ML20044B777

Requests Response to Revised 930126 Request for Addl Info on Valve Reliability within 120 Days of Ltr Receipt

ML20044B777
Person / Time
Site:	05200003
Issue date:	02/09/1993
From:	Kenyon T Office of Nuclear Reactor Regulation
To:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9303040162
Download: ML20044B777 (6)

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NUCLEAR REGULATORY COMMISSION 7, - t WASHINGTON, D. C. 20555 s

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Docket No.52-003 Mr. Nicholas J. Liparulo Nuclear Safety and Regulatory Activities j

Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, Pennsylvania 15230

SUBJECT:

REIISION TO REQUEST FOR ADDITIONAL INFORMATION ON THE AP600 In its letter dated January 26, 1993, the staff requested addition information on valve reliability (Q210.23*). As a result of further analysis, the staff has modified the scope of its request for additional' information (RAI).

Accordingly, enclosed is a revision to Q210.28. The vertical line indicates what portions of the RAI have been modified.

Please respond to this request l

within 120 days of the date of receipt of this letter.

You have requested that portions of the information submitted in the June 1992 application for design certification be exempt from mandatory public disclo-sure. While the staff has not completed its review of your request in accordance with the requirements of 10 CFR 2.790, that portion of the submitted information is being withheld from public disclosure pending the staff's final determination. The staff concludes that this request for additional information does not contain those portions of the information for I

which exemption is sought. However, the staff will withhold this letter from public disclosure for 30 calendar days from the date of this letter to allow ~

Westinghouse the opportunity to verify the staff's conclusions.

If, after that time, you do not request that all or portions of the information in the enclosures be withheld from public disclosure in accordance with 10 CFR 2.790, this letter will be placed in the NRC's Public Document Room.

• The number in parentheses designates the tracking number assigned to the question.

030039 9303040162 930209 goa AOOcx m2Oggg3 y 9

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Mr. Nicholas J. Liparulo February 9, 1993 This request for additional information affects nine or fewer respondents, and therefore is not subject to Office of Management and Bugdet review under P.L.96-511.

If you have any questions regarding this matter, you can contact me at (301) 504-1120.

Sincerely, j

(Original signed by) f Thomas J. Kenyon, Project Manager Standardization Project Directorate Associate Director for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation

Enclosure:

l As stated cc w/ enclosure:

l See next page i

t DISTRIBUTION-

• Central File PDST R/F TMurley/FMiraglia DCrutchfield

• PDR WTravers RBorchardt TKenyon i

RHasselberg GGrant, EDO JMoore, 15B18 MSiemien, 15B18 l

PShea DFischer, 7E23 TSullivan, 7E23 ACRS (11) w/o encl.

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LA:PDST:ADAR PM:PDSf,:fpAR PM:P,D p DAR SC:PDy:ADAR Rfl7sherg RBorhrdt NAME: PSQy TKeny sg DATE:

02/C')93 02/f/93 02/1/93 02/f/93 f

OFFICIAL RECORD COPY:

DOCUMENT NAME: LETTERV.III

• To be held for 30 days l

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Mr. Nicholas J. Liparulo Westinghouse Electric Corporation Docket No.52-003 AP600 cc:

Mr. B. A. McIntyre Advanced Plant Safety & Licensing Westinghouse Electric Corporation Energy Systems Business Unit Box 355 Pittsburgh, Pennsylvania 15230 Mr. John C. Butler Advanced Plant Safety & Licensing Westinghouse Electric Corporation Energy Systems Business Unit Box 355 Pittsburgh, Pennsylvania Mr. M. D. Beaumont Nuclear and Advanced Technology Division Westinghouse Electric Corporation One Montrose Metro 11921 Rockville Pike Suite 450 Rockville, Maryland 20852 Mr. Sterling Franks U. S. Department of Energy NE-42 Washington, D.C.

20585 Mr. S. M. Modro EG&G Idaho Inc.

j Post Office Box 1625 Idaho Falls, Idaho 83415 Mr. Steve Goldberg j

Budget Examiner 725 17th Street, N.W.

Room 8002 Washington, D.C.

20503 l

Mr. Frank Ross U.S. Department of Energy NE-42 Washington, D.C.

2058d

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ENCLOSURE REVISION TO THE JANUARY 26, 1993 REQUEST FOR ADDITIONAL INFORMATION ON THE WESTINGHOUSE AP600 DESIGN t

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VALVES j

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210.28 The staff, with the assistance of the Oak Ridge National Laboratory I

(ORNL), has been assessing critical valves for the AP600 design.

