ML19305E268

Startup Test Procedure 2-ST-13, Simulated Loss of All Onsite & Offsite Power.

ML19305E268
Person / Time
Site:	North Anna
Issue date:	04/21/1980
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML19305E260	List: ML19305E259 ML19305E264 ML19305E268 ML19305E273 ML19305E274
References
2-ST-13, NUDOCS 8004230246
Download: ML19305E268 (31)

Text

__ .-_ ___ _ __ -_. - _ _ _

O Page 1 of _

2 ST 13 L.! ,

VIRG!ti!A ELECTRIC At4D POWER COMPANY Revision No.: O )

Date: i STARTUP TEST PROCEDURE FOR NORTH ANNA POWER CTATION UNIT g 2 b l TITLE: SIMULATED LOSS OF ALL ONSITE AND OFFSITE AC POWER i Prepared By: E.R. SMITH , JR. Date: l Engineering Recommended Approval: Date:

STATICN NUCLEAR SAFETY AND OPERATING COMMITTEE APPROVAL OF PROCEDURE: ,

Chairman's Signature: Date: l All personnel conducting actual testing in accordance with this procedure will i verify by their signature that they have read it in its entirety prior to i connencing any testing.

1 1

h0T A CC% , , .

5 i , C. ; (,,j,,,

TEST RESULTS REVIEVED BY ENGINEERING: I'5I4 ""- Date-l l

TEST RESULTS APPROVED BY STATION NUCLEAR SAFETY AND OPERATING COMMITTEE:

Chairman's Signature: Date: l

\

Connen ts .

1 l

l l

I l

l 8004230 24 gl

. . . . . - - . ~ -.

h

, I e

TEST RESULTS (Use additional pages as needed) Page 2 of ,

Ol$CRE?ANCIES (List by nurneer):  !

se f

i I

I

. 1 b

i i

i

/

~~

RISOLUTICN CF 3tSCRE?hfCIE3 (List by nu.eeer c rrescending :s above): III l l

l f

i CalTICUE: l12 {

i.

i e

l l

l i

l l

. l l

l k

e

6 i

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

t A

i f

CHRONOLOGICAL LOG (Use add'1 pages as needed) Page _ of  ;

F I

I i

5 i

P e

i

'N ,

I i

ii e

h t

d i

e i

l I

f J

i f

i i

l

- l i

l i

n l

~

i i

e i

l l

f I 1

l l

1 e

e e O &

a i

l

2-ST-13 Page 1 of 11 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NO. 2 -

SIMULATED LOSS OF ALL ONSITE AND OFFISTE AC POWER

References:

1. Precautions, Limitation and Setpoints for W>stinghouse NSSS system

2. Technical Specifications, North Anna Unit #2

3. WCAP-8747: North Anna Nuclear Design Report

4. North Anna Station Curve Book '

5. 2-0P-5.2

6. 2-OP-30

7. 2-0P-31

8. 2-OP-32.1 1.0 Purpose 1.1 To demonstrate that following a loss of all onsite and offsite power, including the emergency diesel generators, the decay heat can be removed by natural circulation using the auxiliary feedwater system in the manual mode.

1.2 Verify that hot standby conditions can be maintained by manual control of the auxiliary feedwater system.

1.3 To verify that critical plant operations can be performed using emergency lighting, that the 125-volt DC system has the ability to supply the 125-volt vital AC and that certain equip-ment areas do not exceed maximum design temperature.

2-ST-13 Page 2 of 11 2.0 Initial Conditions 2.1 Low Power Physics Testing has been completed to the extent i necessary for conduct of this test.

2.2 Reactor is critical and manually controlled at approximately 1% j power with control bank D at U 160 steps or as specified by test engineer. (Power determined as indicated in Appendix 6.3.)

2.3 All three reactor coolant pumps are in operation.

2.4 Pressurizer pressure control and level control are in automatic, maintaining RCS pressure at approximately 2235 psig and pressu-rizer level at approximately 22%.

2.5 Steam dump valves are in the pressure control mode, maintaining ,

steam generator pressure at approximately 1005 psig.

2.6 Steam generator level is being maintained at approximately 33%

on the narrow range indicators.

2.7 Feedwater and condensate systems are in service in accordance j with 2-0P-30 and 2-OP-31.  ;

2.8 RCS temperature (T,y ) is being maintained at approximately 547

• F.

2.9 Record the following parameters.

2.9.1 Install brush recorders to record data at the following locations.

Brush Recorder No. 1 Connect To: Monitoring Channel No. 1 FP-414B, C1-432 RCS Flow, Loop 1 Channel No. 2 FP-424B, C1-433 RCS Flow, Loop 2 Channel No. 3 FP-434B, C1-434 RCS Flow, Loop 3 Channel No. 4 PP-455B, C1-427 Pressurizer Pressure Channel No. 5 FP-459B, C1-442 Pressurizer Level

. . i 2-ST-13 l Page 3 of 11 Initials 2.0 Initial Conditions (cont.)

Brush Recorder No. 2 Connect To: Monitoring  ;

Channel No. 1 PP-474B, C2-433 Steam Gen. #1 Press.

Channel No. 2 LP-474B, C1-429 Steam Gen. #1 Level .

Channel No. 3 FP-474B, C3-741 Steam Gen. #1 Stm. Flow i Channel No. 4 PP-484B, C2-444 Steam Gen. #2 Pressure Channel No. 5 CP-489B, C1-430 Steam Gen. #2 Level Channel No. 6 FP-484B, C3-746 Steam Gen. #2 Steam Flow c

Brush Recorder  :

No. 3 Connect To: Monitoring  !

Channel No. 1 PP-494B, C2-445 Steam Gen. #3 Press. i Channel No. 2 LP-494B, Cl-431 Steam Gen. #3 Level Channel No. 3 FP-494B, C3-748 Steam Gen. #3 Sta. Flow '

Channel No. 4 S/6A Aux Feed Flow Channel No. 5 S/6B Aux Feed Flow  !

Channel No. 6 S/6C Aux Feed Flow  !

2.9.2 Record the following on eact strip chart:

a) Test Number '

b) Recorder QA Number c) Time and Date d) Chart Speed e) Scale Used f) Test Point  !

g) Parameters ,

2.9.3 Record on reactivity-computer recorder

a. Flux

b. Average wide range T eo

c. Average wide range Ts ,ld

d. Average Steam generaEor pressure ,

i 2.10 Four incore T/C may be trended on the analog trend recorder on  !

the main control board. (Suggest trending tt.e four hottest i

thermocouples, one from each quadrant.)

2.11 A steady feed to the steam generators should be set up to minimize temperature variation in the RCS.

2.12 Auxiliary feedwater system 7P?ad up in standby in accordance with 2-0P-32.1.

2-ST-13 Page 4 of 11 P

Initials 2.0 Initial Conditions (cont.)

2.13 Steam generator chemistry in a condition that the absolute i

minimum steam generator blowdown can be maintained during the '

duration of this test. (Zero blowdown is possible).

2.14 Excess letdown is available for service if required during the test.

2.15 Verify that battery-powered lights are located in areas where operation of equipment is required after normal lighting is de- ,

energized. (Operations to supply lights and position them i

whste desired). ,

i NOTE: These temporary lights should only be located in areas where operation of equipment would not normally take place in a black- ,

out. Areas which must be operated during a blackout should be  ;

supplied with permanent battery-powered lights.

2.16 125 VDC Busses and 125 VAC Vital Busses are in normal alignment. -

r 2.17 Evacuate non-essential personnel from all Unit 2 work areas in t

the auxiliary and containment buildings, if applicabic. l l

NOTE: This is a safety measure since these work areas will be without lighting for approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

2.18 Block auto actuation of safety injection on Hi Steam A P. 1 2.19 Notify the Shift Supervisor on duty of the impending test and co-ordinates its performance through him.

