ML20205A235

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Rev 2 to Emergency Operating Procedure EOP 572, Reactor Power Control Emergency Operating Procedure
ML20205A235
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 01/13/1987
From: Kraemer R, Palmer R, Romberg W
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20204H467 List: ... further results
References
EOP-572, NUDOCS 8810250431
Download: ML20205A235 (8)
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W. 3. .ior.cer; 3-11-36 86-9 Form Approved by Station Superintense'7it Effective Date IDEC Mtg. No.

STATION PROCEDURE COVER SHEET A. IDENTIFICATION Number E0P 572 Rev. 2, Title Reactor Power Control Emergency Operatina Procedure Prepared By R. Kraemer B. REVIEW I have reviewed the above procedure and have found it to be satisfactory.

TITLE SIGNATURE, DATE DEPARTMENT HEA0 /.1. f ///J/89

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[ Y C. UNREVIEVED SAFETY QUESTION EVALUATION DOCUMENTATION REQUIRED:

(Significant change in procedure method or scope YES [ ] NO W as described in FSAR)

(If yes, document in PORC/SORC meeting minutes)

ENVIRONMENTAL IMPACT

[Kdverseenvironmentalimpact) YES ( ) NO W (If yes, document in PORC/SORC meeting minutes)

D. INTEGRATED SAFETY REVIEV REQUIRED (Affects response of Safety Systems, performance YES ( ) NO ((

of, safety-related control systems or performance of control systems which may indirectly affect safety system response.)

(If yes, document in PORC/50RC meeting minutes.)

E. PROCEDURE REQUIRES PORC/SORC REVIEV YES [ g NO ( )

F. SAFETY EVALUATION REQUIRED YES ( ) NO ((

G. h SORC APPROVAL SORC Meeting Number / . c) 7 T _

H. APPROVAL AND IMPLEMENTATION The attached procedure is hereby approved, and effective on the date below:

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Rx Power Centrol E0P 572 Rev. 2 Pag 3 6 i I

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( 3.6.6.2 E no CRD pump can be started THEN GO T0 step 3.6.7.1 of this procedure.

3.6.6.3 Shut CRD 301-25 ,  ;

3.6.6.4 Shut CRD 302-8 (CR0 drive water PCV)

AAAAAAARAARAAAARAAAAAAAAAAAAAAAAAA2ARAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA CAUTION Bypassing the Rod Worth Minimizer may be required to accomplish this step.

AAAAAAAAAAAARRAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAnAAAAAAAAAAAAAA 3.6.7 Rapidly insert control rods manually until all ,

control rods are inserted beyond position 04.

3.6.7.1 E any control rod is not inserted beyond position 04, THEN individually direct the effluent from M I;F102 (CRD withdraw line vent' valve) to i a floor drain and open CRD-F102 for each ,

control rod not inserted beyond po3ition j 04.

I WHEN a control rod is $ moving inward, t

THEN shut its CRD-F102 (CRD withdraw line vent valve). l WM:j1c I

FINAL O

ICP 57 h 'cwer "unt e

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Rx Power Control E0P 572 Page 1 Rev. 2 l i V

Unit 1 Reactor Power Control Emergency Operating Procedure l

PAGE N0. EFF. REV.

^

l-6 2 ENTRY CosCITIONS:

RPV water level less than +4 inches RPV pressure gnator than 1045 psig Orm11 pressure greater than 2.0 psig An isoletten conditten esists which requires or initiates e reacter scram A condition which requires a reacter scras and reacter power > 3E er carra ,

not be detersined apa osarettvts Place Mode

$ witch in shutdown Insert redundant scram Reduce power l Runbact Recircl i

O i Trip Recirc (2) Reduce power m inject Seren at 110'F pool temp. Shutdown reacter Insert Centrol Rods Dy:

De energite seiereies ,_

Vent air header marwat scras shutdown reacter Manual insertien v

[ScrasProcedurel Re ferences: 1) Emergency Procedure Guidelines, Hillstone Unit One

2) Emergency Procedure Guidelines, Appendix 8
3) Emergency Procedure Guidelines, Appendix C
4) ACP-QA-3.02, Attachment A
5) Emergency Plan Implementing Procedure EPIP 4701 l

