ML20034A300
| ML20034A300 | |
| 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 9004230013 | |
| Download: ML20034A300 (5) | |
Text
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s Alabama Power Company 40 inverness Center Parkway.
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Post Office Box 1295 B6rmingham, Alabama 352o1 f
' Telephone 205 868-5501
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W. G. Hairston, Ill l
Senior Vice President Nuclear Operations AlabamaFbwer the southem electnc system i
April 12, 1990 Docket No. 50-364 t
U. S. Nuclear Regulatory Commission Attention: Document Control Desk j
Vashington, D. C.
20555 e
Centlemen:
Joseph H. Farley Nuclear Plant - Unit 2 Response to the NRC Request for Additional Information for the Inservice Inspection Program By letter dated August 3, 1989, the NRC requested.that Alabama Power.
Company provide additional information pertaining to the review of the Unit 2 updated Inservice Inspection (ISI) Program. Revision 0 of-this program was submitted to the NRC by letter dated December 16, 1988..The NRC granted interim approval of certain reliefs by letter dated March 31, 1989.
As i
discussed in letters dated February 8 and March 23, 1989, approval of the remaining relief requests was deferred.
Alabama Power Company proposed a-schedule for approval of the remaining reliefs by letter dated June 8, 1989.
q Alabama Power Company responded to the NRC's Request for Additional Information (RAI), by letters dated October 5 and December 7, 1989.
In a
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conference call held January 30, 1990, _the NRC Staff requested ansvers'to i
several questions resulting from review of these submittals. These
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questions were answered in a subsequent conference call on March 7, 1990.
l As agreed in the conference calls, enclosed is a summary of the NRC's j
questions and Alabama Power Company's responses.
1 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 have been satisfactorily resolved, Alabama Power Company vill submit j
l 9004230013 900412
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, U. S. Nuclear Regulatory Commission Pcge 2 Revision 1 of the ISI Program which vill incorporate the changes discussed i
in the RAI responses.
t It is also requested that the NRC's review of the ISI Program be completed and SER issued in accordance with the scheduled provisions of the June 8, 1989 letter referenced above. Resolution of the open issues on the remaining relief requests and their granting in accordance with the proposed schedule vill provide approximately one year (not including the Code allowed one-year extension) for Alabama Power Company to complete the required examinations. This vill also permit proper planning of examinations to be performed during the remaining refueling outage tentatively scheduled to begin September 14, 1990.
If there are any questions or if additional information is needed, please advise.
Respectfully submitted, ALABAMA POWER COMPANY a.B. & v V. G. Hairston, III VGH/DEM/STBicht-nre.8.24 Enclosure cct Mr. S. D. Ebneter Mr. S. T. Hoffman Mr. G. F. Maxwell Mr. B. Brown I
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ENCLOSURE Joseph M. Farley Nuclear Plant - Unit 2 Response to the NRC's Request for Additional Information for the Inservice Inspection Program F
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 2, Item 2, Section H)
.i NRC Question:
r.xplain why Attachment 7 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 were 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 were 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 allowable 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 7 (copy attached).
In some cases, the operating pressure is now lower than the design pressure.
For the remaining cases vhere 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 (Reference NRC RAI, Enclosure 2, Item 2, Section M)
NRC Question:
The requested information was not provided for relief request RR-22, item F1 was this an editorial omission?
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' Enclosure-Unit 2 Page 2 APCo Reply:
Yes. The requested information for RR-22, Item F has been added to the revised Attachment 7 (copy attached).
3.
Holding Time for !!ydrostatic Test of Steam Generator Secondary Side and Connecting Piping (Reference NRC RAI, Enclosure 2, Item 2, Section 0) i NRC Ouestions Relief request RR-30 requests a reduced holding time for hydrostatically
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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 from the steam generator secondary side, is it intended that the reduced holding time.
addressed in RR-30 be applied to RR-22 A-D also?
APCo Reply
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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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r ATTACHMENT 7 R311ef '
Code (1.25x) Relief Request-R quest No.
Line No.
Adj. Line No. Op Press. Design Press. Hydro Press. Alt. Press.
RR-22 A DCB-1A S/G 1200 1600 2000 1344 l
DCB-1B-
-S/G 1200 1600 2000 1344 DCB-1C 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 i
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 F 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 t
RR-23 B CCB-57 RCS Loops 2235 2485 3107 2280 RR-23 C CCD-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
_3107-850 RR-23 I CCB-29 RCS Loops 600 2485 3107 2200 RR-23 J CCB-22 RCS Loops 2555 2485 3107 2280 CCB-32 RCS Loops 75 2485
-3107 2280 RR-23 K CCB-9 RCS Loops 2350 2485 3107 2280 RR-23 L CCB-10 RCS Loops 2350 2485 3107 2280-RR-23 H CCB-45 RCS Loops 2350 2485 3107 2280 RR-23 N CCB-48A RCS Loops 75 2485 3107 2280 5
CCB-48B RCS Loops 75 2485 3107 2280 CCB-48C RCS Loops 75 2485 3107 2280 t
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
chtinre.8.29-Unit 2 r
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