ML20042E412

Provides Addl Info Re Review of Second 10-yr Inservice Insp Program,Per NRC 890803 Request.Relief Request RR-30 Requested Reduced Holding Time for Hydrostatically Testing Steam Generator Secondary Side

ML20042E412
Person / Time
Site:	Farley
Issue date:	04/12/1990
From:	Hairston W ALABAMA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9004200741
Download: ML20042E412 (5)

Text

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Alabama ber Company 40 invernes1. C;nter Parkw y Post Office Box 1295 Birmingham, Alabama 35201 Telephone 205 800-5581 W. G. Hairston, til ,

Senior Vice President Nuclear Operation. Alabama Power >

the southem ebctic stJtorrt l 10CFR50.55a(g)

April 12, 1990  ;

i Docket No. 50-348  ;

U. S. Nuclear Regulatory Commission  !

Attentlon: Document Control Desk  ;

Vashington, D. C. 20555 l

Gentlemen:

l l Joseph H. Farley Nuclear Plant - Unit 1 Response to the NRC Request for Additional Information for the Inservice Inspection Program l

By letter dated August 3, 1989, the NRC requested that Alabama Power Company provide additional information pertaining to the review of the Unit 1 Second Ten-Year Inservice Inspection'(ISI) Program. Revision 0 of this program was submitted to the NRC by letter dated November 23, 1987. The. '

NRC granted interim approval of the reliefs requested in Revision 0 by letter ,

dated December 10, 1987. Revisions 1 and 2 of the program including two additional relief requests vere submitted by letter dated September 9, 1988.

Alabama Power Company responded to the NRC's Request for Additional Information (RAI), by letters dated October 5 and December 7, 1989.~ In a L' conference call held January 30, 1990, the NRC Staff requested ansvers to several questions resulting from review of these submittals. These questions were answered in a subsequent conference call on March 7, 1990.

As agreed in the conference calls, enclosed is a summary of the NRC's questions'and Alabama Power Company's responses.

It is requested that the NRC notify Alabama Power Company upon completion of its review of the RAI response and inform Alabama Power Company as to the disposition of each item. Upon receipt of confirmation that all issues g[2p p r a J.8 0

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,,4 U. S. Nuclear Regulatory Commission Page 2 have been satisfactorily resolved, Alabama Power Company vill submit

- Revision 3 of the ISI Program which vill incorporate the changes discussed in the RAI responses.

If there are any questions or if additional information is needed, please advise.

- Respectfully submittedi ALABAMA POWER COMPANY g4l. . .Y= W~

V. G. Hairston, III VGH/DEM/STBacht-nrc.8.21 Enclosore ces'.Mr. S. D. Ebneter Mr. S. T. Hofiman

.Mr. G. F. Maxwell Mr. B. Brown j;

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ENCLOSURE Joseph M. Farley Nuclear Plant - Unit 1 Response to the NRC's Request for Additional Information for the Inservice Inspection Program The following questions and ansvers pertaining to the subject RAI were discussed in conference calls held between Alabama Power Company and the NRC staff:

1. Piping Design and Operating Pressures (Reference NRC RAI, Enclosure 1, Item 2, Section S)

NRC Question:

Explain why Attachment 10 to APCo's October 5, 1989 reply lists several lines with operating pressures which exceed the design pressures.

APCo Reply:

A design review of the lines in question was performed and the existing design and operating pressures and temperatures vere evaluated against applicable ASME Code, Section III requirements. This evaluation concluded that the piping as designed is acceptable for the design and operating conditions specified. Limiting design pressures for the maximum design temperature vere calculated for each of the lines and in all cases the limiting design pressures greatly exceeded the operating and design pressures originally specified. Furthermore, piping designed for.2485 psig at 650'F is acceptable for service at higher operating pressures (than 2485 psig) and correspondingly lover temperatures (than 650*F) provided the ratios of pressure to allovable stress at a given temperature are similar. The evaluation confirmed that in each case where the operating pressure exceeded the design pressure, the operating temperature is less than the design temperature such that the operating pressure to allovable stress ratio is equivalent to or more conservative than the design pressure to allovable stress ratio.

As a result of the review a determination was made that more realistic operating pressures should be specified and the new values are provided in the revised Attachment 10 (copy attached). In some cases, the operating pressure is now lover than the design pressure. For the remaining cases where the operating pressure still exceeds the design pressure, these conditions have been determined to be acceptable for the reasons stated above.

2. Piping Design and Operating Pressures for Relief Request RR-22, Item F q (Reference NRC RAI, Enclosure 1. Item 2, Section S)

• NRC Ouestions  !

The requested information was not provided for relief request RR-22, item F vas this an editorial omission?

