ML20205A222

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Rev 3 to Emergency Operating Procedure EOP 570, Reactor Pressure Vessel Level Control Emergency Procedure
ML20205A222
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 05/20/1988
From: Berry, Palmer R
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20204H467 List: ... further results
References
EOP-570, NUDOCS 8810250427
Download: ML20205A222 (8)
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.a RPV Level Control E0P 570 Page 1 Rev. 3 i )

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Unit 1 RPV Level Control Emergency Procedure PAGE NO. EFF. REV.

1-4 3 2a,3a,4a 3 ENTRY CCN0!TIONS:

RPV =ater level less than +4 incres RPV pressure greater than 1085 psig Orywell pressure greater than 2.0 psig An isolation condition exists which requires or initiates a reactor scram A condition which requires a reactor scram and reactor power > 3% or can-not be determined STEPS CBJECTIVES Confire Auto Actions Sucport subsequent actions E0P 570 ex Restore / Maintain Preferred level control band:

) RPV Level Setween (1) Simplifies plant recovery >+8"

+10" and +5o" (2) Prevents Rx Feed Pumo trips <+52"

./

l Alternate level control bard; allows If Level Can t Be increased flexibility during degraded Maintained > +10*.

conditions onlle still saintaining Maintain Level > TAF adequate core cooling

!f Level Can't de Direct operator to contingency actions Maintained > TAF.

Go to E0P 576 in extremely degraded conditions 1

Proceed To Return to normal procedures Cold Shutdo-n

References:

1) Emergency Procedure Guidelines, Millstone 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

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E0P 570 RPV Level Control 8G10 50427 001007 PDR ADOCK 05000213 P PDR

i RPV Level Control E0P 570 Page 2 *

. Rev. 3 .

1. PURPOSE The purpose of this procedure is to restore and stabilize RPV water levels.
2. ENTRY CONDITIONS 2.1 The entry conditions for this procedure are any of the following:

2.1.1 RPV water level less than +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 requires or initiates a reactor scram, 2.1. 5 A condition which requires a reactor scram and reactor power is above 3% or cannot be determined.

3. OPERATOR ACTIONS O . .

NOTE:

For Rx Plant degraded conditions, refer to EPIP 4701 for Incident Assessment and Classification.

3.1 Confirm or initiate a Reactor Scram. Perform ONP 502 "Emergency Plant Shutdown" concurrently with this procedure.

3. 2 Confirm initiation or initiate the following:

3.1.1 System isolations consistent with plant parameters.

3.2.2 CCc.S sed $8GT operation consistent with plant pa ram.ste rs.

_ 3.2.3 Diesel generator and gas turbine generator operating consistent with plant parameters.

O E0P 570 RPV Level Control

IPV Level Control EP 570 8 age la es ,, )

Syst!4 f 50t. Af f 04 Growo 1 - RPW Low-t.o utter Level (-44") "$1Vs

- daIn 5tese Line mi taa (7 %PPS) Main Steen Liae Oraias ma in Steae Line 41 Flow (120%) (w5 5,6) main Steae Line Teneel M1 Temo (200*F) tectre Loco Sancte Ltae "sin Steae Lire Low Press (82% P in tun) (SM 1,2)

Iso Coad went to "a sta se

(!C-6,7)

Growo 2 IPW Low water Level "(+8*) Orpe l) Ftr Orm (55 3.4)

Cepe11 mi Pressure (2 osig)

  • tot Ora (55 13..s)

.ent ( AC 7) veat self ( AC 9)

Orne11/5wco Cmas ve*t fros As $169 (AC 8)

Dep ell vest to 583f (AC 13)

Swoo Case seat ( AC 11)

  • vest telf ( AC 12)

" 5.c o l y ( AC 6 )

Oryeell Swcoly ( AC'5)

Orpell/Suco C%as 56 coly (AC 4)

Group 3 iPY Low water Level (*8-) $/0 C1g Systen isstation (50-1.2A.28 aA 48.5) is Head C1g !solatioa (>$ 4)

Growo 4 !so Cond Line Mi 81ow !so Coed Systee !solatics (1 !C 1.2.3,4,6,7)

