2CAN049703, Application for Amend to License NPF-6,revising Requirements for Sample Scope Initial Size & Expansion for Inservice Insp Steam Generator Tube Sleeves

Application for Amend to License NPF-6,revising Requirements for Sample Scope Initial Size & Expansion for Inservice Insp Steam Generator Tube Sleeves

ML20138D634
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/24/1997
From:	Hutchinson C ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20138D639	List: 2CAN049703, Application for Amend to License NPF-6,revising Requirements for Sample Scope Initial Size & Expansion for Inservice Insp Steam Generator Tube Sleeves ML20138D641
References
2CAN049703, 2CAN49703, NUDOCS 9705010188
Download: ML20138D634 (7)

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Ent:rgy oper:tions, Inc.

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- Enter'DJ ov 14485H 333 Tel 501858-4888 C. Randy Hutchinson Vcc Pmsrent Operafons ANO April 24,1997 l 2CAN049703 U. S. Nuclear Regulato y Commission Document Control Desk Mail Station PI-137 Washington, DC 20555

Subject:

Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Technical Specification Change Request Regarding Steam Generator Tube Sleeving Inspection Criteria Gentlemen:

This technical specification change request (TSCR) revises the requirements for sample scope initial size and expansion for inservice inspection of steam generator tube sleeves. Table 4.4-3

" Steam Generator Tube Sleeve Inspection," has been added to the Arkansas Nuclear One, Unit 2 (ANO-2) Technical Specifications to require an initial inspection of at least 20% of I each type ofinstalled sleeve and an expansion to 100% upon discovery of a defect. l l

By letter dated April 22,1992 (2CNA049203), the NRC issued license amendment number 133 for ANO-2. This amendment revised the Surveillance Requirements for the steam generator tubing to allow steam generator tube repair by use of Babcock ind Wilcox sleeves.

By letter dated January 26,1993 (2CNA019303), the NRC issued license amendment number 142 for ANO-2. This amendment revised the Surveillance Requirements for the ANO-2 steam generator tubing to alW steam generator tube repair by use of the Combustion )

Engineering Nuclear Services tungsten inert gas welded sleeves. The steam generator tube \

minimum sample size associated with amendments 133 and 142 remained at a 3% initial inspection.

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In a letter dated January 7,1997, the staff requested that ANO modify the existing ANO-2 Technical Specifications related to the periodic inservice inspections of steam genera sleeves. In particular, the staff requested that more conservative requirements for sample scope initial size and expansion criteria be incorporated into the technical specifications. To l implement this request, a new table, Table 4.4-3 has been added.

i Entergy Operations requests that the effective date for this change be within 30 days of issuance of the amendment to allow for distribution and procedural revisions necessary to

! implement the change.

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,ll 9705010188 970424 II l'It'llll@lI.lll,Il PDR ADOCK 05000368 R lllu ll* *ll *l l * *l *II.

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! U. S. NRC

. April 24,1997

.. ', .2CAN049703 Page 2 I

Very truly yo s, C

/N dwb Attachments To the best of my knowledge and belief, the statements contained in this submittal are ,

true.

SUBSCRIBED AND SWORN TO before me, a Notary P,uplic in and for 64c>

County and the State of Arkansas, this JdAday of L%' t ,1997.#

a tt 11 o 0Qu,J Notary PQlic h My Commission Expiresb,, t, i / f 200 f cc: Mr. Ellis W. Merschoff ,

Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064  ;

l' NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 l Mr. George Kalman NRR Project Manager Region IV/ANO-1 & 2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 i

Mr. David D. Snellings I Director, Division of Radiation Control and Emergency Management i Arkansas Department of Health  ;

4815 West Markham Street Little Rock, AR 72205 ,

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ATTACHMENT IQ t

2CAN049703 PROPOSED TECHNICAL SPECIFICATION .

l AND RESPECTIVE SAFETY ANALYSES IN THE MATTER OF AMENDING LICENSE NO. NPF-6 l ENTERGY OPERATIONS. INC.  !

ARKANSAS NUCLEAR ONE. UNIT TWO  ;

DOCKET NO. 50-368 l

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Attachment to 2CAN049703

', ,Page1of3 DESCRIPTION OF PROPOSED CIIANGES .

The proposed technical specifications change revises the requirements for initial sample scope i and expansion for inservice inspection (ISI) of the steam generator tube sleeves. A new Table 4.4-3, " Steam Generator Tube Sleeve Inspection," has been added to require an initial ,

-inspection of a minimum of 20% of each type ofinstalled sleeves. The proposed changes revise the ANO-2 Technical Specifications as follows- i i

1. Revises section 4.4.5.2. by cht.nging " Table 4.4-2" to " Tables 4.4-2 and 4.4-3," and ~  !

inserting "and at least 20% of all installed sleeves." '

2. Revises section 4.4.5.2.c by changing " Table 4.4-2" to " Tables 4.4-2 or 4.4-3."

3. Revises section 4.4.5.3.b,4.4.5.3.c,4.4.5.4.b and 4.4.5.5.c by changing " Table 4.4-2" to

" Tables 4.4-2 and 4.4-3." i I

4. Revises Table 4.4-2, " Steam Generator Tube Inspection," to " Steam Generator Non- j Repaired Tube Inspection," to apply only to tubes that have not been repaired.  ;

5. Adds a new table, Table 4.4-3, " Steam Generator Tube Sleeve Inspection," which requires a mimmum nutial sample of 20% of each type ofinstalled sleeves.  !

