ML19320A051
| ML19320A051 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/10/1973 |
| From: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Phillips J ARKANSAS POWER & LIGHT CO. |
| Shared Package | |
| ML19320A047 | List: |
| References | |
| NUDOCS 8004140668 | |
| Download: ML19320A051 (5) | |
See also: IR 05000313/1973005
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UNITED STATES
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ATOMIC ENERGY COMMISSION
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DIRECTORATE OF REGULATCRY CPERATIONS
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In Reply Refer To:
RO:II:MSK
MAY 101973
50-313/73-5
Arkansas Power and Light Company
Attn: Mr. J. D. Phillips
Vice President and Chief Engineer
Sixth and Pine Streets
Pine Bluff, Arkansas 71601
Gentlemen:
This refers to the inspection conducted by Mr. M. S. Kidd and other
members of t.his office on April 10-13, 1973, of the activities
authorized by AEC Construction Permit No. CPPR-57 for the Arkansas
Nuclear One, Unit 1 facility, and to the discussions held with
Mr. J. W. Anderson and other members of your staff at the conclusion
of the inspection.
Areas examined during this inspection included previously identified
unresolved items, preoperational test procedures and test results,
emergency, alarm, and operating procedures, your zero power 'and power
' ascension test programs, and evaluation of a crack in the reactor
building spray system piping. Within these areas, the inspection
consisted of selective examinations of procedures and representative
records, interviews with plant personnel, and observations by the
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inspectors.
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During this inspection, it was found that certain of your activities
appear to be in violation of the Code of Federal Regulations. These
activities and reference to pertinent requirements are listed in Part I
of the enclosure to this letter.
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This notice is sent to you pursuant to the provisions of Section 2.201
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of the AEC's " Rules of Practice," Part 2, Title 10, Code of Federal
Regulations. Section 2.201 requires you to submit to this office
within thirty (30) days of your receipt of this notice, a written
statement of explanation in reply including:
(1) corrective steps
-wnich have been taken by you, and the results achieved; (2) corrective,
steps which will be taken to avoid further violations; and (3) the
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date when full compliance will be achieved.
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Previously identified and new outstanding items are summarized in
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Parts II through IV of the enclosure to this letter.
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- irkansas Power and Light
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MAY 101973 .
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You should note that this letter and your reply to this letter will
be disclosed to the public by being placed in an AEC Public Document
Room.
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Should you have any questions concerning this letter, we will be glad
to discuss them with you.
Very truly yours,
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orman C. Moseley
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Director
Enclosure:
As stated
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ENCLOSURE'
Arkansas Nuclear One, Unit 1
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Docket No. 50-313
I.
Enforcement Action
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A.
Violations
1.
Criterion V of Appendix B to 10 CFR 50 states, in
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part, " Activities affecting quality shall be prescribed
by documented instructions, procedures . . . and shall
be accomplished in accordance with these instructions,
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procedures,
....
Contrary to the above, three examples of procedure
violation were noted during the review of the test
resulte of TP 204.02, " Reactor Building Spray System
Electrical Test." The examples of violation are as
follows:
a.
The use of jumpers was not logged as required by
OP 1004.09, " Plan for Preoperational Testing."
b.
A portion of the test procedure was deleted
without the proper approval as required by
OP 1004.09, " Plan for-Preoperat'onal Testing."
c.
The test procedure was not followed during
the performance of certain portions of the test.
2.
Paragraph (2) of.10 CFR 50.55(e) states, "The holder
of a construction permit shall promptly notify the
appropriate Atomic Energy Commission Regional ' Regulatory
Operations' office of each reportable deficiency."
Contrary to the above, RO:II was not promptly notified
of a reportable construction deficiency found in the
Jeactor building spray system on March 27, 1973.
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B.
Safety Items
None
II .
Licensee Action on Previously Identified Enforcement Matters
A.
Violations
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Caseous Radwaste Tank Volumes
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Evaluation of the problem of waste gas decay and purge
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tanks which were constructed smaller than FSAR specifica-
tions was being conducted by Bechtel Corporation.
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B.
Safety Items
There were no previously identified safety items.
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III.
New Unresolved Items
73-5/1 Reactor Building Ventilation System Tests
Test procedures for the reactor builcing ventilation
and purge systems do not appear to test certain
functional requirements and capabilities of the
systems described in the FSAR.
73-5/2 Core Flood System Flow Rate T M
The licensee does not plan to perform a flow rate
test on the core flood system which would demonstrate
reflood capabilities discussed in the FSAR.
IV .
Status of Previously Reported Unresolved Items
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72-6/1 Onsite Training Program
The formal classroom-type training program is
almost completc. This item is resolved.
72-6/2 Staffing commitments
One waste control operator is needed to fulfill
FS AR requirements.
72-9/1 Incorporation of All Safety Related Equipment
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in the FSAR Q-List
Not inspected.
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72-9/2 Decumentation of Station Test Coordinator's
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Prerequisire_ Duties in the Conduct of Tests
Documentation has been implemented per the Unit 1
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Plan For Preoperational Testing. This item
is resolved.
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72-9/3 Preparation of Test Procedures to Cover Tests in
" Guide For Planning of Preoperational Test Programs"
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The licensee plans to test safety related systems
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which contain pneumatic devices under loss of air
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73-1/1 Lack of Implementing Procedure For Use of Jumpers
and Bypasses
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This procedure has been written and is in the review
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process.
73-1/2 Comnents on Core Flood Functional Test Procedure
The inspector's connents on this procedure have been
resolved.
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73-3/1 Completion of Construction of Radwaste Systems
Not inspected.
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