ML20094C210

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Forwards Nonproprietary Rev 0 to WCAP-10170, Key Safety Parameter Selection... & Proprietary Rev 1 to WCAP-10170, Key Safety Parameter Selection... (Generic Ltr 82-33). Proprietary Rept Withheld (Ref 10CFR2.790)
ML20094C210
Person / Time
Site: Beaver Valley
Issue date: 08/01/1984
From: Woolever E
DUQUESNE LIGHT CO.
To: Eisenhut D
Office of Nuclear Reactor Regulation
Shared Package
ML19273A408 List:
References
2NRC-4-115, GL-82-33, NUDOCS 8408070414
Download: ML20094C210 (4)


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4 ) 787-5141 Nuclear Construction Division (412) 923-1960 Robinson Plaza Building 2, Suite 210 Telecon (412) 787-2629 Pittsburgh, PA 15205 August I, 1984 United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Mr. Darrell G. Eisenhut, Director Division of Licensing Of fice of Nuclear Reactor Regulation

SUBJECT:

Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Generic Letter 82-33

" Safety Farameter Display System Safety Analysis Report and Implementation Plan Report" Gentlemen:

In accordance with Beaver Valley Power Station Unit 2's (BVPS-2) submittal, Reference (a) in response to Reference (b), BVPS-2 is providing the " Safety Analysis Report and Implementation Plan fo r the Safety Param-eter Diiplay System (SPDS)." This safety analysis is the basis upon which the parameters were selected for display on the SPDS.

The following is the documentstion that de sc ribes the generic Westinghouse Plant Safety Status Display Sytem (PSSD) analysis:

1. WCAP-10170, " Emergency Response Facilities Design and V6V Process," April 29, 1982
2. WCAP- 0170, Appendices A, B, C, and D , E. P. Rahe to W. A.

Paulson, January 2',1983

  • Appendix A, " Introduction"
  • Appendix B , "SPDS Developaent Process"
  • Appendix C, " Key Safety Parameter Selection"
  • Appendix D, " Bibliography"
3. ESD-CR&CD-105, " Design Basis Document -

Plant Safety Status Display, Revision 1," July 18, 1980

4. LS05-84-02-009, " Review of Westinghouse Generic Safety Param-eter Display System," Dennis M. Crutchfield to E. P. Rahe, February 2, 1984 The following areas listed below are discussed in the above documents but are not applicable to the BVPS-2 SPDS. These include the I following: g c,$$. L.9O V 8400070414 840801 96 9 nL PDR ADOCK 05000412 F PDR
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1 . - .,e 1 Unit 0d Stctco Nuclear Regulctcry Commission-

'Mr.;DarrallJGi Eicsnhut,. Directer (Page 2.

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l. . l The terminology _used by: BVPS-2 'is SPDS in lieu of the Westing-house nomenclature.of PSSDi.

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. 2. ' BVPS-2 ;is. implementing the -Westinghouse PSSD software on non--

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' Westinghouse supplied hardware. Hence , any hardware implemen-S --

tation discussions in the ' above reports sare not applicable to M 1the i BVPS-2 ' SPDS design.

3. Since' . BVPS-2 is prograning ~ the ' Westinghouse PSSD sof tware on

.[ 2. , .non-Westinghosue supplied hardware,- the hardware portion of the

'y i functional requirements' discussed in the above documents is not

, applicable _to the BVPS-2 SPDS.

~ 4'. . The BVPS-2 SPDS design ~does not include a Bypass and Inoperable Status Indication -(BISI) ._ Hence, any discussion pertaining to y the BISI system is not. applicable.

-;5. ~Any discussion in ~ the. above l documents pertaining to the Onsite Technical Support Center-(OTSC) is not applicable to the BVPS-2 SPDS design.

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6., - The Verification - and Validation (V&V) ' Process discussed in the

. 'above reports is-not applicable to the'BVPS-2 SPDS design, c8 1 The ~ following is 'BVPS-2's position regarding the above six areas th'ati _ are .'not = applicable 1 to . BVPS-2 in the references that describe the g, < generic-Westinghouse Plant Safety Status analysis:

.i l1. DLC/BVPS-2 is using the term "SPDS" not "PSSD."