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6. Revises Bases 3/4.4.5 to add "or 4.4-3" to the last paragraph. j l -

l 7. Includes three administrative changes: 1) the note following section 4.4.5.0 was deleted ,

l since it applied specifically to outage 2P95-1 which occurred in January 1995, 2) in section 4.4.5.3.c.1, the word " tubes" was changed to " tube," and 3) the generic wording l in Table 4.4-2 was changed from "All other S.G.s are C-1" to "other S.G. is C-1" and l "Some S.G.s C-2 but no additional S. G. are C-3" to "other S. G. is C-2." The clarified

! wording was also utilized in Table 4.4-3.

i l BACKGROUND 1

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By letter dated April 22,1992 (2CNA049203), the NRC issued license amendment number l 133 for ANO-2. This amendment revised the Surveillance Requirements for the steam generator tubing to allow steam generator tube repair by use of Babcock and Wilcox sleeves.

By letter dated January 26,1993 (2CNA019303), the NRC issued license amendment number 142 for ANO-2. This amendment revised the Surveillance Requirements for the ANO-2 i

steam generator tubing to allow steam generator tube repair by use of the Combustion Engineering Nuclear Services tungsten inert gas (TIG) welded sleeves. The steam generator tube minimum sample size associated with amendments 133 and 142 is a 3% initial inspection.

3 In a letter dated January 7,1997 (2CNA019702), the NRC requested that ANO revise the

ANO-2 Technical Specifications to include more conservative ISI ofinstalled steam generator

{ sleeves.

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Attachment to 2CAN049703 f ,

, Pag'e 2 of 3 l DISCUSSION OF CHANGE The proposed change is intended to satisfy the NRC's request for ANO to add specific sleeve inspection criteria to the ANO-2 Technical Specifications. In particular, the staff requested that the sleeve ISI requirements for initial sample scope and expansion criteria be in:orporated into the technical specifications. To implement this request, a new table, Table 4.4-3 has been added which requires an inspection of a minimum of 20% of each type ofinstalled sleeves.

The 20% inspection criterion is conservative with respect to the existing requirement of a 3%

initial inspection of all steam generator tubes.

I Similar requests for changes to the technical specifications at other facilities (e.g., Kewaunee and Callaway plants) have been previously submitted to the NRC and approved.

l DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION An evaluation of the proposed change has been performed in accordance with l 10CFR50.91(a)(1) regarding no significant hazards considerations using the standards in  ;

10CFR50.92(c). A discussion of these standards as they relate to this amendment request follows:

Criterion 1 - Does Not Involve a Significant Increase in the Probability or i Consequences of an Accident Previously Evaluated.  !

1 This change implements a more stringent surveillance requirement than currently exists. It l incorporates a requirement to inspect a minimum of 20% of each type ofinstalled sleeve in l

each steam generator. The 20% inspection criterion is conservative with respect to the existing requirement of a 3% initial inspection of all steam generator tubes. Additionally, since the process for inspections has not changed, the probability or consequences of accidents previously analyzed are not increased as a result of inspection activities. The proposed changes have no impact on any previously analyzed accident in the safety analysis l report.

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The administrative changes made to update the technical specifications or to correct inconsistencies introduced in previous amendments do not affect reactor operations or accident analyses and have no radiological consequences.

Therefore, this change does Eqt involve a significant increase in the probability or {

consequences of any accident previously evaluated.  !

Criterion 2 - Does Not Create the Possibility of a New or Different Kind of Accident from any Previously Evaluated.

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The changes made to increase the initial sample of sleeved tubes inspected during a i surveillance, to update the technical specifications and to correct inconsistencies introduced in i f

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Attachment to 2CAN049703

. Page 3 of 3 previous amendments are administrative and do not change the design, configuration or method of operation of the plant nor does it introduce any new possibility for an accident.

Therefore, this change does not create the possibility of a new or different kind of accident from any previously evaluated.

Criterion 3 - Does Not Involve a Significant Reduction in the Margin of Safety.

As previously discussed, this change implements a more stringent surveillance requirement than currently exists. The existing technical specifications require an initial inspection of 3%

of the tubes in each steam generator while the proposed change requires inspection of a minimum of 20% of each type of installed sleeve. The 20% inspection criterion is conservative with respect to the existing technical specification. Existing technical specification operability and surveillance requirements are not reduced by the proposed change, thus no margins of safety are reduced.

The other administrative changes do not reduce technical specification operability and surveillance requirements, and therefore, do not reduce any margin of safety.

Therefore, this change does not involve a significant reduction in the margin of safety.

Therefore, based upon the reasoning presented above and the previous discussion of the amendment request, Entergy Operations has determined that the requested change does no.1 involve a significant hazards consideration.  !

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! PROPOSED TECHNICAL SPECIFICATION CHANGES i

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