ML20205A900

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Rev 1 to Emergency Operating Procedure EOP 3505, Loss of Shutdown Cooling (Rhr)
ML20205A900
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 11/05/1987
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20204H467 List: ... further results
References
EOP-3505, NUDOCS 8810260126
Download: ML20205A900 (10)
v • d • e


Text

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Stephen E. Scace 3-31-87 87-12 Form Approved by Station Superintendent Effective Date 50RC Mtg. No.

STATION PROCEDURE C0VER SHEET A. IDENTIFICATION Number: E0P 3505 Rev. 1

Title:

LOSS OF SHUTDOWN COOLING (RHR)

Frepared By: T. KULTERMAN B. REVIEW

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

TITLE SIGNATURE DATE DEPARTMENT PEAD 1i 1 -

C. SPECIFIC UNREVIEVED SAFETY QUESTION EVALUATION REQUIRED:

Modifies intent of procedure and changes operation of systems as described in design documents. YES [ ] NO L>]

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

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

D. 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 Cs]

(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 [ ^]

F. PROCEDURE REQUIRES (66RC/SORC REVIE'.4 (In addition to review, items with a YES response must be documented in the @ /50RC meeting minutes.) YES [<] NO [ ]

G. (P[C'/SORC APPROVAL h /50RC Meeting Number M 7 -l4 3 H. APPROVAL AND IMPLEMENTATION ,

The attached p s hereby. approved, and effective on the date below:

/

,W " H- S D O- StTtion/ Service / Unit Superintendent Effective Date 8810260126 881007 SF 301 DR Rev. O ADOCK 05000213 PDR . Page 1 of 1

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E0P 3505 Page 1

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LOSS OF SHUTDOWN COOLING (RHR) EOP 3505 Page 2

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l A. PURPOSE l

3 This procedure will guide the operator on specific steps to maintain the Reactor Plant in a safe condition.

B. ENTRY CONDITIONS

1. Loss of the operating RHR pump when using it for cooling.
2. Loss of RPCCW to RHR heat exchanger.
3. Rx Coolant system is heating up unexpectedly.

1 9

OP50644 3 44

LOSS OF SHUTD0kN COOLING (RRR) E0P 3505 Page 3 Rev. 1

,y STEP ACTuncExPECTED RESPONSE f RESPONSE NOT ORTAINED CAUTION

1. No dilution activites are permitted without RHR Flow.
2. If the operating RHR pump appears to be air bound (i.e low dp, low flow with pump running and flow control valve open)

DO NOT start a second RRR pump until RC3 level has been restored to at least the center line of the hot legs, and, in accordance with Figure 2, RCS temperature and desired RHR flow allow adequate NPSH for pump operation.

1 PZR level greater than 18% Fill the RCS to the with loops intact and head appropriate level tensioned,

a. Identify and isolate OR the leak.

RCS level at the center b. Vent RRR pumps and seal line of the hot legs, cooler 2 Verify RRR pump running Restart RHR pump or start

\- / opposite train. If pump will not start, THEN go to Step 5.

3 Verify RHR flow about Adjust flow with RRR header 1000 gpm flow RHS-FCV618 or RHS-FCV619 4 Verify RRR temperature Ensure 2 RPCCW pumps are stable or decreasing. Go running, to Step 14.  !

a. Adjust heat exchanger cooling flow to increase cooling using with RPCCV Heat Exchanger Flow CCP-TV66A(B).
b. Check Service Water system flow for possible heat exchanger fouling.
c. If RRR temperature is stable or decreasing.

THEN go to Step 14, if not, THEN to to Step 5.

5 RPV head is tensioned Go to Step 9

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Page.4 L0fl 0F SHOTDOWN COOLING (RHR) E0P 3505 Re:v . 1

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i 6 At least one steam generator -

is operable

a. Level ) 4% of Narrow Range

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b. RC loop not partially '

drained

c. Open atmospheric relief
d. Go to Step 13.

7 RCS loops intact or loop Close loop isolation valves.

isolations shut.

NOTE PZR PORVs may not open until pressure reaches 50 to 100 psig.

