ML20217P316

Forwards RAI Re Licensee ,As Suppl by 970825 Requests for Change to TS to Incorporate Combustion Engineering SG Tube Sleeve Designs & Installation & Exam Techniques

ML20217P316
Person / Time
Site:	Prairie Island
Issue date:	08/22/1997
From:	David Diec NRC (Affiliation Not Assigned)
To:	Richard Anderson NORTHERN STATES POWER CO.
References
TAC-M97367, TAC-M97368, NUDOCS 9708270246
Download: ML20217P316 (4)

Text

'

Mr. Rogsr O.' Andsrson, Dir3ctor August 22. 1997 Licensing gnd M:nagsmsnt issuss

/ Northsm St:tss Powsr Company 414 Nicollet Mall I Minneapolis, Minnesota 55401

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2, REVIEW ON INCORPORATION OF COMBUSTION ENGINEERING STEAM GENERATOR WELDED TUBE SLEEVE TOPICAL REPORT j (TAC NOS. M97367 AND M97368)

Dear Mr. Anderson:

By letter datec November 27,1996, as supplemented by letter dated August 25, L 1997, Northem States Power Company (NSP) submitted for staff review a license amendment request for a change to the Technical Specifications (TS), Appendix A of the Operating Licenses for the Prairie Island Nuclear Generating Plant. The proposed changes would be made to TS 4.12, " Steam Generator Tube Surveillance,"

and its associated Bases Section B.4.12. " Steam Generator Tube Surveillance," which l

would incorporate Combustion Engineering steam generator tube sleeve designs and _.

l installation and examination techniques in order to continue the review of your license amendment request, the staff requires some additionalinformation. Our -

request for additional information (RAI) is enclosed.

Please provide your response to the staff's RAI as soon as possible in order to i support your scheduled outage. If you have any questions regarding the content of the RAI, please contact me at (301) 415-2834.

Sincerely,  :

F i

ORIGINAL SIGNED BY:

David T. Diec, Acting Project Manager i Project Directorate 111-1 j

~

Division of Reactor Projects -lil/IV J

Office of Nuclear Reactor Regulation g 4f j

Docket Nos. 50-282, 50-306 bI '

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Enclosure:

As stated ,

qL L..n 7- l na. . a a cc w/ encl: See next page

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j DISTRIBUTION:

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DOCUMENT NAME: G:\WPDOCS\ PRAIRIE \Pl97367.RAI To receive a copy of this document, indicate in the box C= Copy w/o attachment / enclosure E= Copy with attachment / enclosure N = No copy jlh( .

OFFICE APM:PD31 E LA:PD31 E PM:PD31, E D:PD31 [ l NAME DDieh CJamersond BWetzdk JHannon h DATE 08/MJ0i j 08/2//97 FFirlAL RECORD COPY

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%*****;2 August 22, 1997 Mr. Roger O. Anderson, Director Licensing and Management issues Northem States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2, REVIEW ON INCORPORATION OF COMBUSTION ENGINEERING STEAM GENERATOR WELDED TUBE SLEEVE TOPICAL REPORT (TAC NOS. M97367 AND Mb7368)

Dear Mr. Anderson:

By letter dated November 27,1996, as supplemented by 'etter dated August 25, 1997, Northem States Power Company (NSP) submitted for staff review a license amendment request for a change to the Technical Specifications (TS), Appendix A of the Operating Licenses for the Prairie Island Nuclear Generating Plant. The proposed changes would be made to TS 4.12, ' Steam Generator Tube Surveillance,"

and its associated Bases Section B.4.12, " Steam Generator Tube Surveillance,' which would incorporate Combustion Engineering steam generator tube sleeve designs and installation and examination techniques. In order to continue the review of your license amendment request, the staff requires some additionalinformation. Our request for additional information (RAI) is enclosed.

Please provide your response to the staffs RAI as soon as possible in order to support your scheduled outage. If you have any questions regarding the content of the RAI, please contact me at (301) 415-2834.