Growo 5 APV tow-Low =ater Level ( 44*) PwCu Systen Isolettoa j

( CV- 2,2 A ,3,5,23 ) l 5837 auf0 19171Af!C= 150-CC=0 au?O s!f!ar t%

1 w! RA0 in f anawst Pleaos (11 et/me) EPV Low-Low =ater Level (-44*)

2 4! %AO on lefwel Floor (100 et/Mr) IPV Presswre ni (1C85 asig for 3 ;t047 !! !solatten . 15 see) 4 w! ud in Steae Toneel (12 oA/hr)

(005 AVf0-f4fitaf!04 [ftSELCt* av' !*f'! A?!F apt Orne11 mi presswre (2 stig) A=0 APv Low uw eater Levet t tPv tow-Low .eter t.evel ( 44 Th0 Orw ell *1 P esser e (2 asig)

AC !aterloCR (1 C5 or ) I,PCI) d LMP relay SCt atio9 120 SeC If ate (Timed ost)

CJre Soray Orywell Mi Pressdre (2 #sig) 04 025 *.ag ;(4 auf0 lN[?!A?!:%

a PV Low- L ow saterLevel(*44*7 ePy Low Low ester Level ( 43*)

3rpe l t at 8etts.re (2 asig)

L8CI Orwell wi **esswee (2 Jsig) '.3 L8 relay actwat'oa ePV Low Low ' ester Level (-a4* 7 l (OP 570 4PV Level Coetrol O

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-t-RPV Level Control E0P 570 Page 2  !

[- 3; Rev. 3 i h/ .

1. PURPOSE The purpose of this procedure is to restore and stabilize RPV water levels.
2. ENTRY CONDITIONS I 2.1 The entry conditions for this procedure are any of the following: .

2.1.1 RPV water level les; than +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 requires or  ;

initiates a' reactor scram, >

i 2.1. 5 A condition which requires a reactor scram and -

reactor power is' above 3% or cannot be determined.

i

3. OPERATOR ACTIONS i

NOTE:

i

For Rx Plant degraded conditions, refer to EPIP 4701 for Incident {

Assessment and Classification.

3.1 Confirm or initiate a Reactor Scram. Perform ONP 502 i "Emergency Plant Shutdown" concurrently with this procedure.

3.2 Confirm initiation or initiate the following: l r

l 3.2.1 System isolations consistent with plant parameters. {

3.2.2 ECCS and SBGT operation consistent with plant l parameters. }

1

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3.2.3 Diesel generator and gas turbine generator operating i

' consistent with plant parameters, j i

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E0P 570 RPV Level Control

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RPV Level Control E0P 570 Page 3a Rev. 3 l I. CONDITIONS REQUIRING RPV FLOODING A. RPV Level Control (EOP 570)

1. RPV water level cannot be determined.

B. Containment Control (EOP 580)

1. Drywell temperature reaches the RPV Saturation Temperature.
2. Suppression Chamber pressure cannot be maintained belcw the Primary Containment Design Pressure.

C. RPV Level Restoration (EOP 576)

1. RPV water level cannot be determined.

O. RPV Level /Rx Power (EOP 575)

1. RPV water level cannot be determined, and Rx Power cannot be determined or raintained aoove 8%.

II. BORON INJECTION REQUIREMENTS A. Rx Power Control (EOP 572)

1. If the Rx is not shut.down and Suppression Pool Temperature reaches 110*F.

O E0P 570 RPV Level Control

I RPV Level Control E0P 570 Page 3 3_ Rev. 3 (U

'l When executing the following steps:

E Boron Injection is required, THEN GO TO E0P 575 "RPV Level /Rx Power".

E RPV water level cannot be determined, RPV Flooding is required, THEN GO TO E0P 578 "RPV Floodir.g". ,

E RPV Flooding is requir*' for other reasons THEN GO TO E0P 578 "RPV Flooding".

A.AAAAA.224.A.AAAAAAAAAAAAAAAA AA AAAAAAAAAAAA.AAAAA AAA AAAA ARA..AAAAA CAUTION Avoid RPV high water level trip (+52") of reactor feedwater pumps.

CAUTION Oo not secure or plar.e an ECCS in Manual mode unless by at least two O

U independent indications:

l. Misoperation in automatic is confirmed, OR
2. Adequate core cooling is assured.

If an ECCS is placed in Manual, it will not initiate automatically. Make f requent checks of the initiating or controlling parameter. WMen manual operation is no longer required, restore the system to automatic / standby if possible.