3.0 Precautions I 3.1 Do not exceed 5% nuclear power.

3.2 Do not exceed any of the following temperature limits.

3.2.1 610*F for anycore outlet thermocouple.

3.2.2 65'F for any loop Delta-T.

3.2.3 580.3'F for any loop T,y .

2-ST-13 Page 5 of 11 Initials 3.0 Precautions (cont) 3.3 Do not exceed primary to secondary differential pressure of 1600 psi.

3.4 Avoid rapid changes in steam pressure, steam generator level, and feedwater flow to prevent rapid cooling of the reactor coolant.

3.5 Do not exceed 100 psi differential pressure between any two [

steam lines. This will result in a safety injection signal. .

3.6 Maintain reactor coolant pump seal and thermal barrier differen-tial requirements as given in 2-OP-5.2.

3.7 After the reactor coolant pumps are tripped, the normal T,yg and 6T indications will become unreliable. AT and T should avg ,

be calculated by taking the difference and the average of the hot and cold leg termperatures indications respectively.

NOTE: Observe the TSAT meter. ,

3.8 Maintain T at the pretrip temperatures by adjusting the cold steam dump setpoint. '

3.9 Note possible effects of a positive moderator temperature coefficient. i 3.10 When equilibrium is established after the initial transient, avoid any sudden changes in Auxiliary- Feedwater flow or in the Steam Generator water level.

3.11 Ensure seal flow to each Reactor Coolant pump is maintained at or slightly above 6 gpm during the test.

3.12 When the Reactor Coolant pumps are first tripped, Steam Generator water level will first shrink (due to flow coastdown)

I

2-ST-13 Page 6 of 11 Initials 3.0 Precautions (cont) and then swell (as natural circulation Leaches equilibrium).

When complete manual control of auxiliary feedwater is begun, do not reduct feedwater flow below 40 gpm to each steam generator during the swell. (Until normal level is established).

3.13 After the Reactor Coolant pumps are tripped, the normal T d av8 A T indication will become unreliable. A T and T avg should be calculated by taking the difference and the average of the hot l

and cold leg temperature indications respectively.  ;

I 3.14 If the primary system pressure drops to a point where it is i

obvious that saturation pressure for the existing wide range hot leg or incore T/C temperatures will soon be reached, the pressurizer heaters will have to be energized or charging flow l reestablished to increase system pressure 3.15 NIS channels can be used to determine changes in core power level providing the RCS cold leg temperatures are maintained at approximately the same value that existed before tripping l the reactor coolant pumps.

3.16 Test instrumentation should be connected to a reliable source i of power.

4.0 Instructions 4.1 Shutdown the main control room air conditioning and place a l 1

room thermometer on the operator's desk to monitor control j i

room air temperature.  !

1

. l l

2-ST-13 Page 7 of 11 Initials 4.0 Instructions (cont.)

4.2 Clear the auxiliary building of all non-essential personnel and announce over the Public Address System that a blackout test will be beginning shortly.

4.3 Manually adjust Pressurizer Spray Valve controllers to zero %

output (closes pressurizer spray valves) and leave the controllers in manual control.

4.4 Ensure the pressurizer backup heaters will remain off by moving i

control switches to " pull to lock".

4.5 Ensure Auxiliary Feedwater motor driven pumps IA and IB will not start on the simulated blackout by moving switches to the

" pull-to-lock" position.

4.6 Just prior to initiating RCP trips, reduce charging flow to the minimum required to maintain seal injection flow.

4.7 Isolate RCS letdown.

4.8 Close charging line stop valve MOV-22o9A or 2289B once charging flow is reduced.

4.9 Record the data indicated on Attachment 6.2.

4.10 Start the Computer Trend printer printing at 1-minute intervals.

4.11 Record the time, date and initial the charts on the data recorders.

4.12 Start all three reactor coolant pump oil lift pumps.

NOTE: The following step should be conducted immediately before initiating the trips.

4.13 As quickly as possible shutdown the following equipment. As many people as possible should be utilized to complete this step so that a close approximation to a blackout can be simulated.

2-ST-13 Page 8 of 11 Initials i 4.0 Instructions (cont.)

NOTE: Zero Time =

Check / ,

a) Trip pressurizer heater control group.

t

~

b) Trip all three reactor coolant pumps.

c) Close main steam isolation valves.  !

d) Trip the main feed pump presently in operation.

e) Place 25H2 (EDG2H OUTPUT BKR) in

" Pull-to-Lock".

f) Place 25J2 (EDG2J OUTPUT BKR) in

" Pull-to-Lock". -

NOTE: It will be necessary to realign aux. feed flow so that the turbine-driven aux feed pump is flowing to all three S/G's.

g) Place Remote-Local control switches for EDG2H and 2J in Manual, Local position.

h) Trip and lock out 15E3 and 15F4.

(This deenergizes 4KV Emerg Busses.)

i) Trip and lock out 25B1 and 25C1.

(Bus 2A will remain energized to power a Rod Drive MG Set.)

j) Begin monitoring and recording the parameters indicated on Attachment 6.5, Data Sheets at the intervals indicated.

NOTE: Monitor reactor power closely and make any aijustmants necessary to maintain approximately 1% power. T for each leg should be

.maintcined at approximately the pretrip temperature.

l l

l

l 2-ST-13 Page 9 of 11 1

Initials i 4.0 Instructions (cont.)

4.14 Verify the steam-driven Auxiliary Feedwater pump has started and flow established to each steam generator. i l

NOTE: Operators may be dispatched to take manual control of Auxiliary l Feedwater and main ' steam power operated relief valves, if l possible. i 4.15 Verify natural circulation has been established.  ;

4.16 Bring the steam generator levels back to normal operating level (approximately 33%) and manually adjust atmospheric dump and i

auxiliary feedwater flow to maintain the pretrip cold leg temperature. (Establish a steady feedwater flow. Do not stop and start flow to control the level.)

4.17 When equilibrium conditions have been established for each steam generator, make notes on Attachment 6.5 Data Sheets of the time and continue recording data.

4.18 Maintain steam generator level at approximately 33% and reactor power at 1% for a maximum of a two-hour period from the time of i the simulated blackout.

NOTE: The pressurizer water level is not expected to rise above 80%,

however, if it should, put excess letdown into service to reduce the RCS water volume. Maintain letdown until level reaches 50%. (Note letdown established on Attachment 6.5 Data Sheets).

4.19 Adjust the setpoint dial on the pressure controllers to 1005 psig and individually return the power-operated relief valves to " Auto" control.

CAUTION: Let each steam generator come to equilibrium before putting the next power relief valve in Auto.

4.20 Return pressurizer spray controllers to " Auto". (Spray will I

not be available until the reactor coolant pumps are restarted).

l l

l

2-ST-13 Page 10 of 11 Initials 4.0 Instructions (cont.)

NOTE: If the RCS pressure is below 2210 psig, energize one of the pressurizer backup heaters. Realign the applic3ble emeriency ~~~-

~

bus to power the heater. Control RCS pressure by energizing or deenergizing the backup heaters.

4.21 Insert Control bank D until the reactor is in the hot zero power test range.

4.22 Reclose 25B1 and 25C1.

4.23 Reclose 15E3 and 15F4.

4.24 Place EDG 2H and 2J Remote-Local switches to remote, auto i

condition. t 4.25 Return 25H2 and 25J2 to " Auto".

4.26 Return to normal feedwater alignment and, when possible, return to condenser steam dump.

4.27 Return all three reactor coolant pumps to service.

4.28 Restore pressurizer heaters and establish stable RCS pressure l

control.