Sincerely, I n --

David T. Diec, Acting Project Manager Project Directorate Ill-1 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation Docket Nos. 50-282, 50-306

Enclosure:

As stated cc w/ encl: See next page T

Mr. Roger O.' Anderson, Director Prairie Island Nuclear Generating Noithem States Power Company Plant i

cc:-

~J. E. Silberg, Esquire . Site Licensing ,

Shaw, Pittman, Potts and Trowbridge Prairie Island Nuclear Generating

! 2300 N Street, N; W. .

Plant l- Washington DC 20037 Northem States Power Company l 1717 Wakonade Drive East Plant Manager _ Welch, Minnesota 55089 i Prairie Island Nuclear Generating '

Phnt TnbalCoundl Northem States Power Company Prairie Island Indian Community .

!= 1717 Wakonade Drive East ATTN Environmental Department Welch, Minnesota 55089 5636 uturgeon Lake Road h . Welch, Minnesota 55089 Adonis A. Nebiett

Assistant Attomey General l Office of the Attomey General j- - 455 Minnesota Street-Suite 900 St. Paul, Minnesota 55101-2127 i

U.S. Nuclear Regulatory Commission Resident inspector's Office 1

1719 Wakonade Drive East -

2 Welch, Minnesota 55089-9642 l

[ - Regional Administrator, Region lli

. ' U.S. Nuclear Regulatory Commission '

, 801 Warrenville Road Lisle, Illinois 60532-4351 Mr. Jeff Cole, Auditor / Treasurer Goodhue County Courthouse e

Box 408 Red Wing, Minnesota - 55066-0408 4

[

- Kris Sanda, Commissioner Department of Put,lic Service L 121 Seventh Place East 4 - Suite 200-St. Paul, Minnesota _55101-2145 i~

I-a 4

~

~ Novemner 1996 -

i' ,

1

. _ __ _ l ,. ' ~ _ " ~ __ , _ . _. . . _ ,

i REQUEST FOR ADDITIONAL INFORMATION REVIEW OF LICENSE AMENDMENT REGARDING

INCORPORATION OF COMBUSTION ENGINEERING STEAM GENERATOR ,

! WELDED TUBE SLEEVE TOPICAL REPORT FOR >

PRAIRIE ISLAND UNITS 1 AND 2 L

1.' A recent welded sleeve in-service inspection at Kewaunee identified weld zone 9 indications, using a visual technique, that were not detected by either ultrasonic or eddy current technique. The proposed amendments do not specifically require a p

visualinspection of the upper weld for tubesheet sleeves. Discuss the basis for not requiring an upper wold visual inspection during the installation process in light

[ of the fir. dings at Kewaunee.

~

2. Page 6, Exhibit A, inseivice Examination. lt is stated that a 20-percent sample of all installed sleeves in each steam generator will be inspected each refueling =

outage, and an expansion of 100 percent of sleeves, in affected steam generator,

! will be inspected if one pluggable indication has been found. Please clarify -

L whether these requirements have been incorporated into technical specifications

[ - or as a license condition to perform the sleeve examinations in accordance with -

L these specifications.

3J Table 8-1 of the CEN-629-P, Revision 1, " Repair of Westinghouse Series 44 and

! 51 Steam Generator Tubes Using Leak Tight Sleeves," report specifies that a L tensile strength of 90 kai for the sleeve material was assumed rather than the American Society of Mechanical Engineers (ASME) Code minimum value of 80 kal

, for material procured to requirements of Section ll SB-163. The staff does not,

[ generally, approve of the use of material property values differing from the ASME ,

Code Section l! proporties. Provide the basis for assuming that the sleeves to be

installed in the Prairie _lsland steam generators would have an ultimate strength

, greater than or equal to the 90 ksi value assumed in the structural assessment.

l

4. Although NSP indicates in the proposed amendment request that post weld heat treatment (PWHT) of sleeve welds would be performed in the upcoming refueling

- outage, NSP, does not specifically require PWHT in future outages. ~ The F

- elimination of the PWHT step from the installat!on would theoretically increase the susceptibility of sleeve welds to stress corrosion crecidng.~ Provide the te ,hnical-

[ basis for omitting PWHT in the sleevt , stallation process. Spedfica:ly address

! = the potential for the initiation and grrwu of sleeve weld's degradation over a cycle of operation that could challenge the ;JJctural and leakage integrity margins for a

[ _ sleeved tube, c

a

, Enclosure

)

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