ML17192A678

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Emergency Procedure DGA-19,Revision 0, Procedure to Assure Adequate Core Cooling
ML17192A678
Person / Time
Site: Dresden Constellation icon.png
Issue date: 12/20/1979
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML17192A611 List:
References
DGA-19, NUDOCS 8005080522
Download: ML17192A678 (11)
v • d • e


Text

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.F' PROCEDURE; TO ASSURE ADEQUATE.

Revis ion 0 CORE COOLING A.

SYMPTOMS ECCS initiation setpoint has been reached and:

1.

Reactor water level ind1cation is continuing to decrease with ECCS operating.

2.

Reactor water level :.is ranaining at a level below the top of the active fuel as irdicated by available level indications.

3.

Reactor water level 'indication is unavailable.

4.

Less than design flow is indicated on Feedwater or ECC Systems when design flov1 is :required.

B.

AUTOMATIC ACTIONS None.

C.

H1MEDIATE OPERATOR ACTIONS

1.

NOTE The highest priority action is to have any one ECCS pump injecting.

Indication that any one ECCS pump is injecting is a reliable confirmation that inadequate core cooling effects are being mitigated.

Confirmation of ECCS injection indication is*a reliable backup for water level instrumentation.

Recheck and compare water level indications.

a.

Panel 902(3)-3 Hide Range Yarway A (0 to 400 in.)

Hide Range Yarway B

{O to 400 in.)

Hide Range GEt1AC Recorder (0 to 400 in.)

b.

Panel 902(3)-4 '

Hide Range GEMAC

(-70 to +330 in.)

1 of 11 DEC 20'... n

{.J D.O.S.R.

I I

I

c. e Panel 902(3Fs '.

. Narrow Range Yarway A Narrow Range Yarway B Narrow Range GEMAC A Narrow Range GEMAC. 8 I

Revision 0

. (-60 to +60 in)

(-60 to +60 in.)

(Oto 60 in.)

(O to 60 in.)

Reactor Vessel Level/Feedwater Flow Recorder (Black Pen)

(Utilize V~ssel Level Select Switch)

Level A (0-60 in.)

Level B (0-60 in.)

2.

IF LPCI System flow has been diverted for Containr.ient Cooling, restore all flow to the core.

If Containment Cooling is essential, injection water should be routed through the LPCI Heat Exchanger.

3.

IF high pressure systems have failed to maintain level, Auto Slowdown has initiated and reactor pressure is greate-rthan 350 psig, VERIFY that all Auto Slowdown Valves OPENED by checking temperature'recorder and accoustical monitor on Panel 902(3)-21.

4.

IF LPCI initiated and reactor pressure is <350 psig, VERIFY the following:

a.

With Recirculation Loop A Selected for Injection Panel 902(3)-3 t10-2(3)-150l-21A t10-2(3)-150l-22A M0-2(3)-1501-218 M0-2(3)-1501-22~

Panel. 902(3)-4 110-2 ( 3 )-202:-SA t10-2 ( 3 )-202-?A M0-2(3)-202-6A M0-2(3):-202-9A 2 of 11

,., np:-*"":.:D r\\ *-. *-*: 1., I t

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~

\\;

DEC 2.C '79 D.0.S.R.

OPEN * ----

OPEN ----

CLOSED ---

CLOSED ---

CLOSED ---

CLOSED ---

CLOSED ---

CLOSED ---

-====- _:i b

  • ij Revision 0

.L

~i-~e~-ir~ul~tion Loop B: Select~d*r.Injec~io~

.Panel 902(3)-3 t10-2 (3)-1501-2rn.

M0-2(3)-1501-22B M0-2(3)-1501-21A, M0-2(3)-1501-22A Panel 902 (3 )-4 M0-2(3)-202-5B M0-2(3)-202-7B M0-2(3)-202-6B M0-2(3)-202-9B OPEN -----"'

OPEN -----

CLOSED ----

CLOSED ----

CLOSED ----

CLOSED ----

CLOSED ___ _

CLOSED ----

5.