The l

l staff has identified critical valves and their critical failure modes, and is attempting to develop estimates of the initial l

reliability of these types of valves.

Table A is a list of the critical valves that the staff has identified.

However, in order for i

the staff to complete its assessment, detailed technical information i

on many of these valves is required.

The staff recognizes that some I

of this detailed information may not be available at the design i

l certification stage of the review.

However, pertinent assumptions that were used in determining valve design and reliability may be j

beneficial to the staff in helping it assess component operability and reliability. These assumptions should be provided where l

technical information is unavailable. Accordingly, provide the following information for the valves listed in Table, as appropriate:

Information Requested on All Valves a.

What is the process fluid composition (water, steam, raw water, borated water, etc.) assumed for these valves for normal and accident conditions?

b.

What is the maximum temperature of the process fluid assumed for i

these valves?

c.

Provide the range of flow, pressure, and differential pressure assumed for these valves for both normal and accident conditions.

d.

Provide any available design information for these valves, e.g.,

f the manuf acturer and model number of the valve and actuator.

e.

Are there any design changes in the design of these valves as they are used in conventional nuclear generating stations?

f.

List the scope and frequency of planned periodic testing and j

preventive maintenance.

g.

Describe the planned qualification testing and its potential ef fect on replacement intervals.

h.

Is a method of bonnet over-pressurization protection provided for normally closed gate valves?

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' Information Requested on Air-Operated Valves The following information requests pertain to Valve Nos. PXS V108A/B, i

V014ASB, V015A&B, PXS V002A&B, V003A&B, and RC V004A/B/C/D.

i. What elastomeric compounds will be used for the various 0-rings, seats, diaphragms, etc.?

I

j. What lubricants will be used in the valve and solenoids? Provide the manufacturer and trade name, if available.

k.

Will the plant meet ISA Standard 57.3, " Quality Standard for l

Instrument Air," if instrument air is used with these valves?

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Information Requested on Motor-0perated Valves j

1.

What is the anticipated duty cycle of the valve actuator of the following valves: Valve Nos. PXS Vll7A/B, V118A/B, RC l

V001A/B/C/D, V002A/B/C/D, and V003A/B/C/D?

Information Requested on Check Valves l

The following information requests pertain to Valve Nos. PXS V016A/B, t

V017A/B, V006A/B, V007A/B, V119A/B, V120A/B, V122A/B, V123A/B,

.l V124A/B, and V125A/B.

m.

What is the minimum opening pressure differential?

l n.

What kind of position indication system is used?

f Information Requested on Explosive Valves The following information requests pertain to Valve No. PXS V301A/B.

j o.

What is the manuf acturer and model number of the valve and i

actuator?

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What is the predicted reliability based on operating experience and testing to date?

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I Table A Critical Valves For the AP600 (See Q210.28)

Valve No. and Description PSID No.

PXS V002A/B (CMT pressure line) NC globe A0V PXS M6 001 I

PXS V003A/B (CMT pressure line) NC globe A0V PXS M6 001 PXS V006A/B (CMT pressure line) N0 check valve PXS M6 001 j

PXS V007A/B (CMT pressure line) N0 check valve PXS M6 001 PXS V014A/B (CMT outlet) NC globe A0V PXS M6 001 i

PXS V015A/B (CMT outlet) NC globe A0V PXS M6 001-PXS V016A/B (CMT outlet) N0 tilt disc check valve PXS M6 001 l

PXS V017A/B (CMT outlet) N0 tilt disc check valve PXS M6 001 PXS V108A/B (passive RHR HX) NC globe A0V PXS M6 002 PXS V117A/B (IRWST to sump screen) NC gate MOV PXS M6 002 PXS V118A/B (IRWST to sump screen) NC gate MOV PXS M6 002 l

PXS V119A/B (IRWST to sump screen) NC check valve PXS M6 002 I

I PXS V120A/B (IRWST to sump screen) NC check valve PXS M6 002 PXS V122A/B (IRWST injection) check valve PXS M6 002 i

PXS V123A/B (IRWST injection) check valve PXS M6 002 PXS V124A/B (IRWST injection) check valve PXS M6 002 PXS V125A/B (IRWST injection) check valve PXS M6 002 PXS V301A/B (pH adj. tank injection line) NC squib valve PXS M6 004 RC V001A/B/C/D (ADPs) globe DC MOVs RCS M6 002 i

RC V002A/B/C/D (ADPs) gate DC MOVs RCS M6 002 RC V003A/B/C/D (ADPs) gate DC MOVs RCS M6 002 RC V004A/B/C/D (ADPs) NC 12" gate ADV RCS M6 001

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