|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F9701999-10-14014 October 1999 Proposed Tech Specs,Incorporating ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plate Intersections ML20217E4301999-10-12012 October 1999 Proposed Tech Specs,Revising Requirements for Containment Penetrations During Refueling Operations ML20211K1201999-08-30030 August 1999 Proposed Tech Specs,Adding New Specification That Addresses Use of Interim Provisions Upon Discovery of Unintended TS Action ML20211M7341999-08-30030 August 1999 Marked-up & Revised TS Pages,Providing Alternative to Requirement of Actually Measuring Response Times ML20211K1721999-08-30030 August 1999 Proposed Tech Specs,Providing Clarification to Current TS Requirements for Containment Isolation Valves ML20209B7731999-06-30030 June 1999 Proposed Tech Specs Updating Requirmements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196F2211999-06-24024 June 1999 Proposed Tech Specs Pages for Amend to Licenses DPR-77 & DPR-79,allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20196G4701999-06-24024 June 1999 Proposed Tech Specs Pages Re Amends to Licenses DPR-77 & DPR-79,revising TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196G7961999-06-22022 June 1999 Proposed Tech Specs Bases,Clarifying Proper Application of TS Requirements for Power Distribution Systems & Functions That Inverters Provide to Maintain Operability & Providing Updated Info on Cold Leg Injection Accumulators ML20196G8071999-06-22022 June 1999 Revs to Technical Requirements Manual ML20195E9841999-06-0707 June 1999 Proposed Tech Specs,Increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core ML20206E1611999-04-29029 April 1999 Proposed Tech Spec Change 99-04, Auxiliary Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20206E1391999-04-29029 April 1999 Proposed Tech Spec Change 99-03, Main Control Room Emergency Ventilation Sys Versus Radiation Monitors. Changes Add LCOs 3.3.3.1 & 3.7.7 to Address Inoperability of Radiation Monitoring CREVS & NUREG-1431 Recommendations ML20204E8501999-03-21021 March 1999 Plant,Four Yr Simulator Test Rept for Period Ending 990321 ML20204H4081999-03-19019 March 1999 Proposed Tech Specs,Relocating TS 3.8.3.1,3.8.3.2,3.8.3.3 & Associated Bases Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207F7631999-03-0202 March 1999 Proposed Tech Specs Pages Re Application for Amends to Licenses DPR-77 & DPR-79,deleting Iseg from License Conditions ML20207D6011999-02-26026 February 1999 Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20207D6331999-02-26026 February 1999 Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets ML20199K6001999-01-15015 January 1999 Proposed Tech Specs Adding New Action Statement to 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Appropriate Overall Level of Protection ML20206S0131999-01-15015 January 1999 Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual ML20195H6111998-11-16016 November 1998 Proposed Tech Specs Revising EDG SRs by Adding Note That Allows SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Certain Lockout Features Prevent EDG Starting ML20154H7251998-10-0808 October 1998 Proposed Tech Specs Pages,Supplementing Proposed TS Change 96-08,rev 1 to Add CRMP to Administrative Controls Section & Bases of TS ML20238F3001998-08-27027 August 1998 Proposed Tech Specs Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of EDGs ML20238F1091998-08-27027 August 1998 Proposed Tech Specs Providing for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20209J1631998-08-0707 August 1998 Rev 41 to Sequoyah Nuclear Plant Odcm ML20236G5961998-06-29029 June 1998 Proposed Tech Specs Typed Pages for TS Change 95-19, Section 6 - Administrative Controls Deletions ML20249C6371998-06-26026 June 1998 Proposed Tech Specs Lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05 ML20248F0051998-05-28028 May 1998 Proposed Tech Specs for Section 6, Administrative Controls Deletions ML20217N3511998-04-30030 April 1998 Proposed Tech Specs