ML17312B686

From kanterella
Jump to navigation Jump to search

Forwards RAI Re Proposed TS Amend for SG Tube Sleeving for Mentioned Plant
ML17312B686
Person / Time
Site: Palo Verde  
Issue date: 09/11/1997
From: Thomas K
NRC (Affiliation Not Assigned)
To: James M. Levine
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
References
TAC-M98920, TAC-M98921, TAC-M98922, NUDOCS 9709260272
Download: ML17312B686 (10)


Text

September 11, 1997 Mr. James H. Levine Executive Vice President, Nuclear Arizona Public Service Company Post 'Office Box 53999

Phoenix, Arizona 85072-3999

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED TECHNICAL SPECIFICATION AMENDMENT FOR STEAM GENERATOR TUBE SLEEVING FOR THE PALO VERDE NUCLEAR GENERATING STATION (TAC NOS.

M98920.

H98921 AND M98922)

Dear Hr. Levine:

By letter dated May 23 '997, Arizona Public Service Company submitted a

proposed Technical Specification (TS) amendment for the Palo Verde Nuclear Generating Station (PVNGS) that would allow the installation of tube sleeves designed by ABB-Combustion Engineering as an alternative to plugging defective steam generator tubes at PVNGS.

The design, qualification, and installation of the sleeves are described in the ABB-Combustion Engineering topical report CEN-630-P, Revision 1

(November 1996),

"Repair of 3/4 inch O.D. Steam Generator Tubes Using Leak Tight Sleeves."

The staff has reviewed the submittal and has determined tI)at additional information, as discussed in the enclosure.

is needed to complete its review.

To assist the staff in completing its review of the application, please respond in writing to this request for additional information within 30 days from the date of this letter.

k If you have any questions, please contact me at (301) 415-1362.

Sincer ely, Original Signed By

,Kristine H.-Thomas, Project Manager Project Directorate IV-2 Division of Reactor Projects

- III/IV Office of Nuclear Reactor Regulation Docket Nos.

STN 50-528, STN 50-529 DISTRIBUTION:

and STN 50-530

Docket Fi 1.ei,
ACRS, TWFN PUBLIC CBeardslee

Enclosure:

Request for Addit'ional PDIV-2 Reading OGC ! 015B18 Information EAdensam (EGA1)

KPerkins, WCFO WBateman
PGwynn, RIV cc w/encl:

See next page KThomas

DKirsch, WCFO EPeyton

'Tsao DOCUMENT NAME: PV98920.RAI OFC PDIV-2/PH NAME KT omas:ye DATE 9n I /97 F

L R 9709260272 970%ii PDR, ADOCK 05000528 P

PDR PDIV-2/LA EPeeyn 9/!'L /97

~ ll!llll!llll!llll!llll!

IIllllllllllia

h lt

>l,i 1

N f

Mr. James M. Levine September 11, 1997 cc w/encl:.

Mr. Steve Olea Arizona Corporation Commission 1200 W. Washington Street Phoenix. Arizona 85007 Douglas Kent Porter Senior Counsel Southern California Edison Company Law Department.

Generation Resources P.O.

Box 800

Rosemead, Cali fornia 917?0 Senior Resident Inspector USNRC P. 0.

Box 40 Buckeye. Arizona 85326 Regional Administrator, Region IV U. S. Nuclear Regulatory Commission Harris Tower 8 Payillion 611 Ryan Plaza Drive, Suite 400 Arlington. Texas 76011-8064

Chairman, Board of Supervisors ATTN:

Chairman 301 W. Jefferson, 10th Floor Phoenix, Arizona 85003 Mr. Aubrey V. Godwin, Director Arizona Radiation Regulatory Agency 4814 South 40 Street

Phoenix, Arizona 85040 Ms. Angela K. Krainik, Manager Nuclear Licensing Arizona Public Service Company P.O.

Box 52034

Phoenix, Arizona 85072-2034 Mr. John C. Horne, Yice President Power Supply Palo Yerde Services 2025 N. Third Street, Suite 220
Phoenix, Arizona 85004 Mr. Robert Burt Los Angeles Department of Water 8 Power Southern California Public Power Authority ill North Hope Street, Room 1255-B Los Angeles, California 90051 Mr. David Summers Public Service Company of New Mexico 414 Silver SW, ¹0604 Albuquerque, New Mexico 87102 Mr. Robert D. Bledsoe Southern California Edison Company 14300 Mesa
Road, Drop D41-SONGS San Clemente, California 92672 Mr. Robert Henry Salt River Project 6504 East Thomas Road Scottsdale.

Arizona 85251 Terry Bassham, Esq.

General Counsel El Paso Electric Company 123 W. Mills El Paso.

Texas 79901

t

Enclosure RE UEST FOR ADDITIONAL INFORMATION REVIEW OF LICENSE AMENDMENT REGARDING SLEEYING OF STEAM GENERATOR TUBES PALO VERDE NUCLEAR GENERATING STATION UNITS 1 2 AND 3 By letter dated Hay 23, 1997. Arizona Public Service Company (APS) submitted for staff review a request for a technical specification (TS) amendment to allow the installation of tube sleeves as an alternative to plugging defective steam generator tubes at Palo Verde Units 1, 2.

and 3.

The submittal includes a proposed revision to the TS to allow steam generator tube repair using leak tight sleeves designed by ABB-Combustion Engineering (CE).

The design, qualification, and installation of the sleeves are described in the ABB-CE topical report,

'Repair of 3/4" 0.0.