4.29 Discontinue trend recording.

4.30 Establish normal letdown and charging and return pressurizer level to the ; 22% level.

4.31 Place Aux feed pump motor driven pumps in " Auto".

4.32 Announce that blackout testing is complete.

l 4.33 Remove the block of auto actuation of SI on high steam line AP.

l l

l l l i

l l

Completed by: l Date:

2-ST-13 Page 11 of 11 5.0 Accescance Criteria 5.1 Core exit T/C temperature did not exceed 610 F.  !

5.2 Delta-T for any loop did not exceed 65*F.

5.3 Tavg for any loop did not exceed 580.3'F.

5.4 Natural circulation can be established and maintained with the degraded condition of a simulated loss of offsite and onsite power.

5.5 Emergency lighting in the plant is sufficient to operate critcial equipment in the loss of normal lighting.

5.6 Hot standby conditions can be maintained for a 2-hour period with criteial equipment operating off of vital battery power.  ;

5.7 Manual operation of auxiliary feedwater system can be coordi-nated by the unit operator to maintain stable plant conditions.

6.0 Attachments 6.1 Test Equipment Data Sheet 6.2 Initial Conditions 6.3 Appendix A 6.4 Trend Blocks 6.5 Data Sheets P

_ ~_ . _ . _ _ . _ _ _ , . . . . . . _ .-.___

2-ST-13 Attachment 6.1 Page 1 of 1  ;

TEST EQUIPMENT DATA SHEET i

TEST EQUIPMENT DESCRIPTION

• MODEL NUMBER VEPCO QA NUMBER i

f t

h l

l i

1 l

• NOTE: This applies only to temporarily installed test equipment or instrumentation Permanent instrumentation which is part of the system and shown on drawings should not be included.

Completed By:

Date:

- -~. ._ - . - . _ . . . . . - . . . -. - - - - _ . . . . - - - . -

2-ST-13 Attachment 6.2 Page 1 of 3 i

i INITIAL CONDITIONS Pressus12 i-- Pressure ---- psig PR-2444 Red Pen Pressurizer Level  %

LR-2459 Red Pen RCS Loop 1 Hot Leg Temperature 'F TR-2413 Red Pen RCS Loop 1 Cold Leg Temperature 'F TR-2410 Red Pen RCS Loop 2 Hot Leg Temperature *F TR-2423 Green Pen RCS Loop 2 Cold Leg Temperature - *F TR-2420 Green Pen RCS Loop 3 Hot Leg Temperature *F TR-2433 Blue Pen RCS Loop 3 Cold Leg Temperature 'F TR-2430 Blue Pen Steam Generator 1 Level (NR)  %

(LI-2474)

Steam Generator 2 Level (NR)  %

(LI-2484)

Steam Generator 3 Level (NR)  %

(LI-2494)

Steam Generator 1 Level (WR) ,%

LR-2477 Pen 1 Red Pen Steam Generator 2 Level (WR)  %

LR-2477 Pen 2 Green Pen Steam Generator 3 Level (WR)  %

LR-2477 Pen 1 Blue Pep

2-ST-13 Attachment 6.2 Page 2 of 3 INITIAL CONDITIONS ,

i

--~-- -Steam Generator 1 Pressure psig PI-2474 Steam Generator 2 Pressure psig PI-2484 Steam Generator 3 Pressure psig PI-2494 6

Steam Generator 1 Feedwater Flow X10 #/hr i (FI-2476) 0 Steam Generator 2 Feedwater Flow X10 #/hr (FI-2486) 0 Steam Gener..or 3 Feedwater Flow X10 #/hr (FI-2496) i 6

Steam Generator 1 Steam Flow X10 lbs/hr (FI-2474) 6 Steam Generator 2 Steam Flow X10 lbs/hr (FI-2484) 0 Steam Generator 3 Steam Flow X10 lbs/hr (FI-2494) l Leop 1 Tavg protection *F (TI-2412D)

Loop 2 Tavg protection *F (TI-2422D)

Loop 3 Tavg protection *F (TI-2432D)

2-ST-13 ,

Attachment 6.2 Page 3 of 3 INITIAL CONDITIONS Loop 1 AT protection  %

(TI-2412A)

Loop 2 AT protection  %

(TI-2422A)

Loop 3 AT protection  %

(TI-2423A) l NIS Channel N-41  % ,

NIS Channel N-42  % f NIS Channel N-43  %

NIS Channel N-44  %

Attach a copy of the computer printout of the Incore Thermocouple Temperature map. i i

Temperature in Turbine - Drive Aux Feed *F Pump Room Control Room Temperature *F Outside Temperature 'F ,

Completed By: ,

Date:  ;

2-ST-13 Attachment 6.3 Page 1 of 8 I APPENDIX A i r

Outline I. Core Power Determination A. Primary Side Calorimetric (Forced Circulation Only)

1. Reference (s500*F) Calorimetric  !

a) Output used to adjust M/D Power Monitor Program's power conversion constant. '

i B. M/D Power Monitor Program '

1. Power Conversion Constant Adjustment.

a) The output of the REF primary calorimetric will give a

% power output; this output must be input to the M/D 5 Power-Monitor Program so that the program output will be in percent power and equal to the primary calorimetric output.

2. Power Monitoring a) The M/D Power Monitor Program will calculate the integral power as seen by one pass of 4 or 5 detectors. After the output has been calibrated to be equal to the REF primary calorimetric it will be rerun up to once every 2 minutes or as necessary to continuously monitor core power.

. - - - . . ~ . .

-..n

'..~. 13 na..

. 5 k m.a. n. . .. C.3

- O. g y+ a. 1

.a'. 3 t

5 - es

.% .3

. y*- .

._.g...=...

. .m y ..,..*..9 . .. ........a 3

..-.g

,<2 ......_ .. . ...,

.... . :. . .. ., .. .s ....;.<...,.e..

,i .; . .i  !.* a. g ...

.. .'e%.g

.a . 1 .s. 3 g3..

_ ... . . =.%.. a. **a..* *.g

. s - a. -*

a. .b.. e *. s $ .

. ..J.=..=.t f.. e = .s.

.y .. 4..J .J. .4 .J.

.s . .. 3 .,. g. . , . . .

....f . . ..y

. a. .s ,3.. f .g.g a . u. J.,. .

i g . .* wg.t

=

..~ s..g. . ..e _A = . . , - 3.' . .a.m, t .y . .%..g

. . . f'. . ,  ; ..u..,. s.,. ,... . a .s e ... u..,. a. .. , . a.

.k.e *a*e s ..J. . .. .... . . .a . se s .. a. g_ _J . . . . n. ....y . .,.e.

... . ...e .. .... . a.....3..a. .e

,. J. .w . _ .. ,.e.... s.

(Tab?.e A *). (5 ;e:d.1'. Tas- 50.

. 9 v.sas ".ea. se

,a

._ e s-ide .a 2.ge 2.1 1

. 2...,........... .e . .... 3

. . .....<.a.

..w.. .o .. . .

.n.,. .._._3 f

.. . . . . , .... e

.o A. ry

. s.. a .s a , --

..a..,.

. . a, .. .

n. 3 e.-

-- . . ...g ... 4..., s... . .

. .... , . a s 1- 4. .--...e...<.=.....=......'.,...-.-,ce..

~. .P.

.u......

o

.e.. <.

.a .. sac .4.

-.z.,

.. a.

0, 9 .

a s h

l I

b I

e l

t d

2-ST-13 .

Page 3 of 11 Initials 2.0 Initial Conditions (cont.)

Brush Recorder No. 2 Connect To: Monitoring .

Channel No. 1 PP-474B, C2-433 Steam Gen. #1 Press.

Channel No. 2 LP-474B, C1-429 Steam Gen. #1 Level Channel No. 3 FP-474B, C3-741 Steam Gen. #1.Ste. Flow Channel No. 4 PP-484B, C2-444 Steam Gen. #2 Pressure Channel No. 5 CP-489B, C1-430 Steam Gen. #2 Level Channel No. 6 FP-484B, C3-746 Steam Gen. #2 Steam Flow Brush Recorder '

No. 3 Connect To: Monitoring Channel No. 1 PP-494B, C2-445 Steam Gen. #3 Press.

