ML19320C878
| ML19320C878 | |
| Person / Time | |
|---|---|
| Site: | Phipps Bend  |
| Issue date: | 07/02/1980 |
| From: | Murphy C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Parris H TENNESSEE VALLEY AUTHORITY |
| Shared Package | |
| ML19320C879 | List: |
| References | |
| NUDOCS 8007180189 | |
| Download: ML19320C878 (1) | |
See also: IR 05000553/1980008
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION 11
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101 MARIETTA ST., N.W., SUITE 3100
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ATLANTA, GEORGIA 30303
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JUL 2 1980
In Reply Refer To:
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RII:JL
50-553/80-08
50-554/80-07
Tennessee Valley Authority
ATTN:
H. G. Parris
Manager of Power
500A Chestnut Street Tower II
Chattanooga, TN 37401
Gentlemen:
Thank you for your letter of June 19, 1980 informing us of steps you have taken
to correct the item of noncompliance concerning activities under NRC Construction
Permit Nos. CPPR-162 and CPPR-163 brought to your attention in our letter of
May 28, 1980. We will examine your corrective actions and plans during subse-
quent inspections.
We appreciate your cooperation with us.
Sincerely,
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C. E. Murphy, Chief
Reactor Construction and Engineering
Support Branch
W. P. Kelleghan, Project Manager
cc:
J. F. Cox, Supervisor, Nuclear
Licensing Section
J. E. Wills, Project Engineer
H. N. Culver, Chief, Nuclear Safety
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Review Staff
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TENNESSEE VALLEY Ab'THORITY
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CH ATTANOOGA, TENNESSEE 3Y4b'R0 P E F ~ N
400 Chestnut Street Tow'eb I'IN I
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June 19, 1980
Mr. James P. O'Reilly, Director
Office of Inspection and Enforcement
U.S. Nuclear Regulatory Cornmission
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Region II - Suite 3100
101 Marietta Street
Atlanta, Georgia 30303
Dear Mr. O'Reilly:
Enclosed is our responise to C. E. Murphy's May 28, 1980, letter,
RII:JJL 50-553/80-08 and 50-554/80-07, regarding activities at the
Phipps Bend Nuclear Plant which appeared to have been in violation of
NRC regulations.
We have reviewed the subject inspection report and find no proprietary
it formation in the report. If you have any questions regarding this
matter, please call Jim Domer at FTS 857-2014.
Very truly yours,
TENNESSEE VALLEY AUTHORITY
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L. M. Mills, Manager
Nuclear Regulation and Safety
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Enclosure
cc:
Mr. Victor Stello, Director (Enclosure)
Office of Inspection and Enforcement
U.S. Nuclear Regulatory Commission
Washington, DC 20555
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OFFICIAL COPY
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ENCLOSURE
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FINAL RESPONSE TO NRC LETTER
FROM C. E. MURPHY TO H. G. PARRIS
DATED MAY 28, 1980
(REFERENCE RII:JJL 50-553/80-08, 50-554/80-07)
This report responds to the Notice of Violation described in Appendix A
of the OIE Inspection Report referenced above. This is the final
report on the subject noncompliance.
Noncompliance Item - Deficiency 50-553/80-08-01, 50-554/80-07-01
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As required by Criterion " of Appendix B to 10CFR50, implemented by
PSAR Section 17.1A.5, " Activities affecting quality shall be
prescribed by documented instructions, procedures, or drawings . . .
and shall be accomplished in accordance with these instructions,
procedures, or drawings." TVA , specification G-32 requires delivery
of materials from the batching equipment to be within the following
limits of the mix design proportions determined ir. laboratory and
field adjusted mixes: Flyash, 1 percent; sand, 2 percent; and
3/8-inch aggregate, 2 percent. Quality Control Instruction (QCI)
C-212 requires the concrete batch plant inspector to visually inspect
all scale dials as they weigh up and make or witness adjustments if
scale dials indicate weights other than design mix weights. QCI-C-212
also requires the batch plant inspector to verify visually that the
continuous recorder chart readings coincide with scale readings.'
Contrary to the above:
1.
In batching of concrete for placement in safety-related
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structures, flyash quantity exceeded the specified mix design
quantity by 8 percent, the sand quantity exceeded specified mix
design quantity by 4 percent, and the 3/8-inch aggregate exceeded
specified mix design quantity by 6 percent.
2.
The batch plant inspector did not visually inspect the scale dials
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as they weighed up and make or witness adjustments when scale
dials indicated weights other than design mix weights.
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The batch plant inspector did not verify visually that the
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continuous recorder chart readings coincided with dial scale
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readings.
This is a deficiency.
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Response:
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1.
Corrective Steps Taken and Results Achieved
The concrete cylinder breaks for samples representing
safety-related structure placements which were made from May 7,
1980, through May 9, 1980, have been reviewed.
All compressive
strengths exceeded design strength requirements after the 28-day
curing time was complete. Also, the batch plant inspector
involved was immediately assigned to other inspection duties.
He did not resume batch plant duties until June 2,1980, which
was after his being admonished as to the correct procedures and
his obligations in fulfilling those procedures.
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2.
Corrective Steps Taken to Avoid Further Noncompliance
All unit batch plant inspectors have been reminded to inspect
the scale dials more closely during weigh up and to make or
witness adjustments if the scale dials indicate weights other
than design mix weights. The batch plant inspectors were also
reminded to check the continuous recorder chart readings to ensure
that they coincide with dial scale readings with allowable
tolerances.
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Additionally, the final and over limits are being adjusted for
each mix so that the under light on the control panel will stay
on while mix weights are below the final limit and the over light
will come on if mix weights exceed allowable tolerances.
This will help warn the batch plant inspector .and operator when
a dial setting is not within the allowable mix tolerances.
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Date When Full Compliance Was Achieved
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Full compliance was achieved on May 14, 1980.
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