Pages,Modifying Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4 ML20203J1681998-02-25025 February 1998 Proposed Tech Specs Pages,Revising EDG Surveillance Requirements to Delete Requirement for 18-month Insp IAW Procedures Prepared in Conjunction W/Vendor Recommendations & Modify SRs Associated W/Verifying Capability of DGs ML20202J7141998-02-13013 February 1998 Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20202J7651998-02-13013 February 1998 Technical Requirements Manual ML20202J6961998-02-13013 February 1998 Proposed Tech Specs Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20202J7601998-02-13013 February 1998 Proposed Tech Specs Section 3.7.9 Re Relocation of Snubber Requirements ML20198T4311998-01-21021 January 1998 Proposed Tech Specs Re New Position Title & Update of Description of Nuclear Organization ML20199F8231997-11-30030 November 1997 Cycle 9 Restart Physics Test Summary, for 971011-971130 ML20199K4571997-11-21021 November 1997 Proposed Tech Specs Adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required ML20211A3191997-09-17017 September 1997 Proposed Tech Specs Re Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20203B9731997-08-0505 August 1997 Rev 1 to RD-466, Test & Calculated Results Pressure Locking ML20217J5581997-07-31031 July 1997 Cycle Restart Physics Test Summary, for Jul 1997 ML20210J1671997-04-30030 April 1997 Snp Unit 1 Cycle 8 Refueling Outage Mar-Apr 1997,Results of SG Tube ISI as Required by TS Section 4.4.5.5.b & Results of Alternate Plugging Criteria Implementation as Required by Commitment from TS License Condition 2C(9)(d) ML20137T0871997-04-0909 April 1997 Proposed Tech Specs Re Elimination of Cycle 8 Limitation for SG Alternate Plugging Criteria ML20137M8581997-04-0101 April 1997 Proposed Tech Specs 2.1 Re Safety Limits & TS 3/4.2 Re Power Distribution Limits ML20137C8421997-03-19019 March 1997 Proposed Tech Specs Re Conversion from Westinghouse Electric Corp Fuel to Framatome Cogema Fuel ML20136J0381997-03-13013 March 1997 Proposed Tech Specs Section 5.6.1.2,revising Enrichment of Fuel for New Fuel Pit Storage Racks ML20134P8631997-02-14014 February 1997 Proposed Tech Specs Requesting Discretionary Enforcement for 48 Hours Which Is in Addition to 72 Hours Allowed Outage Time Provided by TS Action 3.8.1.1.b ML20134K9981997-02-0707 February 1997 Proposed Tech Specs Revising TS Change Request 96-01, Conversion from W Electric Corp Fuel to Framatome Cogema Fuel (MARK-BW-17), to Ensure That Core Analysis Computer Code Output Actions Are Consistent W/Hot Channel Factor SRs ML20138F2581997-01-17017 January 1997 Rev 39 to Sequoyah Nuclear Plant Odcm ML20134L9261996-11-0808 November 1996 Proposed Tech Specs Re Placing of Channel in Trip for Reactor Trip & Engineered Safety Feature Instrumentation Sys Solely to Perform Testing as Not Requiring Channel to Be Declared Inoperable ML20129D2661996-10-18018 October 1996 Proposed Tech Specs,Removing Existing Footnotes That Limit Application of Apc for Plant S/G Tubes to Cycle 8 Operation for Both Units 1999-08-30
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20196G8071999-06-22022 June 1999 Revs to Technical Requirements Manual ML20209J1631998-08-0707 August 1998 Rev 41 to Sequoyah Nuclear Plant Odcm ML20202J7651998-02-13013 February 1998 Technical Requirements Manual ML20138F2581997-01-17017 January 1997 Rev 39 to Sequoyah Nuclear Plant Odcm ML20134J9991996-09-23023 September 1996 Fuel Assembly Insp Program ML20138F2531996-02-23023 February 1996 Rev 38 to Sequoyah Nuclear Plant Odcm ML20108B4121995-11-0303 November 1995 Rev 37 to Sequoyah Nuclear Plant Odcm ML20094Q2111995-10-30030 October 1995 Rev 1 to ASME ISI Pump Testing Program Basis Document ML20094Q1971995-10-30030 October 1995 Rev 1 to SG Tubing ISI & Augmented Insps, Rev 1 to 0-SI-SXI-068-114.2 ML20094Q2301995-10-30030 October 1995 ASME ISI Valve Testing Program Basis Document, Rev 0 ML20094Q1931995-10-30030 October 1995 Rev 1 to ASME Sys Pressure Testing Program Basis Document