Channel No. 2 LP-494B, C1-431 Steam Gen. #3 Level Channel No. 3 FP-494B, C3-748 Steam Gen. #3 Sta. Flow  !

Channel No. 4 S/6A Aux Feed Flow  !

Channel No. 5 S/6B Aux Feed Flow Channel No. 6 S/6C Aux Feed Flow l l

i 2.9.2 Record the following on eact strip chart:

a) Test Number b) Recorder QA Number i c) Time and Date d) Chart Speed e) Scale Used f) Test Point l g) Parameters 2.9.3 Record on reactivity-computer recorder

a. Flux

b. Average wide range T eold '

c. Average wide range T hot

d. Average Steam generaEor pressure 2.10 Four incore T/C may be trended on the analog trend recorder on the main control board. (Suggest trending the four hottest thermocouples, one from each quadrant.)

f 2.11 A steady feed to the steam generators should be set up to minimize temperature variation in the RCS.

i 2.12 Auxiliary feedwater system lined up in standby in accordance  !

with 2-0P-32.1.

2-ST-13 Page 4 of 11 Initials 2.0 Initial Conditions (cont.)

2.13 Steam generator chemistry in a condition that the absolute i

minimum steam generator blowdown can be maintained during the ,

duration of this test. (Zero blowdown is possible).

2.14 Excess letdown is available for service if required during the test.

2.15 Verify that battery powered lights are located in areas where operation of equipment is required after normal lighting is de-energized. (Operations to supply lights and position them where desired).

NOTE: These temporary lights should only be located in areas where operation of equipment would not normally take place in a black-out. Areas which must be operated during a blackout should be supplied with permanent battery powered lights.

2.16 125 VDC Busses and 125 VAC Vital Busses are in normal alignment.

l 2.17 Evacuate non-essential personnel from all Unit 2 work areas in '

the auxiliary and containment buildings, if applicable.

NOTE: This is a safety measure since these work areas will be without '

lighting for approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

2.18 Block auto actuation of safety injection on Hi Steam a P.

2.19 Notify the Shift Supervisor on duty of the impending test and co-ordinates its performance through him.

r 3.0 Precautions 3.1 Do not exceed 5% nuclear power.

3.2 Do not exceed any of the following temperature limits.

3.2.1 610 F for anycore outlet thermocouple.

3.2.2 65 F for any loop Delta-T.

3.2.3 580.3*F for any loop T,y .

em m

2-ST-13 Page 5 of 11 Initials 3.0 Precautions (cont) 3.3 Do not exceed primary to secondary differential pressure of 1600 psi.

3.4 Avoid rapid changes in steam pressure, steam generator level, and feedwater flow to prevent rapid cooling of the reactor coolant.  ;

3.5 Do not exceed 100 psi differential pressure between any two steam lines. This will result in a safety injection signal. .

3.6 Maintain reactor coolant pump seal and thermal ba-rier differen-tial requirements as given in 2-OP-5.2.  ;

3.7 After the reactor coolant pumps are tripped, the normal T,yg and AT indications will become unreliable. AT and T avg should be calculated by taking the difference and the average of the  !

~  ;

hot and cold leg termperatu _~ indications respectively.

NOTE: Observe the TSAT meter.

t 3.8 Maintain T eold at the pretrip temperatures by adjusting the steam dump setpoint. i 3.9 Note possible effects of a positive moderator temperature coefficient.

3.10 When equilibrium is established after the initial transient, avoid any sudden changes in Auxiliary Feedwater flow or in the Steam Generator water level.

3.11 Ensure seal flow to each Reactor Coolant pump is maintained at or slightly above 6 gpm during the test.

3.12 When the Reactor Coolant pumps are first tripped, Steam Generator water level will first shrink (due to flow coastdown)

, av. -

2-ST-13 Page 6 of 11 Initials 3.0 Precautions (cont) and then swell (as natural circulation reaches equilibrium).

When complete manual control of auxiliary feedwater is begun, do not reduct feedwater flow below 40 gpm to each steam generator during the swell. (Until normal level is established).

3.13 After the Reactor Coolant pumps are tripped, the normal T,y and A T indication will become unreliable. A T and T,y should be calculated by taking the difference and the average of the hot and cold leg temperature indications respectively.

3.14 If the primary system pressure drops to a point where it is obvious that saturation pressure for the existing wide range  !

hot leg or incore T/C temperatures will soon be reached, the -

pressurizer heaters will have to be energized or charging flow reestablished to increase system pressure 3.15 NIS channels can be used to determine changes in core power level providing the RCS cold leg temperatures are maintained at approximately the same value that existed before tripping the reactor coolaat pumps.

3.16 Test instrumentation should be connected to a reliable source of power. .

4.0 Instructions 4.1 Shutdown the main control room air conditioning and place a room thermometer on the operator's desk to monitor control room air temperature.

2-ST-13 ,

Page 7 of 11  ;

Initials 4.0 Instructions (cont.)

t 4.2 Clear the auxiliary building of all non-essential personnel and announce over the Public Address System that a blackout test ,

will be beginning shortly.

4.3 Manually adjust Pressurizer Spray Valve controllers to zero %

output (closes pressurizer spray valves) and leave the controllers in manual control.

4.4 Ensure the pressurizer backup heaters will remain off by moving ,

control switches to " pull to lock".

4.5 Ensure Auxiliary Feedwater motor driven pumps 1A and IB will i not start on the simula'ted blackout by moving switches to the

" pull-to-lock" position.

4.6 Just prior to initiating RCP trips, reduce charging flow to the minimum required to maintain seal injection flow.

4.7 Isolate RCS letdown.

4.8 Close charging line stop valve MOV-2289A or 2289B once charging flow is reduced.

4.9 Record the data indicated on Attachment 6.2.

4.10 Start the Computer Trend printer printing at 1-minute intervals.

4.11 Record the time, date and initial the charts on the data recorders.

4.12 Start all three reactor coolant pump oil lift pumps.

NOTE: The following step should be conducted immediately before initiating the trips.

4.13 As quickly as possible shutdown the following equipment. As many people as possible should be utilized to complete this step so that a close approximation to a blackout can be simulated.

i

,~. .

i 2-ST-13 Page 8 of 11 Initials 4.0 Instructions (cont.)  ;

NOTE: Zero Time =

Check ]

a) Trip pressurizer heater control group.

b) Trip all three reactor coolant pumps.

i c) Close main steam isolation valves. '

d) Trip the main feed pump presently in  !

operation. ,

e) Place 25H2 (EDG2H OUTPUT BKR) in  !

" Pull-to-Lock".

i f) Place 25J2 (EDG2J OUTPUT BKR) in

" Pull-to-Lock".

NOTE: It will be necessary to realign aux. feed flow so that the turbine-driven aux feed pump is flowing to all three S/G's.

g) Place Remote-Local control switches for l EDG2H and 2J in Manual, Local position.  !

l h) Trip and lock out 15E3 and 15F4. (

(This deenergizes 4KV Emerg Busses.) ,

i) Trip and lock out 25B1 and 25C1.  !

(Bus 2A will remain energized to power a Rod Drive MG Set.)  ;

j) Begin monitoring and recording the parameters indicated on Attachment 6.5, Data Sheets at the intervals indicated.

l NOTE: Monitor reactor power closely and make any adjustments necessary ;

I to maintain approximately 1% power. T for each leg should be i maintained at approximately the pretrip temperature.

i

2-ST-13 Page 9 of 11 Initials 4.0 Instructions (cont.)

