ML20064A711
| ML20064A711 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/12/1990 |
| From: | Hairston W ALABAMA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9009270151 | |
| Download: ML20064A711 (7) | |
Text
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-. e A!abama Powsr Company 1*L 40 inverness Center Darkway,
9' lbst Office Box 1295-N Birmingham, Alabama 35201' Y lc
. Telephone 205 808 5581
' W. G. Hairston, til.
Senior Vice President -
mei.ar operanon.
7AlabamaPower-Inesouthem ekclic system 10CFR50.55a(g)
September 12, 1990 Docket No. 50-364
.U. S. Nuclear Regulatory Commission Attentions -Document Control Desk Vashington, D. C.
20555 Ge...lemen t Joseph H. Farley~ Nuclear Plant'- Unit-2
..Second. Ten-Year Interval Inservice Inspection Program for;ASME Code Class 1, 2 and~3 Components By. letter dated August 15,199'.
.labama Power Company submitted Revision 1 of
- the subject -Inservice:Inspectit a gram to the-NRC.
During the-final, review process of an extensive calibrt.uon block evaluation effort,.-it was_ determined-that-several corrections-to three-relief requests submitted with Revision l' vere necessary to reflect latest examination practices.
LRelief-request RR-1 was revised to include calibration block ALA-RV-5, vhich
- has been determined'to be'the appropriate standard for examination of the
, reactor vessel.shell and flango-to-shell velds, instead of ALA-RV-3 as previously indicated. Descriptions of areas examined utilizing ALA-RV-3 and ALA-RV-5 vere revised _for relief-requests RR-1, RR-2 and RR-3.
Information previously supplied-to the NRC (reference. letters to the NRC dated October 5-and December 7,.1989,' Enclosure Item J):for calibration block ALA-RV-3 is also 4
applicable to ALA-RV-5.
Relief request RR-3 was also revised to. indicate that 4
-calibration-block ~APR-7 is utilized for examination of all pressurizer.
circumferential shell velds, not just the: upper-to-middle shell veld as previously stated.
- Enclosed-herevith for use in correcting the Revision 1 submittal are. revised t
g pages which include the required changes, a revised summary of changes sheet 0?iC3 1
9009270151 900912 1
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f.1 U. S. Nuclear Regulatory Commission Page 21 and insertion instructions.
If there are any questions or'if additional information is needed, please advise.
Respectfully submitted, ALABAMA POWER COMPANY i
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n V. G. Hairston, III-VGH/DEM/STBacht-nrc.8.38 l
Enclosure cct-_Mr. S. D. Ebneter Mr. S. T.-Hoffman
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1 l-Mr. G. F. Maxwell Mr. B. Brown 4
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lNSERTION INSTRUCTIONS
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FNP-2-M 068 O
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'E Eagg Iltle Instruction 1 of 3 Summary of Remove existing Page 1 of 3, Revision 3 Replace with revised Page 1 of_3 2>
.i 6-5 RR 1 Remove existing Page 6-5, Replace with revised Page 6-5 j
6-7 RR-2 Remove exirting Page 6-7=
Replace with revised Page 6 7 L
' RR 3' Remove existing Page 6 8 Replace with revised Page 6-8~
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1 FNP 2 M 068 Summary of Revision 1 to the-J. M.. Farley Nuclear Power Plant Unit-2 Ten-Year-Inservice Inspection Program for ASME Code Class 1, 2, and 3 Components l
Paae No./ Description / Reason for Chance 1.
Page 1-2, Section 1.2:
Deleted second paraaraph.
No longer applicable.
2.
Page 1-3, Section 1.7.1:
Revised to clarify requirements for performing ultrasonic examinations, including incorporation of Code Case N-435-1.
Per APCo letter to NRC dated 10/5/89, Enclosure 2, Jtem J.
3.
Page 1-6, Section 1.12: Revised to reflect listing of ASME Code Cases from Regulatory Guide 1.147 applicable for the second year inspection 4
interval.
Reference APCo letter to NRC dated 10/5/89,; Enclosure 2, Item H.
4.
Pages 3-3A and 3-38, Residual Heat Exchangers:
Revised to reflect correct configuration and examination requirements.
Editorial correction 5.
Page_6-1:
Revised " Examination Area" description for RR-2 thru RR-6 to reflect required changes ~ to relief requests.
Editorial.
6.
Page 6-3:
Revised " Examination Area" description for RR-24 to reflect required changes to relief request.
Editorial.
L 7.
'Page 6-4:
Revised " Examination Area" description for RR-45 to reflect L
required changes to relief req'?est and RR-46 from "(7)" system 6
hydrostatic tests to "(3)".
Editorial.-
8.
.Page 6-5:
For relief request RR-1, revised description of welds examined
.using calibration block ALA-RV-3 and ALA-RV-5.
Editorial. correction.
9.
Page 6-7:
For RR-2:, revised descriptions of welds-_ examined using all three calibration blocks.
Editorial correction.
10.
Page 6-8:
Issued relief request RR-3.
Reference APCo letters to NRC dated 10/5/89 and 12/7/89, Enclosure 2, Item J.
11.
Page 6-9:
Previous '.elief request RR-4 was no longer applicable and was rewritten to allow the use of Code Case N-461 where.the thickness dif.ference between calibration blocks and the component exceedsSection XI, Appendix III allowances.
Per APCo letter to.-NRC dated.12/7/89,, Item J, 12.
