Similar Documents at Ginna |
|---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17250B3061999-10-20020 October 1999
Proposed Tech Specs,Consisting of 1999 Changes to TS Bases
ML17265A6941999-06-28028 June 1999
Proposed Tech Specs,Revising ITS Associated with RCS Leakage Detection Instrumentation,As Result of Commitment Submitted as Part of Staff Review of Application of leak-before-break Status to Protions of RHR Piping
ML17265A6401999-05-12012 May 1999
Rev 11 to Technical Requirements Manual for Ginna Station.
ML17265A6261999-04-18018 April 1999
Rev 10 to Technical Requirements Manual (Trm), for Ginna Station
ML17311A0701999-04-14014 April 1999
Rev 10 to AP-PRZR.1, Abnormal Pressurizer Pressure.
ML17309A6521999-04-14014 April 1999
Rev 14 to AP-RCS.1, Reactor Coolant Leak.
ML17309A6531999-04-13013 April 1999
Rev 1 to FIG-2.0, Figure Sdm. with 990413 Ltr
ML17265A6111999-03-26026 March 1999
Rev 9 to Technical Requirements Manual for Ginna Station.
ML17265A5911999-03-0101 March 1999
Proposed Tech Specs Change Revising Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6)
ML17265A5571999-02-25025 February 1999
Rev 4 to Technical Requirements Manual (Trm).
ML17265A5491999-02-12012 February 1999
to EOP FR-H.5, Response to SG Low Level.
ML17265A5481999-02-12012 February 1999
to EOP ATT-22.0, Attachment Restoring Feed Flow.
ML17265A5461999-02-12012 February 1999
0 to EOP AP-TURB.1, Turbine Trip Without Rx Trip Required.
ML17309A6481999-01-25025 January 1999
Revised Ginna Station Emergency Operating Procedures. with 990125 Ltr
ML17265A5151999-01-14014 January 1999
Revised Emergency Operating Procedures,Including Rev 14 to AP-SW.1,rev 3 to ATT-5.2,rev 5 to ATT-8.0,rev 1 to ATT-14.6, Rev 17 to E-1,rev 16 to ECA-1.1,rev 26 to ES-1.3,rev 4 to FR-Z.2 & Index
ML17265A5081999-01-0808 January 1999
Rev 7 to Technical Requirements Manual, for Ginna Station
ML17265A4961998-12-18018 December 1998
Rev 6 to Technical Requirements Manual.
ML20198C0361998-12-14014 December 1998
Rev 11 to ECA-0.2, Loss of All AC Power Recovery with SI Required
ML20198C0121998-12-14014 December 1998
Rev 10 to AP-RCS.2, Loss of Reactor Coolant Flow
ML20198C0581998-12-14014 December 1998
Rev 5 to FR-Z.1, Response to High Containment Pressure
ML20198C0411998-12-14014 December 1998
Rev 16 to FR-C.1, Response to Inadequate Core Cooling
ML20198C0521998-12-14014 December 1998
Rev 13 to FR-S.1, Response to Reactor Restart/Atws
ML17265A4661998-11-24024 November 1998
Proposed Tech Specs 4.2.1,revising Description of Fuel Cladding Matl & Updating List of References Provided in TS 5.6.5 for COLR
ML20155G0301998-10-30030 October 1998
Rev 13 to EOP AP-CCW.1, Leakage Into Component Cooling Loop
ML17265A4091998-08-24024 August 1998
Rev 13 to AP-SW.1, Svc Water Leak. W/980824 Ltr
ML17265A3721998-07-16016 July 1998
Rev 14 to EOP AP-CW.1, Loss of Circ Water Pump. W/980716 Ltr
ML17265A3151998-06-0404 June 1998
Proposed Tech Specs Basis Re Main Steam Isolation Setpoint
ML17265A2941998-05-21021 May 1998
Tech Specs Consisting of Submittal Changes for 1998
ML17265A2861998-05-0606 May 1998
Rev 19 to EOP ECA-3.2, SGTR W/Loss of Reactor Coolant Saturated Recovery Desired & Updated ECA Index.W/980506 Ltr
ML17265A2461998-04-27027 April 1998
Proposed Tech Specs Revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool
ML17265A1821998-02-20020 February 1998
Rev 1 to EWR 5111, MOV Qualification Program Plan, Calculation Assumption Verification Criteria.
