Text

SPDS Displays
	ML20211N421
Person / Time
Site:	Crystal River
Issue date:	12/31/1984
From:	; BABCOCK & WILCOX CO.
To:	;
Shared Package
ML20211N379	List: 3F0686-23, Forwards Responses to NRC 851217 & 860502 Requests for Addl Info Re Isolation Devices & Parameter Selection & Displays, Per Suppl 1 to NUREG-0737.SPDS Functional Description & Display Document Also Encl; ML20211N395; ML20211N421;
References
	51-1121942-02, 51-1121942-2, NUDOCS 8607030092
	Download: ML20211N421 (73)
	v • d • e

ts ENCLOSURE 2 Attachment 2 i

1 51-1121942-02 ;

December 1984 CRYSTAL RIVER UNIT 3 SAFETY PARAMETER DISPLAY SYSTEM (SPDS)

DISPLAYS FOR I~-

FLORIDA POWER CORPORATIO" BY I

The Babcock & Wilcox Company 1

_. Utility power Generation Division P. O. Box 1260 1 Lynchburg, Virginia 24505 B&W 51-1121942-02 CR3 SPDS DISPLAYS 8607030092 860630 PDR ADOCK 05000302 p PDR ,

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8sNP 20440 2 (10 83)

BABCCCK & WILCOX - UPGO ENGINEERINC- INFORMATION RECORO Saf ety Re latec:

DOCUNENT IDENTFIER 51 -1121942-02 YES O ND @

CRYSTAL RIVER UNIT 3 SAFETY PARAMETER DISPLAY SYSTEM (SPDS) DISPLAYS l TITLE PREPARED BY DATE I 7 l REVIEVED BY DATE /2!7!

REMARKS:

This revision pmvides the following changes to 51-112194-01:

1. Section 4.2,1st paragraph on Pg. 4 changed Cycle 5 to Cycle 6.

2. Figu're 4.2 on Pg. 4 provides the Cycle 6 RPS setpoints used in the Power / Imbalance display.

h 3. Sections 4.2.1 Figure 4.2.

.8 on Pgs. 4-6 and 4 provide revised values for the new

4. Section 5.2.4 on Pg. 5 added "(no instrument errors included)" to the paragraph.

.5, Section 5.2.4.2 on Pg. 5 corrected P(A) to 180 psig from 150 psig.

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6. Section 5.2.4.3 on Pg. 5 corrected typo PSIB to -PSIG._ _

7. Section 5.2.4.4 on Pg. 5 corrected typo from 2/2 to 1/1.

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8. Section 7.4 on Pg. 7-5'- corrected typo for exponent .on A 5 to ID b rom 10~b

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TABLE OF CONTENTS t

PAGE 1.0

SUMMARY

1-1

2.0 INTRODUCTION

2-1 3.0 GENERAL INFORMATION ABOUT THE SPDS DISPLAYS 3-1 3.1 Input Signals Required For The SPDS Displays 3-1 3.1.1 Variables Required For The Graphic Displays 3-2 3.1.2 Variables Required For the Alphanumeric Display 3-2 3.1.3 Variables Required For the SPDS Alerts 3-2 4.0 NORMAL DISPLAYS -

4-1 4.1 Reactor Protection Trip Envelope 4-1 4.1.1 Reactor Protection P-T Envelope Data Points And Algorithm -

4-1

@ 4.1.1.1 Upper Line 4-1 4.1.1.2 Lower Line 4-1 4.1.1.3 Upper Portion Of The Right Boundary 4-3 4.1.1.4 lower Portion Of The Right Boundary 4-3 4.1.~1.5 Normal Jperations Box 4-3 4.1.1.6 Upper Line Of The to?sl Operations Box 4 4.1.1.7 Lower Line Of The Normal Operations Box A-4 4.1.1.8 Right Line Of The Normal Operations Box 4-4 4.1.1.9 .Left Line Of The Normal Operations Box 4-4 4.2 Power / Imbalance Display 4-4 4.2.1 Left Vertical Side 4-6 l

4.2.2 Right Vertical Side 4-6 1 4.2.3 Four Pump Operating Limit Upper Line 4-6 4.2.4 Four Pump Operating Limit Left Sloping Line 4-6 4.2.5 Four Pump Operating Limit Right Sloping Line 4-6 ,

4.2.6 Three Pump Operating Limit Upper Line 4-7 I 4.2.7 Tnree Pump Operating Limit Left Sloping Line 4-7

) 4.2.8 Three Pump Operating Limit Right Sloping Line 4-7 i

TABLE OF CONTENTS (Cont'd) f PAGE 5.0 ATOG P-T DISPLAY 5-1 5.1 ATOG P-T Permanent Curves 5-1 5.1.1 Axes For The ATOG P-T 5-1 5.1.2 Post-Trip Window 5-1 5.1.2.1 Post-Trip Window Upper Line 5-3 5.1.2.2 Post-Trip Window Lower Line 5-3 5.1.2.3 Post-Trip Window Left Line 5-3 5.1.2.4 Post-Trip Window Right Line 5-4 5.1.2.5 Normal Hot Leg Water Temperature Box 5-4 5.1.2.5.1 T-Hot Normal Box Upper Line 5-4 5.1.2.5.2 T-Hot Normal Box Lower Line 5-4 5.1.2.5.3 T-Hot Normal Box Right Line 5-4 5.1.2.5.4 T-Hot Normal Box Left Line 5-5 5.1.2.6 Post-Trip Hot Leg Water Temperature Box 5-5 g 5.1.2.6.1 T-Hot Post-Trip Box Upper Line 5-5 5.1.2.6.2 T-Hot ~ Post-Trip Box Lower Line 5-5 5.1.2.6.3 T-Hot Post-Trip Box Right Line 5-5 5.1.2.6.4 7-Hot Post-Trip Box Lef t Line 5-5 ii.i.3 Saturation Curve

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_ 3-5

~ - -- 5.1.3.1 - Saturatioh Curve Tata Points and Algorithm

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3-5_ ,

, 3 .~1.4 Subcooled tiargin Curve 5-7 I i

5.1.4.1 20*F Subcooled Margin Data Points )

and Algorithin ~- --

5.1.4.2 50*F Subcooled Margin Data Points 5-7

--l and Algorithm 5-8 5.1.5 Saturation Temperature of Secondary System 5-9 5.1.5.1 Saturation Temperature Of The Secondary l System Algorithm 5-10 5.1.6 Cooldown Curve 5-10 1

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5.1.6.1 Cooldown Curve Point A to Point B 5-11 5.1,6.2 Cooldown Curve Point B to Point C 5-11

) 5.1.6.3 Cooldown Curve Point C to Point D 5-12 ii

TABLE OF CONTENTS (Cont'd)

PAGE 5.2 ATOG P-T Selectable Curves 5-12 5.2.1 Heatup Curve 5-12 5.2.1.1 Heatup Curve Point A to Point B 5-14 5.2.1.2 Heatup Curve Point B to Point C 5-14 5.2.1.3 Heatup Curve Point C to Point D 5-15 5.2.1.4 Heatup Curve Point D to Point E 5-15 5.2.1.5 Heatup Curve Point E to Point F 5-15 5.2.2 Thermal Shock Curve 5-16 5.2.2.1 Thermal Shock Curve Point A to Point B 5-16 5.2.2.2 Thermal Shock Curve Point B to Point C 5-18

'5.2.2.3 Thermal Shock Curve Point C to Point D 5-18

. 5.2.2.4 Thermal Shock Curve Point D to Point E 5-19 5.2.3 Fuel Compression Limits 5-19 5.2.3.1 Fuel Compression Limits For Natural

, h Circulation Point A to Point B 5-19 5.2.3.2 Fuel Compression Limits For Natural Circulation Point B to Point C 5-21

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5.2.3.3 Fuel Compression Limits For Natural

._- . Circulation Point D to Point E 5-21 h _ . _ _ '-

5.2.3.4 Fuel Compression Limits For Natural ;

Circulation Point E to Point F 5-21 5.2.4 RCP-NPSil Limits 5-12 5.2.4.1 RCP-NPSH Limits _For 2/2 Combination Point A to Point B 5-21 '

5.2,4.2 RCP-NPSH Limits For 2/2 Combination Point B to Point C 5-23 I 5.2.4.3 RCP-NPSH Limits For 1/1 Combination Point D to Point E 5-23 5.2.4.4 RCP-NPSH Limits For 1/1 Combination Point E to Point F 5-23

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i TABLE OF CONTENTS (Cont'd)

PAGE 6.0 LOW RANGE PRESSURE-TEMPERATURE DISPLAY 6-1 6.1 Low Range P-T Display Permanent Curves 6-1 6.1.1 Axes For The Low Range P-T Display -

6-1 6.1.2 Saturation Curve 6-1 6.1.3 Subcooled Margin Curve 6-3 6.1.4 Cooldown Curve -