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Enclosure-Unit 1 Page 2 APCo Replys Yes. The requested information for RR-22, Item F has been added to the revised Attachment 10 (copy attached).

3. Holding Time for Hydrostatic Test of Steam Generator Secondary Side and Connecting Piping (Reference NRC RAI, Encle*Mre 1, Item 2, Section U)

NRC Ouestion:

Relief request RR-30 requests a redenced holding time for hydrostatically testing the steam generator secondary side. Relief request RR-22, items A through D request relief from the hydrostatic test pressure. Since the portions of piping identified in RR-22 A-D are unisolable f rom the steam generator secondary side, is it intended that the reduced holdirig time addressed in RR-30 be applied to RR-22 A-D also?

APCo Reply:

Yes. Relief requests RR-22 and RR-30 vill be revised to include notes which reference the complementing relief request and clarifying that the reduced holding time discussed in RR-30 applies to the unisolable piping discussed in RR-22 A-D.

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ATTACHMENT 10 R;11ef_ _ .

Code (1.25x) Relief Request R quest No. Line No. Adj. Line No. Op Precs. Design Press. Hydro Press. Alt. Press.

RR-22 A. DCB-1A S/G 1200 1600 2000 1344 DCB-1B S/G 1200 1600 2000 1344 DCB-10 S/G 1200 1600 2000 1344 RR-22 B DBB-1 S/G 923 1600 2000 1344 RR-22 C CBB-5 S/G 1000 1500 1875 1344 CBB-6 S/G 1000 1500 1875 1344 CBB-7 S/G 1000 1500 1875 1344 CBB-8 S/G 1000 1500 1875 1344 CBB-9 S/G 1000 1500 1875 1344-CBB-10 S/G 1000 1500 1875 1344 RR-22 D DBB-2 S/G 1270 1600 -2000 1344 RR-22 P CCB-18 HCB-20 2555 2485 3107 188 RR-23 A CCB-27 RCS Loops 2235 2485 3107 2280 CCB-33 RCS Loops 2235 2485 3107 2280 CCB-34 RCS Loops 2235 2485 3107 2280 CCB-38 RCS Loops 2235 2485 3107 2280 CCB-39 RCS Loops- 2235 2485 3107 2280 CCB-40 RCS Loops 2235 2485 3107 2280 CCB-41 RCS Loops 2235 2485 3107 2280 CCB-42 RCS Loops 2235 2485 3107 2280 CCB-43 RCS Loops 2235 2485 3107 2280

_CCB-44 RCS Loops 2235 2485 -3107 2280 CCB-47A RCS Loops 2300 2485 '3107 2280 CCB-47B RCS Loops 2300 2485 3107 2280 CCB-47C RCS Loops 2300 2485 3107 2280 RR-23 B CCB-57 RCS Loops 2235 2485 3107 2280 RR-23 C CCB-37 RCS Loops 2235 2485 3107 2280 CCB-54 RCS Loops 2235 2485- 3107 2280 CCB-55 RCS Loops 2235 2485 3107 2280 CCB-56 RCS Loops 2235 2485 3107 2280 RR-23 D CCB-21 RCS Loops 2555 2485 3107 2280 CCB-50 RCS Loops 2555 2485 3107 2280 RR-23 E CCB-22 RCS Loops 2555 2485 3107 2280 RR-23 F CCB-30 RCS Loops 2555 2485 3107 2280 RR-23 G CCB-31 RCS Loops 2555 2485 3107 2280 RR-23 H CCB-24 CCA-24 650 2485 3107 850' CCB-53 CCA-24 650 2485 3107 850 CCB-54 RCS Loops 650 2485 3107 830

'RR-23 I CCB-29 RCS Loops 600 2485 3107 2280 RR-23 J_ CCB-22 RCS Loops 2555 2485 3107 2280 CCB-32 RCS Loops 75 2485 3107 2280 RR-23 K CCB-9 LOS Loops 2350 2485 3107 2280 RR-23 L CCB-10 RCS. Loops 2350 2485 .3107 2280 RR-23 M COB 45 RCS Loops 2350 2485 3107 2280

, na-23 N CCB-48A RCS Loops 75 2485 3107 2280 CCB-488 RCS Loops 75 2485 3107 2280 CCB-48C RCS Loops 75 2485 3107 2280 RR-23 0 CCB-63 RCS Loops -2235' 2485 3107 2280 RR-25 CCB-36 RV Flange 2235 2485 3107 2280 *-

Gasket RR-29 CCB-62 HCC-263 2735 2485 3107 2750 RR-30 . Steam Gen. .SEE RR-22 775 1085 1344 1344 Secon. Side A,B,C,D

• Only if RV flange gasket leaks.

chtinre.8.28-Unit 1

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