ML17261A981

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Rev 5 to AP-FW.1, Partial or Complete Loss of Main Feedwater
ML17261A981
Person / Time
Site: Ginna 
Issue date: 02/23/1990
From: Widay J
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17261A978 List:
References
AP-FW.1, NUDOCS 9003080330
Download: ML17261A981 (22)


Text

EOP:

AP-W.1

. TITLE:

PARTIAL OR COMPLETE LOSS OF MAIN FEEDWATER REV:

5 PAGE 1 of 6 OCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION ONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIE DATE cP 9~

P T SUP RI D NT cP 0

EFF CTIVE D TE QA~ NON-QA REVIEWED BY:

TEGORY 1.0 G INNASTATION START:

DATE TIME COMPLETED:

DATE TIME' 9003080330 900227 PDR ADOCK 05000244 F

PNV

4 j

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WP AP-FW.1 TITLE:

PARTIAL OR COMPLETE LOSS OF MAIN FEEDWATER REV:

5 PAGE 2 of 6 A.

PURPOSE This procedure provides the steps necessary to respond to a MFW syst: em malfunction resulting in a decrease in or.complete loss of main feedwater.

B.

ENTRY CONDITIONS/SYMPTOMS 1.

SYMPTOMS The symptoms of PARTIAL OR COMPLETE LOSS OF OF MAIN FEEDWATER are; a.

Annunciator G-3(5),

S/G A(B) LEVEL DEVIATION i74, or b.

Annunciator G-19(21),

S/G A(B) FF

< SF CHANNEL ALERT 0.8 x 10~ LB/HR, or c.

Annunciator G-20(22),

S/G A(B)

LO LEVEL CHANNEL ALERT 304 or d.

Annunciator K-18, MAIN FEEDWATER PUMPS TRIPPED, or e.

Low indicated MFW pump suction flow on 1 pump, or f.

MFW pump indicates tripped, or g.

MFW pump discharge valve indicates shut.

0

EVP:

AP-FW.1 TITLE:

PARTIAL OR COMPLETE LOSS OF MAIN FEEDWATER REV:

5 PAGE 3 of 6 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED CAUTION IPf AT ANY TIME DURING THIS PROCEDURE, A REACTOR TRIP OR SI OCCURSf E 0, REACTOR TRIP OR SAFETY INJECTION, SHALL BE PERFORMED.

NOTE:

Step 1 is an IMMEDIATE ACTION step.

O 1

Check MFW Requirements:

a.

Power - GREATER THAN 50X

b. Both MFV pumps - RUNNING
a. IP power less than 50X, THEN go to Step 2.
b. IP only one MFV pump has
tripped, THEN:
1) Start all 3 AFV pumps AND verify maximum flow.
2) Decrease power rapidly to less than 50X.

c.

Go to Step 3

3)

Go to,Step 3.

IP both MPV pumps have tripped, THEN ensure reactor trip and go to E-O, REACTOR TRIP or SAPETY.

INJECTION.

U

't

EOP:

AP-FW.l TITLE:

PARTIAL OR COMPLETE LOSS OF MAIN FEEDWATER REV 5

PAGE 4 of 6 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 2

Check MFW Pumps:

a. At least one MFV pump - RUNNING
a. IF no MFV pumps are running, THEN verify turbine trip and go to AP-TURB.1, TURBINE TRIP VITHOUT RX TRIP REQUIRED OR E-O, REACTOR TRIP or SAFETY INJECTION.

3 Check MFW Pump Indications:

o MPW pump(s) suction pressure-GREATER THAN 185 PSIG IF MPV pump(s) suction pressure is NOT greater than 185 psig, THEN perform the following:

a. Verify standby condensate pump running, if required.

b; Verify condensate bypass valve open.

c. Place trim valve controller to manual and close trim valves.
d. Check if condensate booster pumps have tripped and start as necessary.

NOTE: If a malfunctioning MFV regulating valve is suspected, dispatch personnel to check valve locally.

4 Verify Adequate MFW Flow:

o "A" MFV flow - GREATER THAN "A" STEAM PLOW

-AND-o "B" MPV flow - GREATER THAN "B" STEAM FLOW Check MFW regulating valves controlling in AUTO, OR control feed flow in MANUAL.

IF MPV flow can NOT be controlled, THEN, trip the turbine and go to AP-TURB.l, TURBINE TRIP VITHOUT RX TRIP REQUIRED, or E-O, REACTOR TRIP or SAFETY INJECTION.

1 r

E P:

AP-FW. 1

. TITLE:

PARTIAL OR COMPLETE LOSS OF MAIN FEEDWATER REV:

5 ~

PAGE 5 of 6 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 5

Check S/G Levels:

o Narrov range levels - GREATER THAN 17X AND TRENDING TO PROGRAM LEVEL IF S/G levels can NOT be restored, THEN trip the reactor AND go to E-O, REACTOR TRIP or SAFETY INJECTION.

6 Establish Stable Plant Conditions:

a. Tavg - TRENDING TO TREF b.

PRZR pressure

- APPROXIMATELY 2235 PSIG

c. Narrov range S/G levels - AT PROGRAM LEVEL
a. Restore Tavg to normal:
1) Control rods controlling in
AUTO, OR adjust in MANUAL as necessary.
2) Borate if required for power reduction.
b. Ensure PRZR heaters and spray operating as required, OR if necessary control heaters and spray manually.
c. Ensure MFV regulating valves controlling in AUTO, OR control feed vater in MANUAL.