6-3 6.1.5 Maximum Pressure For The Decay Heat Removal System 6-3 6.2 Selectable Curves For The Low Range P-T Display 6-3 6.2.1 Heatup Curve For The Low Range P-T Display 6-4 6.2.2 Thermal Shock Curve For The Low Range P-T Display 6-4 6.2.3 Fuel Compression Limits 6-4 6.2.4 RCP-NPSH Limits 6-4 7.0 INADEQUATE CORE COOLING DISPLAY 7-1 gg, " 7.1 Axes For The Inadequate Core Cooling Display 7-1 d 7.2 Saturation Curve 7-1 7.3 1400*F T-Clad Line 7-1 7.4 1800*F T-Clad Line 7-4

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8.0 ALPHANUMERIC DISPLAY

2. 8-1' 9.0 ALERTS 9-1 9.1 Reactivity "REACTIV" Alert _ _ _ -_ _

9-1 9.2 " RADIATION" Alert 5 93--

9.3 Reactor Building Pressure "RB PRES" Alert 9-5 9.4 Engineered Safeguards Actuation "ES ACT" Alert 9-7 9.5 Emergency Feedwater Actuation "EFW- ACT" Alert 9-9 9.6 Reactor Trip "RPS ACT" Alert 9-11

10.0 REFERENCES

10-1

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FIGURES

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i 4.1 Reactor Protection Trip Envelope 4-2 4.2 Power / Imbalance Display 4-5 5.1 ATOG P-T With Permanent Curves 5-2 5.2 ATOG P-T With Heatup Curve Overlay 5-13 5.3 ATOG P-T With Thermal Shock Overlay 5-17 5.4 ATOG P-T With Fuel Compression Overlay 5-20 5.5 ATOG P-T With RCP-NPSH Overlay 5-22 6.1 Low Range P-T With Permanent Curves 6-2 6.2 Low Range P-T With Heatup Curve Overlay 6-5 6.3 Low Range P-T With Thermal Shock Overlay ,

6-6 6.4 Low Range P-T With Fuel Compression Overlay 6-7 6.5 Low Range P-T With RCP-NPSH Overlay 6-8

.O 7.1 Inadequate Core Cooling Display 7-2 8.3 Alphanumeric Display, Pages 1 Through 4 8-2,3,4,5 4

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1.0

SUMMARY

This document presents the data points, algorithms, alerts, and description of the CR-3 Safety Parameter Display System (SPDS) displays. The CR-3 SPDS is based on

. B&W's design which complements the operator's procedures, training and background.

The information used to generate the displays included Crystal River Unit Three's Abnormal Transient Operating Guidelines (ATOG), Technical Specifications, Limits and Precautions and Plant Setpoints, as shown in Revision 40 to Operating Procedure 103, The Plant Curve Book.

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1-1

2.0 INTRODUCTION

The purpose of and requirements for a Safety Parameter Display System are defined in Supplement 1 to NUREG-0737, " Requirements for Emergency Response Capability" (Generic Letter No. 82-33). The purpose of this document is to describe the design of the SPDS displays for Crystal River Unit 3 and to provide the necessary information to the hardware / software supplier of the SPDS.

2.1 SPDS Reouirements The SPDS should provide a concise display of critical plant variables to aid control room operators in determining the safety status of the plant. It will be available during all modes of normal operation as well as abnormal and emergency conditions to aid the control room operators. A minimum set of plant variables will be provided to the control room operators such that they can assess the safety status of the plant with respect to:

1. Reactivity control

@ 2. Reactor core cooling and heat removal from the primary system

3. Reactor coolant system integrity

4. Radioactivity control

5. Containment integrity

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' ~ ~ ~ The CR-7 3PDS' displays are designed to provide sufficient information to the con-

- trol room operators for them to assess the safety status of the plant with respect to these five areas. These displays are designed to complement the Abnormal Transient 0perating Guidelines ( ATOG), normal and~ emergency operating procedur_es_

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and operator training.

2-1

3.0 GENERAL INFORMATION ABOUT THE SPDS DISPLAYS ,

The SPDS design for CR-3 provides for.six basic displays. They are the following: i 1

Reactor Protection Trio Envelope Display 1

- Power / Imbalance Display l

- ATOG P-T Display l

- Low-Range P-T Display

- Inadequate Core Cooling Display

- Alphanumeric Display These displays will be discussed in detail in Sections 4.0 through 8.0. The design also provides for alert signals which can appear on any of the above displays. The alerts are discussed in Section 9.0. These displays and alerts 3

allow the control room operator to assess the five safety functions identified in

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Section 2.1 above.

The SPDS includes two Cathode Ray Tubes (CRTs) which will present the various SPDS displays. Select / assign switches will allow the control room operator to select (J any of the displays for presentation and to overlay the selectable curves on the permanent curves. They will also allow the control room operator to assign certain replacement parameters to a display or select either of the RCS loops for*

display on either CRT. _

During normal operation, the Reactor Protection Trip Envelope and Power / Imbalance Displays would be expected to be in use. The SPDS will automatically shift on receipt of a reactor trip signal to -the ATOG P-T displays for each RCS loop with

, the history trace actuated for the T-hot vs. RCS pressure and T-cold vs. RCS pressure operating points. The control room operator can manually switch to any of the displays at any time.

3.1 Incut Siunals Recuired for The SPDS Disolays Input signals for the variables required for the SPDS displays have teen provided by Florida Power Corp. (FPC) to Br;W Special Products (SPIS). That input signal ~

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3-1

list will not be duplicated in this report. However, the variables required for each type of display are provided below.

3.1.1 Variables Reouired For The Graphic Disolays The variables necessary to implement the five graphic displays for the SPDS described in this document are as follows:

1. WR T-hot A, primary signal and redundant spare

2. WR T-hot B, primary signal and redundant spare

3. WR T-cold A, primar~ y signal and redundant spare

4. WR T-cold B, primary signal and redundant spare

5.

RCS Pressure A, primary signal and redundant. spare

6. WR RCS Pressure B, primary signal and redundant spare

7. LR RCS Pressure A, primary signal and redundant spare -

8. LR RCS Pressure B, primary signal and redundant spare i 9. Incore Thermocouples Temperature, average of five (5) highest input signals

10. NI Power, highest of four (4) input signals

@ 11. Imbalance, average of four (4) input signals

12. OTSG Steam Pressure A -

.13. OTSE Steam Pressure B

.14. RCS Flow A C

.15. .RCS Flow'B -

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16. 0TSG Startup Level A

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17. STSGStartude'velB

18. OTSG Ooerate Level A

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19. OTSG Operate Level B __

11.2 Variables Reouired For The Alohanumeric Disalay The variables necessary for the alphanumeric display are provided in the discussion of that display in Section 8.0 1

3.1.3 Variables Reouired For the SPDS Alerts l I

_I The variables required for each of the SPDS alerts are provided in the presentation of the alert's logic in Section 9.0.

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4.0 NORMAL OISPLAYS

~ Two displays have been designed to be used during normal power operations. These displays are the Reactor Protection Trip Envelope (Refer to Figure 4.1) and the Power / Imbalance Display (Refer to Figure 4.2). These displays should be shown simultaneously, one on each of the two CRTs.

4.1 Reactor Protection Trio Enveloce (Refer to Fioure 4.1)

The Reactor Protection Trip Envelope P-T display provides the RPS trip setpoints from the CR-3 Technical Specifications and a normal operations box. This display will be available on one of two CRT's during normal operations. This display will

} provide the control room operator with indication of normal and off-normal conditions and allow him to anticipate a reactor trip.

On this display reactor coolant temperature will be displayed on the horizontal axis with a range from 520*F-to 620*F while reactor coolant pressure will be -

displayed on vertical axis with a range from 1700 to 2500 psig. These ranges

@ provide sufficient resolution of reactor coolant conditions within normal conditiens and make conditions challenging protection system setpoints readily discernable. The wide range temperature and pressure variables to be displayed are described in Section 3.1.l. Numerical indication of % RCS flow and % Power i will be displayed. Bar charts and numerical values -for OTSG Startup level and ;

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Operate Level will also be displayed. ;

4.1.1 Reactor Protection P-T Envelooe Data Points and Alcorithm 4.1.1.1 Upoer Line The upper line of the reactor protection P-T envelope is based upon the high RCS pressure trip. This is a straight line:

P = 2300 PSIG from the points (520,2300) to (618,2300).

4.1.1.2 Lower Line I

j The lower line of the reactor protection P-T envelope is based upon the low RCS pressure trip. This is a straight line:

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P = 1800 PSIG from the points (520,1800) to (590.0,1800).

4.1.1.3 Upoer Portion of the Rioht Boundary The right boundary line is a two part line with each portion of the line based on a different reactor trip. The upper portion of the right boundary is based upon the high hot leg temperature reactor trip. This is a straight line:

T = 618*F between the points (618,2124.8) and (618,2300).

4.1.1.4 Lower Portion of the Rioht Boundary The lower portion of the right boundary is based upon the variable pressure-tem-

- perature reactor trip. The equation for this straight line is:

P = (11.59 T - 5037.8) psig from the point (590.0,1800) to (618,2124.8).