ML17265A1491997-12-31031 December 1997
Rev 1 to Inservice Testing Program.
ML17264B0731997-10-14014 October 1997
Rev 4 to Technical Requirements Manual (TRM) for Ginna Station.
ML17264B0671997-10-0808 October 1997
Proposed Tech Specs,Correcting & Clarifying Info Re RCS Pressure & Temp Limits Rept Administrative Controls Requirements
ML17264B0441997-09-29029 September 1997
Proposed Tech Specs Revising Adminstrative Controls W/ Respect to Reactor Coolant Sys Pressure & Temp Limits Rept
ML17264B0391997-09-29029 September 1997
Proposed Tech Specs Revising Allowable Value & Trip Setpoint for High Steam Flow Input Into LCO Table 3.3.2-1,Function 4d (Main Steam Isolation) to Address Issues Identified in Rev Revised Setpoint Analysis Study
ML17265A1541997-09-16016 September 1997
Rev 1 to DA EE-92-089-21, Design Analysis Ginna Station Instrument Loop Performance Evaluation & Setpoint Verification.
ML17264B0031997-08-19019 August 1997
Proposed Tech Specs Allowing Testing of Three ECCS motor- Operated Valves in Mode 4 Which Currently Requires Entry Into LCO 3.0.3
ML17264A9991997-08-19019 August 1997
Proposed Tech Specs Correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values
ML17264A9791997-08-0505 August 1997
Rev 7 to AP-RCS.3, High Reactor Coolant Activity.
ML17264A9781997-08-0505 August 1997
Rev 12 to AP-RCS.1, Reactor Coolant Leak.
ML17264A9771997-08-0505 August 1997
Rev 11 to AP-RCP.1, RCP Seal Malfunction.
ML17264A9751997-08-0505 August 1997
Rev 14 to AP-ELEC.1, Loss of 12A & 12B Busses.
ML17264A9851997-08-0404 August 1997
Rev 2 to Summary Description of Compliance w/10CFR73 Amend Protection Against Malevolent Use of Vehicles at Nuclear Power Plants.
ML17264A9391997-07-0707 July 1997
Rev 3 to Technical Requirements Manual for Ginna Station, Inserting New Tabs Accordingly Per Previous Transmittal for Rev
ML17264A9341997-07-0101 July 1997
to Technical Requirements Manual (TRM) & inter-office Correspondence Dtd 970624
ML17264A9461997-06-20020 June 1997
to Inservice Insp (ISI) Program.
ML17264A9241997-06-0303 June 1997
Proposed Tech Specs Clarifying Issues Re Low Temperature Overpressure Protection
ML17311A0471997-05-22022 May 1997
Revised Eops,Including Procedures Index,Rev 5 to ATT-15.0, Rev 3 to ATT-15.2,rev 3 to AP-ELEC.3,rev 13 to ECA-0.1 & Rev 9 to ECA-0.2.W/970522 Ltr
ML17264A8671997-04-24024 April 1997
Proposed Tech Specs,Revising Rcs,Pt & Administrative Control Requirements
1999-06-28
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17265A6401999-05-12012 May 1999
Rev 11 to Technical Requirements Manual for Ginna Station.
ML17265A6261999-04-18018 April 1999
Rev 10 to Technical Requirements Manual (Trm), for Ginna Station
ML17309A6521999-04-14014 April 1999
Rev 14 to AP-RCS.1, Reactor Coolant Leak.
ML17311A0701999-04-14014 April 1999
Rev 10 to AP-PRZR.1, Abnormal Pressurizer Pressure.
ML17309A6531999-04-13013 April 1999
Rev 1 to FIG-2.0, Figure Sdm. with 990413 Ltr
ML17265A6111999-03-26026 March 1999
Rev 9 to Technical Requirements Manual for Ginna Station.
ML17265A5571999-02-25025 February 1999
Rev 4 to Technical Requirements Manual (Trm).
ML17265A5481999-02-12012 February 1999
to EOP ATT-22.0, Attachment Restoring Feed Flow.
ML17265A5491999-02-12012 February 1999
to EOP FR-H.5, Response to SG Low Level.
ML17265A5461999-02-12012 February 1999
0 to EOP AP-TURB.1, Turbine Trip Without Rx Trip Required.