ML20094Q1761995-10-13013 October 1995 ASME Section XI Isi/Nde & Augmented Nondestructive Exam Programs, SSP-6.10,rev 2 ML20094Q1841995-10-13013 October 1995 ASME Section XI Isi/Nde Program Units 1 & 2, Rev 0 to 0-SI-DXI-000-114.2 ML20149L6811994-09-30030 September 1994 Concerns Resolution Program - Sequoyah Nuclear Plant ML20063D6691994-01-24024 January 1994 Rev 4 to Sequoyah Nuclear Plant Restart Plan ML20065Q6251993-10-13013 October 1993 Rev 31 to Sequoyah Nuclear Plant Odcm ML20056F3181993-08-20020 August 1993 Rev 0 of Post-Restart Plan ML20056G1841993-08-10010 August 1993 Rev 2 to Sequoyah Nuclear Plant Restart Plan ML20044F3081993-05-20020 May 1993 Rev 0 to Sequoyah Nuclear Plant Restart Plan ML20034F3191993-02-26026 February 1993 Rev 26 to Offsite Dose Calculation/Environ Monitoring Methodologies ML18036B1961993-01-27027 January 1993 Rev 2 to Nuclear Power Training Procedure TRN-31, Fire Brigade Training. ML20127P5461992-12-16016 December 1992 Rev 20 to Surveillance Instruction SI-114.1, ASME Section XI ISI Program,Unit 1 ML20127P6361992-12-16016 December 1992 Rev 19 to Surveillance Instruction SI-114.2, ASME Section XI ISI Program,Unit 2 ML20114C8131992-04-17017 April 1992 Rev 27 to Odcm ML20101F2011992-02-0808 February 1992 Rev 17 to Surveillance Instruction SI-114.1, ASME Section XI ISI Program Unit 1 ML20101F2081992-02-0808 February 1992 Rev 16 to Surveillance Instruction SI-114.2, ASME Section XI ISI Program Unit 2 ML20034C7451990-03-14014 March 1990 Rev 24 to ODCM ML20033F2631990-02-27027 February 1990 Rev 24 to Odcm ML19332D2241989-09-22022 September 1989 Rev 23 to Odcm. ML20245H1421989-08-15015 August 1989 Rev 22 to Offsite Dose Calculation Manual Changes ML20246H4861989-05-16016 May 1989 Rev 1 to Technical Instruction TI-115, Instructions for Sewage Mgt ML20244E2521989-04-28028 April 1989 Rev 14 to Surveillance Instruction SI-114.2, ASME Section XI Inservice Insp Program ML20246E7771989-04-25025 April 1989 Rev 14 to Surveillance Instruction SI-114.1, ASME Section XI Inservice Insp Program ML20206D3421988-10-15015 October 1988 Rev 13 to Surveillance Instruction SI-114.2, Inservice Insp Program ML20154J3221988-09-0909 September 1988 Procedure EA-OR-003-S, Sequoyah Nuclear Plant - Unit 1 Design Baseline & Verification Program,Supplemental Engineering Assurance Oversight Review Rept ML20150F9291988-06-17017 June 1988 Diesel Generator Voltage Response Improvement Plan ML20154L1421988-05-0909 May 1988 Rev 3 to Revised Sequoyah Nuclear Performance Plan ML20153H3891988-03-30030 March 1988 Rev 19 to Sequoyah Nuclear Plant Offsite Dose Calculation Manual ML20196G3301988-02-24024 February 1988 Limited Test Program for Determining Axial Load Capacity of Cast One-Hole Conduit Clamps ML20147E9511988-01-21021 January 1988 Revised, Procedures Generation Package ML20153H3851988-01-0505 January 1988 Rev 18 to Sequoyah Nuclear Plant Offsite Dose Calculation Manual ML20147E5691987-12-17017 December 1987 Rev 4 to Special Maint Instruction SMI-0-317-61, Instrumentation Features Walkdown,Rework & Insp Instructions for CAR 87-014 ML20148L9741987-11-0404 November 1987 Instruction Change 2172,Rev 8 to Essential Instrumentation Operability Verification ML20237C5451987-10-28028 October 1987 Rev 17 to Offsite Dose Calculation Manual ML20236E6931987-10-17017 October 1987 Rev 2 to Engineering Organization & Operating Procedures, TVA Employee Concerns Special Program ML20235X0651987-10-10010 October 1987 Rev 0 to Special Maint Instruction SMI-2-74-1, Repair of 2-FCV-74-2 ML20235X0551987-10-10010 October 1987 Rev 0 to Sys Operating Instruction SOI-74.2, Removal of RHR for Repair of 2-FCV-74-2 ML20245D0661987-09-15015 September 1987 Rev 4 to Surveillance Instruction SI-673, RCS Level Verification Using Sight Glass or Tygon Hose ML20148M0661987-09-11011 September 1987 Rev 8 to SI-604, Essential Instrumentation Operability Verification ML20245D0591987-08-29029 August 1987 Rev 40 to Sys Operating Instruction SOI-74.1, RHR Sys 1999-06-22
[Table view] |
Text
- _ _ _ - - -
(.
