ML20214D732

From kanterella
Jump to navigation Jump to search

Lists Efforts Towards Completion of S&W Confirmation Programs Prior to Fuel Loading,Per LS Rubenstein 870408 Commitment.Efforts Re Equipment Qualification Will Be Addressed in Separate Submittals
ML20214D732
Person / Time
Site: Beaver Valley
Issue date: 05/15/1987
From: Carey J
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
RTR-NUREG-0800, RTR-NUREG-800 2NRC-7-125, TAC-62939, NUDOCS 8705210446
Download: ML20214D732 (6)


Text

- _ _ _ _ _ _ _ _ _ _ _ _

d

'A@

2NRC-7-125 Beaver Valley No. 2 Unit Project Organization Telecopy(4 N. Box 5$s"" May 15, 1987 Shippingport PA 15077 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

Beaver Valley Power Station Unit No. 2 Docket No. 50-412 Confirmation Programs Status

REFERENCES:

(a) NRC Letter dated April 8, 1987, Mr. Lester S. Rubenstein to.

Mr. J. J. Carey [

(b) DLC Letter 2NRC-7-058, dated April,1,1987, Mr. J. J. Carey j to United States Nuclear Regulatory Commission i Gentlemen:

In Reference (a) the NRC requested that Duquesne Light Company (DLC) provide a confirmatory letter, prior to fuel loading, regarding completion of Stone & Webster Engineering Corporation (SWEC) confirmation programs as identi-fled in Beaver Valley Power Station Unit No. 2 (BVPS-2) Project Procedures 2BVM-ll7, " Confirmation Programs for Key Design Documents", and 2BVM-122,

" Engineering Confirmation / Update Program". Section 5.0 of 2BVM-122 lists the major project efforts which constitute the " complete" confirmation program.

The following provides the status of these efforts with the exception of the Equipment Qualification-related efforts which will be addressed in separate submittals, as noted.

1. Licensing Issues
a. IEEE-323, "IEEE Standard for Qualifying Class lE Equipment for Nuclear Power Generating Stations" The status of this effort will be addressed in a separate submittal.

8705210446 870515 PDR P

ADOCK 05000412 PDR

[O!

I

United Stiates Nuclear Regulatory Commission Confirmation Programs' Status

, 'Page 2

b. BVPS-2 SQRT and PV0RT Audit Program The status of this effort will be addressed in a separate submittal.
c. Regulatory Guide 1.75 - Electrical Separation Criteria All engineering and design documents have been finalized to ensure compliance with criteria identified in Project Procedure 2BVM-41 and Installation Specification 2BVS-931.
d. NUREG-0800 (SRP 9.5.1) Fire. Protection for Nuclear Power Plants An amendment to the Fire Protection Safe Shutdown Report is scheduled to be . issued by May 29, 1987.. This amendment will verify that the analysis reflects the plant design as of April 30, 1987,
e. Licensing Comaitments/ Design Criteria Review Revision 3 of 2BVM-163 entitled " Licensing Commitment Design Criteria Correlation" was issued April 13, 1987, bringing this effort up-to-date.
f. Hazards Analysis Program The internally generated missile and seismically induced safety /nonsafety interaction assessments of the " Hazards Analysis Program Audit" (SWEC Engineering Assurance Audit No. 51) have been fully implemented. Open items identified in the Hazards Report have all been addressed and resolution has been provided for all of the interactions identified in the final hazards walk-down which was completed in February 1987. Formal revision of calculations. documenting the confirmation of break locations and rupture / impingement loads will be completed prior to loading fuel.
2. Seismic Category I Stress Reconciliation For Seismic Category I piping, all piping stress analyses including ASME III, Code Class 1 Stress Reports have been reconciled to the as-installed conditions and finalized stress input information in

United States Nuclear Regulatory Commission Confirmation Programs Status Page 3 accordance with 2BVM-156. The stress input information reflects the final plant 1esign and is identified in the Piping Design Specifica-tien, 2BVS-939. The as-installed isometrics, which show actual orientations, locations, and dimensions, were prepared in accordance with FCP-509. These isometrics have been updated to incorporate appropriate reconciliation data and have been certified by the contractor as as-constructed isometrics. All N-5 data packages have been certified by the Authorized Nuclear Inspector.

3. Specification Finalization (All QA Categories)_

Some project specifications will not be formally issued in their final form at the time of fuel loading. However, confirmation of all technical design bases inputs to the specifications will be complete.

