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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 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 ML20207D6331999-02-26026 February 1999 Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets ML20207D6011999-02-26026 February 1999 Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20206S0131999-01-15015 January 1999 Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual 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 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 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 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 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 ML20202J7651998-02-13013 February 1998 Technical Requirements Manual ML20202J7141998-02-13013 February 1998 Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves 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 ML20129G7301996-09-26026 September 1996 Proposed Tech Specs 3/4.3.3 Re Fire Detection instrumentation,3/4.7.11 Re Fire Suppression Systems & 3/4.7.12 Re Fire Protection Penetrations ML20134J9991996-09-23023 September 1996 Fuel Assembly Insp Program 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 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 ML20094Q1971995-10-30030 October 1995 Rev 1 to SG Tubing ISI & Augmented Insps, Rev 1 to 0-SI-SXI-068-114.2 ML20094Q2111995-10-30030 October 1995 Rev 1 to ASME ISI Pump 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. 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 ML20101F2081992-02-0808 February 1992 Rev 16 to Surveillance Instruction SI-114.2, ASME Section XI ISI Program Unit 2 ML20101F2011992-02-0808 February 1992 Rev 17 to Surveillance Instruction SI-114.1, ASME Section XI ISI Program Unit 1 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 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 ML20235X0551987-10-10010 October 1987 Rev 0 to Sys Operating Instruction SOI-74.2, Removal of RHR for Repair of 2-FCV-74-2 ML20235X0651987-10-10010 October 1987 Rev 0 to Special Maint Instruction SMI-2-74-1, Repair of 2-FCV-74-2 ML20237H2051987-08-28028 August 1987 Rev 0 to Civil Engineering Branch Instruction CEB-CI 21.89, Mod Priorities for Pipe Supports on Rigorously Analyzed Category I Piping - Sequoyah Unit 2 ML20207G5821987-08-24024 August 1987 Rev 14, Balance of Plant Temp Monitoring Sys ML20237L3651987-08-21021 August 1987 Unit 2,Regeneration of Support Design Calculations on Rigorously Analyzed Piping,Program Plan ML20236Q1771987-08-0707 August 1987 Rev 9 to Surveillance Instruction SI-114.1, ASME Section XI Inservice Insp Program. Rev Corrects Deficiencies Shown in Caqr CH5870006 & CH5870010,adds Punchlist & Incorporates Icf 87-708 ML20236N7601987-08-0606 August 1987 Revised Radiological Emergency Plan Implementing Procedures, Including Rev 13 to IP-8, Personnel Accountability & Evaluation & Rev 6 to IP-15, Emergency Exposure Guidelines ML20236M7181987-07-28028 July 1987 Rev 1 to WP-17-SQN, Vendor Weld Quality, Welding Project, TVA Employee Concerns Special Program ML20236M7351987-07-24024 July 1987 Rev 5 to 80503-SQN, Document Distribution Control, Element Rept,Tva Employee Concerns Special Program 1999-06-22
[Table view] |
Text
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TENNESSEE VALLEY AUTHORITY j
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- SEQUOYAH NUCLEAR PLANT j
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EMERGENCY INSTRUCTION .
ES-0.2
'->' ~
SI TERMINATION Revision 2 ~
t PREPARED BY: G. Strickland j RESPONSIBLE SECTION: Operations -
REVISED BY: ~~ Gary L. Terpstra SUBMITTED BY:_ , /l' ea , .. ,
R sponsibin 'Section Supervisor PORC REVIEW ATE: ,
Nj 2 %. ,
APPROVED BY:
- .. , Plant Manager DATE APPROVED
- N 12 E Reason for revision (include all Instruction Change Form Nos.):
Revised to add step 11.c (readjust FCV-62-89/93); added 36.a (reset Bit Hts); corrected SOI numbers in step 25: lef t FCV-74-16/28 in. 0 PEN position 7
in step 38: changed SI-407 to SI-407.2 in step 40: and remove comma < from
{ steps 6 and 41.
L ,
l The last page of this instruction is number: 18
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r SEQUOYAH NUCLEAR PLANT PLANT INSTRUCTION REVISION LOG ,
(5 .
2 EMERGENCY INSTRUCTION ES-0.2 REVISION Date Pages REASON FOR REVISION (INCLUDE COMMIT- I LEVEL Approved Affected MENTS AND ALL ICF FORM NUMBERS)
~
Revised to add step to implement REP early in instruction; and to delete .
1 OP/21/85 ALL REP implementation substep.
Revised to add step 11.c (readjust FCV 89/95); added 36.a (reset Bit Hts); cor-rected SOI numbers in step 25; left FCV-74-16/28 in OPEN position in step 38; ;
4,6,12, changed SI-407 to SI-407.2 in step 40; 2 JUN 1 2 1987 16-18 and-remove commas from steps 6 and 41.
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- SQNP ES-0.2 Unit 1 or 2-Page 1 of 18 Rev. 1 SI TERMINATION ..
A. PURPOSE -
This guideline provides the necessary instructions to terminate safety injection and stabilize plant conditions. -
B. SYMPTOMS '
None C. TRANSITION FROM OTHER INSTRUCTIONS ;
- 1. E-0, Reactor Trip Or Safety Injection
- 2. E-1, Loss Of Reactor Or Secondary Coolant .
