ML20205C226
| ML20205C226 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck, 05000000 |
| Issue date: | 12/13/1985 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20204H467 | List:
|
| References | |
| EOP-35-ECA-1.2, NUDOCS 8810260425 | |
| Download: ML20205C226 (6) | |
Text
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E. J. Mroczka 2-1-85 Form Approved by Station Superintendent Effective Date V
STATION PROCEDURE COVER SHEET A.
IDENTIFICATION Number E0P 35 ECA-1.2 Rev.
1 Title LOCA OUTSIDE CONTAINMENT Prepared By J. A. RUTTAR B.
REVIEW I have reviewed the above procedure and have found it to be satisfactory.
TITLE SIGNATURE DATE DEPARTMENT HEAD C.
UNREVIEWED SAFET,_Y, QUESTION EVALUATION DOCUMENTATION REQUIRED:
(Significant change in procedure method or scope YES [ ]
NO ( )
C' as described in FSAR)
(If yes, document in PORC/SORC meeting minutes)
ENVIRONMENTAL IMPACT (Adverse environmental impact)
YES [ ]
N0 ( )
(If yes, document in PORC/50RC meeting minutes) 0.
INTEGRATED SAFETY REVIEW REQUIRED (Affects response of Safety Systems, performance YES ( )
NO ( )
of safety-related control systems or performance of control systems which may indirectly af fect safety system response.)
(If yes, document in PORC/50RC meeting minutes. )
E.
PROCEDURE REQUIRE 1 M SORC REVIEW YES C<l NO ( )
F.
(P' ORC /50RC APPROVAL Q SORC Meeting Number 7 - N (- 49 (
l G.
APPROVAL AND IMPLEMENTATION The attached procedure is hereby approved, and effective on the date below:
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Station /,$ervice/ Unit Superin{endent f.ffective Cate I
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E0P 35 ECA-1.2 Page 1 Rev. 1 2
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LOCA OUTSIDE CONTAINMENT
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I A.
PURPOSE i
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This procedure provides actions to identif, and isolate a LOCA outside containment.
B.
ENTRY CONDITIONS This procedure was written for Modes 1, 2, and 3 assuming RHR system not in service. 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 is entered from E0P 35 E-0, REACTOR TRIP OR SAFETY INJECTION, Step 31, on abt.ormal radiation in the auxiliary or ESF buildings due to a loss of RCS inventory outside containment.
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O O*yA6 2 3 44
LOCA OUTSIDE CONTAINMENT E0P 35 ECA-1.2 Page 3 Res. 1 p
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RESPONSE NOT OBTAINED STEP ACTION / EXPECTED RESPONSE 1
Proceed per affected building a.
Auxiliary Building - go to Step 2 9E b.
ESF Building go to Step 3 2
Verify Proper Valve Alignment Manually CLOSE valves, in Auxiliary Building IF valves can NOT be manually CLOSED, THEN locally CLOSE valves.
a.
Verify Letdown Containment Isolation Valves CLOSED b.
Verify Charging Header Isolation Valves CL0crP-c.
Verify RCP Seal
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Return Containment
/
Isolation Valves CLOSED 4.
Go to Step 5 3
Verify Proper Valve Alignment Menually CLOSE valves, in ESF Building IF valves can NOT be manually CLOSED THFJ locally CLOSE valves.
a.
Verify RJfR Pump Suction Isolation from RCS Valves CLOSED b.
Verify RilR to !!ot Leg Injection Valve CLOSED c.
Verify Safety Injection Pump to llot Leg injection Valves CLOSED C MUf e 1 3 44
LOCA OUTSIDE COSTAINMENT E0P 35 EC.1-1.2 Page 4 Rev. 1
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STEP ACTIOrttXPECTED RESPONSE RESPONSE fiOT OBTAINED 4
Try to Identify and Isolate Break a.
Sequentially CLOSE and OPEN the following valves and monitor for an RCS pressure increase.
- 1) A RER Discharge to Cold Leg Injection
- 2) B RHR Discharge to Cold Leg Injection
- 3) Safety Injection Cold Leg Master Isolation 5
Check If Break Is Isolated a.
Check RCS pressure -
a.
Go to E0P 35 ECA-1,1, Increasing LOSS OF EMERGENCY COOLANT RECIRULATION, Step 1.
b.
Go to 00P 35 E-1, LOSS OF REACTOR OR SECONDAR.' COOLANT, g
Step 1 N-Y
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LOCA OUTSIDE CONTAINMENT E0P 35 ECA-1.2 Page 4 Rev. 1
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- : ACTION /tXPECTED RESPONSE RESPONSE NOT OSTAINED : 8
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Try to Identify and Isolate Break t
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Sequentially CLOSE and OPEN the following valves I
and monito: for an RCS pressure increase.
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- 1) A RER Discharge to Cold Les Injection
- 2) B RER Discharge to I
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Cold Les Injection
- 3) Safety Injection Cold
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Les Master Isolation t
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a.
Check RCS pressure -
a.
Go to E0P 35 ECA-1.1, Increasing LOSS OT EMERGINCY COOLANT RECIRULATION, Step 1.
l b.
Go to E0P 35 E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1
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