(]) 4.1.1.5 Normal Doerations Box I Inside of the reactor protection P-T envelope is a rectangular box that will encompass symbols representing T-hot vs. pressure and T-cold vs. pressure. This box is designed to allow for _some variability and instrument error at normal 7~ operating temperatures and pressures. These parameters vary with reactor power

'livel; therefore, being outside the box is not indicative of anproaching a reactor trip setpoint. However, a trend toward a trip setpoint can be established and

-corrective action taken. __

4.1.1.6 Doner Line of the Normal Doerations Box The upper line of the normal operations box is above the normal operating pressure and close to -the spray valve setpoint. This line is:

P = 2200 PSIG from (555,2200) to (606,2200),

3 4-3

4.1.1.7 Lower Line of the Normal Doerations Box The lower line of the. normal operations box is below the lowest setpoint for the pressurizer heaters. This line is:

P = 2100 PSIG from (555,2100) to (606,2100).

4.1.1.8 Rioht Side of Normal Operations Box The right side of the normal operations box is based upon the maximum normal operating loop outlet water temperature. This line is:

T = 606*F from (606,2100) to (606,2200).

4.1.1.9 Left Side of Normal Operations Box The left side of the normal operations box is based upon the minimum normal operating loop inlet water temperature. This line is:

h T = 555'F from (555,2100) to (555,2200).

4.2 Power / Imbalance Disolay (Refer to Fioure 4.2)

Certain accidents involving high reactivity rates occur _too rapidly to permit effective protection actions based upon either reactor coolant temperature or pressure. There are thermal limits associated with these accidents _ expressed in

~ terms of linear power peaking (kw/f t) on Departure from Nucleate Boiling' Ratio (DNBR) limits, but are physically monitored in terms of neutron flux, both absolute level (% rated -thermal power) and distribution (imbalance = reactor flux in top half of core minus that in lower half, also expressed as % rated tnermal power). These limits are modified to reflect the number of operating reactor coolant pumps (RCPs). These limits'are fuel cycle dependent and reflect the Cycle 6 Technical Specification limits.

, The power / imbalance display is similar to the traditional trip setpoint limit figure with reactor power imbalanc.e ranging from -60% to +60% left to right along the horizontal axis and reactor rower as percent scaled thermal power, increasing 4.4

Figure 4.2 POWER /IMBALANCEDISPLAY I

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from 0 to 110% bottom to top along the vertical axis. Only the limits for 4 and 3 RCP's, the allowable RCP combinations at power are provided. N1 Power and Imbalance variables to be displayed are described in Section 3.1.1. Numerical indication of % RCS flow and % Power will be displayed.

4.2.1 Left Vertical Side The left side of the trip envelope is the vertical line:

I= -34.7%

from (-34.7,0) to (-34.7,00.3).

4.2.2 ~Richt Vertical Side The right side of the trip envelope is the vertical line:

I= 34.7%

from (34.7,0) to (34.7,75.86).

4.2.3 Four Pumo Doeratina Limit Upoer Line b

The four pump limit is bound by the line:

P = 107.0%

from (-18.0,107.0) to (18.0,107.0).

4.2.4 Four Puro Doeratino Limit ieft Slopina Line -- ~

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The four pump limit is bound to the left by the line:

P= (1. 00 I + 125. 0 ) .

from (-34.7,90.3 ) to (-18.0,107.0) .

4.2.5 Four Pumo Operatina Limit Richt Sloaina Side The four pumo limit is bound to the richt by the line:

P= (-1.86467 I + 140.56407)%

from (18.0,107.0) to (34.7,75.86). .

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4.2.6 Three Pumo Operatino Limit Upoer Line i l i

t l -The three pump limit is bound by this line:

P = 79.92%

from (-18.0,79.92) to (18.0,79.92).

4.2.7 Three Pumo Doeratina Limit Left Slopino Line The three pump limit is bound to the left by the line:

P = (1.00 I + 97.92)%

from (-34.7,63.22 ) to (-18.0,79.92 ) .

4.2.8 Three Pumo Doeratina Limit Right Sloping Line The three pump limit is bound to the right by the line: 1 P = (-1.86467 I + 113.48407)%

from (18.0,79.92) to (34.7,48,78).

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5.0 ATOG P-T DISPLAY (REFER TO FIGURE 5.1)

The ATOG displays' consist of permanent and selectable curves shown on a pressure

, versus temperature format. The curves are consistent with CR-3's Technical l

Specifications and operating procedures. Those curves which will be seen on any ATOG display are referred to as permanent curves.

The wide range temperature and pressure variables to be displayed are provided in Section 3.1.1. Numerical indication of % RCS flow and % Power will be displayed.

Bar charts and numsrical values for OTSG Startup Level and Operate Level will also 3

be displayed, i

1 5.1 ATOG P-T Permanent Curves (Refer to Fioure 5.1) t

] The. permanent curves for the ATOG P-T will include the following items: The axes j for the display, the post-trip window, the normal and post-trip T-hot target i boxes, the saturation curve, the subcooled margin curve, and the cooldown curve.

Each of these items are discussed in detail below.

5.1.1 Axes for the ATOG P-T

The horizontal axis represents temperature in -degrees -fahrenheit with a range from t

, 200 to 700*F. This temperature may be T-hot from loop A or B,7-cold from knop A . _ .

j or B, or an average of the five highest incore thermocouples. One CRT can be used

. to show either loops information but not at the same . time. Saturation secondary steam temperature can also be a variable using the horizontal axis. The vertical axis represents pressure in PSIG. This pressure may be RC pressure or OTSG steam pressure with a range from 0 to 2500 PSIG.

5.1.2 Post-Trio Window ,

The " post-trip" operating window has been drawn to show where the reactor coolant I pressure and temperature should end up after reactor and turbine trip. The size of the window has been determined from a review of several actual reactor trips (plus computer simulations) with and without equipment failures. It is pcssible 5-1

1 Fi gure 5. I ATOG P-T WITH PERNAMENT CURVES 8

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to end slightly outside the window and still have a stable plant; however, this window gives a good "first" basis for determining if the plant is operating 4 . .normally" after a trip. If, the reactor coolant system pressure and temperature move outside the window after trip and do not return within about 2 to 3 minutes then an abnormal transient is occurring and operator corrective actions are needed. A review of other plant parameters not on the display may be required "to determine the exact cause. Note that when using the ATOG philosophy for controll-ing abnormal transients, determining the exact cause(s) of the transient is not required; corrective actions are taken to control basic plant symptoms which can be observed on the ATOG P-T display. After the corrective actions have been taken the plant will be stabilized and the stable point can be inside or outside of the window.

4 l

5.1.2.1 Post-Trio Window Upoer Line The upper line of the' post trip window is less than the PORY setpoint (2450 PSIG)

and exceeds the high RCS pressure trip setpoint (2300. PSIG). The upper line does not exceed the RCS code safety setpoint (2500 PSIG). The upper line is

@ P = 2400 PSIG from (542,2400) to (618,2400).

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5.1.2.2 Post-Trio Window Lower Line I

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1 I The lower line is equal to the low RCS pressure ESAS setpoint (1500 PSIG) plus 200

PSIG. The 200 PSIG is added to allow for instrument error and to ensure the operators anticipate ESAS conditions. This line is below the low RC pressure trip (1800 PSIG). jThe lower line is

l P = 1700 PSIG from (542,1700) to (564,1700).

5.1.2.3 Post-Trio Window Left Line l The left boundary line is based on the saturation temperature of the steam follow-ing a reactor trip. An abnormal transient would be indicated if steam pressure falls below 960 PSIG after trip. The steam temperature corresponding to this

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pressure is 542*F. The lef t line of the post-trip window is:

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T = 542*F from (542,2400) to (542,1700).

5.1.2.4 Post-Trio Window Rioht Line The right boundary of the post-trip window is a two-part line. The upper part is a straight vertical line equal to the hot leg temperature trip setpoint of 618'F.

It extends from (618,2400) to (618,2016).

The lower part is equal to the subcooled margin line as described in Section 5.1.4. This line extends from (618,1970) to (594.5,1700).

5.1.2.5 Normal Hot Leo Water Temperature Box The right rectangle inside the post-trip window represents the normal temperature range for T-hot at 100% FP. This box is included as a " target" for the operator

! but not as an absolute requirement.

(h 5.1.2.5.1 T-hot Normal Box Upper Line

( .

'The upperline of the box is a straigtit line as follows:

P = 2200 PSIG

_ _ rom (605,2200)ito (610,2200).. ~

5.1.2.5.2 T-hot Normal Box Lower Line I

)

The lower line is a straight line as follows: ~ ~ ~

P = 2100 PSIG

i from (606,2100) to (610,2100).

5.1.2. 5,3 T-hot Normal Box Richt Line Tne right line is a vertical straight line as follows:

T = 610*F

) from (610,2100) to (610,2200).

1 5-4

^

l 5.1.2.5.4 T-hot Normal Box Left Line i The left line is a vertical straight line as follows:

T = 606*F from the point (606,2100) to (606,2200).