Page 6-10:
Added page in conjunction with rewrite of RR-4 and renumbered following pages as required.
Editorial.
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i FNP-2-M-068-RELIEF-REQUESTS FNP-2 i
RR-1 i
component or-Relief Areat Relief from the material requirements
'7 for calibration blocks used to perform ultrasonic examination of the i
followings:
-t APR-6:
Steam generator channel head-to-tubesheet welds.
APR-7:
Boron injection tank l
head-to-chell circumferential welds and nozzle-to-head welds.
J
-ALA-RV-1:
Reactor vessel lower-head-to-lower shell-weld ande all lower head welds.
Boron-
~
injection tank' head-to-shel1~.
a circumferential. welds.
L ALA-RV-3:
Reactor vessel top head weld.
_ l ALA-RV-5:
Reactor vessel shell' welds.
l-Requirement from which Relief is
. Requested:
Section XI, 1983 Edition with Addenda through; Summer 1983, paragraph.IWA-2232' requires that ultrasonic examination of vessel welds in ferritic materials greater than 2 in. in thickness be' performed in accordance with
' Article-4,Section V.1 Paragraph T-434.1.1(3),
Article 4, requires that=the material-from which' calibration ~ blocks are fabricated be of-the same material specification,. product-form, and heat treatment as one of:the materials being' joined.
Basis for Relief:
During fabrication of.the Farley Unit 2 nuclear steam supply system vessels, the calibration blocks used to perform examinations.by the vessel manufacturer were fabricated to the requirements of American Society of Mechanical u
Engineers (ASME)Section III.
When ASME Section XI was issued for inservice inspection, y
the new requirements for vessel 1 calibration ti blocks rendered the existing blocks unacceptable l
for use.
The original blocks had to be replaced but some vessel materials were no longer-available.
The vessel calibration. blocks had-to be refabricated to the Section XI requirements applicable at that time.
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0461I 6-5 Rev. 1 l
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FNP-2 M 068
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RELIEF REQUESTS FNP-2 l
Co(nponent or Relief Area:
Relief from notch location requirements for calibration-l blocks used to perform the following:
s ALA-RV-1: Boron injection tank head-to-shell I
circumferential welds.
Reactor vessel.
lower head-to lower shell weld and all 4
lower head welds.
ALA-RV-3:
Reactor vessel top head weld.
L ALA-RV-5: Reactor vessel flange-to-shell weld and shell welds.
Requirement from which Relief is -
m Requested:
Section XI, 1983 Edition with Addenda through Summer 1983, W
paragraph IWA-2232, requires that ultrasonic examination r
of vessel welds in ferritic materials greater-than 2 in.
in thickness be conducted in accordance with Article 4,Section V, 1983 Edition.
Figure T-434.1,' Article 4,- -
requires.that the minimum distance from the ends of the 2 in long 2-percent T notches-to the edges of the block-be 3 in.
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- Basis for-h.
Relief:
Figure T-546.1, Article 5,Section V, 1983 Edition, is a L
similar calibration block; however, the clearance required L
'from the ends of the 2-percent notches is 2 in. instead of; l
Lthef3 in, required by' Figure T-434.1, Article 4.
Experience: performing calibrations using these blocks has l_3 proven fully satisfactory.
Alternate i
Examination:
The above-calibration blocks are in compliance with the clearance dimensions required for. notches by Figure l
.T-546.1, Article 5,Section V,'1983 Edition.
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I 000563 6-7 Rev. 1 l;,
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FNP-2 M-068 REllEF REQUEST j
FNP-2 E!bl Component or Relief Area:'
Relief from hole location requirements for calibration blocks' used to perform the following:
ALA-RV-1:
Reactor vessel lower head-to-lower shell: weld,-
all lower head welds and boron injection tank head circumferential welds.
ALA-RV-5:
Reactor vessel flange-to-shell weld and shell welds.
L APR-5:
Steam generator stub barrel-to-upper tubesheet.
weld, lower shell-to-stud barrel weld, s'
transition cone-to-lower shell weld, upper i
shell-to-transition cone weld, and feedwaterc nozzle-to-upper shell weld.
APR-7:
Pressurizer top head-to nozzle welds,' top.
t head-to-upper shell, all circumferential shell welds, lower-to-bottom head weld, all longitudinal shell welds, and bottom head-to-nozzle weld.
L Requirement from which Relief is Requested:
Section XI, 1983 Edition with Addenda.through Summer 1983, paragraph IWA-2232 requires that ultrasonic examination of-vessel welds in-ferritic materials greater than 2 inches in P
thickness be conducted in accordance with Article 4,Section V, 1983 Edition.
Figure T-434.1 of Article 4 requires the aligned' side-drilled holes to be located a minimum distance:of T/2 from the end of the. block. The aligned holes in ALA-RV-1 and-j' ALA-RV-5 are.25 and.50' inches less than the required distance, o
respectively. The non-aligned holes are to be located a minimum I-3.
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of 1.5 inches from the end of ~the block. The non-aligned holes on ALA-RV-1, APR-5 and APR-7 are.25,.625 and.625 inches less than the required distance, respectively.-
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Basis for Relief:
Experience performing calibrations using the blocks mentioned L
above has proven fully satisfactory.
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Alternate a
- Examination:
None; the calibration blocks are acceptable for use as is.
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~000563 6-8 Gen. Rev. 1 I