MONITOR LPCI injection and core flow by ob serving the following:

Panel 902(3)-5 Core Flow Recorder (Black Pen)

Core Differential Pre~sure (Red Pen)

Panel 902(3)-4 JP-1 JP-6 JP-11 JP-16 JP Loop A Flow JP Loop B Flow Panel 902(3)-3 Reactor Differential P~essure 3 of 11

.-:*;..-**~_r-,_,~. -'

0-125 Mlb/hr -----

0-25 psid __ _

0-150% -----

0-150% _____ _

0-150%. ____ _

0-150% -----

0-150% -----

0-150% -----

0-30 psid __ _

D--- -

  • L,.;r; *~,....

-\\.,..'j D.0.S.R.

(100% = 49 Mlb/hr under normal operating conditions)

D.

. SUBSEQUEUr o~r6~ ACTION:S,*

Rev:ision. 0

1.

Core Spray System effectiveness may be checked by:

a.

. System I Pump A Flow Pump A Discharge_ Pressure M0-2(3)-1402-3A M0-2(3)-1402-24A

'M0-2 (3)-1402-25A*

M0-2(3)-1402-9A VALVE-2(3)-1402-6A M0-2(3)-1402-38A; M0-2(3)-1402-4A

b.

System II Pump C Flow Pump C Discharge Pressure M0-2(3)-1402-3B M0-2(3)-1402-24B*

M0-2(3)-1402-25B

  • M0-2(3)-1402-9B VALVE-2(3)-1402-6B M0-2(3)-1402-38B M0-2(3)-1402-4B 0-6000 GPM ---

0-400 psig *---

OPEN ------

OPEN OPEN ------

OPEN OPEN ------

CLOSED -----

CLOSED -----

0-6000 GPM ---

0-400 psig OPEN OPEN ------

OPEN ------

OPEN OPEN CLOSED -----

CLOSED -----

2.

LPCI System effectiven'ess may be checked by:

a.

System I Panel 902(3)-3 Pump Flow 0-20,000 GPM ------

M0-2(3)-1501-SA OPEN

---~--

4 of 11 D.O.S.R.

.'r*~'""'.........

,-L-i-'i-/1 n1FD

      • **'*"' 'i M0.3)-1501-5B M0-2(3)-1501-llA M0-2(3)-1501-21A' M0~2(3)-1501-22A M0-2(3)-1501-25A:

VALVE 2(3)-1501-Z6A M0-2(3)-1501-32A*

M0-2(3)-1501-32B M0-2(3)-1501-13A M0-2 (3)-1501-18A.

M0-2(3)-1501-19A M0-2(3)-1501-38A M0-2(3)-1501-20A M0-2(3)-1501-27A M0-2(3)-1501-28A

b.

System II Panel 9b2(3)-3 Pump Flow LPCI Flow Recorder M0-2(3)-1501-5C M0-2(3)-1501-5D M0-2(3)-1501-llB M0-2(3)-1501-21B

  • M0-2(3)-1501-22B M0-2(3)-1501-25B f VALVE 2(3)-1501-26B M0-2(3)-1501-32A M0-2(3)-1501-32B 5 of 11

.J......,,...___~-.'

Revision 0 OPEN -----

(Condition dependent on LPCI Loop Selection)

OPEN OPEN OPEN -----

OPEN -----

CLOSED ----

CLOSED -----

CLOSED ----

CLOSED CLOSED ----

CLOSED. ----

CLOSED ----

0-20,000 GPM ----

0~20,000 GPM ----

OPEN OPEN -----

OPEN (Condition dependent ~n LPCI Loop Selection)

OPEN OPEN OPEN OPEN

~-r"'l,.....\\

;-.
.:~ I
.!FD M0-2 (3)-1501-13B

M0-2(3)-1S01-18B.

M0-2(3)-1501-19B M0-2 (3)-1501-38B '*

M0-2(3)-1501-20B M0-2(3)-1501-27B M0-2(3)-1501-28B CLOSED Irv.ti. l":r Revision 0.

