ML20059L075

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

ML20059L075
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 9009260095
Download: ML20059L075 (7)

Text

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[ ' Alab:ma Power Company ;

' 4 40 hmmoss CintIt Parkway'.-

=**- Poli Offee Box 1295 - i

,, ,( Dirmingham, Alabama 35201.

' V Telephone 205 868 5581 .,

W. Ol Hairston, til '

. Senior Vice President .

'. Nuefoar Operations gg g  : I tre southem electrc systern -  ;

10CFR50.55a(g)-

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. September 12, 1990 d

Dock- ao. 50-348 N

U. S. Nuclear Regulatory Commission "

Attention: Document Control Desk i

' Washington, D.' C. 20555 j

Gentlemen:

l Joseph M. Farley Nuclear Plant - Unit 1 '

Second Ten-Year Interval Inservice Inspection Program for ASME Code Class 1, 2 and 3 Components

By~ letter dated August 15, 1990, Alabama Power Company submitted Revision'3'of the subject.-Inservice. Inspection Program to the NRC. During the final review process of an extensive calibration block evaluation effort,~1t was. determined that several corrections to three relief requests submitted with Revision 3 were necessary to reflect latest examination practices.. i Relief ~ request RR-l'was revised to include calibration block ALA-RV-5,-which has been: determined to be the appropriate standard'for= examination of,the +

= reactor, vessel shell and flange-to-shell velds, instead of ALA-RV-3 as

..previously' indicated. Descriptiens of areas examined utilizing ALA-RV-3 and

-ALA-RV-5 were.re. vised for relief requests RR-1, RR-2 and RR-3. ..Information:

g previously supplied to the NRC (reference letters to.the NRC dated October 5-E

'and December 7, 1989, Enclosure Item J) for. calibration block ALA-RV-3 is also-applit.ble to.ALA-RV-5. Relief request RR-3 was also revised to indicate that calibraden block APR-7-is utilized for examination of all. pressurizer circumfe.ential shell velds, not just the upper-to-middle shell veld as-  ;'

previously stated.

Enclosed herewith for use in correcting the Revision 3 submittal are revised 1 -pages which' include the required changes, a revised summary of changes sheet 0.W ;

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U. S. Nuclear Regulatory Commission Page 2' and=inser* ion instructions. If thare are any questions or if additional information is needed, please advise.

Respectfully submitted, .;

-ALABAMA POWER COMPANY (kh./ airston, III

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VGil/DEM/STBacht-nrc.8.36 Enclosure cct Mr. S. D. Ebneter Mr. S. T. Hoffman Mr. G. F. Maxwell Hr. B. Brown

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INSERTION INSTRUCTIONS FNP I-M-043

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EAgt Title Instruction  ;

1 of 3 ' Summary of Remove existing Page 1 of 3, Revision 3 Replace with revised Page 1 of13-6-5 RR-1 Remove existing Page 6-5, Replace with revised Page 6 5 .;

6-7 RR 2 Remove existing Page 6-7  ;

Replace with revised Page 6-7  !

6-8 RR-3 Remove existing Page 6 8' Replace with revised Page 6-8  ;

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FNP-1-M 043 Summary of _ Revision 3 to the J. M. Farley Nuclear Power Plant Unit 1 Second Ten-Year Inservice Inspection Program for ASME Code Class 1, 2, and 3 Components i

Paae No./Descriotion/ Reason for Chanae

1. Table of Contents: Changed the title of Section 1.9 from " Repair Procedures" to " Repair and Replacement Program". Editorial correction, t

2. Page 1-3, Section 1.7.1: Revised to clarify-requirements for performing-ultrasonic examinations, including incorporation of Code C?se N-435-1. '

Per APCo letter to NRC dated 10/5/89, Enclosure 1, item J.

3. Page 1-4, Section 1.8; first sentence, 2nd word: Changed " result of. . .".

to "results are...". Editorial correction.

4. Page_l-4, Section 1.9; third sentence: Added " Repaired or~ replaced components which are... with subsequent inservice examinations". To further define the Repair and Replacement Program. ,

5. Page_l-5, Section-l.12: Revised to reflect listing of-ASME Code Cases .

from Regulatory Guide 1.147 applicable for the second 10-year inspection interval. Reference APCo letter to NRC dated 10/5/89, Enclosure 1, item H. i

6. Page.3-3, Residual Heat Exchangers: Revised to reflect correct

• configuration and examination requirements. Editorial correction. '

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7. Page 4-5, Auxiliary Steam System: Moved relief request RR-38 from functional-test to hydrostatic test. Editorial correction. -

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! 8. Page 4-9, RHR Hx.: Revised to' reflect the number of components. -

L Editorial omission.