SOP 572 "x *awer control l

l Rx Power Control E0P 572 Page 2a Rev. 2 -

SYSTEM ISOLATICNC Group 1 - RPV Low-Low Water Level (-48") MSIVs

- Main Steam Line Hi Rad (7 X NFPB) Main Steam Line Drains

- Main Steam Line Hi Flow (12C%) (MS-5,6)

- Main Steam Line Tunnel Hi Temp (200*F) Recire Loop Sample Line

- Main Steam Line Low Press (325 # in Run) (SM-1,2)

Iso Cond vent to Mn Stm Ln (IC-6,7) ;f Group 2 - RPV Low Water Level (+8") Drywell F1r Drn (55-3,4)

- Drpell rit Pressure (2 psig) "

Eqt Orn (55-13,14)

Vent (AC-7)

Vent Relf (AC-9)

Drywell/Supp Cham Vent from Rx B1dg (AC-8) l Orywell Vent to SBGT (AC-10) '

Supp Cham Vent (AC-11)

Vent Relf (AC-12)

Supply (AC-6) .

Drywell Supply (AC-5)

Orywell/Supp Cham Supply .

l (AC-4) '

CS Group 3 - RPV Low Water Level (+8") RWCU Sys Isolation (CU-2,2A, g i 3,5,28) l S/D C1g Sys Isolation (50-1,

! 2A,28,4A,48,5)

Rx Head Cig Isolation (HS-4)

Group 4 - Iso Cond Line Hi-Flow Iso Cond System Isolation (1-IC-1,2,3,4,6,7)

I C0P '72 0x Dawee control

Rx Power Control E0P 572 Page 2 Rev. 2  ;

O U 1. PURPOSE ,

The purpose of this procedure is to shutdown the Reactor using eithar control rods or Boron.

2. ENTRY CONDITIONS 2.1 The entry conditions for this procedure are any of the following:
  • I 2.1.1 RPV water level below +8" inches, 2.1.2 RPV pressure greater than 1085 psig, 2.1.3 Orywell pressure greater than 2.0 psig, 2.1.4 An isolation condition exists which'requir.es or initiates a reactor scram, 2.1.5 A condition which requires a reactor scram and reactor power is greater than 3% or cannot be determined
3. OPERATOR ACTIONS O For Rx Plant degraded conditions, refer to EPIP 4701 for Incident Assessment and Classification.

While executing the following steps:

j, IF,all control rods are inserted beyond position 04, THEN terminate Boron injection and enter ONP 502 "Emergency PTa'nt Shutdown."

IF the RX is shut down and no Boron has been injected TRto the RPV, THEN GO TO ONP 502 "Emergency Plant Shutdown."

3.1 Confirm or initiate a Reactor Scram. Perform ONP 502

Emergency Plant Shutdown" concurrently with this procedure.

_ _ 3.2 Confirm or place the Rx H0DE SWITCH in the SHUTDOWN position.

O E0P E72 1x % e- Control

- Rx 90 wer Control E0P 572 Page 3 Rev. 2 O

D 3.3 E the Main Turbine-Generator is on-line, 4

THEN confirm or initiate recirculation flow runback to minimum. ,

NOTE Premature tripping of Recirculation Pumps may result in a pressure / level transient of sufficient magnitude such that a l Main Turbine and Rx Feed Pump trip could occur .f 3.4 E Rx Power is above 3% or cannot be determined, THEN confirm or initiate Recirculation Pumps trip, and push the actuation buttons for ATVS Train A and C or the actuation buttons for ATWS Train B and D on CRP 905.

Execute steps 3.5 and 3.6 concurrently.

RAAAAtaAAAAAAAAAAAAARRAAAAAAAAmaAAAAAAAAAttaAtaAAARRRAAAAAAAAAAAAAAAAAAA CAUTION Manually trip SLC pumps at 0% level in the SLC tank.

AAAAAAAttAAAAAAAAA22AAAAAAAARRAAAAtkAAAAAAAAAAAAAAAAt2AAAAAAAAAAAAAARRAA NOTE If Baron Injection is not necessary at this time, the operator may go directly to step 3.6 and carry out those actions

, 3.5 g the Rx cannot be shut down (all control rods inserted begond y postion 04) before Suppression Pool temperatu,'e reaches 110 F, i

THEN initiate the Standby Liquid Control system as per OP 304.

