ML19309D887
| ML19309D887 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/04/1973 |
| From: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Phillips J ARKANSAS POWER & LIGHT CO. |
| Shared Package | |
| ML19309D855 | List: |
| References | |
| NUDOCS 8004110722 | |
| Download: ML19309D887 (6) | |
See also: IR 05000313/1973006
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UNITED STATES
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ATOMIC ENERGY COMMISSION
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DIRECTORATE OF REGULATCRY OPERATIONS
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230 PE ACMTREE ST RE ET, NoRT HwEST
A T L. A N T A. G E oRG a A 30303
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In Reply Refer To.
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RO:II:VLB
50-313/73-6
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Arkansas Power and Light Company
Atta: Mr. J. D. Phillips
Vice President and Chief Engineer
Sixth and Pine Streets
Pine Bluff, Arkansas 71601
Gentlemen:
(
This refers to the construction inspection conducted by Mr. Brownlee on
May 9-11, 1973, of activities authorized by AEC Construction Permit No.
CPPR-57 for the Arkansas Nuclear One, Unit 1 facility.
Our findings
were discussed by Mr. Brownlee with Messrs. Moore, Bland, and Bean of
your staff and Messrs. Beckham and Sly of Bechtel Engineering Corpora-
tion at the conclusion of the inspection.
Areas examined during the inspection included status of proje_c, circuit
breakers for engineered safety systems, limitorque valve operators, con-
trol rod drive motor tube defect analysis, paddle-type flow switches,
motor control center reversing starter mechanical interlocks, and under-
voltage trip assemblies of the control rod drive trip breakers.
Within
these areas, the inspection consisted of selective av=h=tions of pro-
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cedures and representative records, interviews with personnel and observa-
tions by the inspector.
During the inspection, it was found that certain of your activities appear
to be in violation with Appendix B to 10 CFR 50 of the AEC regulations,
" Quality Assurance Criteria for Nuclear Power Plants."
The violations
and references to the pertinent requirements are identified in Section I
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of the enclosure.
This notice is sent to you pursuant to the provisions
of Section 2.201 of the AEC's " Rules of Practice," Part 2, Title 10, Code
of Federal Regul'ations.
Section 2.201 requires you to sub.ait to this
office within 30 days of your receipt of this notice, a written statement
or explanation in reply including:
(1) corrective steps which have been
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taken by you, and, the results achieved; (2) corrective steps which will
be taken to avoid further violations; and (3) the date when full compli-
ance will be achieved.
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Arkansas Power and
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Light company
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No new unresolved items resulted from this inspection.
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We have also examined actions you have taken with regard to previously
identified unres,1ved items. The status of these items is identified in
Section IV of the enclosure.
Should you have any questions concerning this letter, you m2y communicate
directly with this office.
Very truly yours,
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f rman C. Moseley
Director
Enclosure:
As stated
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ENCLOSURE
DOCKET No. 50-313
I.
Enforcement Action
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A.
Violations
Certain items appear to be in violation with 10 CFR 50,
Appendix B, " Quality Assurance Criteria for Nuclear Power
Plants," as indicated below:
73-6-Al Lack of Documentation and Effective Followup of
Corrective Action Regarding Possible Nonconforming
Materials, Parts or Components
' Contrary to Criteria XV and XVI, the inspection revealed
that AP&L's program for handling of significant con-
struction deficiencies failed to document and effect
followup evaluation of an apparent significant construc-
tion deficiency regarding the control rod drive trip
breaker undervoltage trip assembly problem identified
at the Oconee nuclear facility.
73-6-A2 Documentation of Nonconforming Materials, Parts or
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Components
Contrary to Criterion XV, the inspection revealed that
2P&L's constructor, Bechtel, has been lax in implementing
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in a timely manner nonconformance reports for the purpose
of reporting, controlling, processing and documenting
resolution of nonconformances identified during inspec-
tion. 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.
B.
Safety Items
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None
II.
Licensee Action on Previously Identified Enforcement Matters
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A.
Violations
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None
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B.
Safety Items
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None
III. New Unresolved Items
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IV.
Status of Previously 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
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systt as separations and loading criteria. It is our
understanding that the licensee will evaluate this item
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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)
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The separation of safety channel wiring inside the B&W
supplied panels may not meet the requirements of the
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safeguards and reactor protection systems separations
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and loading requirements. It is our understanding that
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the licensee will evaluate this item and corrective
measures will be initiated as may become necessary. This
iten remains open.
72-4/4 control Rod Drive Motor Tube Defect Analysis (Region II
Letter, July 27, 1972, Item 2)
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rival of documentation onsite, AP&L will audit the
ND'r records to verify that tubes meet acceptance criteria
of BAW 10047, Rev. 1, and identify physical location of
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installed minimum wall tubes.
AP&L has documented acceptable tubes by serial number and
physical location. This item is closed.
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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 mounting 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)
AP&L has determined that those paddle-type flow switches to
be used do not represent a safety problem. This item is
closed.
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
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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
Beebcel to evaluate cable installation under the control
room and computer room false floor regarding separations,
loading and quality workmanship criteria. This item
remains open.
72-12/2 Valve Wall Thickness Verification (Region II Letter,
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June 30, 1972)
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It is our understanding that AP&L will develop and implement
a verification program when AEC defines the requirements
regarding their letter of exception, July 28, 1972. This
item remains open.
73-2/2 Lack of Material Control Weld Filler Material (R0 Inquiry
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Report No. 50-313/73-lQ/CDR)
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This item is being evaluated by Headquarters staff. This
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item remains open.
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73-4/1 Faulty Overcurrent Trip Lelay Device on Circuit Breakers
For Engineered Safety Systems (R0 Bulletin 73-1, RO:II
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Letter, Dated February 21, 1973)
B&W and Bechtel report that no circuit breakers of the type
identified in the R0 Bulletin are used. This item is closed.
73-4/2 Limitorque valve Operators (Region II Letter, December 4,
1972)
AP&L has identified the defective units and are in the
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process of changing out the defective torque switches.
This item is closed.
73-6/1 Motor Control Center - Reversing Starters (R0 .aquiry
Report No. 50-313/73-2Q)
AP&L has iden'ified the defective units and are in the
process of changing out the defective units. This item
is closed.
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