. 2. Hardware. description is contained in specification 2BVS-738 and

'in. applicable drawings / listings and documents in the 2BVS-738 file.

- . 3. LHardware implementation of functional requirements is -also s

described in 2BVS-738.

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4. BISI' system is implemented ' in the plant computer system and is

' described in Section 7 of the FSAR.

5. The OTSC.is not a part of the licensing submittal for the SPDS. l

.6. V&V ' results will be available for NRC audit during Post-Imple-mentation Review. .DLC is requesting a post-implement at ion

- review of BVPS-2's SPDS by the NRC three months prior to fuel

load versus the ' scheduled post ' implementation review per Refer-encez(a). This.is'due to the recent six-month delay not ifica-tion for commercial operation for BVPS-2.

- The ', BVPS-2 planti specific list of key safety parameters to be displayed ~ on. the BVPS-2 SPDS is provided in WCAP-10170, Appendix C-S1, t

1

United States Nucisar R*gulatory Commission

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Mr. Dntral1~ G. - Eisenhut, Director -

..Page 3 a

Revision 1, . Key 1 Safety Parmaeter Selection for the Beaver Valley Unit 2 Safety Parameter Display System (SPDS),". July,1984 (Attachment 1).

JAs! WCAP-10170, Appendix C-S1, Revision 1, contains information

. proprietary , to . Westinghouse Electric Corporation, it is support ed by an

af fidavit. signed by Westinghouse', the owner of the information. The affi-davit sets forth 'the basis on which the information may be withheld from public. disclosure by ' the - Commission and addresses with specificity the considerations : listed ' in Paragraph (B)(4) of Section 2.790 of the Commis-iion's' regulations.

'Accordingly, . it is respect fully reques ted that the ,information

-which is propriatary to. Westinghouse be withheld from public disclosure in accordance with 10CFR Section 2.790 of -the Commission's regulations.

" " Correspondence ~ with ' respect to the proprietary aspects of the application

- l for dwithholding or the ' supporting Westinghouse -af fidavit should reference AW-89-9, and - should ' be addressed . to R. A. Wiesemann, Manager, Regulatory

. and cLegislative ' Af fairs , Westinghouse Electric Corporation, P.O. Box 355,

< . .. Pittsburgh, PA 15230.

In summary, . the . referenced documents, with the noted except io ns ,

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document- the safety analysis performed in establishing a basis upon which the parameters were selected - for- display on the BVPS-2 SPDS. In addition t'o / fulfilling: BVPS-2's commitments in ' Reference (a), this submittal closes 1 Outstanding Issue No. Il4 of BVPS-2's Draft SER.

DUQUESNE LIGHT COMPANY n

By *

[

E. W . Woolever

,Vice President SDH/wjs j

+J At tachment

cc
-Mr.G. W. Knighton, Chief (w/a)

'Ms.- M. Ley, ~ Project Manager (w/a) '

~.

iMr. E. A..Licitra,-Project Manager (w/a)

t & LMr. .G. Walton, NRC Resident' Inspector (w/a) 1 *' .NRC-Document'. Control Desk (w/a).

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REFERENCES:

(a) 2NRC-3-017, dated 4/15/83 4 L(b)~ Generic -Letter 82-33, Supplement 1 to NUREG-0737," dated 12/17/82 w ,

SUBSCRIBED AND S 45 DAY OF f 9 m

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a + Not ary Public ANITA ELAINE REITER, NOTARY PUBUC ROBINSON TOWNSHIP, ALLEGHENY COUNTY MY COMMISSION EXPIRES OCTOBER 20,1986 Ll

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? Unithd Stctco Nuc1ccr Rhgulttory Commiosion P -Mre D:rrs11 G. Eicinhut, Director Page 4.

COMMONWEALTH OF PENNSYLVANIA )

) SS:

COUNTY OF ALLEGHENY )

On this /d day of e , /(( , before me, a Notary Public in and for said Commohwealth and County, personally appeared ,

E. J. Woolever, who being duly sworn, deposed and said that (1) he is 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 Submit t al' are true and correct to the best of his knowledge..

Notary Public ANITA ELAINE REITER, NOTARY PUBLIC ROBINSON TOWNSHIP, ALLEGHENY COUNTY MY COMMISSION EXPlRES OCTOBER 20,1986 em Y

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