5.1.2.6 Post-Trio Hot Leo Water Temperature Box The left rectangle inside the post-trip window is the post-trip T-hot box. It is expected that T-hot will stabilize within this range of temperature and pressure following a reactor trip.

5.1.2.6.1 T-hot Post-Trio Box Upper Line P

I 4

The upper line of the post-trip T-hot box is a straight line as follows:

.- P = 2200 PSIG from the point (544,2200) to (548,2200).

(h 5.1.2.6.2 T-hot Post-Trio Box Lower Line The lower line of the T-hot post-trip box is a straiS ht line as follows:

P = 2100 PSIG !

i

1 rom (544,2100) to (548,2100). l

, 5.1.2.6.3 T-hot Post-Trio Box Richt Line The right line of the T-hot post-trip box is a vertical straight line as follows:

T = 548*F from (548,2100) to (548,2200) .

1 i

! 5.1.2.6.4 T-hot Post-Trio Box Left Line i The left line of the T-hot post-trip box is a vertical straight line as follows:

T = 544*F from (544,2100) to (544,2200). '

5-5

4 5.1.3 Saturation Curve (Refer to Fioure 5.1)

- -The. saturation curve is a permanent > curve. The data points are taken from the ASME Steam Tables 1967 and changed to PSIG.

5.1.3.1 Saturation Curve Data Points and Alaorithm The data points for this smooth curve are listed below:

T = Temperature (*F) P = RC Pressure (PSIG)

T(1) = 190.0 Pil) = -5.4 T(2) = 200.0 P(2) = -3.2 T(3) = 212.0 P(3) = 0.0 T(4) = 220.0 P(4) = 2.5 T(5) = 230.0 P(5) = 6.1 T(6) = 240.0 P(6) = 10.3

. T(7) = 250.0 P(7) = 15.1 4

, T(8) = 270.0 P(8) = 27.2 j Q T(9) = 290.0 P(9) = 42.9 T(10) = 310.0 P(10) = 63.0

.! T(11) = 330.0

~

P(ll) = 88.4 7(12) = 350.0 P(12) = 119.9

, T(13) = 370.0 -P(13.) -= 158.6

- - ~

T(14) -= 390.0 P(14) = 205.6

T(15) = 410.0 P(15)~= 262.0 T(16) = 430.~0 P(16) = 329.0~

T(17) = 450.0 P(17) = 407.9 . _ .

T(18) = 470.0 P(18) = 500.0 T(19) = 490.0 P(19) = 606.8 T(20) = 510'.0 P(20) = 729.8 T(21) = 530.0 P(21) = 870.5 T(22) = 550.0 P(22) = 1030.7 T(23) = 570.0 -

P(23) = 1212.2 T(24) = 590.0 P(24) = 1416.8 T(25) = 610.0 P(25) = 1646.9 5-6

T(26) = 630.0 P(?0) = 1904.8 T(27) = 650.0 P(f1) = 2193.7 T(28) = 670.0 P(22) = 2517.5 T(29) = 690.0 P(23) = 2881.0 T(30) = 700.0 P(24) = 3079.6 The fourth-degree polynomial which represents the above data points is the l following:

P=A 1 + A2 T + A3 (T)2 + A4 (T)3 + A5(T)4 where: A1 = +1.22886419060 x 102 A2 = -1.67623958166 x 100 A3 = +7.79645939744 x 10-3 A4 = -1.81567540280 x 10-5 A5 = +2.72079610906 2 10-8 The end-point for the ATOG display for the saturation curve is:

(669,2500). .

5.1.4 Subcooled Marcin Curve (Refer to Fioure 5.1)

The Subcooled Margin (SCM) curve is a permanent line on the ATOG P-T display.

3 u _.This~Iurve js a tiree-part curve. Above 1500 psig, the subcooled margin will te a _

fixed, 20*F- mar. gin. Below 1500 psig, the subcooled margin will be a fixed, 50*F margin. At 1500 psig, a straignt horizontal line will connect the 20*F and 50*F margin portions of the curve. The 20oF and 500F margin values were supplied by FPC.

5.1.4.1 20*F Subcooled Marcin Curve Data Points and Alcorithm The dzta points for this smooth curve are as follows:

T = Temperature (*F)

P = RC Pressure (PSIG)

T(1) = 577.5 P(l) = 1500.0 T(2) = 590.0 P(2) = 1646.9 3 T(3) = 610.0 P(3) = 1904.8 T(4) = 630.0 P(4) = 2193.7 5-7

T(5) = 650.0 P(5) = 2517.5 T(6) = 670.0 P(6) = 2881.0 T(7) = 680.0 P(7) = 3079.6 The fourth-degree polynomial which represents the above data points is the following:

P=A 1 + A2 (T) + A3(T)2 + A4(T)3 + A5(T)4 where: A1 = +2.6779943522 x 104 A2 = -1.8385853034 x 102 A3 = +4.7459182429 x 10-1 A4 = -5.4873327532 x 10-4 A5 = +2.5448070350 x 10-7 The end-point for the display is (649,2500).

5.1.4.2 50*F Subcooled Marain Curve Data Points and Alaorithm ._

The data points for this smooth curve are as follows:

T = Temperature (*F)

P = RC Pressure (PSIG)

T(l) = 70.0 P(l) = -13.0

T(2) = 100.0 P(2) = -11.0 _

T(3) = 140.0 _ P(3) =-

--L4 - . _

, T(4) = 150.0 P(4) = -3.2 ._.--

T(5) = 162.0 P(5) = 0.0 T(6) = 170.0 P(6) = 2.5 ,

T(7) = 180.0 P(7) = 6.1 T(8) = 190.0 P(8) = 10.3 T(9) = 200.0 P(9)

15.1 T(10) = 220.0 P(10) = 27.2 T(11) = 240.0 .P(ll) = 42.9 T(12) = 260.0 P(12) = G3.0 ,

T(13) = 280.0 P(13) = 88.4 I T(14) = 300.0 P(.14) = 119.9

-) .

5-8 l

T(15) = 320.0 P(15) = 158.6 T(16) = 340.0 P(16) = 205.6 T(17) = 360.0 P(17) = 262.0 T(18) = 380.0 P(18) = 329.0 T(19) = 400.0 P(19) = 407.9 T(20) = 420.0 P(20) = 500.0 T(21) = 440.0 P(21) = 606.8 T(22) = 460.0 P(22) = 729.8 T(23) = 480.0 P(23) = 870.5 T(24) = 500.0 P(24) = 1030.7 T(25) = 520.0 P(25) = 1212.2 T(26) = 540.0 P(26) = 1416.8 T(27) = 547.5 P(27) = 1500

__ The fourth degree polynominal which represents the above data points is the followin.g:

P=A 1 + A2 (T) + A3(T)2 + A4(T)3 + A5(T)4 h where: A1 = +5.21779673906 x 101 A2 = -9.59235554484 x 10-1

,. Aa = 4.19394427211 x 10-3

~

A4 = -1.21548708151 x 10-5 1; .

A5 = +2.68306139890 x 10-8 A straight horizontal line from (5!7.5,1500) to (577.5,1500) connects this curve to the 20*F curve.

5.1.5 Saturation Temperature of Secondary System (Fioure 5.1)

A vertical line will appear on the ATOG P-T that reoresents the saturation temper-ature of the secondary system (Tsat secondary) based on secondary steam pressure for the loop. The relative movement of Tsat secondary to the RCS cold leg conditions is the means by which the key ATOG symptom of primary-to-secondary heat transfer is evaluated.

)

5-9

5.1.5.1 Saturation Temoerature of the Secondary System Alaorithm

. A line extending from the top to the bottom of the vertical-axis that is movable along the horizontal temperature axis is used to represent saturation steam temperature. The value for this line is determined by inserting steam pressure into the algorithm and calculating the saturation temperature. The fourth-degree algorithm which defines the vertical saturation temperature line is the following:

Tc A_t + A95 + A3 (S)2 + A4(S)3 + Ag(S)4 B 1+B5+B(S)2+B(S)3+ByS)4 2 3 4 where: A1 = +2.142030 x 102 A2 = +7.872187 x 100 A3 = +2.430427 x 10-2 A 4 = -1.045323 x 10-5 A5 = -7.346407 x 10-9 B1 = +1.000000 x 100

@ B2 = +2.294812 x 10-2

_ B3 = +3.798913 x 10-5 B4 = -2.833713 x 10-8 ,

B5 = -6.895084 x 10-12 T = Temperature ( OF) S= Secondary Steam Pressure (PSIG) -

5.1.6 Cooldown Curve (Refer to Fiaures 5-1 and 6.1)

The cooldown Nil Ductility Temperature (NDT) limits on limiting RCS components for the first 8.0 effective full power years are shown on the cooldown curve. The curve may be modified after that time. Tne following nestription covers the entire range of the curve. The ATOG 'P-T disolay will start at Point B1 and '

include the entire upper range while the low range P-T display will only cover from Point A up to 850 PSIG (at 252,850) This curve includes margins of 25 psig and 10*F to account for possible instrumentation errors.

