ML20129E716

Forwards Request for Addl Info Re Request to Amend 10CFR50, App H Surveillance Program & Info Provided in WCAP-14484

ML20129E716
Person / Time
Site:	Beaver Valley
Issue date:	09/30/1996
From:	Wichman K NRC (Affiliation Not Assigned)
To:	Stolz J NRC (Affiliation Not Assigned)
References
NUDOCS 9610030261
Download: ML20129E716 (5)

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%g UNITED STATES j NUCLEAR REGULATORY COMMISSION 0,,

I WASHINGTON, D.C. 20066 0001 s,

• • • • • / TEP 3 012 MEMORANDUM TO: John F. Stolz, Project Director Project Directorate I-2 Division of Reactor Projects I/II FROM:

U Keith R. Wichman, Section Chief aterials Integrity Section Q M aterials and Chemical Engineering Branch

SUBJECT:

DUSQUESNE LIGHT COMPANY PROPOSAL TO AMEND THE 10 CFR PART 50, APPENDIX H CAPSULE WITHDRAWAL SCHEDULE On March 27, 1996, the Dusquesne Light Company (DLC) submitted MCAP-14484,

" Analysis on Capsule V from the Dusquesne Light Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program," to the staff. WCAP-14484 was issued to summarize the results of the mechanical property tests conducted on Surveillance Capsule V, which was withdrawn from the Beaver Valley Unit 2 (BV2) reactor vessel after 5.98 effective full power years (EFPY).

In its submittal, DLC provided the staff with the proposed changes to the BV2 Surveillance Capsule Removal Schedule, as described in Section 7.0 of WCAP- l 14484 and required by the regulations.Section III.B.3 of Appendix H to Title 10 of the Code of Federal Regulations, Part 50 (10 CFR 50, Appendix H),

requires that proposed surveillance programs and withdrawal schedules be submitted to the staff for review. The staff has reviewed DLC's submittal of March 27, 1996, and WCAP-14484, and has a number of issues regarding these submittals. The staff requires further information regarding these issues in order to complete its review of DLC's submittal and WCAP-14484. The staff is listing these issues and the requested information that is needed for completion of the staff's review in a Request for Additional Information (RAI). This RAI is provided in Attachment I to this memorandum.

Please note that on October 4,1995, the Atomic Safety and Licensing Board (ASLB) issued a ruling (LPB-95-17) that proposed changes to surveillance programs for reactor vessel beltline materials (i.e. surveillance programs as defined and required in'10 CFR Part 50, Appendix H) must be submitted to the staff as license amendments per the requirements of 10 CFR 50.90. Such amendments to operating licenses are required by 10 CFR 50.91 to include a "no significant hazards" statement regarding the changes to the surveillance capsule withdrawal program. In LPB-95-17, the ASLB also ruled that such amendments to the surveillance capsule withdrawal program must be filed in the Federal Register in order to allow for a 30 day public comment period.

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Contact:

J. Medoff, NRR NRC FR.E CENTES C0py (301)415-2715

, 4 9610030261 960930 PDR ADOCK 05000412 P PDR

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'$rp 3 019W J. F. Stolz The staff has noticed that Dusquesne Light Company (DLC) has requested NRC review of the proposed changes to the surveillance capsule withdrawal schedule for Beaver Valley Unit 2 (as requested in the DLC submittal to the staff of March 27, 1996), but did not submit its changes to the withdrawal schedule as a license amendment to Operating License No. NPF-73. In accordance with ASLB Ruling ~ LPB-95-17, the staff requires that DLC amend its submittal of March 27, 1996 as a license amendment to Operating License No. NPF-73, and include in the submittal a "no significant hazards" consideration regarding the proposed changes to the surveillance program and withdrawal schedule.

Docket No. 50-412

Attachment:

As stated cc: J.R. Strosnider D.S. Brinkman Docket No. 50-412

Attachment:

As stated cc: J.R. Strosnider D.S. Brinkman Distribution:

Central Files PDR EMCB/RF ADLee BJE1110t Concurrence:

DOCUMENT NAME: G:\MED0FF\BV2.RAlf Ta receive e copy of this document, Indicate in thefox: "C" = Copy without enclosures *E" = Copy with enclosures *N" = No copy 0FFICE DE:EMCB l6 QB JflC$ V l E l l l NAME JMedoff DN KiGh6hYan DATE 09/2G /96 4/ 09/34y96 09/ /96 09/ /96 09/ /96

Contact:

J. Medoff, NRR (301)415-2715 0FFICIAL RECORD COPY l

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. "g? 30 1%6 J. F. Stolz .