ML17309A6481999-01-25025 January 1999
Revised Ginna Station Emergency Operating Procedures. with 990125 Ltr
ML17265A5151999-01-14014 January 1999
Revised Emergency Operating Procedures,Including Rev 14 to AP-SW.1,rev 3 to ATT-5.2,rev 5 to ATT-8.0,rev 1 to ATT-14.6, Rev 17 to E-1,rev 16 to ECA-1.1,rev 26 to ES-1.3,rev 4 to FR-Z.2 & Index
ML17265A5081999-01-0808 January 1999
Rev 7 to Technical Requirements Manual, for Ginna Station
ML17265A4961998-12-18018 December 1998
Rev 6 to Technical Requirements Manual.
ML20198C0581998-12-14014 December 1998
Rev 5 to FR-Z.1, Response to High Containment Pressure
ML20198C0361998-12-14014 December 1998
Rev 11 to ECA-0.2, Loss of All AC Power Recovery with SI Required
ML20198C0521998-12-14014 December 1998
Rev 13 to FR-S.1, Response to Reactor Restart/Atws
ML20198C0411998-12-14014 December 1998
Rev 16 to FR-C.1, Response to Inadequate Core Cooling
ML20198C0121998-12-14014 December 1998
Rev 10 to AP-RCS.2, Loss of Reactor Coolant Flow
ML20155G0301998-10-30030 October 1998
Rev 13 to EOP AP-CCW.1, Leakage Into Component Cooling Loop
ML17265A4091998-08-24024 August 1998
Rev 13 to AP-SW.1, Svc Water Leak. W/980824 Ltr
ML17265A3721998-07-16016 July 1998
Rev 14 to EOP AP-CW.1, Loss of Circ Water Pump. W/980716 Ltr
ML17265A2861998-05-0606 May 1998
Rev 19 to EOP ECA-3.2, SGTR W/Loss of Reactor Coolant Saturated Recovery Desired & Updated ECA Index.W/980506 Ltr
ML17265A1821998-02-20020 February 1998
Rev 1 to EWR 5111, MOV Qualification Program Plan, Calculation Assumption Verification Criteria.
ML17265A1491997-12-31031 December 1997
Rev 1 to Inservice Testing Program.
ML17264B0731997-10-14014 October 1997
Rev 4 to Technical Requirements Manual (TRM) for Ginna Station.
ML17265A1541997-09-16016 September 1997
Rev 1 to DA EE-92-089-21, Design Analysis Ginna Station Instrument Loop Performance Evaluation & Setpoint Verification.
ML17264A9751997-08-0505 August 1997
Rev 14 to AP-ELEC.1, Loss of 12A & 12B Busses.
ML17264A9771997-08-0505 August 1997
Rev 11 to AP-RCP.1, RCP Seal Malfunction.
ML17264A9791997-08-0505 August 1997
Rev 7 to AP-RCS.3, High Reactor Coolant Activity.
ML17264A9781997-08-0505 August 1997
Rev 12 to AP-RCS.1, Reactor Coolant Leak.
ML17264A9851997-08-0404 August 1997
Rev 2 to Summary Description of Compliance w/10CFR73 Amend Protection Against Malevolent Use of Vehicles at Nuclear Power Plants.
ML17264A9391997-07-0707 July 1997
Rev 3 to Technical Requirements Manual for Ginna Station, Inserting New Tabs Accordingly Per Previous Transmittal for Rev
ML17264A9341997-07-0101 July 1997
to Technical Requirements Manual (TRM) & inter-office Correspondence Dtd 970624
ML17264A9461997-06-20020 June 1997
to Inservice Insp (ISI) Program.
ML17311A0471997-05-22022 May 1997
Revised Eops,Including Procedures Index,Rev 5 to ATT-15.0, Rev 3 to ATT-15.2,rev 3 to AP-ELEC.3,rev 13 to ECA-0.1 & Rev 9 to ECA-0.2.W/970522 Ltr
ML20140B8291997-03-24024 March 1997
Rev 3 to EOP ATT-12.0, Attachment N2 Porvs
ML17264A8221997-02-0606 February 1997
Rev 15 to FR-P.1, Response to Imminent Pressurized Thermal Shock Condition.
ML17264A8201997-02-0606 February 1997
Rev 7 to AP-RCC.2, Rcc/Rpi Malfunction.