4 I

5-10 l

l

f 5.1.6.1 Cooldown Curve Point A to Point B l i

The cooldown curve from Points A to B is the straight line P = 1.1653543 T + 243.425197 psig from (70,325) to (197,473).

5.1.6.2 Cooldown Curve Point B to Point C The cooldown curve from Points 8 to C is a smooth curve through the following data points:

T = Temperature (*F) P = RC Pressure (PSIG)

T(B) = 197 P(B) = 473 T(B1) = 200 P(Bl ) = 484.5 !

T(1) = 203 P(1) = 497 T(2) = 208 P(2) = 523 .

T(3) = 214 P(3) = 552 T(4) = 219 P(4) = 577

+

T(5) = 225 P(5) = 618 T(6) = 230 .

P(6) = 655 T(7) = 236 P(7) = 696 I T(B) = 241 P(8) = 742 T(9) = 247 P(9) = 793

~'

_- - -- T(10) = 252 P(10) = B49 T(11) =.258 P(11) = 906 T(12) = 263 P(12) = 954 '

T(13) = 269._-. _

P(13) =_1005

~

T(14) = 274 --

P(14) = 1062 T(15) = 280 P(15) = 1123

~ - '

7(16) = 290 P(16) = 1553

~

T(17) = 301 P(17) = 1413 T(18) = 312 P(18) = 1601 T(19) = 323 P(19) = 1821 T(C) = 326 P(C) = 1840 1

5-11 l

l I

l The fourth-degree polynomial which represents the above data points is:

i P=A 1 + A2 T + A3 (T)2 + A4 (T)3 + A5(T)4 where: A1 = +6.5021121229 x 103

, A2 = -9.7476248845 x 101 A3 = +5.6111613007 x 10-1 A4 = -1.4102170007 x 10-3

A5 = +1.4467381429 x 10-6

, 5.1.6.3 Cooldown Curve Point C to Point D l The cooldown curve from Point-C to Point D is the straioht line L P = 8.0392157 T - 780.78431 psig from (325.1840) to (377,2250).

f 5.2 ATOG P-T Selectable Curves i

The ATOG P-T has a number of control room operator selectable curves associated

)

with it to enhance its usefulness during normal and abnormal conditions. The number of curves selected is left to the control room operator's discretion. ,Any combination of the selectable curves can be overlayed on the permanent curves.

1 4_ CR-3 specific information has been used to generate the algorithms. Some of the

~

l selectable -curves will be subject to changi for varying reasons (i.e. core

!, depletion, neutron embrittlement, fuel loading changes, etc.). Those curves

- susceptible to change will be identified.

[ 5.2.1 Heatuo Curve (Refer to Fiaures 5-2 and 6.2)

Tne heatup NDT limit -is based upon limitations that are applicable for the first 8.0 effective full power years. Beyond that time, this curve may need to be !

changed. The entire curve is described below. Figure 5.2 provides points above 200*F while Figure 6.2 only extends up to 850 psig. This curve includes margins '

of 25 psig and 10*F to account for possible instrumentation errors.

4 i

5-12

r Fi gu re 5.2 ATOG P-T W!TH HEATUP CURVE OVERLAY l

l o 8

m o a

a. =

o #

8

~

i -

g w

6 I I3 -

6 3

A.

=o

= E o -

g p

, o

-3 eo . . .

_E o

R w ,

a

<o o

g I f I I h

@ 8 8 8 8 m g # o #

5 !s d - sa nssaJd n io

5.2.1.1 Heatuo Curve Point A to Point B

?

The heatup curve from Point A to Point B is a straight line with the following equation:

P = 300 PSIG from (70,300) to (157,300)

B 5.2.1.2 Heatuo Curve Point B to Point C The heatup curve from Point B to Point d is a smooth curve with the following data points:

T = Temperature (*F) P = Pressure (PSIG)

T(B) = 157 P(B) = 300

, T(1) = 168 P(l) = 311 T(2) = 179 P(2) = 327 T(3) = 190 P(3) = 350

[h T(4) = 201 P(4) = 380 T(5) = 212 P(5) = 417 T(6) = 223 P(6) = 463 i

T(7) = 234 P(7) = 518 T(C) = 235 ,

, _ P(C) = 328 ---

, The fourth-degree polynomial which represents the above data points is the following:

P =.A 1 + A2 T + A3 (T)2 + A4 (T)3 + A5(T)4 __

A1 = 4.1411381684 x 102

~

where:

A2 = +1.4976594313 x 101 A3 = -1.3399696599 x 10-1 A4 = +4.8730512817 x 10-4 A5 = -5.2692810237 x 10-7

)

S 5-14

t 5.2.1.3 HeatuD Curve Point C to Point D

'The-heatup curve from Point C to Point D is a straight line with the following equation:

P = 528 PSIG from (236,528) to (260,528).

5.2.1.4 Heatuo Curve Point D to Point E The heatup curve from Point D to Point E is a straight line with the following equation:

P = 33.667 T - 8225.3 PSIG from (260,528) to (266,730).

5.2.1.5 Heatup Curve Point E to Point F The heatup curve from Point E to Point F is a smooth curve containing the

. following data. points:

rq._

T = Temperature (*F) P = RC Pressure (PSIG)

T(E) = 266 P(E) = 730 T(1) = 267 P(1) = 752 T(2) = ~278 P(2) = B23 _2.

~

T(3) = 289 P(3) = 906 T(4) = 300 P(4) = 1002 T(5) = 311 P(5) = 1116 l

___ T(6) = 322 P(6) = 1248 T(7) = 333 P(7) = 1403 T(8) = 344 P(8) = 1584 T(9) = 355 P(9) = 1797 i l

T(10) = 366 P(10) = 1970 T(F) = 377 P(F) = 2251 The fourth-degree polynomial which represents the above data points is the following:

_ P=A 1 + A2 (T) + A3(T)2 + A4(T)3 + A5(T)4 5-15

- - .,-,-,u

~

4 where: A1 = -2.5879521327 x'10 A2 = +3.2825168932 x 102 l A3 = -1.5234527481 x 100 A4 = +3.0904452931 x 10-3 A5 = -2.2126772540 x 10-6 ,s

)

5.2.2 Thermal Shock Curve (Refer to Fioures 5.3 and 6.3) 1 The Pressurized Thermal Shock Limit shall be known as the thermal shock curve.

This curve is to be used during a small break LOCA with HPI actuated and No forced circulation. Under these conditions pressure and temperature are to be kept below and to the right of this line. The lower end of the thermal shock curve includes the Decay Heat Removal System Pressure limits.

, Figure 4.3 only includes the curve above 200*F, while Figure 5.3 only include the curve up to 850 psig.

, i 5.2.2.1 Thermal Shock Curve Point A to Point B The thermal shock curve from Point A to Point B is based upon the maximum pressure

-for the Decay Heat Removal System (DHRS) as shown on turve 5.3 of CR-3 Operating 1

Procedure 103. Data points for this portion of the curve are the following: ,

t _

~

' ; T = Temperature (*F) ~

'7 =~RC Pressure (PSIG) i

, T(A) = 70 - - -

P(A) = 276 --

T(1) = 90 P(1) = 276.2

'T(2) = 120 ~~

~

P(2) =-277.5 --

T(3) = 140

-~

P(3) = 278

~~

T(4) = 160 P(4) = 27S T(5) ~= 180 P(5) = 282 T(6) = 200 P(6) = 283 T(7) = 220 P(7) = 285 T(8) = 240 P(8) = 287.5 T(9) = 260 P(9) = 288.5 l T(10) = 280 P(10) = 291.5

) l 5-16 1

1

i Fi gu re 5.3 ATOG P-T WITH THERMAL SHOCK OVERLAY '

i i

8

- 8 o u o :

n.

O 3 E/3 o

o N

N -

e m o i -

o g

w

' O 4

O ' 1 b

t 2

%O 2 oW Ji -

~

3.