4.14 Verify the steam-driven Auxiliary Feedwater pump has started and flow established to each steam generator.

NOTE: Operators may be dispatched to take manual control of Auxiliary Feedwater and main steam power operated relief valves, if ,

possible.

4.15 Verify natural circulation has been established.

4.16 Bring the steam generator levels back to normal operating level (approximately 33%) and manually adjust atmospheric dump and auxiliary faedwater flow to maintain the pretrip cold leg temperature. (Establish a steady feedwater flow. Do not stop ,

and start flow to control the level.)

4.17 When equilibrium conditions have been established for each steam generator, make notes on Attachment 6.5 Data Sheets of the time and continue recording data.

4.18 Maintain steam generator level at approximately 33% and reactor power at 1% for a maximum of a two-hour period from the time of the simulated blackout.

NOTE: The pressurizer water level is not expected to rise above 80%,

however, if it should, put excess letdown into service to reduce the RCS water volume. Maintain letdown until level reaches 50%. (Note letdown established on Attachment 6.5 Data Sheets).

4.19 Adjust the setpoint dial on the pressure controllers to 2005 L

psig and individually return the power-operated relief valves to " Auto" control. ,

CAUTION: Let each steam generator come to equilibrium before putting the next power relief valve in Auto.

4.20 Return pressurizer spray controllers to " Auto". (Spray will not be available until the reactor coolant pumps are restarted).

..x-._ . . _ - - - - . . . . . . --

l 2-ST-13 Page 10 of 11 ,

1 I

Initials 4.0 Instructions (cont.)

NOTE: If the RCS pressure is below 2210 psig, energize one of the pressurizer backup heaters. Realign the applicable emergency bus to power the heater. Control RCS pressure by energizing or deenergizing the backup heaters.

4.21 Insert Control bank D until the reactor is in the hot zero i power test range.

4.22 Reclose 25B1 and 25C1. t 4.23 Reclose 15E3 and 15F4. I 4.24 Place EDG 2H and 2J Remote-Local switches to remote, auto  !

condition.

4.25 Return 25H2 and 25J2 to " Auto".

4.26 Return to normal feedwater alignment and, when possible, return .

to condenser steam dump.

4.27 Return all three reactor coolant pumps to service.

4.28 Restore pressurizer heaters and establish stable RCS pressure control.

4.29 Discontinue trend recording.

4.30 Establish normal letdown and charging and return pressurizer level to the ; 22% level.

4.31 Place Aux feed pump motor driven pumps in " Auto".

4.32. Announce that blackout tcsting is complete.

4.33 Remove the block of auto actuation of SI on high steam line AP.

J Completed by:

Date:

2-ST-13 Page 11 of 11 5.0 Acceptance Criteria 5.1 Core exit T/C temperature did not exceed 610*F.

5.2 Delta-T for any loop did not exceed 65*F.

5.3 Tavg for any loop did not exceed 580.3*F. ,

5.4 Natural circulation can be c:tablished and maintained with the degraded condition of a simulated loss of offsite and onsite power.

5.5 Emergency lighting in the plant is sufficient to operate criteial equipment in the loss of normal lighting.

5.6 Hot standby conditions can be maintained for a 2-hour period with criteial equipment operating off of vital battery power. i 5.7 Manual operation of auxiliary feedwater system can be coordi-nated by the unit operator to maintain stable plant conditions.

6.0 Attachments

(

6.1 Test Equipment Data Sheet 6.2 Initial Conditions l

6.3 Appendix A 6.4 Trend Blocks 6.5 Data Sheets l

f 4

2-ST-13 I Attachment 6.1 Page 1 of 1  ;

TEST EQUIPMENT [

DATA SHEET l

TEST EQUIPMENT DESCRIPTION

• MODEL NUMBER VEPCO QA NUMBER

- , . . I l

i i

-]

I i

i

?

4 8 i.

[

L i i 1

4 i

t

• NOTE: This applies only to temporarily installed test equipment or instrumentation Permanent instrumentation which is part of the system and shown on drawings should not be included.  ;

Completed By:

, Date:  !

J r e -w- m - - -

2-ST-13 Attachment 6.2 Page 1 of 3 INITIAL CONDITIONS Pressurizer Pressure -

psig PR-2444 Red Pen i e

Pressurizer Level  %

LR-2459 Red Pen RCS Loop 1 Hot Leg Temperature *F TR-2413 Red Pen RCS Loop 1 Cold Leg Temperature *F TR-2410 Red Pen I

RCS Loop 2 Hot Leg Temperature *F TR-2423 Green Pen RCS Loop 2 Cold Leg Temperature - *F  :

TR-2420 Green Pen i

RCS Loop 3 Hot Leg Temperature *F TR-2433 Blue Pen RCS Loop 3 Cold Leg Temperature *F TR-2430 Blue Pen l

Steam Generator 1 Level (NR)  %

(LI-2474)

Steam Generator 2 Level (NR)  %

(L1-2484)

Steam Generator 3 Level (NR)  %

(LI-2494)

Steam Generator 1 Level (WR)  %

LR-2477 Pen 1 Red Pen Steam Generator 2 Level (WR) __

LR-2477 Pen 2 Green Pen Steam Generator 3 Level (WR)  %

LR-2477 Pen 1 Blue Pep

2-ST-13 Attachment 6.2 Page 2 of 3 l

INITIAL CONDITIONS , ,

Steam GeneratortPressure ~~- - - - P818 PI-2474 i

Steam Generator 2 Pressure psig l PI-2484 '

Steam Generator 3 Pressure psig PI-2494 0

Steam Generator 1 Feedwater Flow X10 #/hr (FI-2476) ,

0 Steam Generator 2 Feedwater Flow X10 #/hr (EI-2486) ,

0 Steam Generator 3 Feedwater Flow X10 #/hr (FI-2496) 0 Steam Generator 1 Steam Flow X10 lbs/hr (FI-2474) 6 Steam Generator 2 Steam Flow X10 lbs/hr ,

(FI-2484) 0 Steam Generator 3 Steam Flow X10 lbs/hr (FI-2494) '

Locp 1 Tavg protection *F (TI-2412D)

Loop 2 Tavg protection *F (TI-2422D)

Loop 3 Tavg protection *F (TI-2432D)

2-ST-13 Attachment 6.2 Page 3 of 3 INITIAL CONDITIONS Lc6p'~1"AT protection  %

(TI-2412A)

Loop 2 AT protection  %

(TI-2422A)

Lcop 3 AT protection  %

(TI-2423A)

NIS Channel N-41  % .

NIS Channel N-42  %

NIS Channel N-43  % l NIS Channel N-44  %

Attach a copy of the computer printout of the Incore Thermocouple Temperature map. ,

Temperature in Turbine - Drive Aux Feed 'F Pump Room Control Room Temperature 'F Outside Temperature 'F Completed By:

Date: -

9

. es u.4- + =,e *

• 2-ST-13 Attachment 6.3 Page 1 of 8 APPENDIX A Outline i

I. Core Power Determination A. Primary Side Calorimetric (Forced Circulation Only)

1. Reference ($500*F) Calorimetric a) Output used to adjust M/D Power Monitor Program's power conversion constant.

B. M/D Power Monitor Program

1. Power Conversion Constant Adjustment.

a) The output of the REF primary calorimetric will give a

% power output; this output must be input to the M/D Fower-Monitor Program so that the program output will be in percent power and equal to the primary calorimetric output.

2. Power Monitoring a) The M/D Power Monitor Program will calculate the integral power as seen by one pass of 4 or 5 detectors. After the output has been calibrated to be equal to the REF primary calorimetric it will be rerun up to on e every 2 minutes or as necessary to continuously monitor core power.

h t

{

4 7

j t

9 6..-. 13  ;

~

A :a:h.e.:' 6. 3 I

- .s,.e

, .1

.4

. 3 i

t t .

l . ,

% . a...3. . A a ...,. s. , . .. . . ,

....p........ >

... ..n.....

i.

