ML20064A711

Forwards Rev 1 to Relief Request RR-1, Second 10-Yr Interval Inservice Insp Program for ASME Code Class 1,2 & 3 Components

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)

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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 5-4 and December 7,.1989,' Enclosure Item J):for calibration block ALA-RV-3 is also applicable to ALA-RV-5. Relief request RR-3 was also revised to. indicate that

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-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

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f.1 U. S. Nuclear Regulatory Commission Page 21 E and insertion instructions. If there are any questions or'if additional  !

information is needed, please advise.

Respectfully submitted, ALABAMA POWER COMPANY i al A. / tat'n V. G. Hairston, III-i

,- VGH/DEM/STBacht-nrc.8.38 l Enclosure cct-_Mr. S. D. Ebneter l Mr. S. T.-Hoffman 1

' t l- Mr. G. F. Maxwell Mr. B. Brown 4

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m. - h: lNSERTION INSTRUCTIONS ,

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'E Eagg Iltle Instruction 1 of 3 Summary of Remove existing Page 1 of 3, 2> . Revision 3 Replace with revised Page 1 of_3

.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

L , 68 ' RR 3' Remove existing Page 6 8 Replace with revised Page 6-8~

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. 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 4 from Regulatory Guide 1.147 applicable for the second year inspection -

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, Enclosure 2, 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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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

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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 i .- requirements applicable at that time.

0461I 6-5 Rev. 1 l

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FNP-2 M 068 RELIEF REQUESTS  !

FNP-2 l

Co(nponent or Relief Area: Relief from notch location requirements for calibration- l' s

blocks used to perform the following:

ALA-RV-1: Boron injection tank head-to-shell I circumferential welds. Reactor vessel.

4 lower head-to lower shell weld and all 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.

O  : 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.

Reactor vessel flange-to-shell weld and ALA-RV-5:

shell welds. ,

L APR-5: Steam generator stub barrel-to-upper tubesheet.

s' weld, lower shell-to-stud barrel weld, 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' o ALA-RV-5 are .25 and .50' inches less than the required distance, I- 3. respectively. The non-aligned holes are to be located a minimum L of 1.5 inches from the end of ~the block. The non-aligned holes I 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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- Examination: None; the calibration blocks are acceptable for use as is. ,

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~000563 6-8 Gen. Rev. 1 I