels have been removed and valves are to be repaired or replaced. Smaller handwheels are to be installed. Velan in-formed Bechtel/AP&L that torque switches must be set ar minimum.
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8.
Mixing of Fuel Pellets AP&L informeli RO:II June 27, 1973, that there had been some
minor mixing of ANO-1 and SMUD fuel pellets at the B&W Fuel Fabrication Plant, Lynchburg, Virginia.
AP&L had noti received the B&W report at the time of the inspection.
AP&L assured the inspector that RO:II would receive a copy of the B&W report. AP&L has requested that R. T. Lally, Middle South Services (AP&L's fuel consultant), perform an investigation of the fuel matter.
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RO Rpt. No. 50-313/73-9 I-4 AP&L, at present, does not consider the item as reportable to the AEC in accordance with 10 CFR 50.55(e). AP&L's position is that though there was a breakdown in plant QC, the mixup
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involving the 3.05% enrichment for ANO-1 and 2.01% enrichment
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for SMUD does not create a safety factor for ANO-1.
RO:II Facilities Test and Startup Branch will follow up on this item.
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9.
B&W Safety Cabinets - Internal Panel Wiring B&W and Bechtel have reviewed the cabinet internal and intercabinet wiring separation, philosophy and physical installation of the engineered safety actuation system (ESAS) and reactor protection system (RPS) and conclude that separation is adequate and that there is no violation of single failure criteria.
The philosophy of the ESAS is that each of the two digital sub-systems monitor the trip of each of the three analog subsystems and produce actuation outputs when two or more analog subsystems call for protective action. The RPS is a parallel case, except there is a two-out-of-four logic.
,v The nature of the coincidence logic requires that all of the redundant inputs be brought together at the coincidence logic.
In the ESAS, the analog subsystems produce electrically isolated outputs for each of the digital subsystems. This isolation prevents faults in one subsystem from propagating into other subsystems and preclude the system from performing its safety function. Within a given digital subsystem, the input transmission lines are brought together in a common wireway and routed to a common coincidence logic.
This common wireway routing into the cabinet and cabinet internal wiring was RO:II's question. RO:II has no further questions regarding this item.
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10. Emergency Core Cooling System Modification Completion of crossover piping modification is not expected to be completed until the latter part of August 1973.
M. W. Kellogg is procuring material and shop fabricating spool pieces. Material is expected onsite the first part of August and site personnel anticipate approximately two weeks installation time.
11. Failure of Valve Disc Retainers - RCE 73-1
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AP&L has verified that the B&W and Bechtel scope of supply does noc include the type valve specified in the RCE.
RO:II has no further questions regarding this item.
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