3  :

I'

,.y. . ; .. ..e_ ., ., a

. .Jg .,

• ..s

.y . 4. .

.g . g . gg...s.. .

. . . . .; . .e ... . . ...* ,g . s . ! [

r i . = *

e.. 44 4 . . . .. s.. e.S ..

113..... t .s..&

. ..c. .

333 1. . t. a .. t. s . .,.

. . . s. .. 3 3., t 4..J .s 4.J

[

i.

s.

. . e L C . .= C.r . .

.. .,.4 .a SS p , 3 3.* 4

• d.,. . &

1

= * .

.g.a

. .., . < , t.7... . *.. g . f =. . ., . .. s.. a g. .a.

+

i s.. sg .t ..-. . , g . .. . . s. g .A . ., 3.,. < e..s. e s.. g g ..

4 j .'.e 'Je s. d ...' .. .s a '. e s . a s ._d a .a. .'* .. . v 2.u c'. .~.~.a ..-.a a.=. . .-.s .e ,.e.2.~..-a 1

(Tab's A-1.). (!;eC11. Tas: W. 9 c.sas .if.4 s ;a A so a i

.., e .a .

s 1 ..... .> 3 . , .g , a. . , , . e ., z . g

. s . . ... . s . ,.._, ,. ,g.s..,

. . . .. .... .>,. t

.o

. A.,..ey .. a..>

. .a c. ..= ...,}. >

P

, , b

. . . e. . ..- . . ..g

. . ., .s. .

. . .. .g.,, 1: 2. . .a.n. .. . .

.. g . g . , ... .. .... .

s . . . . ,. e .,. g .. . . . , . ,

u..r..

. . . . . s.s ... s. s.: . . .s . ,z .. .. , .,

l b

. i i

I 1 >

l i-D q

o'D 9 3  !

t e 5 - e i l

i 4

I

=

b I

d f b

i i

F i

1 h . t f

f f a

. i I

t"- a l e l

f i,

a l

i 1

f 5

s y . - ye ,- , -=.7,e- -q r - - ,, , y-- - , , , ,. -

4

, ,__.7__...

2-ST- 13

... ..1..

pt. . . . 43. . .3 PS79 J .3 .,

r* ; .; &.s 5

-.. a a...... ..J ,.4.)

.'w. ..

a *

. . . 4 s ~. 4 . 4 ...- . .. . .. 1. s. .

O .t ".".

. - 1. .

• f .'. M.

. S .. 4

... .v. . e.... . . . ..... ....

.4 . ... .. '.. .A.... . . .%L . .= t .ai.S . .... ... , .-.e.., .3 . . .

s. L *

. y 3e3 . e A ..

. . a. L. ...

.y

- a *

.s *. . .. .4,. , . 34.g ... .s..... . s. a . +. .. .. . , g g3 ,. g ...t. . . ...s. e.g

. 2. e

%. 4.? .. . .1

. .s .... :C . ar.

• • .t

.... 1e. 3.1.%.. . e...

3. '3 3. 4. . 3 C o... _ .r 0 C 1. m. a .3 3

C 3

?. ,

~.. ggg . .g 4....e f

. g ,g.y %. g g .' ...

. . g ,.3 '.; . . , '...a.. .SS a...ag.. ge.e, .  %. gg gi.s n..r s.3

.=.*..g=. .a r .*3~4 ~ 3=. ~~ g g6.s-. ~. . g g n .a =4 . . g~. - j, ...i7 3.s~====.

. 4 , + . g *~,. . --- 4.

. 4 r=* ** ~.g3 s 4.m-r I e- A. 1 * - . -

3 *

a. .;. 4,.,..... ..... . . c. s .o.

. =. d... 3. . 4 . 4 .s.e

.. a .

.E.4 ...

.. 3_*4 a.J. . 3 1

. . . . . ...a . .. ..

...a*r-

. ' . . . . . .s3 4 * .... * .. .S. .

• *

• E .* A a' 2 ',  ?..*..*.*'.* . , .. . . * *. d ... *. 3

• b. .. e. * ' .'s 8.*.

7. . .. ..b.S 1.4.J. . 2 5.+ 4 3 a-b . . a. . . . d.==.

A . ... s. . a g. 4. .,J .

• t

. .- .. .. g . .- .s ., g. u.

• 3g.g.... .... . . g. ..: .. .%.43

. 34 . ..

4., ..

32 . . . ,

. . .. .r .f g.. . g g .t ..... , ,. . ... . g. . .s... . s. ,. S 3 ,. .. ..

.-.....,a...,. . . , ..

1

. . . ... .1.

. ...-1 .

. . s. t . A.

J . S ... , . . . .. . . a _* d 4 .. 4.

. . 3=.$.

. _. 3 ...J..

• . 1

., 4 f.* .., .e . s*. . .* .

,. . . . ..4 .... 434 .s...... a....... . . . . . 2.= .a 1. o.. .

. . . 3....4 . 3 . .

o. ... .%.a

v. .e, .. 3 a.

4 J ... .. . 4. ..i . . 3. .s. .?4 . %. , 1 . .%. ,

s.,.. -a... t m. = .* .t a

. .a .a. . t $ $ om. <.. . 3 . . . .. . . . . .

D**]D

]DO hwN o NUS J =

-... .m

~

. .- . . .$ 3 e g=.........3 a.. .%.

rtie s. 0,. : -

.k.$ ...e 1 m. **.n * / *. .. .. d_.

. . , . . , 4 C0:s .*-.t C e: a::d. .2:1:n v..*... .. .. . .....4a.s, f

4 1.t .a **

'.* g ..

. a .s ;.. ..g..

. . u. & 9

. .9 m ., g ., R...a . ... ..J.,;... .s ..,

. . . . . .s ...a. .

.e ..

..  %. .= a s g.f g . ..%. g p ... .., . e . .y g a ... g g. .... . w 3. .s..,.

. . . .  :.atg

. .. ._ .s.a g.;... . ag.,.. g .. ... ...

• • pda:a

. A4 raqu' rad.

Addrass **alua

.  ?.....d....

. . 't K090 *. '. ae. .... - .e.2.. . .. . e . 1. .e . . . e ,. . . . .sc...

.. s .

z e ., ..a..... s . .e .-..

. u..a ,. a.

yJ 325 t

. a ..; . ._. v. . se e. u._ ..

.a ..,.2...,

C900 0 ...e.e.1.e.

a 3.1ss e..- ... ..

C1. < ....s . s .... .

.. s.1 ... .a..

. . u.s, ,

K0ss; g . <. . ,. ( -. )

. 3. . 3. . v..s... .

/'T s-a.... ...e.4.s. .

• 4 .$. .T &.* . . .- 1....&.J

.. .ss& 1.. .a. . . :... ., s. .. . :41. .; .a. 4 ..- . . s... 4 .. s.

. s.e..S .A

.. . S. ;.. t.. . (f.,

. . . . b. .C .oA.L m

. .- ,t.

.. . ...s

...s. S v.. ../*e c1.' . . '-1.., A. .e e.... s. . / **Cr. . ,=. *2 )

.a

.. as .s.e ..

. ... . . 2.4..e. < .a.,;

• (K025'). # :: iz'.ua

• as ::es: en:arad :. :s (K 561) a::4:

0.25.

i - d2 :t:a shee- c.1 521 (K".36'.) = Curra.: (K056.'.) x (?.0905 ) .

. ... ... .c ,. ,. a. .. a . s . a . . . a

. ... .-.. , . . z .a ... s ,. n. . a 1.,

. .. ..n a,

e.a M/D's need .c: ha '.:hd:2. Se:;se: ; asses, med passes :sy be

...,.es.a; , ..a.e g3 g

.. . . ., . . .g . . : .g .. ., a :2... a . .s.,,.....,) . . . . .

