ML20209C560

Forwards Core Performance Branch Input to Draft SER, Addressing Sections 4.4, Thermal-Hydraulic Design & 4.4.1, Loose Parts Monitoring Sys. Sample Table of Contents for Loose Part Detection Program Description Also Encl

ML20209C560
Person / Time
Site:	Satsop
Issue date:	11/02/1983
From:	Rubenstein L Office of Nuclear Reactor Regulation
To:	Novak T Office of Nuclear Reactor Regulation
References
CON-WNP-1467, TASK-2.F.2, TASK-TM NUDOCS 8311140109
Download: ML20209C560 (8)

Text

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f NOV 2 1983 PE"0RAflDU'1 FOR: T. ft. f!ovak, Assistant Director for Licensing, DL FR0ft: L. S. Rubenstein, Assistant Director for Core and Plant Systens, DSI

SUBJECT:

INPUT FOR DRAFT SER FOR til!P-3 Plant Mane: tlNP-3 Docket f! umber: 50-508 Licensee: Ifashington Public Power Supply Systen Licensing Stage: CL Pes;;onsible Branch: Licensing Branch #3 Project l'anager: A. Vietti (492-4349)

Peview Status: Incomplete (Awaiting Information)

Attached is the Core Perfomance Branch input to the Uf!P-3 Draft SER from the Physics and Themal-Hydraulics Sections. The input from the Fuels Section is scheduled for February 6,1984 as stated in the nenorandun from L. S. Rubenstein to T. fi. flovak dated October 7,1983.

The Reactor Physics Section draft SER for UDP-3 will be identical to that for CESSAR Systen 80 for the following SRP sections:

l _ 4.3 f!uclear Design 15.4.1 CEA Withdrawal from Low Power 15.4.2 CEA liithdrawal from Full Power '

15.4.3 CEA :11soperation Events 15.4.7 Fuel flisloading Event l 15.4.8 CEA CEA Ejection Event The Thernal-Hydraulics Section draft SER for tiMP-3 nill be identical to that for CESSAR Systen 80 for SRP Section 4.4 except for the plant specific itens j related to: (1) the loose parts nonitoring systen (LPf1S); the instrunentation for detection of inadequate cooling requirements as described in iten II.F.2 of NUREG-0737 and; (3) the Core Protection Calculators (CPCs) and statistical combination of uncertainties (SCU).

Contacts: H. Salukjian:CPD:DSI L. Kopp, CPR:DSI X-2942? X-29431 y, -

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'!o response was received on cuestions raised for itens (2) and (3).

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L S.Rubenstein L. S. Rubenstein, Assistant Director for Core and Plant Systems, DSI

Enclosure:

As stated cc: R..Mattson ' ~

D. Eisenhut G. Knf0hton A. Vietti 1

t DISTRIBUTION:

DOCKET FILE: 50-508 CPB:r/f L. RUBENSTEIN .

C. BERLINGER D. FIEN0 L. PHILLIPS H. BALUKJIAN L. K0PP L. na -'

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Washington Public Power Supply Nuclear Project No. 3 (WNP-3) 4.3 The input to the Nuclear Design section is identical to the corresponding-item in the CESSAR FSAR.

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i Washington Public Power Supply Nuclear Project No.3 WNP-3 4.4 Thermal-Hydraulic Design The CESSAR SER discusses all items in this section except for the staff review of: (1) the loose parts monitoring system; (2) the instrumentation for detection of inadequate core cooling requirements as described in item II.F.2 of NUREG-0737 and; (3) the plant-specific infonnation on the Core Protection Calculators -(CPCs) and statistical combination of uncertainties

- (SCU).