ML17264A8081997-01-23023 January 1997
Revised Emergency Operating Procedures,Including Rev 14 to E-1,Rev 19 to E-3,Rev 14 to ECA-2.1,Rev ECA-3.3,Rev 20 to ES-1.3,Rev 13 to FR-C.1,Rev 12 to FR-C.2 & Rev 14 to FR-P.1
ML20133N3351997-01-10010 January 1997
Rev 7 to FR-C.3, Response to Saturated Core Cooling
ML17264A8881996-10-10010 October 1996
Rev 9 to ODCM for Ginna Station.
ML20128N0681996-10-0303 October 1996
Revised Emergency Operating Procedures,Including Rev 5 to Att-10.0, Attachment Faulted S/G & Rev 6 to Att-16.0, Attachment Ruptured S/G
ML17264A5311996-05-31031 May 1996
Revised Emergency Operating Procedures,Including Rev 10 to AP-RCP.1,Rev 12 to ECA-0.1,Rev 12 to ECA-2.1,Rev 3 to FR-H.2,Rev 3 to FR-H.4,Rev 7 to FR-I.1,Rev 12 to FR-P.1,Rev 10 to FR-S-1 & Rev 6 to FR-S.2
ML17264A5161996-05-22022 May 1996
Rev 2 to Technical Requirements Manual (TRM)
ML17264A4581996-04-0808 April 1996
Rev 7 to ODCM for Ginna Station.
ML17264A4371996-04-0101 April 1996
Rev 1 to Technical Requirements Manual (TRM)
ML17264A4391996-04-0101 April 1996
Rev 1 to Updated Technical Requirements Manual (TRM)
ML17264A4191996-02-24024 February 1996
Rev 0 to Technical Requirements Manual (Trm).
ML17264A6901996-02-23023 February 1996
Rev 0 to Inservice Testing Program.
1999-05-12
[Table view] |
Text
EOP: TITLE:
REV: 6 AP-CVCS.1 CVCS LEAK PAGE 1 of 12 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT'SUPERINTENDENT EF ECT VE DATE CATEGORY 1.0 REVIEWED BY:
920blb0408 920b05 PDR ADOCK 05000244 P PDR
gl
~ ~
4 ~
ea
~ .
Ss I
4
EOP:
REV 6 AP-CVCS.1 CVCS LEAK PAGE 2 of 12 A. PURPOSE This procedure provides the necessary instructions to mitigate the consequences of a CVCS leak.
B. ENTRY CONDITIONS/SYMPTOMS
- 1. ENTRY CONDITIONS This procedure is entered from;
- a. AP-RCS.1, REACTOR COOLANT LEAK, when conditions indicate a CVCS leak.
- 2. SYMPTOMS The symptoms of CVCS leak are;
- a. Annunciator B-9 (B-10), RCP A(B) LABYR SEAL LO DIFF PRESS 15" H20, lit, or
- b. Charging line pressure low, or
- c. Annunciator F-14, CHARGING PUMP SPEED, lit, or
- d. Annunciator A-4, REGEN HX LETDOWN OUT HI TEMP 395'F, lit, or
- e. Letdown line low pressure and/or low flow, or
- f. ,Charging Pump Room area monitor R-4 on alarm.
q
1 'g
EOP: T!TLE:
REV: 6 AP-CVCS.1 CVCS LEAK PAGE 3 of 12 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: o Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION.
o A local radiation emergency should be declared for any unexplained area radiation monitor alarm.
1 Monitor PRZR Level STABLE IF PRZR level decreasing, THEN AT 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.
P I
~ t f'
EOP: TITLE:
REV: 6 AP-CVCS.1 CVCS LEAK PAGE 4 of 12 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 the following: a. Adjust controls as necessary.
- 1) RMW mode selector switch in AUTO
- 2) RMW control armed - RED LIGHT LIT
- b. Check VCT level: b. Check letdown divert valve, LCV-112A, aligned to VCT.
o Level GREATER THAN 20%
Manually increase VCT makeup
-OR- flow as follows:
o Level - STABLE OR INCREASING 1) Ensure BA transfer pumps and RMW pumps running.
- 2) Place RMW flow contxol valve, HCV-111, in MANUAL and increase RMW flow.
- 3) Increase boric acid flow as necessary.
IF VCT level can NOT be maintained, THEN refer to ER-CVCS.2, REACTOR MAKEUP CONTROL MALFUNCTION, if necessary.