7 Check AFW pumps IN STANDBY MODE IF AFV pumps running, THEN stop and place in standby.

8 Establish CAUSE OF LOSS OF MFW FLOW NOTE:

Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.

9 Complete NOTIFICATION OF HIGHER SUPERVISION

EOP:

AP-FW.1

. TITLE:

PARTIAL OR COMPLETE LOSS OF MAIN FEEDWATER REV:

5 PAGE 6 of 6 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 10 Establish Further Guidance:

o Return to - APPROPRIATE OPERATING PROCEDURES

-END-

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V 4

AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY REV:

4 PAGE 1 of 5 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVXEW DATE T SUPERIN EN ENT

<<o7-49 0

EFFECTXVE DATE QA~ NON-QA REVIEWED BY:

CATEGORY 1.0 G INNASTATION START:

DATE TIME COMPLETED.

DATE

AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY REV 4

PAGE 2 of 5 A.

PURPOSE - This procedure provides guidance necessary to operate the plant with indication of high reactor coolant activity.

B.

ENTRY CONDITIONS/SYMPTOMS 1.

SYMPTOMS The symptoms of HIGH REACTOR COOLANT ACTIVITY are; a.

Unexplained increase in letdown line monitor, R-9, or b.

Sampling indicates I-131 equivalent GREATER THAN 0.2 uCi/gm, or c.

Sampling indicates gross degassed activity GREATER THAN 20 uCi/gm, or d.

Sampling indicates that total specific activity exceeds 84/E.

EOP:

AP-RCS.3 TITLE:

HIGH REACTOR COOLANT ACTIVITY REV:

4 PAGE 3 of 5 STEP ACTION/EXPECTED RESPONSE RBSPONSE NOT OBTAINED CAUTION IF LETDOWN PLOW BXCBEDS 60 GPM WHEN USING AOV-202, D/P ACROSS THE CVCS DEMINERALIZERS SHOULD BE MONITORED TO VBRIFY THAT FLOW IS CONTINUING THROUGH THE DI'S.

HOWBVER, PLOW THROUGH THE,DI'S SHOULD NOT EXCBBD 90 GPM.

1 Verify RCS Activity:

a. Direct HP - TO SAMPLE RCS FOR ACTIVITY b.

RCS activity - GREATER THAN NORMAL (Check with HP Department for normal activity)

b. IF normal activity verified,-

THEN direct ISC to check operability of R-9, letdown line

monitor, AND return to normal operations.

2 Increase Letdown Flow To 60 GPM:

a. Verify deborating DI isolated-DIVERT VLV CATION DEBOR DI AOV-244 IN BYPASS POSITION
b. Place PCV-135 to manual AND adjust as necessary

- TO CONTROL LETDOWN PRESSURE

a. Place AOV-244 in bypass position.

c.

Change orifices - CLOSE 40 GPM ORIFICE AND OPEN 60 GPM LTDN ORIFICB AOV-202 IMMEDIATELY

d. Ad5ust letdown pressure

- TO APPROXIMATELY 250 PSIG

e. Return PCV-135 - TO AUTO, IP DESIRED

C li l

EOP:

AP-RCS.3 TITLE:

HIGH REACTOR COOLANT ACTIVITY REV:

4

, PAGE 4 of 5 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED NOTE:

Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.

3 Check Area Monitor R9 Letdown Line LESS THAN 500 mr/hr ABOVE BACKGROUND CAUTION Refer to SC-100, GINNA STATION EVENT EVALUATION AND CLASSIFICATION.

WHEN A NEW DI IS VALVED IN, THERE MAY BE A DUE TO A BORON CHANGE.

(REPER TO S-3.2B TO PLUS OR MINUS REACTIVITY ADDITION PREVENT A REACTIVITY CHANGE.)

4 Verify Proper Operation Of Letdown DI DECONTAMINATION FACTOR GREATER THAN 10 IP DI efficiency is NOT acceptable, THEN place a nev mixed bed in service.

(Refer to S-4.5.7A, A

LETDOWN MIXED BED DI RESIN REPLACEMENT, OR S-4.5.7B, B LETDOWN MIXED BED DI RESIN REPLACEMENT).

5 Check Sampling Requirements REFER TO TECHNICAL SPECIFICATION TABLE 4.1-4 6

Check If Continued Plant

,Power Operation Allowed:

o Continued plant pover operation

- ALLOWED, REFER TO TECHNICAL SPECIFICATION SECTION 3'1.4 IP shutdown is required, THEN refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN.

o ~

EOP:

AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY REV:

4 PAGE 5 of 5 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 7

Check Aux Bldg For Increased Radiation Levels:

a. Notify HP Department

- TO SURVEY AUX BLDG

b. Aux Bldg radiation levels-NORMAL (Check vith HP for normal readings)
b. IF Aux Bldg radiation levels indicate above normal, THEN have HP Department establish controls for the higher radiation areas.

8 Complete NOTIFICATION TO HIGHER SUPERVISION AND THE REACTOR ENGINEER 9

Check Conditions For Offsite Reporting:

o Refer to - SC-100, GINNA STATION EVENT EVALUATION AND CLASSIFICATION

-END-

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