... .a..........a..,....

. . . . . . . ...  :..e

s. r. e. s- ). . ,.

. ..a....a,. a.a.e . ez . ,, ass t.a.

_,3.,

. .st . t .2e. .,. ...,.

. . w

..w a.

. .a ,. , .a . ., .a . . .a a.s..

. . . a..a ..g a . ....

.s.a....

,g. .< , a. ... , . 3 _3 3.,

. g.3 ,. ..a... . , a. .

..__n... . _ . . . . . . - - . - -- - ~ - - - ~ ~ - - ~ - - - - - ~ ~~ --*~ ~- - ' " ' - * " ~

L l

o

.  :-s!-13 Atta:h: e-- 5.3

. a ,

, r&q9 .2 ..

t g; T. u. , -. *

. . a J. s,

. . .4 (w..

, . .. . ._4

. . . . . . t

• .'* g ( *

• n.r

.g se

- .: .a.,.

~, . . . _ o .:- ..

. ..._..../ .,

I t 355 1.250 3.644( x 10 ,

l

<* 4

' 255

.. 3 . ' .*. .* 3 '. .' O '

7

, .e 3.- .

.t . .,. 0 3 . *. d .t 9 . .' "s

.0 ,

..43,5

. 4.,. . , ... .3 3'3 ' 40

.. 2 . .* c' A. ..' ... ' ' . ' ,

.e . o" 1 914 ,

. . ..cada...s e ...

5 4.'. '. 23 1 3. 703 7 x 10 '

, ... ....$ .. 2.1.33 x 0.s

,.,.. ., . ..., . . .s_ .v ,.,

j i

.c v. .....

2 ,e.

., 4. . . . . e 3.., .. 2. . . 3, J

.o , ,,,

. . . . , .. . .; .c ., ,.

1r

<.* 7

.. ...e.9

.. 3.a .. . 0

,. , ,, . ..e

.... ... e 3...,, , 2 . ., .. ..

9

, .. . o

.v ...... . ..s... .: .

.. .ns ,

b

'~' 7 e..s a e:has are f::= : a ' '5 7 ArG 3 :a::: 7/i: .es . 721..as a a f-2 ;; ass :a

., .a .... .s t .

5 i

I E

D*n'II, D D 3 . 3 .

r o

@ 4-/ ) .Q - "'

M q.n.r.p$ E$. , .

.I 1

V

, w]hn\tM w m .0  ;

. a , ,

g I l s

. 8 d

• t

' l 6

, . l -

6 J l L .

i 7

i

! l . . . ,

, i .

F, 4 l' s

O e , i .

O l f b

M E g L M  ::

i  ?. e . l h$ h l "

5

'.' a ** $ 1

- c i e r < L

• i t I

! e

- l 1

j .'

1 l l ,

."L i t I g ,.

g

., e E l "f I g .

==. +

1 1

! t l I

~

A a

= l * ..

t .

h A, 2; l

~

l Et ~~~ =

-= . .e 1 Oi >Oz -

- 4 . I -j al -e he l l ml C 'i ==t 24 2 9 e s 1 tr . i Og 4 , e c l, 1- E U U g g

r , L '

p, -O- Of -=

g. .  :

v .

. 2 8

: =. -

N, G J l g O' > j =

< u . ,

. W

=

f, W ad -.

, .- .C.

. == = t.  : .

t

• 0 <j =

l = 0 ^. -

4 L

-4 c' -:;  :

G I

! , L 8

== l -.i 'J l

< 0,8

. 1-=

^e N' f a 1 rf m  : I

.J 4 E & %f A @ b  !

f i

g O. l. .e h .

w; Ot NI mg

w. l f I .v. I < is t e O. j I

cl .,o;. dw .a Ot I

. '. l us y w N.  : *1 l

- l t

v.

ci I ==

.: . f ' % "'*, ! O[

%~ -

Mj

= l i

' ^ W M ""N l l

6 Eh v

e* .

si:

. ,. ~.

2 o

j 64 =

Es 6'. .2 Cl V.

> x[  :. w- => e i, 1 a g

i

fo=s k c

e x l' q - i . T;u;u W.

3 ~,

si :

- : il v 1 u

4

- l =,  %  % , u, ,

F

-wt. == w V, 34 L k 36 c'  :: U :l N  !

l

+

a t i tj

• a !

b {' b:-

.e : W :'

0el 3.

. w o i

-j

- bl b

:* f, wl C{ .:" ;.l

&=l l hf u I

c. --

. , y c. =  ! bt, el  : ,

f *Ji N:  :  %  %. '"* !  : G1 d l

. l

'e ::' :# # 1.

EU E':.

N- 3:

i 3  !' '.

i

- --.i s .:

i -i

.. ..g'-c .0 -

-s N.!  :

4 8 s . .

i I

t I e b

. 1 I [

s .:

s t e n

. s .

i .. . ,

t .e .. .-

D < b go t .  ; '

= a = -.

E U

L ==, N' j

.* h* .: "'= 2 ~l 4

^

• J -[- -

O

. , . t' {. e 6 i 4 8

, j i - L T O I 8

. l j ' ' V  % O l l

. , _ . , - . - , - - - .-.., -- A_ . - - - - . . . . - - . - . _ ~ . . . ., ..._... ~ ~ ....- _ _ w.. a

..:. 13 A *,*. 3 0'.".'". 9 5 0 b**4

. s ."

?3:4 .

/ C.

75-

.h. e. ?.

a n

(a ..<

. . . . . . . .4;./

+

. A..% .; ._.

.m =. M.3 .

. ... . = 3... . = 0,. =

- \

- 0.I = -

I,

=

A.

• w

=

_ 1. = _. C, =

. 0. =

. I, =

= ,

.4 A .0 N. = A.1

. =

IA/*? =

J.'.~

.6 Y.,I .

se

.s.

e. =%.a = .6 31 1 =

9 .

e... e 9 a

%s$.

.t. =..I f = uC %,

v.

=

d d..

1 dI .

I 2 .* %

. .y a .

'm- de. .

7 _

=,I.

.?..

.4 QA O D D g@' W .2'  := ,

.%4.J.< .. . .4 . . 3 r.. e 1..' s w.a 3..e

.g a y

. *e.

.' .8 =. 3*.

• - d #*"

• M--

• 2 " * **

• 4 '3'*

• 1 *' #**~

i 2

.a.a . .. ... ..

4

& .. . . 1., **"".*.3*~*~'~.*

. 4 J '?' *** ** 1 ** *I*

a. .. . .... . . .a.s 3 ..

f eesa.

~

1. . .

=

.a . .

=

m. =

. . .... .. .g.4

• 4

3. .a ...g6-*- ...* s...

=

,a. g. . ...

g e. . . .

t. g. a. g..3.....

3.m .'. g?. s. -. 4. w ..

4

..,s... . . .t . .,, 3 ,. . .. ;

f 133.

. . . . . ..t., s.e ... e. 3 , s.p . m a a d 4.1 ... . . ..

.w  :. . . . 1.* .a 2 . < ...... .J., ... 2 ., 43 ,..

2.,....

t.4 2:"h3:

~ ...

~ A.4 ..

. I5

~. -.

2 *- 13 .

n.....n <.. ..e ... ...  : ,

.a 2.1.s a .. .

A.3.

. .m

, . < . . . , 2. )

1... . .

.s. .

...a.--......,......a s .. . .

. .s .a .. . . s ... u.

.. . ... s ...,. . . . , , , s , . s .. , as. 5, ,-.- -..u...<-..

. . .. .. . ........, .s

-.a.. . . . ..-......1 . . . ....s e.. s .<a.s

.,.1....,, . , 1. a s .a.. -., .. ....._.,1s .

...,a. . .o...,.. e ,. ,,

. . . 3. ...u. ..-..s . .,,.. . ss... s. -. . . . .. . .s

..1a.1..