'\
I~
EOP: TITLE:
REV: 6 AP-CVCS.1 CVCS LEAK PAGE 5 of 12 STEP ACTIONEEXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Check Charging Pump Suction Aligned To VCT:
- a. VCT 'level - GREATER THAN 20% a. IF VCT level can NOT be maintained greater than 5S, THEN perform the following:
- 1) Ensure 'charging pump suction aligned to RWST o LCV-112B open o LCV-112C closed
- 2) Continue with Step 4. WHEN VCT level greater, than 20%,
THEN do Step 3b.
- b. Verify charging pumps aligned to b.'anually align valves as VCT necessary.
o LCV-112C open o LCV-112B closed 4 Check Xf 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 5 WHEN CNMT
~
~ R-10A cleared for entry, THEN dispatch
~ R-ll personnel to investigate CNMT
~ R-12 for RCS leakage.
o CNMT sump A pump run frequency-NORMAL (Refer to leakage surveillance sheet)
e
~ l
EOP: TITLE REV: 6 AP-CVCS.1 CVCS LEAK PAGE 6 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION HEALTH PHYSICS TECHNICIAN SHOULD BE CONSULTED PRIOR TO ENTERING A HIGH AIRBORNE AREA.
5 Check BLDG:
If RCS Leakage In AUX Dispatch AO To AUX BLDG To Investigate For CVCS Leak (locked area keys required)
- a. Check AUX BLDG radiation monitors - NORMAL
~ R-4
~ R-9
~ R-lOB
~ R-13
~ R-14
- b. AUX BLDG sump pump run frequency
- NORMAL (Refer to leakage surveillance sheet)
- c. AUX BLDG sump tank leak rate NORMAL (Refer to leakage surveillance sheet)
l
~1 1
EOP:
REV' AP-CVCS.1 CVCS LEAK PAGE 7 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Check For Leak In Charging Perform the following:
Line To REGEN Hx:
a.'lose or verify closed loop B o Annunciator A-4, REGEN HX cold leg to REGEN Hx, AOV-427.
LETDOWN OUT HI TENP 395'F EXTINGUISHED b. Close letdown orifice valves (AOV-200A, AOV-200B, and o REGEN Hx letdown outlet AOV-202).
temperature - LESS THAN 350'F AND STABLE (archive PPCS point c. Control charging pump speed as ID T0127) necessary to maintain RCP labyrinth seal D/P less than 80 inches.
- d. Close charging flow control valve, HCV-142.
- e. Close charging to loop B cold leg, AOV-294.
- f. Go to Step 9.
rj, tT
~ k 4
~ t
EOP: TlTLE:
REV: 6 AP-CVCS.1 CVCS LEAK PAGE 8 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION o IF LEAK EXISTS IN THE LETDOWN LINE, H2 GASES FROM THE VCT MAY DIFFUSE OUT THE LEAK AND CAUSE A HAZARDOUS CONDITIONS o "
WHILE ON EXCESS LETDOWN, VCT LEVEL MAY BE DECREASED BY MANUALLY DIVERTING EXCESS LETDOWN FLOW TO THE RCDT USING AOV-312.
7 Check Normal Letdown:
- a. Normal letdown - IN SERVICE a. Perform the following:
- 1) IF excess letdown in service, THEN perform the following:
a) Close excess letdown isolation valve, AOV-310.
b) Close excess letdown flow control valve, HCV-123.
- 2) Go to Step 8.
- b. Check Letdown Indications: b. Isolate Normal Letdown:
o Letdown flow - APPROXIMATELY 1) Close loop B cold leg to 40 GPM REGEN Hx, AOV-427 o Low pressure LTDN pressure 2) Close letdown orifice valves APPROXIMATELY 250 PSIG (AOV-200A, AOV-200B, and AOV-202) o Pressure control valve, PCV-135, demand- , 3) Control charging pump speed APPROXIMATELY 35% OPEN as necessary to maintain RCP labyrinth seal D/P less than 80 inches.
- 4) Close charging flow control valve, HCV-142
- 5) Close charging to loop B cold leg, AOV-294.
- 6) Establish excess letdown (Refer to Attachment EXCESS LETDOWN).
- 7) Go to Step 12.
d ~
EOP: TITLE:
REV: 6 AP-CVCSe1 CVCS LEAK PAGE 9 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Check For Leakage To CCW IF leakage to the CCW system is System: indicated, THEN go to AP-CCW.1, LEAKAGE INTO THE COMPONENT COOLING o CCW radiation monitor (R-17) LOOP.
