ML19253B491

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Forwards Response to IE Bulletin 79-12.Four of Six Level Measuring Sys within Each Steam Generator Are Used for Both Safety Action Initiation & post-accident Monitoring. Pressurizer Uses Two Sys for post-accident Purposes Only
ML19253B491
Person / Time
Site: Millstone Dominion icon.png
Issue date: 09/17/1979
From: Counsil W
NORTHEAST UTILITIES
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 7910160285
Download: ML19253B491 (18)


Text

{{#Wiki_filter:. Mro IMHtTHI!AST IFFII.ITIIIS } bin RTFORo CONNECTICUT 06101 ,,s ,.;.7,; 7 - ,ses.egi, L L m: ': ', J';; ' "l ' September 17, 1979 Docket No. 50-336 Mr. Boyce H. Grier, Director Region I Office of Inspection and Enfort:ement U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

Reference:

(1) B. H. Grier letter to W. G. Counsil dated August 13, 1979, transmitting I&E Bulletin No. 79-21. Gentlemen: Millstone Nuc1 Lear Power Station, Unit No. 2 Temperature Effects on Level Transmitters, I&E Bulletin No. 79-21 Reference (1) requested Northeast Nuclear Energy Company (NN"CO) to review the liquid level measuring systems within containment, in particular, to: (1) Determine if signals from these systems are used to initiate safety actions or provide post-accident monitoring information and, if so, provide a description of such systems. (2) Evaluate the effect of post-accident ambient temperatures on the indicated water level as measured by those systems identified in Item (1). (3) Review all safety and control setpoints derived from level signals to verify that the setpoints will initiate the z.ction required by the plant safety analysis throughout the range of ambient temperatures, including accident conditions, encountered by the instrumentation. (4) Review and revise emergency procedures, if necessary, to ensure that operators are instructed on the potential for and magnitude of erroneous level signals. In addition, the NRC Staff requested that this information be submitted within 30 days from the date of Reference (1). NNECO hereby provides the responses to Items (1) through (4) of I&E Bulletin No. 79-21 as Attachment (1). NNECO has determined that present safety and control setpoints derived from level signals need not be revised. The basis for this determination is that the potential errors in level measurement due to I ) rJ 79101602E 5

. reference leg heating will not occur in the adverse direction, such that the safety analysis assumptions will be invalidated, during transients for which credit is taken for low steam generator water level trips in the safety analysis. The basis for this is that during transients for which credit is taken for low steam generator water level, containment temperature will not effect the level measurement prior to the actuation of the reactor trip. NNECO trusts you find this information responsive to your requests, and satis-factorily dispositions the Reference (1) concerns. Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY A Y Wf W. ' d. Counsil' Vice Fresident Attachment ^* ,, / a

DOCKET NO. 50-336 ATTACHMENT (1) MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 ISE BULLETIN No. 79-21 TEMPERATURE EFFECTS ON LEVEL TRANSMITTERS r l ] t w SEPTEMBER, 1979

Item (1) Review the liquid level measuring systems within containment to determine if the signals are used to initiate safety actions or are used to p ride post-accident monitoring information. Provide a description of systmas that are so employed; a description of the type of reference leg shall be included, i.e., open column or sealed reference leg. Res ponse Both steam generator and pressurizer level measurements are derived from liquid level measuring systems within containment. Each steam generator has six (6) level measuring systems associated with it. Signals from four (4) of these systems are utilized for both safety action initiation and post-accident nonitoring. The pressurizer has two (2) level measuring systems which are utilized for post-accident monitoring. The steam generator and pressurizer levels are measured by differential pressure (D/P) cells. These cells produce signals t.at are proportional to the water level. Figure 1 is a schematic illustration of the steam generator level measurement system. The D/P cells are electronic force balance type transmitters which convert the differential pressure signal to a 10 - 50 milliamp current signal where the maximum current output occurs at the maximum water lave ~. Tbc cells measure the pressure difference between a reference and variable leg. The reference leg (high level tap, Figure 1) has a constant level which is maintained by a condensate pot. Both the condensate pot and the reference leg are unlagged and located externally to the stenm generator and pressurizer. In the pot, steam is condensed due to the telatively low (120*F) ambient temperature. The variable leg (low level tap, Figure 1) los a changing level matching changes in the steam generator downcomer or pressurizer water level. For the steam generators, the level transmitter DC output current is applied to the Reactor Protection System bistables as safety actuation signals. The outpur current then goes through isolation devices and is recorded anu displayed on the main control boards. For the pressurizer, the level transmitter DC output current is recorded and displayed on the main control boards. Item (2) On those systems described in Item (1) above, evaluate the effect of post-accident ambient temperatures on the indicated water level to determine any change in indicated level relative to actual water level. This evaluation must ~ ' 3?? I kj e ~

. include other sources of error including the effects of varying fluid pressure and flashing of reference leg to steam on the water level measurements. The resulta of this evaluation should be presented in a tabular form similar to Tables 1 and 2 of Attachment 1.

