ML20093J086

Forwards Supplemental Response to Draft SER Open Items 78-81,per 840821 Telcon.W/Submittal,Open Item 78 Becomes Confirmatory Item & Open Item VI Closed Unless Util Notified by NRC

ML20093J086
Person / Time
Site:	Beaver Valley
Issue date:	10/10/1984
From:	Woolever E DUQUESNE LIGHT CO.
To:	Knighton G Office of Nuclear Reactor Regulation
Shared Package
ML19269A632	List: ML20093J086 ML20093J091 ML20093J094 ML20093J096 ML20093J105
References
2NRC-4-163, NUDOCS 8410160490
Download: ML20093J086 (5)

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'Af Duquesne UKJit 2;R7g,i83 Nuclear Construction Division 2) 923-1960 Robinson Plaza, Building 2, Suite 210 ebcon W 2) 787-2629 Pittsburgh, PA 15205 October 10, 1984 United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Mr. George W. Knighton, Chief Licensing Branch 3 Of fice of Nuclear Reactor Regulation

SUBJECT:

Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Supplemental Submittal in Response to Draft SER Open Items 78 and 81 Gentlemen:

In letter 2NRC-4-042, dated April 12, 1984, DLC provided responses to the NRC Chemical Technology Section's Draf t SER Open Items 78 through 81, including the apprcpriate FSAR revisions. In a telephone conference with the Chemical Technology Section reviewer, Mr. J. Wing, on August 21, 1984, Mr. Wing requested that DLC provide additional information in response to Open Items 78 and 81. Specifically, the additional information requested is as follows:

Open Item 78: Describe the modifications thac will be made to the generic Westinghouse Owners Group Post-Accident Core Damage Assess-ment Methodology (dated February 1984) to make it the BVPS-2 plant specific core damage estimate procedure.

Open Item 81: Provide appropriate documentation to verify that the PASS instrumentation is capable of performing its intended func-tion in an accident environment.

The supplemental response to Open Item 78 is provided in Attachment I and the supplemental response to Open Item 81 is provided in Attachment

2. Based on the aforementioned August 21, 1984, telephone conferance with the NRC, it is DLC's understanding that, with this submittal, Open Item 78 becomes a confirmatory item and Open Item 81 is closed, unless further notification indicating otherwise is received from the NRC.

DUQUESNE LIGHT COMPANY O BEFORE ME THIS SUBSPRIBED

/t% DAY OF A AND J)WO L_ , 1984.

• ck s l Notar P bl By .

E. vJ . Woolever ANITA ELAINE REITER, NOTAdY PYJBL}d Vice President ROBINSON TOWNSHIP, ALLEGHENY COUNTY JD0/wjs MY COMMISSION EXPIRF.S OCTO,3ra ;'O,1986 }

Attachments cc: Ms.'M. Ley, Project Manager (w/a) , l

' Mr. E. A. Licitra, Project Manager (w/o) p Mr. G. Walton, NRC Resident Inspector (w/o) j@

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p C- 0N 8410160490 841010 M PDR ADOCK 05000412 E PDR

~ Unitcd Stctaa Nuclocr R!gulctory Conuniscion

- Mr. G;org2 W. Knightsn, Chisf

-Page 2 l COMMONWEALTH OF. PENNSYLVANIA ')

) SS:

COUNTY OF ALLEGHENY )

On this /d day of , /[ , before me, a Notary Public in and for said Commonwealth 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 Submittal are true and correct to the best of his knowledge.

4 Notary Public ANITA ELAINE REITER, NOTARY PUBUC ROBINSON TOWNSHIP, ALLEGHENY COUNTY MY COMMISSION EXPIRES OCTODER 20,1986 i-L

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j. . ATTACHMENT 1 Supplemental Response to Draft SER Open Item 78 (Section 9.3.2.2) - Procedure l to estimate extent of core damage:

I DLC . is planning to make the following modifications to the generic Westinghouse Owners Group Post Accident Core Damage Assessment Methodol-ogy (dated February 1984) to make it the BVPS-2 plant specific core damage estimate procedure:

(1) Delete references to 2-loop, 4-loop, and ice condenser containment plants in Tables 2-2, 2-3, 2-3-1, 2-8, 4-1, and in Figure 3-1.

(2) Ratio source inventories given in Tables 2-2, 2-3, 2-3-1, and 2-8 from the 2900 Mwt standard 3-loop plant to the 2652 Mwt core of BVPS-2.

) (3) Replace Figure 3-2 with a drawing of BVPS-2 core thermocouple locations. l I

(4) Delete references to 2-loop, 4-loop, and ice condenser containment plants in Sections 3.1 and 5.0.

The above modifications are minor and could be done now. The only remaining modification required is to Section 3.3, " Containment Radia-tion Monitors and Core Damage." This section will be finalized when more details are available on the BVPS-2 containment radiation monitor I and its location within containment. It is anticipated that the final version of the BVPS-2 post-accident core damage . estimate procedure will

. be available for submittal.to the NRC by June 1985.

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ATTACHMENT 2

. Supplemental Response to Draft SER Open Item 81 (Section 9.3.2.2) - Perfor-mar.ce of PASS instrumentation and analytica! procedures:

Table 0181-1 (attached) lists the' BVPS-2 PASS instrumentation test reports prepared by NUS Corporation, the associated instruments, and the analysis performed by each of the instruments. The NUS test . reports, which are attached, verify that the BVPS-2 ' PASS instrumentation is capable of performing its intended function in an accident environment.

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' TABLE OI81-1

-j Test Report Instrument Analysis Performed by Instrument- ' I Report No. NSAC/46, dated April Ionics Digichem 3000 Reactor Coolant-Boron -)

'I 1982: An Evaluation of On-Line Boron Analyzers Report No. R-27-4-1-1, dated April. Dionex lon Chromatograph 2010i Reactor Coolant Chloride 1981: Development of Procedures end Analysis Methods for Post-Acci-dent Reactor. Coolant Samples Report No. R-27-10-0-2, dated Octo-ber 1980: Analyses for Dissolved Hydrogen, Dissolved Oxygen, Boron, Chloride, pH, and Conductivity under Normal and Post-Accident Conditions Reactor Coolant Dissolved Hydrogen; Report No. R-27-3-1-1A, dated May Baseline Gas Chromatograph Containment Atmospheric 0xygen 1981: An Evaluation of the Base-line System for Determination of Total Gas Concentration ' During Normal or Post-Accident Conditions Reactor Coolant Dissolved Oxygen Report No. CSD-84-144, revised Orbisphere Dissolved Oxygen Ana-March 26, 1984: Testing of Dis- lyzer 2606 colved Oxygen Analyzers for Post-Accident Analysis Application Reactor Coolant pH Report No. CSD-2-84-13, dated L&N pH Monitor 7075-3 February 7, 1984- Testing of L&N 7075-3 pH Receiver and Electrode Preamplifier and Meridian pH Electrode for PASS Applications

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