JAFP-06-0085, Revision to Response for Additional Information Regarding Request for Approval of Relief Request No. 39, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspect

Revision to Response for Additional Information Regarding Request for Approval of Relief Request No. 39, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspection

ML061640320
Person / Time
Site:	FitzPatrick
Issue date:	05/31/2006
From:	Jim Costedio Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
JAFP-06-0085, TAC MC8587
Download: ML061640320 (4)

Text

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

James A. Fitzpatrick NPP 7 --Entergy P.O. Box 110 Lycoming, NY 13093 Tel 315 342 3840 JAFP-06-0085 May 31, 2006 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-000 1

SUBJECT:

Entergy Nuclear Operations, Inc.

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59 Revision to Response to Request for Additional Information (RAI) Reearding Request for Approval of Relief Request No.

39, Implementation of BWRVIiP Guidelines in lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspection (TAC No. MC 8587)

REFERENCES:

1. Telecom dated May 11, 2006 between NRC Staff and JAF Regarding Clarification on Use of BWvRVIP Guidelines.

2. Entergy Nuclear Operations, Inc. letter to USNRC (JAFP-06-0059), Response to RAI Regarding Request for Approval of Relief Request No. 39, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspection (TAC No. MC 8587) dated April 3, 2006.

3. USNRC letter to Entergy Nuclear Operations, Inc., Request for Additional Information (RAI) Regarding Relief Request RR-39, Implementation of BWRVIP Guidelines, (TAC No.

MC8587) dated February 9, 2006.

4. Entergy Nuclear Operations, Inc. letter to USNRC (JAFP-05 -015 1), Request for Approval of Relief Request No. 39, dated October 7, 2005.

Dear Sir:

On May 11, 2006, a telecom (Reference 1) was held with your Staff to discuss Entergy Nuclear Operation, Inc.'s response (Reference 2) to an NRC Request for Additional Information (RAI) (Reference 3).

404-7

This letter contains the revised information as discussed in the May 11, 2006 telecom.

This response does not change the conclusions in the original Relief Request (Reference 4). However, the scope of the original Relief Request has been revised to no longer include BWVRVIP-25, "B WRVIP Core Plate Inspection and Flaw Evaluation Guidelines" as a proposed alternative inspection program for the Core Plate Rim Hold-Down Bolts.

There are no commitments contained in this letter.

Sincerely, _ __

Regulatory Compliance Manager JC:GB:gb

Attachment:

Revised Reactor Vessel Internals Inspection Five (5) Cycle Look-Ahead cc:

Regional Administrator, Region 1 Resident Inspector's Office U. S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission 475 Allendale Road James A. FitzPatrick Nuclear Power Plant King of Prussia, PA 19406-1415 P0 Box 136 Lycoming, NY 13093 Mr. John Boska, Project Manager Plant Licensing Branch I-1 Mr. Paul Eddy Division of Operating Reactor Licensing New York State Dept. of Public Service Office of Nuclear Reactor'Regulation 3 Empire State Plaza U. S. Nuclear Regulatory Commission Albany,ý NY 12223-1350 Mail Stop O-8-C2 Washington, DC 20555 Mr. Peter R. Smith, President New York State Energy, Research,

& Development Authority 17 Columbia Circle Albany, NY 12203-6399

Attachment 1 to JAFP-06-0085 Entergy Nuclear Operations, Inc. - FitzPatrick Docket No. 50-333 Reactor Vessel Internals Inspection Five (5) Cycle Look-Ahead Reactor Internal Comp onent Inspection Bowes R07 2006 R018O 12008)L R020(0 1 L2) O~L Control Rod Drive Guide Tube Body Welds BWRVIP-47-A, Table 3-3 EVT-l EVT-l(In) _____ EVT-I Control Rod Drive Guide Tube Lug and Pin BWRVIP-47-A, Table 3-3 VT-3 VT-3(!n) _____ VT-3 Core Plate Rim Hold-Down Bolts (OTE 1)___________

Core Shroud Vertical & Bing Segent Welds BWRVIP-76, Figure 3-3 & 3-4 EVT-l/UT EVT-1(IN) EVT-l(N EVT-l EVT-l Core Shroud Tie-Rod Repair BWRVIP-76, Section 3.5 VT-3/EVT-l(10) VT-3/EVT-1(6) ______

Core Shroud Supprt Welds (H9) (OTE 3) BWRVIP-38, Figure 3-5 EVT-l EVT-l _____ EVT-1 Core Shroud Gusset Welds BWRVIP-38, Figure 3-2 and EVT-l EVT-l EVT-l BWRVIP-76,_Section 3.6 _____ ______

