ML20236V165
| ML20236V165 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 11/25/1987 |
| From: | Johnston W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Heider L YANKEE ATOMIC ELECTRIC CO. |
| References | |
| NUDOCS 8712040127 | |
| Download: ML20236V165 (2) | |
See also: IR 05000029/1987007
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Docket No.
50-29
Yankee Atomic Electric Company
ATTN: Mr. L. H. Heider
Vice President of Operations
1671 Worcester Road
Framingham, Massachusetts 01701
Gentlemen:
Subject:
Inspection No. 50-29/87-07
.This refers to your letter dated October 15, 1987, in response to our letter
dated September 16, 1987.
Your response' to the identified violation appears adequate and the corrective
actions should preclude repetition of this failure to plug defective tubes in
your steam generators. The NRC staff looks forward to receiving the
additional information requested in our letter dated September 16, 1987 no
later that January 15, 1987 as you stated in your letter of October 15, 1987.
Thank you for informing us of the corrective and preventive actions documented
in your letter. These actions will be examinea during a future inspection of
your licensed program.
Your cooperation with us is appreciated.
Sincerely,
L
William V. Johnston, Acting Director
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Division of Reactor Safety
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cc:
N. N. St. Laurent, Plant Superintendent
J. E. Tribble, President
G. J. Papanic, Jr. , Senior Project Engineer - Licensing
Peter W. Agnes, Assistant Secretary of Public Safety
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NRC Resident Inspector
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Commonwealth of Massachusetts (2)
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11/23/87
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Tetsphons (617) 872-8100
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YANKEE ATOMIC ELECTRIC COMPANY
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1671 Worcester Road, Framingham, Massachusetts 01701
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Or.uber 15, 1987
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FYR 87-110
United States Nuclear Regulatory Commission
Document Control Desk
Washington, DC 20555
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References:
(a) License No. DPR-3 (Docket No. 50-29)
)
(b) USNRC Region I Letter to YAEC, NYR 87-173, dated
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September 16, 1987
(c) YAEC Letter to William T. Russell, FYR 87-65, dated
June 15, 1987
(d) YAEC LER 87-06, FYR 87-69, dated July 2, 1987
Subject:
Reply to a Notice of Violation
(Inspection No. 50-29/87-07)
Dear Sir:
This letter is in response to the Notice of Violation resulting from
Inspection No. 50-29/87-07 conducted during the period May 11-29, 1987. The
Notice of Violation identified one item which apparently was not conducted in
full compliance with Nuclear Regulatory Commission (NRC) requirements.
In
accordance with Section 2.201 of the NRC's " Rules of Practices," Title 10,
Code of Federal Regulations, we hereby submit the following information:
Apparent Violation
License No. DPR-3 Appendix A, Technical Specifications, Section 4.4.10.4(b), Surveillance Requirements, states, in part, that the
steam generators shall be determined operable after completing the
corresponding actions required during sample tube inspections. One such
actibn includes plugging all tubes txceeding the defect plugging limit of
greater than 40% throughwall.
Contrary to the above, during the 1984 refueling outage, the licensee
failed to plug all steam generator tubes exceeding the Technical Specification
plugging limit.
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Response
During the 1984 steam generator Eddy Current Test (ECT) program, one
defective (ECT indication >40% throughwall) indication was analyzed correctly
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United States Nuclear Regulatory Commission
October 15, 1987
page 2
but was not' properly transcribed to the final report or to the list of tubes
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to be plugged.
Consequently, the tube remained unplugged, and the steam
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generator was placed in service fog two full operating cycles.
This is contrary to Yankee Nuclear power Station.(YNpS) Technical
Specification Surveillance Requirement 4.4 10.4(b) which states the steam
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generators shall be determined operable af ter plugging all tubes exceeding the
plugging limit.
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Evaluation
The cause of this event was a lack of secondary or independent review of
the ECT data generated during the 1984 examinations.
Corrective Actions Which Have Been Taken and Resulto Achieved
This is the first occurrence of this nature.
Steps were taken
immediately to ensure the integrity of the steam generator tubes. These steps
and their effectiveness were reviewed in Inspection No. 50-29/87-07.
Specifically, the following corrective action was implemented.
The latest ECT data sets for each steam generator were re-evaluated for
defects. Although additional defects were discovered due to the advanced
capabilities of the 1987 analytical instrumentation, no additional defects
were found which could have been identified at the time the data was taken.
All defective tubes were plugged, and the steam generators were determined
operable prior to startup es required by Technical Specification 4.4.10.4(b).
Corrective Actions Which Will be Taken to prevent Recurrence
Secondary and independent ECT data interpretation and processing will be
specified for all future steam generator ECT programs.
Date on Which Full Compliance Will be Achieved
. Full compliance will be achieved with procedural modifications which
formalize the requirements for independent review of ECT data.
These
modifications will be completed prior to the next ECT program.
The additional information requested in Reference 2 will be forwarded by
separate letter no later than January 15, 1988.
If you have any questions or desire additional information, please
contact us.
Sinc ely,
(
7t'7W
.,
Heider
Vice president and
Manager of Operations
LHH/25.198
cc:
Region I
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Resident Inspector
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