TENNESSEE VALLEY. AUTHORITY CI(
SEQUOYAH NUCLEAR PLANT 1
~.
j FUNCTION RESTORATION GUIDELINES
' l FR-H.1 RESPONSE TO L'OSS OF SECONDARY HEAT SINK L
Revision 1 PREPARED BY:
,G. Stric_kland RESPONSIBLE SECTION:
Operation [] /
REVISED BY:
G.
S I
SUBMITTED BY:
//[M h.
k R6sp6nsible $e ti'on Supervisor f
PORC REVIEW DATE:
'AUG 2-1985 APPROVED BY:
~P3 %)
ism Plaht Manager DATE APPROVED:
'AUG 211985 Reason for revision (include all Instruction Change Fdrm Nos.):
Revised to add reference to status tree; clarify basis for stopping RCP during loss of AFW; change flow criteria to ensure pumps running, to add reactor vessel head vent valves; add
^
allowance tio exceed RCS cooldown limit.
The last page of this instruction is number:
11 8
e
1 T-
-S5dUOYAH-NUCLEAR PLANT I
PLANT INSTRUCTION REVISION LOG
~
FUNCTIOt{. RESTO_ RATION _ GUID.ELINES FR-H.1 REVISION Date Pages REASON FOR REVISION (INCLUDE COMMIT-LEVEL Approved Affected
_MENTS AND ALL ICF FORM NUMBERS) 0 10/.04/84.
ALL Revised to add reference to status tree; clarify basis for stopping FCP during loss of AFW; change flow criteria to en-sure pumps running, to add reactor 1
21 E vessel head vent valves; add allowance i
1,s,8,10 to exceed RCS cooldown limit.
~
,r-
=.. = - -.
0279L/mbs en I
SQNP FR-H.1 Unit 1 or 2 o
Page 1 of 11 Rev. 1 RESP'ONSE TO LOSS OF SECONDARY HEAT SINK A.
PURPOSE This guideline provides actions to respond to a loss of secondary heat sink in all steam generators.
B.
SYMPTOMS
~
t All S/G levels less than 25% and total AFW flow less than 440 gpm C.
TRANSITION FROM OTHER INSTRUCTIONS 1.
E-0, Reactor Trip Or Safety Injection
-)+
2.
Status Tree
.e d
_-___~
SQNP FR-H.1 Unit 1 or 2 i
l Page 2 of 11 Rev. 0
]
1 RESPONSE TO LOSS OF SECONDARY HEAT SINK i
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED Note:
This instruction is NOT required if RHR is in service or RCS press is below intact S/G press s.
s 1
Check S/G WIDE Range Levels a.
At least one S/G WIDE a.
IF all S/G WIDE range range level > 25%
levels < 25%
[35% FOR ADVERSE
[35% FOR ADVERGE CNTMT]
CNTMT],
THEN:
- 1) Stop all RCPs
- 2) Immediately initiate RCS feed and bleed per steps 11 to 13
.e 2
Check CST Level a.
CST level > 3 ft a.
I_F CST level < 3 ft, THEN verify ERCW aligned to AFW b.
CST level > 17 ft b.
