ML20205B101
| ML20205B101 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck, 05000000 |
| Issue date: | 06/15/1988 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20204H467 | List:
|
| References | |
| EOP-35-E-2, NUDOCS 8810260182 | |
| Download: ML20205B101 (6) | |
Text
. _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _
Stephen E
'cace 3-31-87 87-12 Fom Approved by Stat,on Superintend:nt EffGctt/* Dato 50RC Mtg. No.
STATION PROCEDURE COVER SHEET 7..
.)
A.
IDENTIFICATION Number: E0P 35 E-2 Rev.
2
Title:
FAULTED STEAM GENERATOR ISOLATION Drepared By: L K. COVIN B.
REVIEW I have reviewed the above procedure and have found it to be satisfactory.
TITLE SIGNATURE DATE Io !/![
f DEPARTMENT HEAD 4
a C.
SPECIFIC UNREVIEWED SAFETY QUESTION EVALUATION REQUIRED:
Modifies intent of procedure and changes operation y
of systems as described in design documents.
YES [ ]
NO [-J (If yes, perform written USQ.'eterminstion and Safety Evaluation, and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)
h 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 j-may indirectly affect safety system response.
YE's [ ]
NO [ 212*F.
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 l
1)
E0P 35 E-0 REACTOR TRIP OR SAFETY INJECTION, Step 23, with the 4
following symptoms l
l a.
Any SG pressure decreasing in an uncontrolled manner.
)
b.
Any SG completely depressurized.
]
a 2)
EOP 35 E-1. LOSS OF REACTOR OR SECONDARY COOLANT, Step 2.
EOP 35 E-3, STEAM GENERATOR TUBE RUPTURE, Step 6, E0P 35 ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED i
RECOVERY DESIRED, Step 8, and E0P 35 ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT - SATURATED RECOVERY DESIRED, Step 3, with the,following symptoms and/or i
conditions a
a.
Any SG pressure decreasing in an uncontrolled manner.
l b.
Any SG completely depressurized.
c.
Faulted SG isolation not verified.
)
3)
E0P 35 FR-H.5, RESPONSE TO STEAM GENERATOR LOW LEVEL, Step 3, 3'
when the affected SG is identified as faulted.
I 4)
Other procedures whenever a faulted SG is identified.
1,
?L 3
O
kAULitU d1LA.'l UL.NtKAIUR ISO LATION EOP 35 E-2 Page 3 Rev. 2
/N STEP ACTH3N, EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION
- 2. Any faulted SG or secondary break should remain isolated during subsequent recovery actions unless needed for RCS cooldown.
1 Check Main Steamline Isolation Manually close valves.
And Bypass Valves Of Affected SG(s) - CLOSED 2
Check If Any SG Is Not Faulted a.
Check pressures in all a.
IF all SG pressures SGs - ANY STABLE OR decreasing in an INCREASING uncontrolled manner, THEN I'
go to E0P 35 ECA-2.1,
\\_-
UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS, Step 1.
3 Identify Faulted SG(s) 4.
Check pressures in all a.
Search for initiating SGs -
break
- 1. ANY SG PRESSURE
- 1. Main steamlines.
DECREASING IN AN
- 2. Main feedlines.
UNCONTROLLED MANNER
- 3. SG Blowdown
- 4. Main steamline drains OR~~
downstream of Main Steam isolation
- 2. ANY SG COMPLETELY valves.
DEPRESSURIZED
- 5. Steam lines to TD AFW pump Go to Step 5.
(
crvssa au
FAULTED STEAM GENERATOR ISOLATION E0P 35 E-2 Page 4 Rev. 2 V) i STEP ACTION /.XPECTED RESPONSE RESPONSE NOT QBTAINED 4
Isolate Faulted SG(s)
Manually close valves.
If a.
Isolate main feedline valves can NOT be closed, THEN dispatch operator to b.
Icolate AFW flow locally close valves or block valves.
c.
CLOSE steam supply valves to TD AFW pump d.
Verify SG atmosphere damp valves - CLOSED e.
Isolate other secondary piping
- 1) SG blowdown
- 2) Main steamline drains upstream of main steam isolation valves
- 3) SG Blowdown Sample Isolation 5
Check DWST Level >80,000 gal Shift AFW pump suction to l
7-the CST r
\\--
6 Check Secondary Radiation a.
Request periodic activity samples of all SGs OP 3311A, REACTOR PLANT SAMPLING b.
Check unisolated secondary radiation monitors
- 1. Main Steam Relief Line
- 2. SG Blowdown c.
Secondary radiation -
c.
Go to E0P 35 E-3, NORMAL STEAM GENERATOR TUBE
- 1) If the radiation RUPTURE, Step 1.
monitoring computer is NOT available.
THEN have an HP technician manually determine main steam line radiation -
NORMAL OPK681 3 44
t
- AUtitu dit VI UthtHATOR ISOLATION EOP 35 E-2 Page 5 Rev. 2
['%
STEP ACTION. EXPECTED RESPONSE AESPONSE NOT OSTAINED 7
Go to E0P 35 E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1
-FINAL-l CPSX4-1 3 64