ML20205C565

Rev 1 to Emergency Operating Procedure EOP 35 FR-H.3, Response to Steam Generator High Level

ML20205C565
Person / Time
Site:	Millstone, Haddam Neck, 05000000
Issue date:	12/13/1985
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20204H467	List: A07413, Forwards Specific Emergency Operating Procedures for Use During Incident Response Ctr Activation ML20204H704 ML20204H734 ML20204H868 ML20204H928 ML20204H963 ML20204J027 ML20204J039 ML20204J092 ML20204J109 ML20204J115 ML20204J120 ML20204J128 ML20204J133 ML20204J139 ML20204J147 ML20204J497 ML20204J543 ML20204J565 ML20204J627 ML20204J633 ML20204J638 ML20204J642 ML20204J659 ML20204J669 ML20204J685 ML20204J707 ML20204J733 ML20204J739 ML20204J746 ML20204J767 ML20204J781 ML20204J786 ML20204J814 ML20204J824 ML20204J849 ML20204J853 ML20204J865 ML20204J878 ML20204J902 ML20204J914 ML20204J920 ML20204J939 ML20204J947 ML20204J954 ML20204J958 ML20204J965 ML20204J975 ML20204J982 ML20204J994 ... further results
References
EOP-35-FR-H.3, NUDOCS 8810260528
Download: ML20205C565 (6)

Text

, _ _ _ - _ _ _ _ _

E. J. Mroc2

• 85 Form Apprav;d by Station supsrintendent Effactive Date STATION PROCEDURE COVER SHEET A.

IDENTIFI5ATION Number E0P 35 FR-H.3 Rev.

1 Title RESPONSE TO STEAM GENERATOR HIGH LEVEL Prepared By J. D. Catlin B.

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

TITLE SIGNATURE DATE DEPARTMENT HEAD 4 H

/2 C.

UNREVIEWEDSAFETYQUESTIONEVALUATIONDOCUMENTATIONREQUfRED:

(Significant change in procedure method or scope YES ( )

NO M as described in FSAR)

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

ENVIRONMENTAL IMPACT (Adverse environmental impact)

YES ( )

NO X (If yes, document in PORC/SORC meeting minutes)

D.

INTEGRATED SAFETY REVIEW REQUIRED (Affects response of Safety Systems, performance YES [ ]

h0C>F of safety-related control systems or performance of control systems which may indirectly affect cafety system response.)

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

E.

PROCEDURE REQUIRES M SORC REVIEW YES PQ NO ( )

F.

ddRC'dSORCAPPROVAL O ORC Meeting Number DOS ~ C3c'A4 G.

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

W_ AWV l.2 -/3-[S~

Station /Safvice/ Unit Superintendent Effective Date SF 301 Rev. 7 O

g o2g0y $$o 3

Page 1 of 1 P

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e E0P 35 FR-H.3 Page 1

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O RESPONSE TO.il,"Q,,r... RATOR HIGH LEVEL Pace No.

Eff. Rev.

1-5 1

O O

RESPONSETOSTEAMGbERATORHIGHLEVEL E0P 35 FR-H.3 Peg 2 2 Rev. 1

~

r A.

PURPOSE This procedure provides acticas to respond to a steam generator high level condition and to address the steam generator overfill concern.

B.

ENTRY CONDITIONS This procedure was written for Modes 1, 2, 3, and 4.

Using this procedure when not in these modes requires a step by step evaluation to determine if the required action is still applicable to current plant conditions.

This procedure entered from 1)

E0P 35 F-0.3, HEAT SINK Critical Safety Function Status Tree on a YELLOW condition, and 2)

E0P 35 FR-H.2, RESPONSE TO STEAM GENERATOR OVERPRESSURE, Step 3 if the affected SG narrow range level f.s high.

O O

e RESPONSE TO STEAM GENERATOR HIGH LEVEL E0P 35 FR-H.3 Pcg2 3 Rev. 1

,m,

(

)

'Ad STEP ACTION / EXPECTED RESPONSE RESPONSE NOT 09TAINED CAUTION If SG narrow range level has increased to greater than 32% (77% for adverse containment) an evaluation should be made for SG overfill considerations.

Steam should not be released from any SG with level greater than 92% (77%

for adverse containment) prior to overfill evaluation.

l NOTE c})

Throughout this procedure "affected" refeus to any SG iu which narrow range level is 1l greater than 80%.

1 Identify Affected SG(s) a.

Narrow range level -

a.

IF less than 82% in all GREATER THAN 82%

SGs, THEN return to (7 w) procedure and step in effect.

2 Verify TV ! solation a.

Main FW pumps - STOPPED a.

Manually stop pumps, b.

FW Flow control b.

Manually close valves.

valves - CLOSED c.

Flow bypass level c.

Manually close valves.

control valves - CLOSED d.

Feedline Isolation d.

Manually close valves, valves - CLOSED 3

Isolate AFW Flow To Affected SG(s)

O)

\\s _-

OP W 8-1 3 44

e r t RESPONSE TO STEAM GENERATOR HIGH LEVEL E0P 35 FE H.3 Peas 4 Rev. 1

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eTap Actiewespecteo naapones naspowes wof osTAswee 4

Check Affected SG(s) Level a.

Narrow range level -

a.

Go to Step 5.

LESS THAN 92% (77% for ADVERSE CONTAINMENT) b.

Narrow range level -

b.

Go to Step e f

DECREASING c.

Control AW flow to i

maintain narrow range 5

level between 4%

(34% for adverse j

containment) and 50%

1 I

d.

Return to procedure and j

step in effect j

i i

j 5

Close Affected SG(s) Steam r

Supply Isolation Valves To i

i l

Turbine-Driven AW Pump i

,6 Close Affected SG(s) Main i

Steamline Isolation and i

j Bypass Valves l

l 7

Cbeck Affected SG(s)

IF any E0P 35 E-3 or E0P Radiation - NORMAL 35 ECA-3 Series procedure

[

is in effect, THEN return to procedure and step in effect, i

IF NOT, THEN so to E0P 35 E.3, STEAM GENERATOR TURE RUPTL%E, Step 1.

a.

Main Steamlines b.

Steam generator blowdown radiation monitor, if not isolated.

I 8

Establish Blowdown From i

Affected SG(s)

~

j a.

In accordance with OP 3316C STEAM j

GENERATOR BLOWOW, if l

SG blowdown is isolated, j

b.

If SG blowdown and AW were in service,

[

OPEN SG Blowdown Ctat t

4 h Isolation Valve (s) to

[

i v

affected SG(s).

t i

i.

oes m m i

i l

e RESPONSE TO STEAM GENERATOR HIGli LFXEL E0P 35 FR-H.3 Pcg? $

Rev. 1

,a

(

)

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STEP ACTION /EEPECTED RESPONSE RESPONSE NOT OSTAINED 9

Return To Procedure And Step In Effect

-TINAL-S 6

0 v

CPSC641 3 44