. 3.5.1 E the Standby Liquid Control system is initiated, i

THEN prevent automatic RPV depressurization by I depressing the APR Timer Reset pushbutton and CONTINUE to reset every minute UNTIL, RPV water level is > -48", @

Drywell pressure is < 2 psig and the "High Orywell

]-

Pressure Reset" key is in the reset position, @

All Core Spray and LPCI pumps are not running, AND the "APR Aute Blowdown A/C Interlock" alarm is clear.

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e Rx Power Control E0P 572 Page 4

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Rev. 2

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NOTE Consideration should be given to removing the core spray and LPCI Pumps' Breakers' control power fuses located in each breaker cubicle to prevent inadvertent starting of the LPCI and C.S. Pumps.

NOTE Recall that when Boron injection is required, E0P 575 "RPV Level /Rx Power Control" is performed concurrently with steps 3.5 and 3.6 of E0P 572 "RX Power Control" 3.5.2 E Boron cannot be injected with SBLC, THEN inject Boron into the RPV by one or more of the alternate methods: ,

3.5.2.1 CRD 3.5.2.2 F.W. system (OP 316, sect. 7.10) 3.5.2.3 Hydro pump into SBLC (OP 304, sect. 7.6) 3.5.2.4 RWCU (OP 303, sect. 7.15) x")

- (~'s 3.5.3 IF Boron is not being injected into the RPV by the ECU system, i

THEN confirm automatic isslation of or manually IsoTate the RWCU system.

t 3.5.4 WHEN 470 pounds of Boron have been injected into the ~

RPV, (SLC Storage Tank FINAL LEVEL ,< 14% on CRP 905) c i

THEN GO TO Og 502 "Emergency Plant Shutdown."

l 3.6 Insert Control Rods as follows:

3.6.1 E any scram valve is not open, THEN set the INDIVIDUAL $ CRAM & SELECT SWITCHES on CRP 916 in the center (SCRAM) position.

3.6.2 g any scram valve is still not open, THEN shut 1-IA-58A and 1-IA-5SB (scram air header supply valves) AND open 1-IA-200 (scram air header vent valve). ,

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E0P 572 Rx Power Control

Rx Power Control E0P 572 Page 5

- Rev. 2 h

U 3.6.3 WHEN the control rods are not moving inward, TEER place the INDIVIDUAL RTtAM & SELECT SWITCHES in the up (NORMAL) position, AND close 1-IA-200, AND ,

open 1-IA-58A and 1-IA-588.

3.6.4 Reset the Rx scram 3.'6. 4.1 E the Rx scram cannot be reset, i

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THEN start all CRD pumps. {

3.6.4.2 E no CRD pump can be started. .

THEN GO T0 step 3.6.7.1 of this procedure. ,

3.6.4.3 Shut CR0 301-25 (CR0 charging water header ~

.L valve). -

[

3.6 4.4 Shut CRD 302-8 (CRD drivewater PCV)

RAAAAAAAA4AAAAAAAAAAAhAAAAAAAAAAAAAAAAARRAAAAAAAAAARRAAAAAAAAAAAAAAAAAAAA

, CAUTION Bypassing the Rod Worth Minimizer may be required to' accomplish this O step.

222222222A222222A22222AA=2222222AAAAAAAAAAAARRnRRARAAAAAAAAAAAAAR22222222 r

3.6.4.5 Rapidly insert control rods manually until the Rx scram can be reset.

3.6.4.6 Reset the Rx scram.

3.6.4.7 Open CRD 301-25 3.6.4.8 Position CRD 302-8 (CR0 drive water PCV) in the throttle position.

3.6,5 E the Scram Discharge Volume vent and drain valves are open, THEN initiate a manual Rx Scram.

3.6.5.1 E controls rods moved inward, THEN G0 BACK T0 step 3.6.4.

3.6.6 Reset the Rx scram 3.6.6.1 E the Rx scram cannot be reset, T:lEN start all CRD pumps.

E0P 572 Rx Power Control

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