ML17264A978

Rev 12 to AP-RCS.1, Reactor Coolant Leak.

ML17264A978
Person / Time
Site:	Ginna
Issue date:	08/05/1997
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17264A976	List: ML17264A975 ML17264A977 ML17264A978 ML17264A979 ML17311A050
References
AP-RCS.1, NUDOCS 9708130138
Download: ML17264A978 (14)

Text

EOP:

REV: 12 AP-RCS.1 REACTOR COOLANT LEAK PAGE 1 of 11 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIB MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BX:

9708130%38 970805 05000244 PDR ADQCK

EOP:

REV: 12 AP-RCS.1 REACTOR COOLANT LEAK PAGE 2 of 11 A. PURPOSE This procedure provides the instructions necessary to mitigate the consequences of a reactor coolant leak.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS This procedure is entered from:

a. S-12.2, OPERATOR ACTION IN THE EVENT OF INDICATION OF SIGNIFICANT INCREASE IN LEAKAGE, when a significant increase in RCS leakage is indicated.

b. AP-CVCS.1, CVCS LEAK, when leak cannot be isolated.

2. SYMPTOMS The symptoms of REACTOR COOLANT LEAK are;

a. Annunciator F-14, CHARGING PUMP, SPEED, lit, or

b. Annunciator A-2, VCT LEVEL 144 86, lit, or

c. Annunciator E-16, RMS PROCESS MONITOR HIGH ACTIVITY, lit, or

d. Annunciator E-24, RMS AREA MONITOR HIGH ACTIVITY, or lit, lit,'r

e. Annunciator F-4, PRESSURIZER LEVEL DEVIATION -5 NORMAL +5,

f. Annunciator F-10, PRESSURIZER LO PRESS 2185 PSI, lit, or

g. Annunciator F-11, PRESSURIZER LO LEVEL 134, lit.

EOP:

REV: 12 AP-RCS.1 REACTOR COOLANT LEAK PAGE 3 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF, AT ANY TIME DURING THIS PROCEDURE, A REACTOR TRIP OR SI OCCURS, E-O, REACTOR TRIP OR SAFETY INJECTION, SHALL BE PERFORMED.

NOTE:- Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION.

1 Check PRZR Level STABLE AT IF PRZR level decreasing, THEN PROGRAM LEVEL start additional charging pumps and increase speed as necessary to stabilize PRZR level.

IF PRZR level continues to decrease, THEN close loop B cold leg to REGEN Hx isolation valve, AOV-427.

IF available charging pumps are running at maximum speed with letdown isolated, AND PRZR level is decreasing, THEN trip the reactor and go to E-O, REACTOR TRIP or SAFETY INJECTION.

EOP: T1TLE:

REV: 12 AP-RCS.1 REACTOR COOLANT LEAK PAGE 4 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: IF VCT level decreases to 5%, charging pump suction will swap to the RWST. This may require a load reduction.

2 Check VCT Makeup System:

a. Verify VCT level - GREATER THAN a. Ensure charging pump suction 5a aligned to RWST.

~ LCV-112B - OPEN

~ LCV-112C - CLOSED

b. Verify the following: b. Adjust controls as necessary.

1) RMW mode selector switch in AUTO

2) RMW control armed - RED LIGHT LIT

c. Check VCT -level: c. Check letdown divert valve, LCV-112A, closed.

o Level GREATER THAN 20$

IF VCT makeup flow NOT adequate,

-OR- THEN perform the following:

o Level - STABLE OR INCREASING 1) Ensure BA transfer pumps and RMW pumps running.

2) Adjust RMW flow control valve, HCV-111, to increase RMW flow.

3) Increase boric acid flow as necessary to maintain required concentration.

IF VCT level can NOT be maintained, THEN refer to ER-CVCS.1, REACTOR MAKEUP CONTROL MALFUNCTION, necessary.

if

EOP: TITLE:

REV: 12 AP-RCS.l REACTOR COOLANT LEAK PAGE 5 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Check If RCS Leakage In CNMT: IF leakage is indicated in CNMT, THEN perform the following:

o Check CNMT radiation monitors-NORMAL a. Direct HP to sample CNMT for entry.

~ R-2

~ R-7 b. Continue'with Step 4. WHEN CNMT

~ R-lOA cleared for entry, THEN dispatch

~ R-11 personnel to investigate CNMT

~ R-12 for RCS leakage. /

o CNMT sump A pump run frequency-NORMAL (Refer to RCS Daily Leakage Log)

CAUTION RADIATION PROTECTION TECHNICIAN SHOULD BE CONSULTED PRIOR TO ENTERING A HIGH AIRBORNE AREA.