CLOSED ----

CLOSED ----

CLOSED CLOSED CLOSED CLOSED ----

3.

HPCI System effectiveness may be checked by:

Pump Flow Pump Discharge Pressur.e Pump Inlet Pressure Turbine RPM Turbine Inlet Pressur~

Turbine Exhaust Pressure M0-2(3)-2301-6 OR M0-2(3)-2301-35 AND M0-2(3)-2301-36 M0-2(3)-2301-9 M0-2(3)-2301-8 A0-2(3)-2301-7 M0-2(3)-2301-4 M0-2(3)-2301-5 M0-2(3)-2301-3 Turbine Stop Valve 0 to 100%

(94% = 5600 GPM) -----

0 to 1500 psig -------

30 in Hg to

+ 30 psig ----

0-6000 RPM 0-1500 psig 0-150 psig OPEN (CLOSE)

(Condition dependent on source of HPCI suction)

CLOSED (OPEN)

CLOSED (OPEN)

OPEN OPEN -------

OPEN -------

OPEN OPEN OPEN OPEN

4.

Feedwater and Condensa~e System effectiveness may be checked by:

Condensate Pump Amps 0-300 amps ---

6 of 11

f:*

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      • e Condensate Pump Disch~rge Header Pressure Condensate Booster Pu~p Suction Pressure Condensate Booster Pump Discharge

RFP Amps RFP Flow RFP Discharge Header (common)

Feedwater Temperature Hotwell Level DGA I9

-.. Revision 0 0-200 psig *---

0-200 psig ---

0-600 psig ---

0-600 psig ---

0-1.5 KVA ----

0-6000 lbs/hr ----

0-2000 psig ---

0-500°F 0-50 in -----

Condensate Storage Tank Level 2/3A 0-32 ft -----

Condensate Storage Tank Level 2/3B 0-32.ft

.Condensate Makeup Recorder Normal : (Black)

Emergency (Red)

M0-2-3304 M0-2-3303 M0-2-3403 RFP Minimum Flow Valve 2-3201A RFP Minimum Flow Valve 2-3201B RFP Minimum Flow Valve. 2-3201C M0-2-3201-A M0-2-3201-B M0-2-3201-C M0-2-3206-A 7 of 11 0-500 GPM ----

0-1000 GPM

  • OPEN (if desired) ---

OPEN (if desired) ---

OPEN (if any LP Heater String isolated) ---

CLOSED CLOSED CLOSED OPEN (if A Pump running)

OPEN(if B Pump running)

OPEN (if C Pump running)

OPEN

  • -(.*

D.. O.S.R..

II UGA f9'

'.*e

!t' e

Revision 0 A0-2-642A OPEN M0-2-3206-8 OPEN A0-2-6428 OPEN Low Fl ow Feed Regulating Valve OPEN t10-2-3202 OPEN (if any HP Heater String isolated)

.M0-2-3205A OPEN

. M0-2-32058

\\)

OPEN

5.

The effectiveness of:Priniary Containment Isolation can be checked by verifying the following:

CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED I':!"""'**-,...,r-., D

  • *- *-**t...,-
*i.... \\

ill ;

  • ,..... ; L*

CLOSED r.r*** - -

l.J**' /""'

'-"*' -,} ! 'j CLOSED D n R

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DGA 19

  • e
  • e*

Revision 0

. A0-2001-5 CLOSED A0-2001-6 CLOSED A0-1599-61 CLOSED A0-1599-62 CLOSED

c.

Group II I

  • M0-1201-1 CLOSED M0-1201-2 CLOSED rm-1201-3 CLOSED

. M0-1201-7 CLOSED M0-1001-lA CLOSED M0-1001-2A CLOSED t10- 1001-4A CLOSED MO-l001-5A CLOSED M0-1001-18 CLOSED M0-1001-28 CLOSED M0-1001-48 CLOSED M0-1001-58 CLOSED f10- l 001-2C CLOSED M0-1001-4C CLOSED

d.

Group IV M0-2301-4 CLOSED M0-2301-5 CLOSED

\\:

M0-2301-35 CLOSED M0-2301-36 CLOSED

e.