'- CAUTION RPV Head temperature must remain above 70*F when the head is tensioned.  ;

8 Establish a feed and bleed

a. Select open on PORVs and i block valves
b. Fill RCS at a rate determined by Figure 1
c. Go to Step 13 t

9 RPV head removed Go to Step 11 10 Monitor temperature of cavity j t

t

a. Establish fuel Pool [

cooling to the Reactor

, Cavity

b. Go to Step 13 CPSMS 2 344

e LOSS OF SHUTDOWN COOLING (RRR) E0P 3505 Page 5 Rev. 1 Lj STEP ACTION! EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION

1. If the Steam Generator or RCP seals are opened, water may spill to the Containment floor.

Evacuate unnecessary personnel.

2. If boiling occurs in the Reactor Vessel, a pressure buildup in the Reactor Vessel Head could occur.

This pressure buildup could force water out a Cold Leg leak or component opening resulting in l degraded core cooling. A Hot Leg injection path l

from the RWST to the Reactor Vessel should j be established to ensure adequate core cooling j capability, j i

3. Reliable RCS and Reactor Vessel temperature indication may not be available if RRR is lost and Core Exit Thermocouples are disconnected. RHR pamp suction pressure indication and trending available on the Plant Process Computer should be utilized to indicate T potential Reactor Vessel boiling as pressute increases.

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11 Establish feed and bleed from RWST

a. Establish normal Charging Establish one of the following flow from the RWST at alternate fill paths.

100 gpm or less to remove decay heat. Refer to Figure 1 for appropriate flow

a. Charging Pumps (s) from the RWST i Alternate Charging (Cold Leg)
11. High Head safety injection (Cold Leg) '

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CN348 2 44

o LOSS OF SHUTDOWN COOLING (RRR) E0P 3505 Page 6 Rev. 1

,cs i/

'y ,i STEP ACTION / EXPECTED RESPONSE RESPONSE NOT ORTAINED

b. RHR Pump (s) from the .

RWST

i. Low Head safety injection (Cold Leg)
11. Low Head safety injection (Hot Leg)

SE

c. Boric Acid Transfer Pump (s) from Boric Acid ,

Tank (s) via Charging Pump (s) suction to no rma l/ alte rna te charging or high head safety injection (assuming idle charging pumps)

O__R .

d. Safety Injection Pump (s) from RWST O-sm- 1. Safety injection (Cold Leg)
11. Safety injection (Hot Leg) '

CAUTION: 4 The Containment Recire Pumps should never be run at greater than 5000 gpm and can run for only i one hour at flows greater than 4600 gpm. 1 I

Excessive flows through the heat exchanger can cause tube failure. ,

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e. Containment Recirculation Spray 9 Pumps from the RWST via j low pressure safety  ;

injection

i. Hot Leg
11. Cold Leg l

- RB

f. RWST gravity via all above paths with the j exception of "c" N-in w 3 sa i

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4

'hS.S OF SHUIDOWN COOLING (RRR) E0P 3505 Page 7 Rev. I t

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STEP ACTION /gXPECTED RESPONSE RESPONSE NOT ORTAINED

b. Bleed from RRR suction to Bleed f rom manual drain valves RWST via QSS test line on RHR system. (Pump Heat 3-RHS-V43 exchangers or system piping) ,

12 Establish Containment Integrity

a. Close personnel hatch Seal openings as best possible
b. Close equipment hatch (at least 4 bolts)
c. Perform Con *ainment Purge Containment via Integrity During Core Auxilia ry Building Alterations or Movement Filtered Exhaust of Irradiated Fuel, SP 3613F.3 13 Declare an UNUSUAL EVENT
4. Implement EPIP 4101 (v)
14. Restore RHR System
a. Maintain Core Cooling
b. Verify temperature control
c. Consult Plant Staff

-FINAL-1 m

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mr l'Oll'1 APPPOVED liY UNIT 3 SUPERINTENDENT

p. s - ry EFFECTIVE DATE

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OPS FORM EOP 3505-2 Rev. 0 Page 1 ot'I

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