9. Page 4-16, Spent-fuel Pool Pumps: Added relief' request RR-33 to hydrostatic test.

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Editorial omission.

10. Page 6-1: Revised " Examination Area" description for RR-2 thru RR-6 to reflect required changes to relief requests. Editorial. "

11. Page 6-3: Revised " Examination Area" description for RR-24 to reflect required changes to relief request. Editorial.

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i. 12. 'Page 6-4: Revised " Examination Area" description for RR-45 to reflect required changes to relief request and RR-46 from "(7)" system hydrostatic tests to "(8)". Editorial.

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13. Page 6-5: For relief request RR-l', revised description of welds examined using calibration block ALA-RV-3 and ALA-RV-5. Editorial correction.

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Page 1 of 3

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l FNP-1-M-043 '

• j RELIEF REQUESTS FNP-1 RR-1

~ Component or o Relief Area: Relief from the material requirements for calibration blocks used to perform ultrasonic examination of the following:

APR-6: Steam generator channel

• head-to-tubesheet welds, a APR-?: Boron injection tank -i head-to-shell circumferential welds and nozzle-to-head welds, p ALA-RV-1: Reactor vessel lower head-to-lower shell weld.and all lower head welds. Boron injection tank head-to-shell circumferential welds.

ALA-RV-3: Reactor vessel top head welds. ~l .i ALA-RV-5: Reactor vessel shell welds. . ['

Requirement from which Relief ic ,

Requested: Section XI, 1983 Edition with Addenda through Summer 1983, paragraph IWA-2232 requires that 'i ultrasonic examination of vessel welds in ferritic materials greater than 2 in. in.

thickness be performed in accordance with-Article.4,'Section V. 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 cne 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 Engineers (ASME)Section III. When ASME I Section XI was issued for inservice inspection, the new requirements =for vessel calibration blocks rendered the existing blocks' unacceptable 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.

04611 6-5 REV. 3 i

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FNP-1-M 043 RELIEF REQUEST FNPd -

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-Component or .

Relief Area: Relief from notch location requirements for calibration. '

blocks used to perform the,following:-

ALA RV-1: Boron injection tank head-to shell circumferential welds. Reactor vessel lower head-to-lower shell weld- and all. lower head welds.

ALA-RV-3: Reactor vessel top head welds. ,

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

Requirement from  !

which Relief is <

Requested: Section XI, 1983 Edition with Addenda through Summer 1983, '

paragraph IWA-2232, requires that ult asonic examination of vessel welds in ferritic materir s greater than 2 in.

in thickness be conducted in acesrdance with Article 4,Section V, 1983 Edition. Figure T-434.1, Article 4, requires that the minimum dist'.nce from.the ends of the 2 in. long 2-percent T notches to the edges.of the block be 3 in..

Basis for. Relief: Figure T-546 1, Article 5,Section V, 1983 Edition, is a similar calibration' block; however, the clearance required from the ends of the 2-percent notches'is 2 in. instead of -

the 3 _in, required by Figure T-434.1, Article.4.

Experience performing. calibrations using these blocks has  ;

proven fully satisfactory.

Alternate Examination: The above calibration blocks are in compliance with the clearance dimensions required for notches by Figure  ;

T 546.1, Article 5,Section V, 1983 Edition.

000564 6 Rev. 3 i

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RELIEF REQUEST FNP-1 >

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Component'or Relief Area: Relief from hole location requirements for calibration blocks

• used to perform the following: ,

4 ALA-RV-1: Reactor vessel lower head-to-lower shell weld, all lower head welds and boron inject',on tank head circumferential welds.

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

4 APR-5:' Steam generator stub barrel-to-upper-tubesheet! '

weld, lower shell-to stud barrel weld, transition cone-to lower shell weld, upper i shell-to transition cone weld, and feedwater.

nozzle-to upper shell weld.  ;

APR-7: Pressurizer top head to nozzle welds, top .

j head-to-upper shell, all circumferential shell >

welds, ' lower-to-bottom head weld, all longitudinal shell welds, and bottom .

head-to nozzle weld. f 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 i thickness be conducted'in accordan'ce with Article 4, Sectior 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-ALA-RV-5 are .25 and .50 inches less than the required distance, respectively. The non-aligned holes are to be located a minimum 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.

Basis for Relief: Experience performing calibrations using the blocks mentioned above has proven fully satisfactory.

Alternate  !

Examination: None; the calibration blocks are acceptable for use as is.

000564 6-8 Gen. Rev. 3