4. Drawing Finalization (All 0A Categories)

Drawing finalization (Type I) is essentially in the maintenance mode, that is, Engineering and Design Coordination Reports and Nonconform-ance and Disposition Reports are incorporated, as required, on a continuing basis. These change documents are " stand-alone" documents which receive a thorough engineering review and address-any potential impact to the technical adequacy of a system design prior to being issued. The project procedure for SWEC interface with the DLC Opera-tions Design Change Control Program, 2BVM-186, was issued March 31, 1987.

5. Close Out of " Confirmation Required" in Calculations (All QA Categories)

Project calculation confirmation is presently 99 percent complete.

The remaining one percent will be completed in support of the fuel loading schedule.

6. Maintenance of Calculations / Studies (QA Category I)

Maintenance of QA Category I calculations and studies is completed.

7. New Calculations / Studies This effort, as defined and controlled by Project Procedure 2BVM-117, is complete.

r United States Nuclear Regulatory Commission Confirmation Programs Status Page 4

8. Embedment Plates / Structural Steel Attachment Verification (Local)

This effort is 99 percent complete and will be finalized in support of the fuel loading schedule.

9. Structural Steel Verification Analysis This effort is complete.
10. Maintenance of Project Technical / Licensing Procedures This activity will continue on an "as-needed" basis in support of the project's transition program.
11. Maintenance of the Model This activity has been discontinued in accordance,with the direction of DLC.
12. Vendor Wirir.g Diagrams (Changes After Shipment)

The status of this effort is the same as the status of the " Drawing Finalization" effort discussed in Item 4.

13. Vendor Documents - Environmental Qualification, Seismic, and Operability The status of this effort will be addressed in a separate submittal.
14. Seismic Raceway Oualification The seismic raceway qualification program is complete.

Reference (a) also requested confirmation that the corrective actions in response to Action Items P13 and P15 from the SWEC Engineering Assurance (EA)

Audit No. 52 have been completed. Action Item P13, concerning the SWEC review of the stress data packages for six Westinghouse designed systems to assure the validity of the input data, has been completed. Action Item P15 involved SWEC verification of design inputs to instrument tubing design calculations. All QA Category I calculations reflect associated temperatures and pressures which were current as of January 1, 1987. Changes to these temperatures and pressures identified after January 1, 1987, will be reconciled with the associated QA Category I calculations by fuel load.

i

. +

United States Nuclear Regulatory Commission ,

.i -

Confirmation Programs Status s Page 5 t

t.

Reference (a) also listed Action Item C01 from SWEC EA ' Audit No. 52 among the action items- that were resolved based on a commitment toi submit proposed FSAR changes to the NRC. It was noted that all of -the proposed FSAR changes were submitted in FSAR Amendments 13 and 15 with the exception of those result-ing from Action Item C01. This action item involved clarifications to. Westing-house generated Regulatory Guide positions and Standard Review Plan Conformance

evaluations in the BVPS-2 FSAR. The required changes' were incorporated into FSAR Amendment 16 which was submitted to the NRC in Reference (b). '

DUQUESNE LIGHT COMPANY s>f W. Carey '

Senior Vice President-JD0/ijr NR/JD0/PRG/ STAT AR/NAR i cc: Mr. P. Tam, Project Manager Mr. J. Beall, NRC Sr. Resident Inspector

)'

Mr. L.'Prividy, NRC Resident Inspector Mr. W. T. Russell, NRC Region I Administrator INP0 Records, Center o

3 -United States Nuclear Regulatory Commission

.; .'~

Confirmation Programs Status W ," Page 6 COMMONWEALTH OF PENNSYLVANIA )

) SS:

COUNTY OF BEAVER )

On this / f / / day of 7 / M - ,. / [ M _, before me, a

~

U Notary Public in and for said Commondith and County, personally . appeared J.

J. Carey, who being duly sworn, deposed and said that (1) he is Senior Vice President of Duquesne Light, (2) he is duly authorized to execute and file the foregoing Submittal on behalf of said Company, and (3) the statements set forth in the Submittal are true and correct to the best of his knowledge.

&ktLl6LNotary Al / Public 76MWt s

/

ShutA S. FAIT 9tt,30TaisY rudus ElllPPINE##!00m, SEAVER COUNTY BY COEl918510R DPitFS SCT. 23. !les lasweer.Pasravemenis Aseachtim of 8serlig s

/

i