Response

The effect of post-accident ambient temperatures on the indicated water level relative to the actual water level, for both the steam generator and pressurizer, is shown graphically in Attachment 2. An instrument error of + 3% must be added to these curves. Boiling will not occur in the refere. a leg unless the pressure drops below the saturation pressure for the temperature of the water in the reference leg. Analyses have shown that the highest containment temperature during the worst case accident is less than 280*F. The system pressure would have to decrease to 49.2 psia, the saturation pressure at 280 F, for boiling to occur in the reference leg. Item (3) Review all safety and control setpoints derived from level signals to verify that the setpoints will iaitiate the action required by the plant safety analyses throughout the range of ambient temperatures encountered by the instrumentation, including accident temperatures. Provide a listing of these setpoints. F.esponse Potential errors in level indication, due to reference leg heating, are not involved during transients for which low steam generator level trips are relied upon to provide reactor trips as analyzed in current safety analyses. As shown in Table 1, the low steam generator level trip is relied upon for, a) the excess load transient, b) loss of feedwater flow, and c) transients resulting from the malfunction of one steam generator. NNECO has determined that setpoint adjustments are not required to compensate for reference leg heating because safety analyses only take credit for low steam generator level trip at normal operating temperatures and pressures. ~ '

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. Iten (4), Review and revise, as necessary, emergency procedures to include specific informa-tion obtained from the review and evaluation of Items (1), (2), and (3) to insure that the operators are instructed on the potential for and magnitude of erroneous level signals. All tables, curves, or correction factors that would be applied to post-accident monitors should be readily available to the operator. If revisions to procedures are required, provide a c.ompletion date for the revisions and a completion date for operator training cn the revisions.

Response

All Emergency Operating Procedures will be reviewed and revised, as necessary, to take into account level measurement errors resulting from reference leg heating, process variable change, to include flashing, and instrument error by January 18, 1980. In addition, all operators will have completed training on the revisions by the same date. The information presented in Attachment (2) will be used to revise post-accident monitoring level limits to envelop the most conservative conditions. ~ ' ,r, a w )

M., \\ STEAM SEPARATOR IGH LEVEL CONDENSATE TAP POT xn 1 HIGH LEVEL ggggg ~~~--- ~~----~- ALARM I NWL k ) FIGURE I \\ @\\] LOW LEVEL ALARM STEAM GENERATOR LEVEL MEASUREMENT S.G. -p FEED RING l T u >o 6c STEAM GENER TdR LOW v %l g_ TUBES D

TABLE 1 MILLSTONE II LOW STEAM GENERATOR LEVEL TRIP lRIP STTPOTNT SAFETY ANALYSIS / TECH SPEC) IN UNITS OF % OF TOTAL TAP SPAN EVENT MILLSTONE II 1. Control Element Assembly Withdrawal 2. Boron Dilution 3. Stattup of Inactive Loop 4. Excess Load 31.5/36.0 5. Loss of Load 6. Loss of Feedwater 31.5/36.0 7. Excess Heat Removal due to Feedwater Malfunction 8. RCS Depressurization 9. Loss of Coolant Flow

10. Loss of AC 11.

Full Length CEA Drop

12. Transients Resulting from Malfunction of 31.5/36.0 Steam Generator
13. CEA Ejection
14. Large Steam Line Break
15. Steam Generator Tube Rupture

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16. Seized Rotor

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DOCKET NO. 50-336 ATTACHMENT (2) MILLSTONE NUCLEAR POWER STATION, 'JNIT NO. 2 1&E BULLETIN No. 79-21 PRESSURIZER AND STEAM GENERATOR LEVEL CORRECTION CURVES 'c? i 6 .; } SEPTEMBER, 1979

Pressurizer and Steam Generator level correction curves to account for Reference Leg Heatup and varying fluid pressure effects (post-accident monitoring) The enclosed curves provide the necessary Pressurizer and Steam Generator level corrections to account for Reference Leg Heatup and varying fluid pressure ef f ects for post accident monitoring. The curves only provide density ef fect corrections and do not include transmitter or indicator errors. Ba sis : Pressurizer Le el Calibration Pressure 2250 psia Reference Leg Calibration Temperature 120*F Steam Generator Level Calibration Pressure 900 psia Reference Leg Calibration Temperature 120*F Flashing in Reference Leg not assumed. Instrument error of + 3% must be included. j l 15 7 '~ J :.

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