,. ., . s

(.s g.. . ... .,. ..a

, . .e s .a. .a t .. .n 1., .. ... ,.--. . .<..sy .,,

. . . . s. o.: ..

. .a .s

...,2

. . . . u. ,. . ... . . .a.-. s a. , a. .

o ;.;.t ,

g. .a.e.. s., ,

., r,

. . . .. .u.a .s. .. t a <- :1 . ..... 3

.c eg. 0, ._u..

.. 1.,s.. .. .u.e ,a.s...s2 .. .o .. ., .A . .< s . .-.,. _. ,., . u. ., ,. .

C'3 *. - 0.0~5, C::a 's7 as s :v ':1::'.:n  %

M C ' 's = .; , '. =. .' Ls ~_*. e ..+.- . uo.. .' s 3 . .- ~3 . _< ~ % u

~

.., a 1d ' ~..~ s . .' ' . a..~. ..~. c ~. t.. . _' a s 1, . ..... .>.. .s -. n.,,... g . aS-..... s .a .- . ,. . 1,- .--.. .. 1 6_ - . . <,_. ..2..,. . . >.s

. .... ,,.... .a. . ,. . ... . . .. ... .:ns

.. . n.s3 e.,. ..a .. . u. , ...,.-.,.,_.,v.,.g.a..

3....,_...g..

. _, ., . . . . v. 3 se...;s

.- . . . o. : ... s e ... . ;. . s .m .. . . .. t

. . . . . .. .,.,, ,.,..._3

u. . .,32 .. u...,. . ..

.. 2...

.. . _ . . . , . , , . . 34

.  ;..e.s' . s., 2 .,e

. . - - q. 12 1 . s ( s ,. ,. .;...,.... :a3,;.. . . c.

. . 2. .1 . .s - ' .-..,..

s. . . s; . ., . . ,. ...

. s >..<... . . . . .../ . .. ...e-,.,.2 . .... . u. .. . ,.. ....o,s.,..,,.....-

... . . ... ., t . .. ag.. g.

. . . 3 -. . , ,z _2, s. , .c .

. .s .,a.a.., .. .s . - . ..s 1 a s~ .a a 1.s. ...,

.a .,c..e.

u -.

s..s a. ,. .>- s ...n. . .a u.e ..a ;,2..... s..

2.--...s-,..,.,.

er..- .. , . .. . -. . . . ,

.. 4. . .,. . . s.

......;. . .e.,2....<.,.

..- 1a s..aa s z- .. s .1 ..,s 1 ,. . -...

. .a .:- .1. .. ...< . .s 3

,a ... .L ..a. .1. . n al.,e.s,%..,..

... n. 1. . . ,- . . .

_? r.*- *. . z a.

6 .

.s .. *s:9

. 1

..... D ., .

2 w

o u . .. . s,.s V. - -

. ..,.g.

> s ..a 3 .....a.

. s ....... .. ..

o.1, s .u., . .. . . : . a . .. ,. .a.

. g.a .--. . . . ,. . . . , . .... .,..ss. s... . . . ..a .,s.

g. 4 .e.... u .. -

, _ ,. . . e a s _ . _; , . 3.. .. ... . . .. ....

.2 . . ,

. . . - . . . . ... --..c......

... .... .. 3..e ... , .. .. .. .. ..

u s ...g .,.. ,,z,.g a .s ,.e s sa.u. .a . .. .,.. ,..uc

..,...<.,...,...a..,

v. .<. . . 1,e.....

- . . . .. , a s , s . .. .. .. .. .e. ..s .n ...

. 1.....s .u......., . ......r.. -r , s.

.,.. ...,.: .... .. .. .....,...,.2.

. < a 1, s a . . . .. a.

. . . . ..e

.,.....,.a.

..a...

.. ..<s n.. .. . ,.. ,..2 . .: .... ., .. .,s..

=

- - - . - . . . - - - - - . . ~ - - -

2-ST-13 Attachment 6.4 Page 1 of 2 PROCESS COMPUTER TREND BLOCK A COLUMNS ADDRESS PARAMETER UNITS 1 T0406A RCL A T COLD 2 T0426A RCL B T COLD 3 T0446A RCL C T COLD 4 T0419A RCL A T HOT 5 T0939A RCL B T HOT 6 T0959A RCL C T HOT 7 T0400A T A 'F AVG 8 T0420A T AVG 9 T0440A T AVG 10 T0403A AT LOOP A  %

11 T0423A AT LOOP B  %

12 T0443A AT LOOP C  %

13 F0128A CHARGING FLOW GPM 14 F0134A LETDOWN FLOW GPM 15 U1250 HIGHEST REL FUEL ASSY PWR ,

16 LO480A PRESSURIZER LEVEL  %

17 LO112A VCT LEVEL  %

l 18 U1251 HIGHEST REL ASSY P'JR INDENT l

l

2-ST-13 i Attachment 6.5 i Page 1 of 3 DATA SHEET 1 Record the following temperatures at the indicated intervals.

Turbine Driven Time Auxiliary Main Control After Trip F.P. Room Room 15 mins.

t 30 mins.

45 mins.

60 mins.

75 mins.

90 mins.

105 mins.

120 mins. l After test, record Outside Temperature 'F. ,

Completed By:

Date:

l l

l a

t i

VV I

c- -

a2 v

0 s 2 u 1 B l

a t

iI VI I c-a2 v

0 s 2 u 1B l

a t

i VI I

c-5 a2 v

6 0 s 3 2 u t 1 B nf s eo e 3 m s 1 h2 s l

- c u a Tae B t  : :

St g i y e

- t a l V B t 2AP a I a t c- d D i a2 e V v t 2 0 s e c ) 2 u l T a e 1 B p E v g m o

E a H 5 t C S 2 l V 1 o CI A V D -

T d ( 2 A n v D a 5 s 2 u y 1 B r

e t

t I a I B CI D -

V 2

- v 5 5 s 2 2 u 1 1 B I

CI D - ,

2 v

5 s 2 u 1 B C1 D -

2 v

5 s 2 u 1 B

)

(

T ly O. . . .

eB . . . . . . . . . n n n s t ag n n n n n n n n n i i i l n i i i i i i i i i m m m ao in m m m m m m m m m ii di 0 0 0 tt ii ew mo 0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

0 9

0 1

1 1

2 1

nd ml I n Il + + + + + + + + + + + +

o o C F T T T T T T T T T T T T t

t l .! ' 4 l !' (  ! ll !i i ' l ,

y r

e 2 tV H tI a

B m o .

Vo .

- R p 5 m 2 e 1 T y

r eI 2 tI H tI a

B m o .

l Vo 5

• R p

• 5 m 6

• 2 e 3 L 1 "

t nf 2 eo H 3 m 1 h3 &

- c Tae s  :  :

St g e y e

- t a ) r B t 2AP d u a e t d D u a e n r t i e e t p y l n m r p o e e 2 m C T tI H o

( tI C m a 2 o Bm o o .

T R Vo . m E - R p o E y 5 m o K r 2 e r S e 1 T t e A t t T a a A B l D i l t a r t e i v V ,

V l

- e 5 v 2 y e 1 r l e 2 t H l tI a a c B m i o t Vo . i r

- R p 5 m c 2 e 1 T s e

h c

a o

r P

P a

2 H

n n n f n n n n n n n n n i i i I s i i i i i i i i i m m m n m m m m m m m m m o 0 0 0  :  :

li 0 0 0 0 0 0 0 0 0 0 1 2 N s at 1 2 3 4 5 6 7 8 9 1 1 1 O k ii I r td + + + + + + + + + + + + T a i n U m no T T T T T T T T T T T T A e IC C R 1  ! l!'

h. .

'j ' i!  :! '  !  ! ' i

.l'