4.4.1 Loose Parts Monitoring System The acceptance criter4 for the Loose Parts Monitoring System (LPMS) are set forth in Regulatory Guide 1.133, Revision 1 " Loose-Part Detection Program for the Primary System of Light Water Reactors," May 1981. The applicant has provided a description of the LPMS which will be used at WNP-3. The design will include pairs of pieso-electric accelerometers located at the following natural collection regions: (1) hot leg nozzles adjacent to steam generator inlet plenum; (2) incore -instrument nozzle located on the vessel bottom bean, adjacent to vessel inlet plenum; (3) Control Element Drive Mechanism (CEDM) n.ozzle located on vessel head. The system will provide eight channels with the capability of monitoring and detecting loose parts impacting within 3 ft. of a sensor having a kinetic energy of 0.5 ft-lb and weighing from 0.25 to 30 lb. The system will remain functional following an Operating Basis Earthquake (0BE).

! In response to the staffs request for additional information on the LPMS system, the applicant responded (Letter G. C. Sorensen to G. W. Knighton, September 2, 1983) that the LPMS will be in full compliance with the requirements of Regulatory Guide 1.133. This will include the submission of a training program for plant personnel prior to power operation which will address Technical l

l Specifications, purpose and operation of the LPMS system. The applicant has

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committed to provide Technical Specifications for the LPMS in accordance with i

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2 Position C.5 of Regulatory Guide 1.133 which will specify the limiting conditions for operation and the surveillance requirements. We will also ,

require the applicant to commit to provide prior to power operation a final design report showing comformance with positions C.1 through C.6 of Regulatory Guide 1.133 which contains the following:

1. An evaluation of the LPNS for confomance to Regulatory Guide 1.133.

2. A description of the system hardware, operation and implementation of the

, loose parts detection program after start-up testing. This should also include the baseline data and alam settings.

3. A description and evaluation of diagnostic procedures used to confim the presence of a loose part.

A sample table of contents of the LPMS description is enclosed in. Enclosure 1.

4.4.2 Inadequate Core Cooling Requirements (SRP-4.4-Section II.9)

The applicant has not responded to questions asked relative to inadequate core cooling requirements as specified in Item II.F.2 of NUREG-0737 and this is therefore an open item.

4.4.3 Plant Specific Information (SRP 4.4-Section II.1)

The applicant has not responded to a question asked relative to plant-l specific information on: (1) the application of statistical combination

of uncertainties (SCU) and plant-specific instrument uncertainties; and

(2) the digital core protection calculator (CPC) including the Reactor Power Cutback System (RPCS) for which infomation is needed on the plant-l specific data base constants, software implementation testing and effects

( of SCU on DNBR. This is therefore an open item.

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15.4 Reactivity and Powei Distribution Anomalies The input for the following items are identical to the corresponding items in the CESSAR FSAR:

15.4.1 CEA Withdrawal from Low Power 15.4.2 CEA Withdrawal from Full Power 15.4.3 CEA Misoperation Events 15.4.7 Fuel Misloading. Event 15.4.8 CEA Ejection Event I

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ATTACHMENT I SAMPLE TABLE OF CONTENTS LOOSE PART DETECTION PROGRAM DESCRIPTION I. System Description A. Scale piping diagram showing LPM sensor locations.

B. Sensor specifications (type, manufacturer, sensitivity, tenperature rating,etc.).

C. Sensor mounting details (drawing and procedure).

D. Preamplifier or line driver (type, manufacturer, location and specifications) .

E. Functional description of LPMS.

1. Theory of operation, detection logic, alarm display.

2. Data recorder specifications (No. of channels, length of recording, frequency range, and conditions under which recording is initiated).

II. Operational Procedures A. System Calibration Procedures and Results

1. Initial and subsequent calibrations

2. Functional check, as defined in Regulatory Guide 1.133

3. Channel check, as defined in Regulatory Guide 1.133 B. Plant Operator Instructions for Use of LPMS

1. Procedures for routine operation

2. Procedures to be used following indication of a loose part

a. Method to confirm existence of loose part

b. Method of diagnose a loose part (size and location) f

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5-III. Evaluation for Conformance to Regulatory Guide 1.133 A. Loose Part Detection Program B. Loose Part Detection System e

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