4 Dispatch AO To AUX BLDG To Investigate For CVCS Leak (locked area keys required) 5 Check For Leak To CCW System: Go to AP-CCW.1, LEAKAGE INTO THE COMPONENT COOLING LOOP.

o CCW surge tank level-APPROXIMATELY 50% AND'TABLE o CCW radiation monitor, R NORMAL

EOP: TITLE:

REV: 12 AP-RCS.1 REACTOR COOLANT LEAK PAGE 6 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Check CVCS Conditions:

a. Letdown indication: a. IF letdown isolated, THEN continue with Step 6b. IF NOT o Letdown flow - APPROXIMATELY isolated, THEN go to AP-CVCS.1, 40 GPM CVCS LEAK, Step 6.

o Low pressure LTDN pressure-APPROXIMATELY 250 PSIG o Letdown pressure control valve, PCV-135, demand-APPROXIMATELY 35% OPEN

b. Charging indication: b. Go to AP-CVCS.1, CVCS LEAK, Step 6.

o Seal injection flows GREATER THAN 6 GPM AND STABLE o RCP Labyrinth seal D/Ps GREATER THAN 15 INCHES AND APPROXIMATELY EQUAL o Charging pump discharge pressure - GREATER THAN RCS PRESSURE

c. AUX BLDG radiation levels c. Go to AP-CVCS.1, CVCS LEAK, NORMAL Step 6 and refer to CVCS piping diagrams for further guidance.

~ R-4

~ R-9

~ R-10B

~ R-13

~ R-14

EOP: TlTLE:

REV: 12 AP-RCS.1 REACTOR COOLANT LEAK PAGE 7 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check PRT Indications: Check tailpipe and valve leakoff temperatures for the PRZR safety

a. Level - >BETWEEN 61% AND 84% valves and PORVs for indication of leakage.

b. Pressure - APPROXIMATELY 1.5 PSIG AND STABLE IF no PORV,or safety valve leakage is indicated, THEN check other leak

c. Temperature - AT CNMT AMBIENT paths from the RCS to the PRT.

TEMPERATURE AND STABLE

~ Letdown relief valve, RV-203

~ Seal return relief valve, RV-314 CAUTION STEAM GENERATOR TUBE LEAKAGE IN ONE S/G SHALL NOT EXCEED 0.1 GPM WHEN AVERAGED OVER 24 HOURS.

8 Check S/Gs For Leakage: IF S/G tube leak indicated, THEN refer to 0-6.10, PLANT OPERATION o Air ejector radiation monitors - ~

WITH A S/G TUBE LEAK INDICATION.

NORMAL

~ R-15

~ R-15A o S/G blowdown radiation monitor (R-19) - NORMAL o Steamline radiation monitors NORMAL

~ R-31

~ R-32 o S/G sample activity - NORMAL (Check with RP Department for normal)

EOP:

REV: 12 AP-RCS.1 REACTOR COOLANT LEAK PAGE 8 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Check SI Accumulator Levels Calculate inleakage to SI STABLE accumulators (Refer to S-16.11, MONITORING INLEAKAGE TO SI ACCUMULATORS).

10 Check RCP Seal Leakoff Flows: Go to AP-RCP.l, RCP SEAL MALFUNCTION.

o Leakoff flows - WITHIN THE NORMAL OPERATING RANGE OF FIGURE RCP SEAL LEAKOFF o Leakoff flows - STABLE 11 Check RCDT Leak Rate NORMAL Check other sources of in leakage (Refer to RCS Daily Leakage to RCDT:

Log and PPCS point ID L1003)

a. IF Rx vessel flange leakoff temperature has increased, THEN close Rx VESS FLANGE VLV, AOV-521.

SEAL'EAKOFF

b. Verify excess letdown isolated.

IF NOT, THEN ensure RCDT divert valve, AOV-312, in the VCT position.

c. IF source of leakage NOT determined, THEN suspect loop drains.

EOP: TITLE REV: 12 AP-RCS.1 REACTOR COOLANT LEAK PAGE 9 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check Valve Leakoff IF any valve leakoff temperature is Temperatures NORMAL (Refer abnormally high, THEN initiate to Pressurizer Valve Leak-Off investigation of that leakage path.

Temperature Record Log) 13 Establish Stable Plant Conditions:

a. PRZR level - TRENDING TO PROGRAM a. Control charging and letdown flows to restore PRZR level to program.

b. Check PRZR pressure control: b. Verify proper operation of PRZR heaters and spray or take manual o Pressure - TRENDING TO control of PRZR pressure 2235 PSIG controller 431K. IF pressure can NOT be controlled, THEN o PRZR backup heaters - OFF refer to AP-PRZR,l, ABNORMAL PRESSURIZER PRESSURE, 14 Evaluate RCS Leakage:

a. Leakage within limits (Refer to a. IF leak NOT isolable, but PRZR leakage surveillance sheet and level and seal injection can be ITS section 3.4.13) maintained, THEN shut the plant down (Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN or AP-TURB.5, RAPID LOAD REDUCTION).

b. Leak location identified b. Return to Step l.

REV: 12 AP-RCS.1 REACTOR COOLANT LEAK PAGE 10 of ll STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.

15 Notify Higher Supervision

-END-

EOP:

REV: 12 REACTOR COOLANT LEAK PAGE 11 of ll AP-RCS.1 APPENDIX LIST TITLE PAGES

1) FIGURE RCP SEAL LEAKOFF

EOP: TITLE:

REV: 12 AP-RCS.1 REACTOR COOLANT LEAK PAGE 1 of 1 FIGURE RCP SEAL LEAKOFF kl SEAL LEAK RATE (GPH) 6 LEAK RATE INCREHENTS 0.2 GPH 3

NORHAL OPERATING RANGE DP INCREHENTS 50 PSI 250 500 750 1000 1250 1500 1750 2000 2250 2500 81 SEAL DP (RCS PRESS - VCT PRESS) PSI

J