NORMAL o CCW surge tank level APPROXIMATELY 50% AND STABLE CAUTION RCP OPERATION WITHOUT SEAL INJECTION SHOULD BE MINIMIZED.
9 Check RCP Seal Injection IF RCP seal injection leak is Indications: suspected, THEN perform the following:
o Seal injection flows - GREATER THAN 6 GPM AND STABLE a. Verify charging flow control valve, HCV-142, open. IF no o RCP labyrinth seal D/Ps charging path through REGEN Hx GREATER THAN 15 INCHES AND available, THEN go to Step 15.
APPROXIMATELY EQUAL
- b. Verify CCW cooling to operating o RCP seal inlet temperatures RCF thermal barriers. IF NOT, STABLE THEN seal injection should be maintained.
- c. Attempt to locate and isolate leak.
- d. Go to Step 12.
%A I
~ 'P
EOP: TITLE:
REV: 6 AP-CVCS.1 CVCS LEAK PAGE 10 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Check RCP Seal Leakoff Flows: Dispatch AO with a key to the RWST gate to .check seal return line for o RCP seal leakoff flows - GREATER leakage.
THAN 0.,25 GPM IF a seal return line leak is o RCP seal leakoff flows - STABLE indicated downstream of RCP seal return isolation valve, MOV-313, THEN perform the following:
- a. Close RCP seal return isolation valve, MOV-313.
- b. Monitor RCP indications.
- c. Evaluate leak location. IF possible, THEN isolate the seal
.return line from the VCT.
- d. Go to Step 12.
IF no seal return line leakage, indicated in the AUX BLDG, THEN investigate for leakage in CNMT.
11 Evaluate Local Leak Determine if leak can be isolated Investigation CVCS SYSTEM (Refer to CVCS piping diagrams. as INTACT IN AUX BLDG necessary).
12 Evaluate Plant Status:
- a. Leak location identified a. IF CVCS leak NOT indicated, THEN go to AP-RCS.1, REACTOR COOLANT LEAK.
- b. Check RCS conditions: b. Perform the following:
o Leakage within limits (Refer 1) Ini.tiate plant shutdown to leakage surveillance sheet (Refer to 0-2.1, NORMAL and Tech Spec section 3.1.5) SHUTDOWN TO HOT SHUTDOWN).
o At least one charging 2) Go to Step 15.
flowpath - AVAILABLE FOR INVENTORY,CONTROL
I
EOP: TITLE:
REV: 6 AP-CVCS.1 CVCS LEAK PAGE 11 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Check Normal Or Excess IF normal letdown desired, THEN Letdown IN SERVICE perform the following:
- a. Verify charging line flow to REGEN Hx - GREATER THAN 20 GPM
- b. Place letdown controllers in MANUAL at 35% open.
~ TCV-130
~ PCV-135
- c. Verify letdown isolation valve, AOV-371, - OPEN
- d. Open B loop cold to REGEN Hx, AOV-427
- e. Open letdown orifice valves as necessary
- f. Place TCV-130 in auto at 105 'F
- g. Place PCV-135 in AUTO at 250 psig
- h. Adjust charging pump and HCV-142 as necessary to control PRZR level and RCP labyrinth seal D/P IF normal letdown NOT available, THEN establish excess letdown if desired (Refer to Attachment EXCESS LETDOWN).
EOP:
REV: 6 AP-CVCS.1 CVCS LEAK PAGE 12 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Establish Stable Plant Conditions:
- a. PRZR level - TRENDING TO PROGRAM a. Control charging flow as necessary to restore PRZR level to program.
- b. PRZR pressure - AT OR TRENDING b. Verify proper operation of PRZR TO 2235 PSIG heaters and spray or take manual control of PRZR pressure controller 431K. IF pressure can NOT be controlled, THEN refer to AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE.
NOTE: Refer to 0-9.3, NRC STATE AND COUNTIES IMMEDIATE NOTIFICATION, for reporting requirements.
15 Notify Higher Supervision
-END-
EOP:
REV: 6 AP-CVCS.1 CVCS LEAK PAGE 1 of 1 AP-CVCS.1 APPENDIX LIST TITLES PAGES
- 1) Attachment EXCESS LETDOWN
i I