} The staff has noticed that Dusquesne Light Company (DLC) has requested NRC review of the proposed changes to the surveillance capsule withdrawal schedule for Beaver Valley Unit 2 (as requested in the DLC submittal to the staff of March 27, 1996), but did not submit its changes to the withdrawal schedule as a license amendment to Operating License No. NPF-73. In accordance with ASLB Ruling LPB-95-17, the staff requires that DLC amend its submittal of March 27, 1996 as a license amendment to Operating License No. NPF-73, and include in the submittal a "no significant hazards" consideration regarding the proposed changes to the surveillance program and withdrawal schedule.

i Docket No. 50-412 4

Attachment:

As stated cc: J.R. Strosnider D.S. Brinkman Docket No. 50-412

Attachment:

As stated cc: J.R. Strosnider D.S. Brinkman Distribution:

Central Files PDR EMCB/RF ADLee BJElliot

, Concurrence:

. DOCUMENT NAME: G:\MED0FF\BV2.RAIj

Ts receive a copy of this document, indcate in thefon

"C" = Copy without enclosures *E* = Copy with enclosures "N* = No copy

0FFICE DE

EMCB l 6C QE/J6C l E l l l NAME JMedoff DN KiGft6hifan DATE 09/26/96 6/ 09434y96 09/ /96 09/ /96 09/ /96

Contact:

J. Medoff, NRR (301)415-2715 0FFICIAL RECORD COPY

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i; i ATTACl# LENT 1  ;

.Reauest for Additional Information for the Dusauesne Licht Company Reaardino the Reauest to Amend the  ;

l 10 CFR Part 50. Annendix H Surveillance Proaram -t and Reaardina Information Provided in WCAP-14484 Beaver Vallev Unit 2 Docket No. 50-412 l 3

l 1. The staff has been using the NRC's Reactor Vessel Integrity Database L (RVID) as its evaluation bases for evaluating vessel integrity -

submittals. With the exception of the fluences for the axial welds ,

fabricated from weld heat 83642, the current version of the RVID lists i the 1/4Tneutron fluences locations as beingfor the belgline gaterials at' thy ID s,urface and 6.207x10 n/cm and 3.869x10' n/cm ,

respectively. The current version of the RVID lists the fluences for the axial welds fabricated from gatn/cm Ng.and 83642 at th9 'ID sgrface and the 1.160x10 i 1/4T locations as being 1.861x10 n/cm ,  :

l respectively. Westinghouse, in WCAP-14484, states (on page 1-2) that l the (revised) fluences for the Beaver falley git 2, vessel at,'the ID, l l

surface, 1/4g and ,3/4T locations are 3.85x10 n/cm,2.24x10 -n/cm , l and 0.551x10 n/cm , respectively.

Since the fluences for the axial welds differ from those reported for the other beltline materials in the vessel, provide the updated f_luence -

values for each beltline material in Beaver Valley Unit 2 vessel at the vessel's inner surface, the 1/4T and 3/4T locations at 32 EFPY. In addition, provide the reference documents where the details regarding these fluences may be found.

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2. Table 4-1 of WCAP-14484 lists the chemistries _for the surveillance materials corresponding to Intermediate Shell Plate B9004-2 and the beltline axial and girth welds. However, no reference documents were provided in WCAP-14484 for the chemistries for these surveillance materials. Provide the reference document for the revised copper and nickel content values for these materials, and provide the basis for the revised best estimate chemistry values.

3. In the Section 5.3.4 to NUREG-1507, Supplement 5, " Safety Evaluation related to the operation of Beaver Valley Nuclear Plant Unit 2," the staff required that the 10 CFR 50.61 (PTS) assessment for " . . . 1 protection against pressurized th rmal shock" be " updated whenever '

changes in core loadings, surveillance measurements or other information {

indicate a significant change in projected values." To date, no revised  ;

10 CFR 50.61 (PTS) assessment has been submitted in regard to integrity l of the BV2 reactor vessel as determined from the information and data provided in WCAP-14484. In accordance with the staff's assessment in NUREG-1507, Supplement 5, either submit a revised PTS assessment based l

' on the data and information provided in WCAP-14484, or provide a basis  ;

why the changes to the reactor vessel integrity data in WCAP-14484 are not significant.

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, , 4. Update the data for the fabrication heat numbers for the Beaver Valley Unit 2 shell plates. The only heat numbers that are currently on record are Heat No. C0544-2 for Intermediate Shell Plate 89004-2, and Heat No.

C1408-1 for Lower Shell Plate B9005-2. In addition provide the most current best estimate chemistries for the BV2 beltline materials, and the most current reference document (s) where these chemistries can be found.

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