CAUTION If a high drywell pressure ECCS initiation signal 2.0 psig occurs or exists while depressurizing, prevent injection from those CS and LPCI pumps not required to assure adequate core cooling prior to reaching their maximum injection pressure. When the high drywell pressure ECCS initiation signal clears, restore CS and LPCI to AUTOMATIC / STANDBY mode.

..A.A.......A.........A........................A..A....A..............A.

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E0P 570 RPV Level Control

9 RPV Level Control ECP 570 Page 4a Rev. 3 CONDITIONS REQUIRING ALTERNATE SHUTDOWN COOLING A. RPV Pressure Control (EOP 571) {

1. If RPV cooldown '- required but cannot be accomplished AND all control rods -

are inserted beyond position 04.

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E0P 570 RPV Level Control'

s RPV Level Control E0P 570 Page 4

y Rev. 3 G'

3.3 Restore and maintain RPV water level +10" - +50" with one or more of the following systems, consistent with existing RPV pressure.

Make-up Make up System System OP RATED FLOW Pressure Range 6

____ C o nt FW '31.5/316 7.9 x 10 lbm/hr 2300 psig - O psig

~~~~

CR0 ; isch t 302 200 GPM 1500 psig - O psig

,_,' - 336 3600 GPM/ Loop 330 psig - O psig

~~ ~

it'I ps os. 3J5 15,000 GPM 250 psig - O psig

3. 3. 4 ;F RP'> watar level cannot be maintained above +10",

.~19N maintain RPV water level above -127" (TAF)

/~'N 3.3.2' IF RPV water level can be maintained above -127" k, s [T.4), AND the APR timer has initiated, TH5h prevent automatic RPV depressurization by depressing the APR Timer Reset pushbutton and CONTINUE to reset every minute UNTIL, RFV water level is > -48", OR Drywell pressure is ( 2 psig and the "High Orywell Pretsure Reset" key is in the reset position, OR All Core Spray and LPCI pumps are not running, AND the "APR Auto-Blowdown A/C Interlock" alarm is clear.

IF to'! water lev;l has not stabilized and approaches -127" (TAF),

ThEN 00 .a E0P $76 "RPV Level Restoration" IF Alternate Shutdown Cooling is required IEN GO TO E0P 579 "Alternate Shutdown Cooling".

3.4 WHEN OP 206 "Plant Cooldown to Cold Shutdown" is entered from E0P 571 "RPV Pressure Control" at Step 3.7.

s THEN GO TO OP 206 "Plant Cooldown to Cold Shutdown." ,

U(N RP:j1c FINAL E0P 570 RPV Level Control

STATION PROCEDURE COVER SHEET A. IDENTIFICATION Number: E0P 570 Rev. 3

Title:

RPV LEVEL CONTROL EMERGENCY PROCEDURE Prepared By: EO BERRY ,

8. REVIEW '

I have reviewed the above procedure and have found it to be satisfactory.

TITLE SIGNATURE DATE DEPARTMENT HEAD ).

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C. SPECIFIC UNREVIEVED SAFETY QUESTION EVALUATION REQUIRED:

Modifies intent of procedure and cnanges operation of systems as described in design documents. YES ( ] NO ( @

(If yes, perform written USQ determination and Safety Evaluation, and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)

ENVIRONMENTAL REVIEW REQUIRED (Adverse environmental impact) YES [ ] NO ( T

0. SPECIFIC SAFETY EVALUATION REQUIRED Affects response of safety systems, performance of systems which may have been credited in the safety analysis or non-credited systems which may indirectly affect safety system response. YES [ ] NO (1 (If yes, perform written Safety Evaluation and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)

E. INTEGRATED SAFETY EVALUATION REQUIRED YES ( ) NO ( 7 F. PROCEDURE RECUIRES PORC/50RC REVIEW (In addition to review, items with a YES response must be documented in the PORC/50RC meeting minutes.)

f YES T ] NO ( )

G. USORC APPROVAL SORC Meeting Number / ~ d'd - Y H. APPROVAL AND IMPLEMENTATION The attacned procedure is hereby approved, and effective on the date below:

h /$ & hO $b sta,*fon/ Sarvice//Jnit Superintendent Ef fective/Date SF301/9/s/SES/97-12/lofi s

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