Steam Generator Tubes Using Leak Tight Sleeves,'EN-630-P, Revision 1.

November 1996.

In order to complete its review. the staff requests the following additional information:

The proposed TS changes describe eddy current inspection criteria for steam generator (SG) tubes without particular reference to sleeve inspections.

Without explicit inspection criteria in the TS, the requirements for the initial sample scope and subsequent expansion criteria for sleeve inspections would be based on existing TS requirements (e.g..

3X initial sample scope).

The staff believes that the proposed TS do not provide adequate inservice inspection (ISI) of sleeved steam generator tubes.

and that the inspection and expansion criteria in the EPRI Steam Generator Tube Examination Guidelines should be satisfied, as a minimum, for all sleeved tubes.

Please provide appropriate wording in the TS reflecting this criteria.

For reference, a previously adopted table incorporated in the TS for another licensee is attached.

Further, several TS sections (4.4.4.2; 4.4.4.3.b; 4.4.4.3.c; and 4'.4.4.b) will be affected and need to be modified when a separate table is generated for sleeve inspections.

2.

3.

4 Describe the extent to which APS subscribes to the EPRI PWR Steam Generator Tube Examination Guidelines.

For example, does APS use the Appendix G, "Qualified Personnel" and Appendix H

Qualified Techniques" in the EPRI Guidelines7 Describe the approach APS plans for adopting new and improved eddy current techniques for 'sleeve inspections.

Recent experience at the Kewaunee nuclear plant showed that visual test (VT) examinations of welded freespan joints may detect significant process-induced defects that were not detectable or resolvable by ultrasonic tests (UT) or eddy current (EC) examinations.

The ABB-CE

t 5.

6.

report discussed two VTs associated with the sleeving process.

but does not specifically state that a

VT is required.

Clarify if APS will per form a VT in accordance with the topical report and how often a VT will be performed.

If a VT will not be performed, provide the details of the nondestructive examination qualification efforts that justify the use of UT and EC inspections.

without a VT, as a sufficient means to demonstrate acceptable sleeve weld'quality.

APS stated in TS Bases Section 3/4.4.4 that it will perform post weld heat treatment (PWHT) to the sleeve weld joints.

The staff believes that commitments made in the Bases section are subjected to change under 10 CFR 50.59 and, therefore, are inappropriate for inclusion in staff safety evaluations.

The staff requests APS incorporate the commitment to perform PWHT in, the surveillance requirements section of TS, preferably in TS Section 4.4.4.4., As an alternative.

APS may submit for staff review an evaluation that demonstrates the acceptabi lity of weld joints integrity without the PWHT.

The current TS Limiting Condition for Operation (LCO) 3.4.5.2.c specifies an allowable leakage of 1 gpm for the total primary-to.-

secondary leakage through all steam generators and 720 gallons per day through any one steam generator.

The NRC staff position regarding operational leakage limits is that allowable operational leakage limits should be reduced to 150 gallons per day through any one steam generator when sleeying of steam generator tubes is performed.

Please revise the TS accordingly.

7(a).

APS has proposed a plugging limit for ABB-CE sleeves of 35K of the nominal sleeve wall thickness.

This is documented in the proposed TS.

However, the topical report.

CEN-630-P. calculated a

"X allowable degradation" that is different from 35K.

Please clarify the basis for the 35K TS limit. and its relation to the calculated value in the topical report.

7(b).

The associated proposed TS Section 4.4.4.4.a.7.b does not clearly document that the plugging limit is 35K of the sleeve wall thickness.

Please modify the proposed TS to address this.

The following wording for TS Section 4.4.4.4a.7.b would clarify the matter:

"b.

ABB-CE Leak Tight Sleeve Wall 35K",

8.

As part of the TS amendment request to use ABB-CE sleeves, APS submitted two proposed revisions of TS changes.

The first version proposed changes to the current.

approved TS.

The second version proposed changes to the Improved TS.

The staff will only review the proposed changes associated with the current TS.

The Improved TS are being reviewed under a separate TS amendment request.

The proposed sleeve inspection changes to the Improved TS should be submitted under that TS amendment request.

The staff suggests that the TS issues addressed in this Request for Additional Information also be addressed in the Improved TS.

Attachment:

Table

~ ~

ST SAMPLE INSPECTION

'ABLE 4 ~4M/

STEAM GENERATOR TUBE ~EE+~g INSPECTION 2ND SAMPLE INSPECTION S

le S'ixe Result Act on Re red Result Act on Re re Beet&4 A ainimua of 6 Sahee ~st c C-1 None N A N A perS.G.~

C-2 P uy tube conta n n defective

@shee sleeves and inspect all remai stal ed sleeves in this S.G.

C-1 None P ug ubes conta n detacttve tutee sleeves C-2 Inspect a

sta e

~eaves ashes in t s

s G

s pluy tubes

~o~tai >~idefective ashes s~leev s

and inspect ~00\\ ~o sta e

sleeves 66 epee in each ~te other SeGS Special Report to NRC per Specification 6.9.2 C-3 t er S.G.e-eee C-1 6eae-~Ot e

S.G.a~ C-2 hue-he edtfk440htlk

&r4~tea ~

C~tha S,G, le C-3 PerforaL act on for C-3 result of first 6s le None eaeg4a lu tubes contai de ect v sleeves Inspect all sleeves tutee ln each S.G.

and plug

~shee ~eaves special Report to NRC per Spec.

6.9.2.

o s de e

se a

~

~

r