I. -

, 5

=

s 5

, e o, -$

l 1

i i i i 8 m

) g o 8

o S o 8

=

u m - -

5 !sd - aanssaJd

--,-e,,-r-,--.,.-.-,-.-,,,,----,-------,--,------_,.,--------,_w,,., ,,c.--+,-..,-,-,.~--,nn--- ~

T(B) = 290 P(B) = 292.5 r

The equation representing the above points is:

P=A 1 + A2 T + A3 (T)2 + A4(T)3 l where: A1 = +2.7924159210 x 102 A2 = -9.4396164073 x 10-2 ~

A3 = +7.5809585301 x 10-4 A4 = -9.5238005350 x 10-7 5.2.2.2 Thermal Shock Curve Point B to Point C The thermal shock curve from Point B to Point C is a horizontal extension of the maximtn decay heat system pressure to the Tsat - 100*F curve. l

_ i l

r The equation is:

P = 292.5 PSIG from (290,292.5) to (319.2,292.5)

.5.2.2.3 Thermal Shock Curve Point C to Point D j -

The themal shock r.urve from Point y to Point D is a smooth Jcurve_ defined in

~00-103, curve 2.3B and represents the saturation line minus 100*E. It contains the following data points: __

T = Temperature (*F) P = RC Pressure (PSIG) - _ _

T(C) = 319.2 P(C) = 292.5 -

T(1) = 338 P(1) = 360 T(2) = 358 P(2) -= 443 T(3) = 378 P(3) = 540 )

T(4) = 398 P(4) = 653 i T(5) = 418 P(5) = 782 T(6) = 438 P(6) = 930 l T(7) = 458 P(7) = 1098

. T(8) = 478 P(8) = 1289 l

-l 5-18 i

4 T(9) = 498 P(9) = 1505 e

T(0) = 500 P(D) = 1528 a

The fourth-degree polynomial that represents the above data points is:

P=A 1 + A2 T + A3 (T)2 + A4 (T)3 + A5(T)4 where: A1 = +1.74210520742 x 102 A2 = -2.19301675205 x 100 A3 = +1.02995858058 x 10-2 A4 = -1.78919264653 x 10-5 A5 = +3.37897267870 x 10-8 1

5.2.2.4 Thermal Shock Curve Point D to Point E i' The thermal shock curve from Point D to Point E is a vertical straight line:

T = 500*F from (500,1528) to (500,2500).

[) 5.2.3 Fuel Comoression Limits (Refer to Fioures 5.4 and 6.4)

During plant cooldowns, the RCS conditions should be controlled in such a manner t

to insure that the nuclear fuel pins are maintained in compression. Two curves

- - - - are necessary to provide the RCS limits for fuel compression. One is to be used

~

4 i [during natural circulation cooldowns and the other during -forced circulation cool-downs. Each of these curves will extend only to the 50*F subcooled margin curve.

The information for generating these two curves is from OP-103. Allowances of 10'F and 50 psig have been made for instrument errors.

. 5.2.3.1 Fuel Compression Limits Tor Matural Circulation Point A to Point B

~

This segment of the fuel compression limits for natural circulation conditions is a straight vertical line at:

T = 375*F from (375,312.5) to (375,1380).

_)

1 5-19 l

l O

i i

I 2500 -

y i

?

g =

11 0 e 2000 -

(Fuel Compression for OP

Natural Circulallon) -

100 g o

o I, O h

x

) , 1500 -

3 F y l,a ,

j i .

. as MIvelCompression _ 0 a

j

~

g Iot Forced g 1000 Cltculation) 2 SU i g - -

250 g w

E O

500 D b

r-I A l 0 i I I I l 1

l 200 300 180 0 500 600 700 l

Temperaturn *F 4

1 1

5.2.3.2 Fuel Comoression Limits For Natural Circulation Point B to Point C This segment of the fuel compression limits for natural circulation conditions is a straight line defined by the following equation:

P = 1.60(T) + 780 PSIG from (375,1380) to (535,1636)'.

5.2.3.3 Fuel Comoression Limits For Forced Circulation Point D to Point E This segment of the fuel compression limits for forced circulation conditions is a straight vertical line at:

T = 405"F from (405,439) to (405,1380).

5.2.3.4 Fuel Comoression Limits For Forced Circulation Point E to Point F i

This segment of the fuel compression limits for forced circulation conditions is a straight line oefined by the following equation:

P = 1.5556(T) + 750 PSIG

-from (405,1380) to (535,1582).

12.4_ RCP--NPSH Limits (Refer to Figures 5.5 and 6.5)

Duriog plant cooldowns,2the operator needs to know the limits for the Reactor Coolant Pumps based on NPSH. There are two curves provided; one is for the 2/2 ;

combination and the other_is A r the 1/1 combination. The information for

~

_ generating these curves is from OP-103, Curve 2.5.. (no instrument errors included). !

1

- ~ ~

4

5. 2. 4.1 RCP-NP.SH Limits for 2/2 Combination Point A to Point B This portion of the RCP-NPSH limits for 2/2 combination is a straignt horizontal line at:

P = 180 PSIG f rom (70,180) to (200,180). On Figure 5.5, tnis portion of the curve will only g extend down to (200,180) rather than (70,180).

5-21

Figure 5.5 ATOG P-T WITH RCP-NPSH OVERLAY I

! 1 e o

_O ,

3 o N O '

g D !

o a l

_g l l

l l

1 N

- x

_ 8 w

O-

=

6 m

9 ElL w "

o E S*

1 & L ~

O tJ ..

g g . -.

~

N

- N

4. L.

O O ae= ee-S N g g O

=

= - g f

\

o i I I &&J < islt '

o N

o g o :

N 8 w 8 $

o i N - - <

) 6 ! sd 'aanssaJd I

I 5-22 I

I I

l . - _ . _ - ~ _ _ . _-. _ . . _ _ _ , . . . , . _ . , , _

. 5.2.4.2 RCP-NPSH Limits for 2/2 Combination Point B to Point C This' portion of the curve'is based on the following data points:

T = Temperature (*F)

P = RC Pressure (PSIG)

T(A) = 200 P(A) = 180 T(1) = 250 P(1) = 194 T(2) = 300 P(2) = 227 T(3) .= 350 P(3) = 289 T(4) = 400 P(4) = 396 T(5) = 450 P(5) = 565 The third-cegree polynomial wnich represents' the above data points is the following:

P=A 1 + A2 (T) + A3(T)2 + A4(T)3 where: A1 = -1.2013419913 x 102 A2 = +3.5511111111 x 100 (k A3 = -1.4915584416 x 10-2 A4 = +2.3131313131 x 10-5 The end point of this curve is (405,408), Point C.

_ 5.2.4.3 RCP-NPSH Limits for 1/1 Comnination Point D to Point E

_ This portion of the RCP - NPSH limits for_lll comDination is a straight horizontal

~

Tine at: --

P = 315 PSIG from (70,315) to (200,315)- .

On Figure 5.5, this portion of the ' curve will only extend down to (200,315) rather tnan (70,315).

5.2.4.4 RCP-NPSH Limits for 1/1 Combination Point E to Point F This portion of the curve is based on the following data points:

5-23

T = Temperature ('F) P = RC Pressure (PSIG) ,

i T(A) = 200 P(A) = 315 4

T(1) = 25 0 P(1) = 327' l T(2) = 300 P(2) = 356 T(3) = 350 P(3) = 415

T(4) = 400 P(4) = 517 T(5) = 450 P(5) = 680 The third-degree polynomial which represents the above data points is the following:

P=A 1 + A2 (T) + A3(T)2 + A4(T)3 where: A1 = +2.5947402597 x 101 A2 = +3.4991428571 x 100

__A3 = -1.4885800866 x 10-2

, A4 = +2.2993939394 x 10-5 4

The end point of this curve is (405,529), Point F.

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6.0 LOW-RANGE PRESSURE-TEMPERATURE DISPLAY (Refer to Figure 6.1)

-Because of the limitations of CRT~ screen width, visibility, and distortion, the range of the AT0G P-T display is not preferred for all modes of operation. To enhance the SPDS's usefulness to the operator during low pressure and temperature operations, a low-range P-T display is included.

The wide range temperature and wide and low range pressure variables to be displayed are provided in Section 3.1.1. Numerical indication of % RCS flow and %

Power will be displayed. Bar charts and numerical values for OTSG Startup Level and Operate Level will also be displayed.

6.1 Low Range P-T Disolay' Permanent Curves (Refer to Figure 6.1) i The low range P-T display consists of pennanent and selectable curves. The permanent curves include the following: the axes, saturation curve, a subcooled margin curve, cooldown curve, and maximum pressure for the DHRS. The algorithms for these curves are referenced in this section and different end points are

] given. ~

- _- 6.1.1 Axes for the Low Range P-T Disolay 4

- -. _ The. axes for the low range P-T display will . provide the operator with 2n expanded

~

, viewI nf the lower left corner of thh ATOG P-T display. ;

\

'The horizontal axis will cover a range of 400*F from 50 to 450'F. The vertical

~

axis will cover a range of 850 PSIG from 0 to 850 PIIG.~ The wide' range pressure variables will be used down to 435 psig at which time .the system will automati-cally switch over to the low range pressure variables. This occurs when the loop low range transmitter is less than or equal to 435 psig.

1 l

5.'1.2 Saturation Curve '

1 j The saturation curve will be permanently shown on the low range P-T display. The data points are the same as snown in Section 5.1.3 except the start point for this I display will be (212, 0) and the end point for this is (450, 407.9).

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The algorithm for the curve is the same as in Section 5.1.3 and is not repeated.

6.1.3 Subcooled Margin Curve (Refer to Figure 6.1)

On the Low-Range P-T Display, the subcooled margin curve will be 50'F subcooled margin curve as discussed in Section 5.1.4.2. The end point for the curve will be (450,665).

The algorithm for thus curve is the same as shown in Section 5.1.4.2.