Group V fl0-1301-1 CLOSED l

A DDDr>.~ 1rQ M0-1301-2 CLOSED I

~ ~.: ;: ~

U'C )n *-....

-. '-\\...' /'j 9 of 11 Dnsp

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DGA 19

-~:

Revis ion 0 e

I M0-1301-3 CLOSED M0-1301-4 CLOSED A0-1301-17 CLOSED A0-1301-20 CLOSED

6.

If the inadequacy of cooling is due to insufficient water supplies in the Condensate Storage tanks, Torus and Condensate Hotwell, the following sources of water should be considered available:

  • CAUTION Standby Coolant Supply is a last

'resort and should only be used as directed by the Operating Assistant Superintendent or the GSEP Technical Director.

a.

Unprocessed Hater in Radwa ste tanks.

b.

Standby Coolant Supply.

E.

DISCUSSION This procedure is a supplementary guideline to the General Abnonnal proced~res.

The syr.iptoms which dictate the use of this procedure

  • would ~ost probably occur after the immediate actions of the procedures for breaks inside the drywell, breaks outside the drywell, reactor low \\'later level and stuck open relief valve have been

.fol 1 owed.

If the operator already has an inference as to the cause of the inadequate cooling, he need not follow the procedure step by step.

He should refer to the steps affecting that system first.

(Even immediate actions may be skipped.)

The blank lines next to para-meters are not intended to make this a checklist.

These bl an ks are a convenience *iten that the operator can use at his discretion.

The immediate actions within this procedure attempt to detect some of the more probable causes of inadequate core cooling.

The indicated water level, \\'1here provided by Yarway instrumentation utilizing reference legs in the drywell, is dependent upon drywell temperature.. Very large increases in drywell ter.iperature (an increase from 135°F to 340°F) could result in a level inaccuracy (as much as 14 *inches depending on drywel l temperature and type of instrument) with indicated level being higher than actual level.

10 of 11 APf:JPn\\/E~

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I t!I DEC 2G7g D.O... R.*

.~..

w

I Ltuli l:'9' Revision 0 **

  • Durin~.*~apid... act~r depr.~ssurization (~ith.* operation for example), and particularly below 500 psig, the operator should utilize the GEMAC level indication to give backup information on vessel water.level.

The operator should not turn off any ECCS unless there is***sufficient': confirming information from GEMAC reference leg level instrumentation that vessel water level has been restored.

The operators should not rely on the Yarways if erratic

  • behavior, indicative of reference leg flashing, has occurred until the Yarway readings are on scale and in reasonable agreement with GEMAC level instruments.

The operator should VERIFY that automatic ECCS actuations occur when:the levels are at the trip points.

The operator should be prepared to manually" actuate ECCS during a suspected LOCA if automatic actuation is not achieved.

It should be noted that core flow instrumentation such as core dif~erential pressure, ie~~tor differential pressure and core flow will not provide. conclusiv~ evidence as to the adequacy of core cooling.

These instruments are intended to be used in conjunction with other indications.. Recirculation loop temperatures and vessel temperatures may be consulted but the validity of such indication is questionable as it relates to core cobling.

Subsequent actions address effectiveness of various inventory makeup systems and containment isolations.

Some parameters such as LPCI pump amps and discharge pressure and Core Spray header dp are not listed within the procedure.

These instruments may be used but must be read locally.

Before attempting to confirm core cooling by local indications, consideration must be given to the effect of radiation levels and atmospheric contamination on personnel.

The only valves listed under Group II Isolation are those which could result in a significant water inventory loss from the contain-ment.

The highest priority action is to have ~riy one ECCS pump injecting.

Indication that any one ECCS pump is injecting is a reliable con-firmation that inadequate core cooling effects are being mitigated.

Confirmation of ECCS injection indication is a reliable backup for water level instrumentation.

Indications such.as incore instrumentation are not considered sufficiently reliable to include in this procedure.

11 of 11 IF'lNALJ r, 0 r.

u..0.R.
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