ML061700484

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Vermont Yankee Amp/Amr/Tlaa Audit Question and Answer Database, Rev 1 (B)
ML061700484
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 06/19/2006
From:
Vermont Yankee
To: Rowley J
NRC/NRR/ADRO/DLR/RLRB
Rowley J, NRR/DRIP/RLEP, 415-4053
Shared Package
ML061700483 List:
References
%dam200610
Download: ML061700484 (2)


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(\) 0- (\) 0-how ~ VY developed ui:J t:O~Ethe condensed list of transients ID ID 0 ID A) Discuss ro 4: provided in Table 4.

J - -t:: 2 from the complete list in the design spec. Also provide a copy of the 1::~0 0- CD ID C-t:O-  ;:. CU

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CD ' 0 ~ CO 4:a5m~ '00 :J ro t: Response ~  ;:':s:;:.A) The condensed list of -;Q:e CD-(\)transients CD;:' ~ in Table 4. 2 was developed to ID simplify cycle tracking by the plant operations staff. The basis for reducing the number of ro.....

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1 I- ...o in Calculations VYC-378 Rev. O and.ERev. .i- 1. Attachment 1 of VYC- 378 Rev. 1 is titled " Recommendations for Tracking/Limiting

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t: Xof VYC- 378 Rev. O and Rev. 1 were.Eprovided CD 0 Q) November 13, 1987. The complete list of design transients is contained in Attachment 1 pgs 0 Q)

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a; ID ~ ~ 0 CD The updated Reactor Vessel ID OJ ID Specification

(\) for Extended Power Uprate is GE Specification No. 26A6019 Rev. 1 dated 6/2/2003. It is supplemented by the original

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CD.o The VYNPS(\) CO Fatigue Monitoring m:::::: ID gj"8 IDProgram will assure that the allowed number of transient cycles is not exceeded. The program requires corrective action if transient

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j2.c 21 (c)(1 )(i). However, when the effectsII: of reactor coolant environment (5) on fatigue are added to the existing fatigue analyses, several c.:i - E~locations have a projected

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cumulative usage factor in excess of 1. 0.

(\)c:t:CU  ::J See section 4. 3 for further discussion of the effects of reactor water environment on fatigue.

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The correct .o t:CQ.$2 reference is letter BVY96- 96, not 96- 48. The originator, addressee, title and date were correct, only the letter number was wrong. The following is the correct citation

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Modification, " BVY 96- 96, &~oC\3 letter dated August 7 1996.

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RequestQ I- a5LRA Section 4.

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3. CQ t:3 will be revised to eliminate " TLAA - metal fatigue " whenever there is no corresponding TLAA in Section 4.

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326 Cate!:lorv Closed Reauest Please provide the fatigue analysis as referenced in the EPU- FSAR:

- PUSAR Table 3.

Response There is no reactor vessel internals fatigue analysis using the 1986 ASME Section III code as a guideline. The fatigue analysis listed in the PUSAR is Task 0303 and it references NEDC- 32424P- A and NEDC- 32523P- A; copies of these analyses were provided in response to question 325.

327 Cateaorv Open Reauest Do you have any plans to use " Fatigue- Pro " other than for cycle counting? If so, explain and supplement application as appropriate.

Response Current plans for implementing FatiguePro at VY are to use Stress Based Fatigue (SBF) monitoring for the Feedwater Nozzles. Automated or manual cycle counting (CBF) are planned for the remaining components. Components identified for automated CBF were selected using the following criteria; components with a design basis usage factor greater 0.40 for 40 yrs, Emergency Core Cooling System (ECCS) components, or where field experience suggests that a fatigue concern exists.

The transient data acquisition capabilities in FatiguePro may be used for future development of SBF models and/or operational transient cycle counting for components as required to address operational changes and/or environmentally assisted fatigue concerns.

328 Cateaorv Accepted uest 13-The staff has discovered, as a result of previous discussions with the applicant, that the VY FAC program calculations are very specific in terms of calculations, as compared to other wall thickness applicants that we have reviewed.

Res onse Provided RFO 25 (Fall 2005) large bore inspection report evaluations for inspection nos. 2005 - , 2005- , 2005- 09, 2005- 10, 2005- 36, and 2005- 37: and small bore evaluations 05- SB02 and 05 SB03. Also provided a copy of RFO outage inspection report VY- RPT 000002 Rev.

329 Cateaorv Accepted uest 113-The staff has also noted in their review of the LRA, that the VYNPS program operational experience appears to be above !'lverage in discovery FAC-related issues. Please provide us with a couple of examples of piping FAC discovery using the present program.

Res onse Provided scoping / planning worksheets for both RFO 25 and RFO 26. These list FAC industry OE evaluation for VYNPS.

330 Cate!:lorv Accepted uest 1 How does Vermont Yankee do volumetric examinations of small bore p!ping socket welds?

Response 330 - VYNPS performs visual examinations of these welds as required by Section XI of the ASME code.

The One-Time Inspection program will also include destructive or non- destructive examination of one (1) socket welded connection using techniques proven by past industry experience to be effective for the identification of cracking in small bore socket welds. Should an inspection opportunity not occur (e. g., socket weld failure or socket weld replacement), a susceptible small- bore socket weld will be examined either destructively or non- destructively prior to entering the period of extended operation.