IF CST level < 17 ft, THEN attempt to refill CST while continuing with this instruction i
~ ' -
SQNP l
FR-H.1 Unit 1 or 2 Page 3 of 11 Rev. O RESPONSE TO LOSS OF SECONDARY HEAT SINK STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 3
Establish Motor-Driven AFW Pump Flow a.
Verify both motor-driven a.
Start pumps from the AFW Pumps - RUNNING shutdown board t
b.
Verify AFW level control b.
Open valves from one valves - OPEN of the following:
- 1) Auxiliary control room
- 2) Remove valve control power
- 3) Remove valve operating air
(
,,, J c., Verify motor-driven AFW c.
Verify AFW manual valve k
Pump flow alignment per SOI-3.2 while continuing with this instruction
j SQNP FR-H.1 Unit 1 or 2 Page 4 of 11 Rev. O RESPONSL TO LOSS OF SECONDARY HEAT SINK
~
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l
4 Establish Turbine-Driven AFW Pump Flow a.
Turbine steam supply ~
a.
Open valves FCV-1-15, valves - OPEN 16,17, or 18 from Rx MOV Bd
- 1) FCV-1-15 or 16 IF FCV-1-51 closed
- 2) FCV-1-17 and 18 (HS-46-56),
THEN evaluate following:
j
- 3) Trip and throttle valve
- 1) Valve latched to motor operator f
- 2) Mechanical everspeed reset
- 3) Thermal overloads
..c reset b.
Verify AFW level control b.
Open valves from one of valves - OPEN the following:
- 1) Auxiliary control for LCV next to pump room
- 2) S/G 2 and 3 LCV handwheel at Aux Bldg 714
- 3) S/G 1 and 4 LCV handwheel in West Valve Room c.
Verify AFW Pump speed c.
Control pump speed indication locally d.
Verify turbine-driven AFW d.
Verify AFW manual Pump flow valve alignment per S01-3.2 while continuing with this instruction
SQNP FR-H.1 Unit 1 or 2 Page 5 of 11 Rev. 1
((
(
RESP'ONSE TO LOSS OF SECONDARY HEAT SINK STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBh'AINED 5
Check If Secondary Heat Sink IF total AFW flow < 440 gpm Restored AND au S/G narrow range levels < 10%, [25% FOR a.
I_F one of the following ADVERSE CNTMT],
conditions met:
THEN evaluate stopping
-)6 RCPs based on following:
- 1) Total AFW flow to S/Gs > 440 gpm Delaying the time before S/G dry out OR
~-
Availability of
- 2) Narrow range level secondary system.
in at least one S/G
> 10% [25% FOR Continue with this y
ADVERSE CNTMT]
instruction.
THEN return to instruction
[
in effect
,e k i
e
.~' l. _ _ _ _ _ _ _
SQNP FR-H.1 Unit 1 or 2 Page 6 of 11 Rev. O RESPONSE TO LOSS OF SECONDARY HEAT SINK STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 6
Establish Main Feedwater Flow a.
Start condensate pumps as required:
- 1) Hotwell Pumps
- 2) Condensate Booster Pumps
- 3) DI Booster Pumps b.
Restart MFW Pump b.
IF SI has actuated, THEN the following must
- 1) MFW pump controllers be performed prior to in manual and set to restarting the MFW Pump zero
(
Reset SI
..cl
- 2) MFW reg valve and k
bypass valve controllers Notify inst to lift in manual and set to zero TB506-4 in back of SSPS logic cabinets
- 3) Reset MFW isolation 47 and 50 (clears P-4 seal-in for MFW isolation)
- 4) Restart MFW pump turbine
- 5) Open MFW isolation valves
- 6) Control MFW pump speed and feedwater bypass valve position to restore S/G icvel
SQNP FR-H.1 Unit 1 or 2 Page 7 of 11 Rev. O I
RESPONSE TO LOSS OF SECONDARY HEAT SINK STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OETAINED 7
Check If Secondary Heat IF MFW flow to at least one Sink Restored S/G verified, THEN maintain flow to a.
