ML19338G461
| ML19338G461 | |
| Person / Time | |
|---|---|
| Site: | Brunswick |
| Issue date: | 10/16/1980 |
| From: | Murphy C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Jackie Jones CAROLINA POWER & LIGHT CO. |
| Shared Package | |
| ML19338G462 | List: |
| References | |
| NUDOCS 8010290392 | |
| Download: ML19338G461 (1) | |
See also: IR 05000324/1980029
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UNITED STATES
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NUCLEAR REGULATORY COf.it.ilSSION
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101 MARIE TT A ST., N.W., SulTE 3100
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ATL ANTA, GEoHGIA 30303
OCT 16 w80
In Reply Refer To:
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0-324/80-29
,50-325/80-32
Carolina Power & Light Company
ATTN:
J. A. Jones, Senior Executive
Vice President & Chief Operating
Officer
411 Fayetteville Street
Raleigh, NC 27602
Centlemen:
Thank you for your letter of October 1,1980, informing us of steps you h
taken to correct thi item of noncompliance concerning activities u d ave
Operating License Nos. DPR-71 and DPR-62 brought to your attention in
n er NRC
of September 10, 1980.
subsequent inspections. We will examine your corrective actions and plans during
our letter
We appreciate your cooperation with us.
Sincerely,
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Charles E. Murphy, Chief
Reactor Construction & Engineering
Support Branch
A. C. Tollison, Jr.
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Plant Manager
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Carolina Power & Light Company
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Brunswick Steam Electric Plant
P. O. Box 10429
Southport, N. C.
28461
October 1, 1980
FILE: B09-13514
SERIAL: BSEP/80-1631
Mr. James P. O'Reilly, Director
U. S. Nuclear Regulatory Commission
Region II, Suite 3100
101 Marietta Street N.W.
Atlanta, GA 30303
BRUNSWICK STEA'4 ELECTRIC PLANT, UNIT NOS. 1 & 2
LICENSC NOS. DPR-71 AND DPR-62
DOCKET NOS. 50-325 AND 50-324
RESPONSE TO INFRACTIONS OF NRC REQUIREMENTS
Dear Mr. O'Reilly:
The Brunswick Steam Electric PJant (BSEP) has received IE Inspection
Report 50-324/80-29 and 50-32K/80-32 and finds that it does not contain
any information of a proprietary nature.
The report identified an item that appears to be in noncompliance with
NRC requirements. This item and Carolina Power & Light Company's re-
sponse is addressed in the following text:
Infraction:
As required by Section 6.8 of the Technical Specification " Written
proedures shall be established, implemented, and maintained...as
recommended in Appendix A of Reg. Guide 1.33, Nov. 1972."
Contrarf to the above, CP&L's Special Test procedure SP-79-22
" Inspection and Testing Procedure for Concrete Expansicn Anchors"
and response to IE Bulletin 79-14, Serial: GD-79-1844 dated
June 23, 1979, failed to list the Control Rod Drive (CRD) and
Recirculation lines as safety related. The inspections required by
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Bulletins 79-02 and 79-14 were not performed.
.
G7FICIAL COPY
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Mr. J. P. O'Reilly
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October 1, 1980
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Carolina Power & Light Compaav's Response:
1.
Corrective steps which have been taken and the results achieved:
The inspections required by IE Bulletins 79-02 and 79-14 were
ic=ediately performed on both systems when the omission was dis-
covered and the initial results for the CRD system were reported in
LER's 1-80-61 and 2-80-55.
Final reports on the CRD inspections
will be issued by December 31, 1980. No problems were noted with
the Reactor Recirculation System.
A comprehensive review of all safety related systems to assure that
no other systems or portions of systems were omitted from the
original program conducted by our A/E is in progress.
The base
documents used in this review include the Brunswick FSAR, the Plant
Q-list, the IE Bulletin 79-07 list and the Brunswick final stress
report for Unit-2 (1978).
The results of this review to date indicate that no systems were
overlooked, with the exception of the CRD and reactor recirculation
piping which were previously reported and discussed with Mr. Modenos
on August 5 - 7.
We have, however, determined that fuel oil supply
lines to the diesel generators and service water supply and return
lines for the diesel generators were not reanalyzed as required by
IE Bulletin 79-07, nor were the anchor bolts tested in accordance
with 79-02.
These lines were inadvertently omitted from the listing
supplied to the NRC even though they were on the UE&C internal
listing of lines to be analyzed. This omission was discovered on
September 23, 1980. Necessary reanalysis has been performed on an
expedited basis with no resulting short term fixes required.
Thirty-seven (37) long term support fixes will be needed.
Anchor
bolt testing required under IE Bulletin 79-02 has been completed on
the 26 base plates contained within this piping. Of these 26
plates, one anchor bolt failed and has been repaired. This was
reported by Mr. W. M. Tucker, BSEP, to Mr. L. Modenos, of your
office, at 1445 on October 1, 1980.
2.
Corrective steps which will be taken to avoid further non-compliance:
Increased CP&L involvement in directing and monitoring A/E support
in IE Bulletin and other safety related activities will provide
better contact and help assure proper compliance. This increased
involvement is being provided by a site engineering unit which will
manage this Brunswick related A/E activity.
In addition, the A/E
is better structuring his organization and upgrading procedures to
provide " task planning documents" which delineate the activities to
be conducted to accomplish a given task.
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Mr. J. P. O'Reilly
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October 1, 1980
3.
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The date when full compliance will be achieved:
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The engineering review to assure no other systems or portions of
systems were omitted from the original program will be completed by
November 15, 1980. A supplement to this response will be provided
by November 30, 1980, documenting the results of the program review,
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providing an updated status on the work in progress, and providing
a schedule for completion of the identified long term fixes.
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Very truly yours,
A. C. Tolliso , Jr., General Manager
Brunswick Steam Electric Plant
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Mr. R. A. Hartfield
Mr. V. Stello, Jr.
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