6.1.4 Cooldown Curve The first region of the cooldown curve will be the same as given in Section 5.1.6.

The last region of the cooldown curve will have a new end point for the low range P-T cooldown curve because of the limited range of the display. The end point will be (252,850).

The algorithm for this curve is shown in Section 5.1.6.

6.1.5 Maximum Pressure for the Decay Heat Removal System (DHRS)

The maximum pressure the DHRS wil1 be displayed as part of the thennal shock curve

: _and-wiIl .be . displayed m Point-A to Point B of the thennal shock curve.- On this display (Figure '6d)this straight line will be Point X to Point Y. The maximum-pressure for the DHRS algorithm is given in Section 5.2.2.1.

~

6.2 Selectable Curves for the Low Range P-T Disolay --

The selectable curves for the low range P ~T display provide the operator ease of l

transition fran RCP flow to DHRS flow. This display will allow the operator to {

see the limits of the RCP's and DHRS while starting the DHRS or following RCP startup. As can be seen from Figure 6.5, the " window" between the maximum pressure for the DHRS and the expected RCP configuration (2A/2B) is very tight.

This display will aid the operator in preventing overpressurizing the DHRS.

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6.2.1 heatuo Curve for the Low Range P-T Display (Refer to Figure 6.2) t

- The- heatup curve 'for the low range P-T- display will use the same data points as for Section 5.2.1. The data points and algorithms for these regions are given in Sections 5.2.1.

The heatup curve will have a new end point because of the limited range of the i display. The end point for the low range P-T will be as (288,850).

6.2.2 Thermal Shock Curve for the Low Range P-T Display (Refer to Figure 6.3)

The thermal shock curve will be used during a natural circulation cooldown to aid the operator in starting the DHRS. The algorithm and data points for this curve were given in Section 5.2.2. The end point for the low range P-T will be (428,850). .

6.2.3 Fuel Comoression Limits (Refer to Figure 6.4)

([) The fuel compression limits on the low range P-T display will be the same as those discussed in Sections 5.2.3.1 and 5.2.3.3.

6.2.4 RCP - NPSH Limits (Refer to Figure 6.5)

? _-

' _[ _~ 'The RCP-NPSH ' limits for the 2/2 and 1/1 RCP combinations displayed on the ATOG P-T ;

display will also be displayed on the low range P-T display. The data points and algorithms are given in Section 5.2.4.

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l 7.0 INADE00 ATE CORE COOLING DISPLAY (Refer to Figure 7.1)

The inadequate core cooling display is a series of curves that will provide opera-tor actions based on the Abnormal Transient Operating Guidelines (AT0G) and small break guidelines. The curves consist of the saturation line which provides a reference point from the ATOG P-T curve to the ICC curves; a 1400'F clad tempera-ture line; and an 1800*F clad temperature line. Specific operator actions will be required when the 1400'F and 1800*F limit lines are exceeded. These curves will be. displayed when the ICC display is selected by the operator.

7.1 Axes for the Inadeouate Core Cooling Display The axes for the inadequate core cooling display are the same variables as for the I

AT0G P-T. The use of the sama variables on both displays provides continuity to the operator in a. difficult situation. The horizontal-axis represents temperature in degrees Fahrenheit. This temperature will be T-incore and will have a range from 400 to 1300'F. The vertical axis represents RCS pressure from 200 to 2200 psig. The incore temperature displayed will be the average of the five highest (I) incore thermocouple temperatures. The RCS pressure displayed will be the average of the two middle pressures from four input signals, tina from Loop A and two from Loop B._

- - 1.2- Saturstion Curve The saturation curve is put on the ICC display to provice continuity and a refer ~

ence point for the operator. The data points and.algorittg_for this curve were given in Section 5.1.3.1. The beginning point 'for ~this display is (400,234). The end point for this display is (650,2200).

7.3 1400'F T-clad Line The 1400'T ~T-clad line data points .and algorithm are listed below:

T = Temperature (*F) P = Pressure (PSIG)

T(1) = 470 P(1) = 200

_ T(2) = 510 P(2) = 280 I i

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T(3) = 546 P(3) = 360 l T(4) = 573 P(4) = 440 I T(5) = 596 P(5) = 520 T(6) = 617 P(6) = 600 l T(7) = 635 P(7) = 68 0 l T(8) = 654 P(8) = 760 T(9) = 670 P(9) = 840 T(10) = 687 P(10) = 920 T(11) = 702 P(11) = 1000 T(12) = 716 P(12) = 1080 T(13) = 733 P(13) = 1160 T(14) = 748 P(14) = 1240 T(15) = 760 P(15) = 1320 T(16) = 775 P(16) = 1400 T(17) = 789 P(17) = 1480 !

T(18) = 802 P(18) = 1560 T(19) = 815 P(19) = 1640 T(20) = 829 P(20) = 1720

) T(21) = 840 P(21) = 1800 T(22) = 853 P(22) = 1880 T(23) = 865 P(23) = 1960 T(24) = 877 P(24) = 2040

~

T(25) = 888 '

P(25) = 2120

~T(26) = 900 _ P(26) = 2200 __

l i

The fourth-degree polynomial which represents the above data points.is as follows-T = A1 . -+ A 2 T+A3 (T)2 + A4 (T)3 + A5 (T)4 --

where: A1-= 42.8251681894 x 103 A2 = -1.4432877705 x 101 A3 = +2.3289446543.x 10-2 A4 = -1.0080474143 x 10-5 A5 = +1.2858097886 x 10-9 i

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7-3 I l

7.4 1800*F T-clad Line ,

The 1800*F T-clad line data points and algorithm are listed below: .

T = Temperature (*F) P = Pressure (PSIG)

T(1) = 774 P(1) = 200 T(2) = 806 P(2) = 280 ;

T(3) = 838 P(3) = 360 T(4) = 865 P(4) = 440 ,

t T(5) = 891 P(5) = 520 T(6) = 916 P(6) = 600 T(7) = 940 P(7) = 680 l T(8) = 960 P(8) = 760 T(9) = 981 P(9) = 840 :

T(10) = 1000 P(10) = 920 ,

T(11) = 1020 P(11) = 1000 T(12) = 1038 P(12) = 1080

, T(13) = 1057 P(13) = 1160

[h T(14) = 1075 P(14) = 1240 T(15) = 1092 P(15) = 1320 I T(16) = 1110

, P(16) = 1400 T(17) = 1126 P(17) = 1480

?

.T(18) = 1141 P(18) = 1560

~~

T(19) = 1157 P(19) = 1640 T(20) = 1170 P(20) = 1720 i

~~

T(21) = 1184 P(21) = 1800 T(22)-= 1196 --

~P(22) = 1880 T(23) =.1208 .

P(23) = 1960 T(24) = 1219 P(24) = 2040 T(25) = 1223 P(25) = 2120 T(26) = 1235 P(26) = 2200 3 The fourth-degree polynomial which represents the above data points is as follows:

P=A 1 + A2 T + A3 (T)2 + A4 (T)3 + A5 (T)4

) .

7-4

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L j where: A1 = +1.8806685160 x 103 A2 = -1.1596602365 x 101 A3 = +2.1451859650 x 10-2

. A4 = -1.5964631335 x 10-5 i

4 A5 = +5.1365299950 x 10~9

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8.0 ALPHANUMERIC DISPLAY (Refer to Figure 8.1) t

- -The Alphanumeric Display is a four page display. The first two pages provide numerical indication of many key parameters to the control room operator during normal operation of the plant. The third page provides specific status informa-tion on the fourteen (14) radiation monitors which are used in the RADIATION Alert. The fourth page provides specific status information concerning the ESAS channels monitored by the ES ACT alert, EFW ACT alert and RPS ACT alert. If an alert message is received for one of these SPDS Alerts, then the control room operator can select the appropriate page of the Alphanumeric Display to determine l

which parameter (s) is causing the alert.

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l FIGURE 8.1

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i ALPHANUMERIC DISPLAY (PG.1)

(SPARE)

SOURCE RANGE NI-1 XX CPS SOURCE RANGE NI-2 XX CPS INTERMED RANGE NI-3 XX AMP INTERMED RANGE NI-4 XX AMP POWER RANGE NI-5 XXX %

POWER RANGE NI-6 XXX %

POWER RANGE NI-7 XXX %

POWER RANGE NI-8 XXX %

T-COLD LOOP A XXX/XXX DEG F T-COLD LOOP B XXX/XXX DEG F T-HOT LOOP A XXX/XXX DEG F

{ T-HOT LOOP B XXX/XXX DEG F RCS PRES LOOP A XXXX/XXXX PSIG Ih RCS PRES LOOP B XXXX/XXXX PSIG DTSG FULL RNG LVL A XXX IN

! OTSG FULL RNG LYL B XXX IN OTSG OP RNE LYL A XXX %

~

r OTSG DP RNG LYL 3 XXX %

OTSG PRES A XXXX PSTB .

