ML19322A630
| ML19322A630 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/14/1971 |
| From: | Jennifer Davis US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Thies A DUKE POWER CO. |
| References | |
| NUDOCS 7911210700 | |
| Download: ML19322A630 (3) | |
Text
_ _.E 1._
g e"%
m:r a snT:s
/[D[h/
ATOMIC ENERGY COMMISSION fd-J:.((
OtVIStoN CF CoMPLf ANCE T*
AEGloN ll * $UTE S13 d'
V 230 PE ACHTREE STP EEr, NOR THWEST UJ7is 66 T3 5 2 6-4 5J 7 AT t.A NT A. GE ors:A 3C333 APR 141371 4
Duke Power Company Attn: Mr. A. C. Thies, Vice President Production and Ope;ation Power Building 422 South Church Street Charlotte, North Carolina 28201 l
Gentlemen:
This letter relates to the discussion Messrs. C. E. Murphy, R. F. Warnick and H. L. Whitener of this office held with Messrs. J. C. Rogers, D. G. Beam, G. L. Hunnicutt, J. W. Hampton and K. S. Canady of your staff at the con-clusion of the inspection conducted on April 6 through 9,1971, regarding the construction activities authorized by AEC Construction Permit No. CPPR-33.
l As noted during the discussion, certain itets were identified which apparently vere not in conformanca with statements in the Final Safety Analysis Report and with Appendix B to 10 CFR 50, " Quality Assurance Program for Nuclear Power Plants," as identified below, or which may otherwise raise questions concerning the adequacy of the construction. These ite=s are as follows:
j 1.
The Final Safety Analysis Report, Section 8.2.2.13, specifies the per-missible cable tray fill.
1 Section 8.2.2.13(h) states in part, "The maximum fill in control and instrument 2 tion cable trays is such that trays will be filled to the top of the tray rails."
Contrary to this requirement, the inspectors observed that cable trays with safety feature cables in the spreading room and the electrical equipment room were filled above the level of the tray rails.
2.
Appendix 3 to 10 CFR 50, Criterion VIII, specifies that ceasures be established for the identification and control of components.
Criterion VIII requires in part that =casures be established for the identification and control of components to assure that identification of the items are maintained.
1911210 7C&
m
O
..~..,.
-~~
~ ~ -
O APR 141971 Duke Power Company Contrary to these requirements, a review of the data packages for the four main coolant pumps revealed that the references to the individual pump positions in the data packages did not correspond to the positions in which the pumps were actually installed.
3.
Appendix B to 10 CFR 50, Criterion XV, " Nonconforming Materials, Parts or Components," specifies the requirements for handling nonconforming materials, parts or components.
Criterion IV requires that measures be established to control materials, parts or components which do not conform to requirements in order to prevent their inadvertent use or installation.
Contrary to these requirements, the inspector observed that the control rod d.c. breaker cabinet had been dropped and damaged. At the time of dhe inspection, there was no evidence that the unit had been tested for hidden damage prior to installation. Neither had it been tagged or otherwise identified as being discrepant as required by the Electrical Quality Control Manual.
4.
Appendix B to 10 CFR 50, Criterion VIII, specifies that methods be established for the identification and control of materials.
Criterion VIII requires that ceasures be established to assure that the identification of materials is maintained by heat number, part number or serial nunber or other appropriate means as required through-out fabrication and use of the materials.
Contrary to these requirements, the inspector observed stainless steel welding rods in the high pressure injection pu=p room that could not be identified as to heat number. The inspector had also observed unidenti-fied rods during inspections on January 25, 1971, and on February 24 through 26, 1971, and had discussed this matter at the conclusion of these inspections.
5.
The Final Safety Analysis Report, Section 12.3.1, requires the use of operating procedures during the conduct of plant operations. Operating Procedure OP 1503 02 describes the procedures to be used in storing fuel in dhe temporary fuel storage building.
Operating Procedure OP 1503 02, checklist C, Step 14, provides for recording the fuel assembly identification nunber and serial nu=her on the map df the storage rack.
Contrary to these requirements, the inspectors observed one fuel element, No.1C44, in the storage rack but not identified on the map. A review Nm 'rh.
...... -. ~.
~-
- ~
n._
Duha Po*:cr Con?an7 A?314 'r3 i of the records indicated that c to nadora of the cocratine. staf f and one nenber of the ;Fi organisation had signed the data chect certifying that the entry had been nado en t'.ia nap of the storage rack.
Pleaac provide us, within 30 dayc, : ith your connents concernin these itens and any steps whic.t have been t. san or vill be tchen to correct then and to nininico recurrence includin: cny apt:ropriate changes that have been or vill be nade to increc :c the ef fectivences of your quality assurance pro::ran.
Should you have any questions concerning this natter, you =ay cer.gnicato directly with this effice.
Very truly yours,
- >: u! L:nea y i G Can John G. Davis CO:II:C:11 Director bec:
J. P. O 'Reilly, CO:HQ (4)e J. B. Henderson, CO:HQ A. Gianbusso, CO:HQ L. Kornblich, Jr., CO:HQ R. H. Engelken, CO:HQ CO:II.,
C0_:II
/EdCO.;{TI omer>
WCS'e'46'e
';V
- idl JGDavis summaut >....C..D...i.u..r.p.h.v :wb -
a -
D ATE >..
.$[.kh.......
Form AEC-Sto (Rev. 9-33) AICM OHO
- c. & ocvrasua; Pa:xTsc orr:cs a tato o. sos-se
-