ML20129B521

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Forwards RAI Re Proposal to Amend 10CFR50,App H Capsule Withholding Schedule for Plant,Unit 2
ML20129B521
Person / Time
Site: Beaver Valley
Issue date: 10/18/1996
From: Brinkman D
NRC (Affiliation Not Assigned)
To: Cross J
DUQUESNE LIGHT CO.
References
TAC-M95102, NUDOCS 9610230033
Download: ML20129B521 (5)


Text

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          • October 18, 1996 Mr. J. E. CFoss President-Generation Group Duquesne Light Company Post Office Box 4 l Shippingport, PA 15077 i

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING PROPOSAL TO AMEND

10 CFR PART 50, APPENDIX H CAPSULE WITHHOLDING SCHEDULE FOR BEAVER l VALLEY POWER STATION, UNIT N0. 2 (BVPS-2) (TAC NO. M95102)

Dear Mr. Cross:

l By letter dated March 27, 1996, Duquesne Light Company (DLC) submitted WCAP-14484, " Analysis'of Capsule V from the Duquesne Light Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance-Program," for NRC staff review. '

WCAP-14484 was issued to summarize the results of the mechanical property tests conducted on surveillance capsule V, which was withdrawn from the BVPS-2 reactor vessel after 5.98 effective full power years.

As described in Section 7.0 of WCAP-14484 and as required by NRC regulations, i the March 27, 1996, submittal proposed changes to the BVPS-2 surveillance capsule removal schedule.Section III.B.3 of Appendix H to 10 CFR Part 50 -t j

requires that proposed surveillance programs and withdrawal schedules be submitted for NRC staff review. We have performed a preliminary review of the

March 27, 1996, submittal. I!owever, we have determined that additional information is required for us to complete our review. The additional  ;

information that is required is described in our attached RAI. DLC is '

requested to provide its response to this RAI within 60 days of receipt of i this letter for us to complete our review within a timely manner.

Please note that on October 4, 1995, an Atomic Safety and Licensing Board (ASLB) issued a Memorandum and Order (LBP-95-17) which requires that proposed

, changes to surveillance programs for reactor vessel beltline materials (i.e.,

! surveillance programs as defined and required by 10 CFR Part 50, Appendix H)

, must be' submitted as proposed license amendments in accordance with the provisions of 10 CFR 50.90. Such proposed amendments require the submittal of a no significant hazards evaluation in accordance with the provisions of i"' 10 CFR 50.91. Therefore, please supplement the March 27, 1996, submittal to include a proposed license amendment and a no significant hazards evaluation.

This material may be included with DLC's response to the enclosed RAI or may l be submitted separately to expedite our review.

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/ i i- 9610230033 961018

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J. Cross ,

Should you have any questions on this matter, please contact me on (301) 415-1409.

Sincerely,

/S/ .,

Donald S. Brinkman, Senior Project Manager Project Directorate 1-2 Division of Reactor Projects - I/II-Office of Nuclear Reactor Regulation Docket No. 50-412 Enclosurei RAI cc w/ encl: See next page DISTRIBUTION tDocket File- -

PUBLIC PDI-2 Reading .

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DOCUMENT NAME: BV95102.RAI

b J. Cross Should you have any questions on this matter, please contact me on (301) 415-1409.

Sincerely, n . W Donald S. Brinkman, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation ,

Docket No. 50-412

Enclosure:

RAI cc w/ encl: See next page t

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J. E. Cross Beaver Valley Power Station Duquesne Light Company Units 1 & 2 cc:

Jay E. Silberg, Esquire Bureau of Radiation Protection Shaw, Pittman, Potts & Trowbridge Pennsylvania Department of 2300 N Street, NW. Environmental Resources Washington, DC 20037 ATTN: R. Barkanic Post Office Box 2063 R. K. Brosi, Manager Harrisburg, PA 17120 Nuclear Safety Department (BV-A)

Duquesne Light Company Beaver Valley Power Station Mayor of the Borrough of PO Box 4 Shippingport Shv(pingport,PA 15077 Post Office Box 3 Shippingport, PA 15077 Commissioner Roy M. Smith West Virginia Department of Labor Regional Administrator, Region I Building 3, Room 319 U.S. Nuclear Regulatory Commission Capitol Complex 475 Allendale Road Charleston, WVA 25305 King of Prussia, PA 19406 John D. Borrows Resident Inspector Director, Utilities Department U.S. Nuclear Regulatory Commission Public Utilities Commission Post Office Box 298 180 East Broad Street Shippingport, PA 15077 Columbus, OH 43266-0573 Director, Pennsylvania Emergency Duquesne Light Company Management Agency Beaver Valley Power Station Post Office Box 3321 PO Box 4 Harrisburg, PA 17105-3321 Shippingport, PA 15077 ATTN: S. C. Jain, Vice President Ohio EPA-DERR Nuclear Services (BV-A)

ATTN: Zack A. Clayton Post Office Box 1049 Columbus, OH 43266-0149 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803

  • REQUEST FOR ADDITIONAL INFORMATION  :
  • REGARDING THE REQUEST TO AMEND THE '

' 10 CFR PART 50. APPENDIX H SURVEILLANCE PROGRAM  !

AND REGARDING INFORMATION PROVIDED IN WCAP-14484 BEAVER VALLEY POWER STATION. UNIT NO. 2 (BVPS-2)

DOCKET NO. 50-412 j 1. The NRC staff has been using the NRC's Reactor Vessel Integrity Database  !

(RVID) as its evaluation bases for evaluating vessel integrity submittals.

With the exception of the fluences for the axial welds fabricated from J

weld heat 83642, the current ver: ion of the RVID lists the neutron fluences as for the geltlige materials agthe I,0 surface and 1/4T locations being 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 HeatNo.,83642attheIDsurgceagdthe1/4Tlocationsasbeing 1.861x10 2 n/cm and 1.160x10 n/cm , respectively. Westinghouse, in WCAP-14484, states (on page 1-2) that the (revised) fluences for ,the BVPS-i 2vesse}'attgeIDsurface,y4T,gnd3/4Tlocationsare3.85x10' 2.24x10 n/cm , and 0.551x10 n/cm , respectively.

n/cm2 ,

Since the fluences for the axial welds differ from those reported for the 4 other beltline materials in the vessel, provide the updated fluence values for each beltline material in the BVPS-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 J

found.

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 '

a provided in WCAP-14484 for the chemistries for these surveillance i materials. Provide the reference document for the revised copper and i- . nickel content values for these materials, and provide the basis for the i revised best estimate chemistry values.

! 3 In the Section 5.3.4 to NUREG-1507, Supplement 5, " Safety Evaluation  ;

related to the opcration of Beaver Valley Nuclear Plant Unit 2," the NRC '

staff required that the 10 CFR 50.61 (PTS) assessment for " . . .

protection against pressurized thermal 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 of the

.' BVPS-2 reactor vessel as determined from the information and data provided  !

in WCAP-14484. In accordance with the NRC staff's assessment in NUREG-  ;

1507,. Supplement 5, either submit a revised PTS assessment based on the 1 i

data and information provided in WCAP-14484, or provide a basis why the 1 changes to the reactor vessel integrity data in WCAP-14484 are not '

significant.

4  !

4. Update the data for the fabrication heat numbers for the BVPS-2 shell l plates. The only heat numbers that are currently on record are Heat No.

C0544-2 for intermediate shell plate B9004-2, and Heat No. C1408-1 for lower shell plate B9005-2. In addition, provide the most current best estimate chemistries for the BVPS-2 beltline materials, and the most current reference document (s) where these chemistries can be found.

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