,, OTSG PRES B XXXX PSIG MAIN FDW FLOW A X MLB/HR MAIN FDW FLOW B I MLB/HR P

(SPARE)

)

8-2

FIGURE 8.1 (CONT'D)

ALPHANUMERIC DISPLAY (PG.2)

RCS PRES LOW RNG A XXX/XXX PSIG f RCS PRES LOW RNG B XXX/XXX PSIG

{ CST LEVEL XXX IN SERVICE WTR PRESS XXX PSIG

, CONTNMNT PRES A XXX PSIG CONTNMNT PRES B XXX PSIG RCS TOTAL FLOW A XX MLB/HR RCS TOTAL FLOW B XX MLB/HR RCS LOOP A DELTA T XXX DEG F RCS LOOP B DELTA T XXX DEG F MAKEUP TANK LEVEL XXX IN MAKEUP FLOW XXX GPM -

LETDOWN FLOW XXX GPM HPI FLOW MUV-25 XX GPM

, HPI FLOW MUV-23 XX GPM

'M HPI FLOW MUV-26 XX GPM HPI FLOW MUV-24 XX GPM DECAY HEAT FLOW A XXXX GPM .

IECAY HEAT FLOW B XXXX GPM

~~-

.PZR- LEVEL .A XXX IN

~

1 EMERG FDW FLOW A _ XXXX GPM I -

EMERG FDW FLOW B XXXX GPM DISCH TEMP RCV-1D XXX DEG F 1 DISCH TEMP RCV-9 XXX DEG F DISCH TEMP RCV-8 XXX DEG F l

i 8-3

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l FIGURE 8.1 (CONT'D)

. ALPHANUMERIC DISPLAY (PG.3)

RB DOME RAD G19 XXX R/H RB PURGE DUCT RAD A1 XXX UC/CC FUEL HANDLING DUCT RAD A2 XX UC/CC RB VENT RAD A6 XX UC/CC COND VACUUM PUMP RAD A12 XX UC/CC CONTROL ROOM VENT RAD A5 XX UC/CC CONTROL ROOM RAD G1 XX MR/HR (SPARE)

MAIN STEAM RAD G25 XXX R/H MAIN STEAM RAD G26 XXX R/H MAIN STEAM RAD G27 XXX R/H MAIN STEAM RAD G2B XXX R/H PRIMARY COOLANT RAD L1 XXX UC/CC PLANT DISCHARGE RAD L2 XXX UC/CC g TB SUMP RELEASE RAD L7 XXX UC/CC V (SPARE)

(SPARE)

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8-4 i

FIGURE 8.1 (CONT'D)

ALPHANUMERIC DISPLAY (PG.4)

RC1 ES CHAN A TRIPPED XXX RC2 ES CHAN A TRIPPED XXX RC3 ES CHAN A TRIPPED XXX RC4 ES CHAN A TRIPPED XXX RC5 ES CHAN A TRIPPED XXX RC6 ES CHAN A TRIPPED XXX i.

RB1 ES CHAN A TRIPPED XXX RB2 ES CHAN A TRIPPED XXX RB3 ES CHAN A TRIPPED XXX RC1 ES CHAN B TRIPPED XXX RC2 ES CHAN B TRIPPED XXX

~

RC3 ES CHAN B TRIPPED XXX RC4 ES CHAN B TRIPPED XXX RC5 ES CHAN B TRIPPED XXX RC6 ES CHAN B TRIPPED XXX i

RB1 ES CHAN B TRIPPED XXX ,

RB2 ES CHAN B TRIPPED XXX RB3 ES CHAN B TRIPPED 'XXX RX TRIP XXX

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(SPARE) w yLy RCV.B -

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RLF VLV RCV-9 XXXXX REF VLV RCV-10 XXXXX I

i 8-5

9.0 ALERTS I

.The-purpose of the Alerts on the CR-3 SPDS is to warn the control room operator of potential problems in the control of those safety functions which are not being monitored on the five available displays. When conditions warrant, the alert message will appear on the CRT screen and will flash until the control room operator acknowledges the alert signal. The alert message will remain on the screen until the conditions do not warrant an alert. Then the alert message will automatically clear provided the control room operator has acknowledged the alert. !

l l

g.1 Reactivity "REACTIV" Alert i

i Tne purpose of the "REACTIV" alert is to warn the control room operator that adequate control of the reactivity safety function is not occurring. This alert is activated if any of the following occur:

a. All control rods are not fully inserted within three (3) seconds following a reactor trip or an asymmetric fault exists.

h

'b. The neutron flux has not decayed to below 103 cps within 25 minutes following a reactor trip.

The following signal sources from the Inputs to SPDSlist will be monitored in this alert:-

1. Source Range NI-01 t

.2. Source _ Range NI-02

3. All Rods In

4. Reactor Tripped 4

The simplified alert logic flow chart is on the following page.

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l 9.2 " RADIATION" Alert

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The purpose of the " RADIATION" alert is to warn the control room operator of increasing radiation levels in one or more of the monitored release paths. The l

" RADIATION" alert will alarm and be displayed anytime the condition exists where 1

one or more radiation monitors exceeds it alarm setpoint. The following signal sources and their limits from the Inputs to SPDS List will be monitored in this alert.

Monitor Limit

1. RMG-19 6R/HR

2. RMA-1 SK CPM

3. RMA-2 1K CPM

4. _RMA-6 SK CPM

5. RMA-12 500 CPM

6. RMG-25 1 MR/HR

7. RMG-26 1 MR/HR

()) 8. RMG-27 1 MR/HR

9. RMG-28 1 MR/HR

10. RML-1 80K IPM

11. RML-2 ,

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13. RML-5 200 CPM

~~~~

~ 14. RMG-1 2 MR/HR

--~~~- The simplified alert logic flow chart is on -the following page.

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9.3 Reactor Building Pressure "RB PRES" Alert t

The purpose of the "RB PRESS" alert is to warn the control room operator of increasing pressure conditions in the Reactor Buildi.ng before they reach ESAS actuation setpoint. The "RB PRESS" alert will alarm and be displayed anytime the condition exists where either of the redundant RB pressure signals exceeds 1.5 psig. The following signal sources from the Inputs to SPDS List will be monitored in this alert:

1. BS90 - PT

2. BS91 - PT The simplified alert logic flow chart is on the following page.

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9.4 Engineered Safeguards Actuation "ES ACT" Alert The purpose of the "E3 ACT" alert is to inform the control room operator that signals for the Engineered Safeguards Actuation System to actuate are present.

There are a total of 18 ES channels monitored, arranged in six groups of three.

When two of three redundant channels in any of these six groups indicates

" tripped", then the "ES ACT" alert will be alarmed and displayed. The following signal sources from the Inputs to SPDS List will be monitored in this alert.

Group 1: Ch RC1 A, Ch RC2 A, Ch RC3 A Group 2: Ch RC4 A, Ch RC5 A, Ch RC6 A Group 3: Ch RB1 A, Ch RB2 A, Ch RB3 A Group 4: Ch RC1 B, Ch RC2 B, Ch RC3 B Group 5: Ch RC4 B, Ch RC5 B, Ch RC6 B Group 6: Ch RB1 B, Ch RB2 B, Ch RB3 B The simplified alert logic flow chart is on the following page.

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1. (L4TER)

The simplified alert logic flow chart is on the following page.

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l 9.6 Reactor Trio "RPS ACT" Alert i l The purpose of the "RPS ACT" alert is to warn the control room operator that a signal for the reactor to trip is present. The signal source from the Inputs to SPDS List will be an open or closed signal from the following:

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10.0 REFERENCES

10.1 !

74-1126473-00, Crystal River Unit 3 Abnormal Transient Operating Guidelines l (AT0G), Part I and II, dated October 1, 1982.

10.2

" Supplement 1 to NUREG-0737, Requirements for Engineering Response Capability (Generic Letter 82-33)", dated December 17, 1982.

10.3 Crystal River 3 Plant Technical Specifications, Amend. 46, dated December 4, 1982.

4 i

10.4 CR-3 Technical Specification P-T Limits (for 8 EFPY), File 582-7158, T4.7, dated August 11, 1982.

10.5 Crystal River Unit 3 Operating Procedure OP-103, Plant Curve Book, Rev. 35, dated August 11, 1982.

I 10.6 74-1123094-00, Operating Guidelines For Small Breaks For Crystal River 3, dated January 8,1981.

d 10.7 86-1105508-00, "

Analysis Summary .In Support Of ~ Inadequate Core Cooling Guidelines For A loss Of RCS Inventory," dated November 2,1973.

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,, __ .-a M&

i 10-1

--. --. _- - - ._ . --. . . . _ - -. . . - .- . .. . .,

ML20211N421

Contents

Text

SUMMARY

2.0 INTRODUCTION

10.0 REFERENCES

SUMMARY

2.0 INTRODUCTION

st u R=

10.0 REFERENCES

Navigation menu

ML20211N421

Text

SUMMARY

2.0 INTRODUCTION

10.0 REFERENCES

SUMMARY

2.0 INTRODUCTION

st u R=

10.0 REFERENCES

Navigation menu

Search