ML19210C903

Forwards Addl Info Re IE Bulletin 79-14, Seismic Analysis for As-Built Safety-Related Piping Sys. Lists Accessible Discrepancies Which Will Be Corrected by 791130

ML19210C903
Person / Time
Site:	Farley
Issue date:	11/02/1979
From:	Clayton F ALABAMA POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
IEB-79-14, NUDOCS 7911200286
Download: ML19210C903 (4)

Text

Alabarca Power Company 600 Nortn 13th Street Post office Box 2641 g // C,,

t Birmingham, Alat sma 35291 Telephone 205 323-5341 Q- Oz(f 36Y F. L. CLAYTON, JR.

m Senior Wce President AlabamaPower n{_! rl f, } . the souttern entoc sys:r",

Novenber 2,1979 NRC IE Bulletin No. 79-14 Docket Nos. 50-340 50-364 Mr. James P. O'Reilly U. S. Nuclear Regulatory C%xmtission Region II 101 Marietta Street, N. W.

Suite 3100 Atlanta, Gecrgia 30303

Dear Mr. O'Reilly:

Alabama Power C%xnpany subnits the enclosed additional information on the subject I.E. Bulletin as comtitted in my letter to you dated August 2, 1979.

The enclosure to this letter provides response concerning accessible safety-related piping involved in reviews under this bulletin for Unit-1 and information on the Unit-2 review program.

If you have any questions, please advise.

Yours very tr- ,

/

A%

g ( F. L. Clayton, Jr.

Enclosure cc: Mr. R. A. Thcznas l3bl ))f Mr. G. F. Trowbridge Office of I&E, Div. of Reactor Operations Inspection Washington, D. C. 20555 Office of I&E, Div. of Cbnstruction Inspection Washington, D. C. 20555 Mr. M. D. Hunt, I&E, Region II Director of the Office of Inspection & Enforcemnt Office of Nuclear Reactor Regulation Washington, D. C. 20555 79C p $

g *: . ,.

'l Enclosure 1 - Response to IE Bulletin 79-14 (120 day) t This enclosure represents Alabama Power Company's letter for the 120 day reporting requirements of the IE Bulletin No. 79-14.

UNIT _1 As indicated in Alabama Power company's 1. s p~ s e to the NRC dated October 5, 1979, Alabana Powe; has csmple _ the field inspection of inaccessible and accessibie areas of the scoped systems. The initial engineering review of inaccessible and accersible areas has identified no discrepancy which affects operability; however, those discrepancies that would otherwise require additional analyses will be corrected. Discrepancies located in the inaccessible area were corrected prior to start-up on October 31, 1979. Attachment 1 is a list of these discrepancies for accessible areas which will be corrected by November 30, 1979.

As a part of its previously implemented IE 79-14 program, Alabama Power Company verified valve weights by the use of vendor valve drawings. To supplement this effort, Alabama Power Company will randomly select valves and contact vendors to verify that valve weights taken from vendor drawings used as inputs *o seismic analyses are correct. This will be completed by the end of the second refueling outage. As indicated in Alabama Power Company's letter to the NRC dated October 5, 1979, portions of the RCS inside the pressurizer shield wall were considered inaccessible for direct measurement due to space limitations for physical access and were therefore visually inspected. To more fully comply with bulletin require-ments, Alabama Power Company will re-inspect by the end of the second refueling outage the inaccessible portions of the RCS to obtain, through other means, more precision in the measurement of inspection elements.

UNIT 2 Unit 2 of the Farley Nuclear Plant is still under construction and the final seismic analyses have not been performed. For this reason an inspection of the completed plant configuration for the purposes of confirming the seismic analyses input information in existing design documents is not possible. Alabama Power Company is in the process of developing a program and will implement this program to ensure that the final seismic analyses, when dor., will be based on the actual configuration of the plant.

The scope of this program will include all safety related piping 2 inches in diameter and greater and all seismic Category I piping, regardless of size, which was dynamically 1361 J38

'l analyzed by computer.

When the program is fully developed, a more detailed description of this program will be submitted to the NRC.

It is anticipated that this additional information will be submitted by November 30, 1979.

1361 239

L.

Attachment I Corrected 79-14 Accessible Discrepancies ISOMETRIC NO. SYSTEM HANGER NO./ ACTION REQUIRED

1. 394 RHR Excessive clearance between hanger (SI-R21) and pipe (14"-ECB-5)

2. 46 RHR Excessive clearance between hanger (RHR10-R47) and pipe (12"-ECB-13)

3. 154 CCW Remove clamp on pipe (4"-HCB-25)

4. 33 SW Remove temporary hanger (14"-HBC-39)

5. 796 SW Excessive clec ance between hanger (SW-H970) and pipe (2 " HBC-126)

6. 386 CVCS Remove temporary hanger (3"-HCC-181)

7. 137 CCW Remove temporary hanger (18"-HBC-2)

8. 44 RHR Add missing jam not on sway strut (RHR8-R54) (10"-ECB-17)

9. M507-66(364) SW Excessive clearance in load carrying direction, add 1/16" shim to hanger (SW-R783)

(8"-HBC-214) 1361 J40 4