ML20128B375

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Forwards Responses to NRC Questions on RHR Alarms & Mod to SSAR Subsection 9.3.2.3.2 Re Feedwater Corrosion Product Monitor Per Accelerated Advanced BWR Review Schedule
ML20128B375
Person / Time
Site: 05200001
Issue date: 01/28/1993
From: Fox J
GENERAL ELECTRIC CO.
To: Poslusny C
Office of Nuclear Reactor Regulation
References
NUDOCS 9302030027
Download: ML20128B375 (5)


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' [h 9 5125 January 28,1993 Docket No. STN 52-001 Chet Posiusny, Senior Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation

Subject:

Submittal Supporting Accelerated AllWR Review Schedule

Dear Chet:

Enclosed are: (1) responses to NRC questions on RH R alarms, and (2) a modification to SSAR Subsection 93.23.2.

please provide a copies of this transmittal to David Diec and George Georgiev.

Sincerely, b&

. ek Fox Advanced Reactor Programs cc: Jack Duncan (GE)

Norman Fletcher (DOE) g (gpf#

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RESPONSE TO NRC QUESTION ON RilR ALARMS Question 1: What are the locations of the alarms associated with the ABWR RHR system?

Response 1: All the RHR system control room alarms will actuate an RHR Trouble Alarm on the main control board alarm panel. This panel will be directly in front of the operator and one tile will be reserved for the RHR system. Upon receiving an alarm, the operator can then call up the alarm on a CRT to determine the specific cause for the alarm condition.

Question 2: Where is the location of the CUW high temperature alarm?

Response 2: The CUW outlet frora the nonregenerative heat exchanger (NRHX) high temperature alarm is located in the control room. Indication of CUW temperature can be obtained in the control room by calling it up on a CRT display. This display contains temperature indications for inlet to CUW and outlet from both NRHXs.

. ABWR uxsiooxii Slandard Plant wn systera. A vacuum pump is provided to transfer the 9.3.2.3.3 Residual liest Removal, Fuel Pool and

  • s sample from a sample holding rack to a sampling Suppression Pool Sampling ga rack. The sample is mixed uniformly. In the sam-pling rack, the gas is passed through and collected in.

Residual heat removal (RHR)) system process a gas sample holder. After isolation, the gas sample samples are withdrawn for conductivity analysis. Con.

holder is removed and transported to the laboratory ductivity monitoring is performed on a continuous for analysis.

basis. Grab samples are available at the station for purposes of instrument calibration and any special The upper limit for activity levels in liquid and laboratory analysis desired during operation of the gas samples are:

RHR System.

3

/cm Fuel pool water can be continuously monitored for liquid samples 1Cj#C1/cm 3

gas samples 10 conductivity at both inte.t and outlet of the fuel pool filter demineralizers. Grab sample facilities are also Means to reduce radiation exposure are pro-provided at each station.

vided such as, shielding, remotely operated valves, and sample transporting casks. The radiation expo-Suppression pool monitoring is performed while sure to any individual shall not be in excess of 3 and rnonitoring the RHR System.

18 3/4 rem to the whole body or extremities, respec-tively.

93.23.4 Turbine Building Condensate Sampling Acceptauce Criterion II.K.5 of SRP Section 93.2 Required conductivity instrumentation for the requireg the capability of sampling liquids of turbine building condensate system is outlined in 10Ci/cm. The ABWR design Table 93 5 and contained in the reactor building sampling liquids of 1 Ci/cm,has the capability of

. Sampling will be sample station. The sample probe is shown in Figure performed and area radiation measurement will be 93-4.

performed if levels are above safe limits, handling samples will be delayed.-T%pk.miica:Si+y.

93.23.5 Radwaste System Sampling Imbdecays-4e-ebout-1Ci/c a whca i aiva redissaLmL oa safw i The radwaste sptem sampling station is located in

/ /v' SERT the radwaste building. This station maintains 93.2.3.2 Feedwater Corrosion Product Monitor continuous conductivity monitoring of radwaste sam-ples drawn from selected locations in the radwaste The feedwater corrosion product monitoring system. Facilities for obtaining grab samples with system panelis used to monitor feedwater quality, fume hood and exhaust fan are included, measure metallic impurities and measure dissolved oxygen. The panel is located in the turbine building.

93.2.4 Sample Probe Design The sample probe is located downstream of the feedwater heaters.

Condensate and feedwater sample probes are constructed in accordance with Figure 93-4. All The monitoring system consists of feedwater other probes are constructed in accordance with sample conditioning equipment and metalimpurity Figure 93-5.

collection equipment. Valves and coolers reduce the pressure and temperature of the sample. A sample.

93.2.5 Sample Piping Design of the suspended solids is normally collected on in line snembrane filters for 24-hour periods at a Satuple lines are routed to be as short as possi-measured flow rate of 100 ml/ min.

ble, avoiding traps, dead legs and dips upstream of the 9 3-Ic Amendment 22

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The area radiation levels are safe when the sample radioac-tivity is about 1 Ci/cm3 or less.

During abnormal or emergency conditions, The immediate re-sponses of the control room personnel are as discussed in Subsection 18.4.2.11, Safety Parameter Display System, and Subsection 18A.13, Contingency #6, Primary containment Flooding.

Whenever core uncovering is suspected, the reactor vessel is depressurized.

Thus, pressurized reactor water samples are not necessary.

Reactor water gross activity and radioisotopic analyses are obtained to aid in planning an accident recovery strategy.

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