Core Spray Thermal Sleeve Welds (idden) (OTE 2) BWRVIP-1 8-A, Section 3.2.4 UT ()UT (IN) UTU UT (IN)

Core Spray Piping Welds BWRVIP-18-A, Table 3-5 EVT-1 -EVT-1 EVT-1 EVT-l EVT-1 Core Spray Sparer Lre Circ Welds BWRVIP-18-A, Table 3-5 EVT-1 EVT-l EVT-1 Core Spray Spaer Nozzle Welds BWRVIP-1 8-A, Table 3-5 ______ VT-I Ti(0)(50%) ______ Tl(0%)

Core Spa Piping Brackets BWRVIP-18-A, Table 3-5 EVT-l _____ EVT-l Core Spray Sparer Brackets BWRVIP-18-A, Table 3-5 VT-I _____ VT-I VT-i Feedwater Sparger Tee Welds NUREG 0619 _ ________ VT-i_____

Feedwater Sparer Bracket Attachment BWRVIP-48-A, Table 3-2 _ ________ EVT-l ________

Feedwater Sparer Assembly NUREG 0619 _ ___ ____ VT-3_____

Jet Pump Beams BWRVIP-41, Rev.l1, Table 3.3-1 and UT UT

/ ~~~BWRVIP-13S, Section 6.4 ____________ _____ ______

Jet Pump Thermal Sleeve Welds (idden) O 2) BWRVIP-41, Rev. 1, Table 3.3-1 _____ UT*M ~ UT(N T(N T(N Jet Pump Assembly (igh Priorit Welds) BWRVIP-41, Rev.l1, Table 3.3-1 UT/EVT-l ____________ EVT-1 (50%) ______

Jet Pump Assembly (Medium & Low Priorit Welds) BWRVIP-4 1, Rev.l1, Table 3.3-1 EVT-I ____ ____ EVT-l (25%0/) _ ___

Jet Pump Riser Brace Welds BWRVIP-4 1, Rev.l1, Table 3.3-1 EVT-l I____ ____ EVT-l (25%) _ ___

Jet Pump Restrainer Wedges BWRVEP-4 1, Rev.l1, Table 3.3-1 VT-I I____ ____ VT..l(50-%') ____

Lower Plenum BWRVIP-47-A, Section 3.2 _____WHNACCESSIBLE _____

Miscellaneous Vessel Internal Attachments BWRVIP-48-A, Table 3-2 VT-3 _________JVT..3/EVT-1 Orificed Fuel Supprt Castings (Sampling BWRVIP-47-A, Table 3.2-I VT-3 VT-3 VT-3 VT-3 VT-3 SLC Nozzle-to-Safe End Weld (OTE 2) BWRVIP-27-A, Section 3.3.1 PT or EVT-2* EVT-2* (IN) PT or EVT-2* EVT-2* (IN) PT or EVT-2*

Top Guide Hold-down Assemblies BWRVIP-26-A, Table 3-2 VT-l (2) ___ _ ___ VT-1 _(2) _______ V-(2 Top Guide Grid Beams (Sampting BWRVIP-26-A, Section 3.2.2 VT-31 VT-1 _____

NOTES: (1) Inspection performed per ASME Code Section XI requirements (this component is excluded from Relief Request No. 39).

(2) Inspection of these welds to be performed when UT technology is available in accordance with BWRVIP requirements of the applicable BWRVIP document.

(3) For clarification purposes only: H12 weld does not apply to the FitzPatrick Plant.

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Attachment 1 to JAFP-06-0085 Entergy Nuclear Operations, Inc. - FitzPatrick Docket No. 50-333 Reactor Vessel Internals Inspection Five (5) Cycle Look-Ahead Table Key Standard Print = Inspections mandated by BWRVIP I & E Guidelines Italics = Inspections recommended for Risk-To-Generation purposes UT = Ultrasonic Testing planned UT M* =Ultrasonic Testing when the technique becomes available VT-3/VT-1(*) = Contingency examination subject to lower plenum access VT = Visual Testing planned EVT-1 = EVT-1; Enhanced Visual Test to look for cracking; 1/2 mil wire resolution with cleaning assessment EVT-2* =Enhanced Leakage Inspection (direct view of component during pressure test)

VT-I =VT-i; Visual Test to look for cracks, wear, corrosion, etc.; resolution required: 1/32" black line VT-3 =VT-3; Visual Test to determine general mechanical/structural condition; no resolution requirements PT = Surface examination (IN) = If necessary, to complete number of inspections not performed in previous outage(s)

(all, number, or %/) = Perform inspection on all or on remainder components, limited number (or percentage) of components, or just flawed components Page 2 of 2