I_F narrow range level restore narrow range level in at least'one S/G
> 10% [25% FOR IF MFW flow NOT established, I
ADVERSE CNTMT],
THEN refer to SOI-2.1 while THEN return to continuing with this instruction instruction in effect 1
l 1e l
l l
l
! 1
)
2
y r, SQNP FR-H,1 Unit 1 or 2 Page 8 of 11 Fev. 1
~
RESPONSE TO LOSS OF SECONDARY HEAT SINK STEP ACTION / EXPECTED RESPONSE RESPONSE NOT CBTAINED 8
Establish Condensate Flow a.
IF SI has NOT actuated, a.
IF SI has actuated, THEN THEN the following must t
be performed prior to
- 1)
- Block P-11 when RCS resetting MFW isolation:
press < 1970 psig Reset SI
- 2) Block P-12 when RCS temp < 540 F Notify inst to lift TB506-4 in back of GSPS logic cabinets
-47 and 50 (clears P-4 seal-in for MFW isolation b.
Depressurize at least one S/G g
IA /
- 1) Rapidly dump steam
- 1) IF condenser NOT to condenser available, THEN use S/G PORV W
- 2) Normal RCS cooldown M
limit 100 F/hr may be exceeded M
- 3) Depressurize S/G until condensate flow established I
l l
l 1
SQNP FR-H.1 Unit 1 or 2 Page 9 of 11 Rev. 0 l.
RESPONSE TO LOSS OF SECONDARY HEAT SINI' STEP ACTION /EXP!"'"D RESPONSE RESPONSE NOT OBTAINED 9
Check If Secondary Heat Sink IF condensate flow to at Restored least one S/G verified, THEN maintain flow to a.
IF narrow range level in restore narrow range at least one S/G > 10%
level (25% FOR ADVERSE CNTMT],
THEN return to instruction IF condensate flow NOT in effect stablished, THEN refer to SOI-2.1 while continuing with this instruction 10 Check S/G WIDE Range Levels a.
IF at least one S/G WIDE a.
IF all S/G WIDE range range level > 25%
13vels < 25%
(
[35% FOR ADVERSE
[35% FOR ADVERSE
,,, { k CNTMT],
CNTMT],
e THEN continue attempts THEN immediately to establish one of the initiate RCS feed and following:
bleed per following steps
- 1) AFW flow
- 2) MFW flow
- 3) Condensate flow wme e,-e-
.s-,
- osr
\\
SQNP l
FR-H.1 Unit 1 or 2 j
Page 10 of 11 Rev. 1 I
RESP'ONSE TO LOSS OF SECONDARY HEAT SINK STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OB' PAINED 11 Actuate Phase A Isolation a.
Pnl M-6 l
u l
12 Establish RCS Feed Path Do not proceed until at l
least one CCP or SI Pump a.
Ensure CCPs injecting running and injection through BIT valves open b.
Ensure SI Pumps - RUNNING 13 Establish RCS Bleed Path IF both pzr PORVs can NOT Fe opened, a.
Open both pzr PORVs THEN b.
Open both pzr block valves Open reactor vessel head vent valves y
c.
Stop all RCPs l
Align High Pressure Fire Protection to at least one intact S/G Dcpressurize S/G until HPFP flow established 14 Attempt To Restore Secondary Heat Sink a.
AFW Pumps b.
MFW Pumps c.
Condensate Pumps
~
it.
High Pressure Fire Protection Pumps
- 1) Install spool piece SQNP FR-H.1 Unit 1 or 2 Page 11 of 11 Rev. O RESPONSE TO LOSS OF SECONDARY HEAT SINK STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Check If RCS Feed And Bleed Do not terminate RCS feed Can Be Terminated and bleed until all criteria satisfied a.
Secondary heat sink restored b.
Core exit T/C - DECREASING c.
T-hot - DECREASING d.
RCS subcooling > 40 F e.
Reduce ECCS flow by stopping ECCS pumps and closing pzr PORV as required to maintain RCS subcooling > 40 F and pzr level > 20%
[50% FOR ADVERSE CNTMT)
.,e f.
Align normal charging and letdown prior to closing the last pzr PORV 16 Return To Instruction In Effect
- END -
i l 1 u-_--__-___-________
._ _