W De a e
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SQNP ES-0.2 Unit 1 or 2 i Page 2 of 18
.. Rev. 1
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S1 TERMINATION
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STEP ACTION / EXPECTED RESPONS_E_ RESPONSE NOT OBTAINED CAUTION: If offsite power is lost after SI resec, then manual -
action will be required to restart the SI Pumps and RHR Pumps. ,
1 Reset SI Check P-4 interlock with SI reset, SI-268 2 Stop One CCP i
,p ' **
3 Check RCS IF pzr level or RCS press 3ecreasing, 1
- a. Pzr level - STABLE OR THEN start CCPs and go '
INCREASING to
- E-1, LOSS OF REACTOR l OR SECONDARY COOLANT
- b. RCS press - STABLE OR INCREASING e
g,-
SQNP ES-0.2 Unit 1 or 2
, Page 3 of 18 Rev. 1 i
i( r SI TERMINATION O
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT'OBTAINED ,.
4 Check If SI Pumps Should .
Be Stopped -
- a. RCS press greater than a. IF_ RCS press less SI Pump injection than SI Pump injection press press, THEN:
- 1) RCS press > 1500 psig Stop one SI Pump OR_
Allow pzr level
- 2) SI Pump flow 0 gpm and RCS press to (FI-63-20 and 151) stabilize, THEN stop second
- b. Stop SI Pumps SI Pump i e # ~ IF SI Pumps are required t6 maintain pzr level, THEN start SI Pumps and go to
- E-1, LOSS OF REACTOR OR SECONDARY COOLANT 5 Stop RHR Pumps l
C e >e
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SQNP ES-0. 2 Unit 1 or 2 Page 4 of 18
, Rev. 2 r
SI TERMINATION -
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Verify ECCS Not Required IF pzr level or RCS subcooling can NOT be maintained,
- a. Pzr level > 20% THEN start CCP and/or SI
[50% FOR ADVERSE Pamp's as necessary.
CNTMT] . .
-- Go to
- E-1, LOSS OF REACTOR OR SECONDARY COOLANT
- b. .RCS subcooling > 40 F s
7 Reset Phase A And Phase B "
r I 8 Ensure Cntmt Air Supply In Service I y- -
- a. Air compressors - RUNNING
- b. Cntmt air supply valves on elev 714 - OPEN
- 1) FCV-32-80 (81)
- 2) FCV-32-102 (103)
L 3) FCV-32-110 (111)
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- _________--__.___--___------A
,- SQNP 4
- ES-0. 2 - Unit- 1 or 2 l
,. Page 5 of 18-Rev. 1 _
~
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SI TERMINATION l 1
-STEP ACTION / EXPECTED RESPONSE ' RESPONSE NOT'OBTAINED .,
'l 9- Establish Normal Charging
- a. Close FCV-62-89 l t i
- b. Open charging line isolation FCV-62-90 and 91
- c. Open FCV-62-85 or 86 '
- d. Adjust FCV-62-89 and 93 to establish following: ,
.1) Seal injection flow
~ 2) . Pzr level stable or increasing .
)~ n
- e. Open seal water return FCV-62-61 and 63 10 - Establish Letdown IF letdown can' NOT be established
- a. Open letdown isolation THEN establish excess valves:
letdown
- 1) FCV-62-69 .
- 2) FCV-62-70
- 3) FCV-62-77 l
- b. Adjust letdown press i
controller, FCV-62-81, ^
s 25% open in manual -
d 1
- c. Open an orifice . valve i
- d. Adjust FCV-62-81 for desired press, then place in AUTO
- 1) 320 psig at normal letdown temp I
l
SQNP
Page 6 of 18
.s Rev. 2
~
o SI TERMINATION- -
s STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 Isolate BIT
- a. - Close BIT inlet FCV-63-39 and 40 '
x -'
, b. Close BIT outlet FCV-63-25 and 26 c '. Adjust FCV-62-89 and- 93 "
to establish following:
- 1) Seal injection flow
^8 gpm per RCP '
- 2) Pzr level stable or increasing
( 12 Check RCS
" , , Control charging to maintain pzr level and
- a. Pzr level ' STABLE OR RCS press INCREASING IF pzr level or RCS. press
- b. RCS press - STABLE.OR can NOT be maintained, INCREASING realign BIT, isolate charging and letdown.
Go to
- E-1, LOSS OF REACTOR OR SECONDARY COOLANT 13 . Align CCP Suction To VCT
- a. Open VCT outlet valves FCV-62-132 and 133
- b. Close RWST valves '
FCV-62-135 and 136 14 Check VCT Makeup System
- a. Makeup set for RCS boron concentration
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m' SQNP ES-0. 2 Unit 1 or 2 Page 7 of 18 Rev. 1 SI TERMINATION j STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Stabilize RCS Press
- a. Control pzr heaters -
as necessary
- b. Control pzr normal sprays b. IF normal p2r sprays as necessary TOT available AND letdown in service, THEN use aux spray IF letdown or aux spray
- NDT available, THEN use one pzr PORV 16 Stabilize T-hot f
I a. Transfer condenser steam a. IF condenser NOT
.A ~ dump to press control airailable, mode THEN use S/G PORVs
- b. Control steam dump as necessary
- c. Control AFW as necessary C
e .
t.
, SQNP ES-0. 2 Unit 1 or 2 Page 8 of 18 Rev. 1 SI-TERMINATION .
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED '
17 Initiate REP IP-1 ,
- a. Notify Operations Duty Specialist within 5 min 18 Check If D/G Should Be Stopped
- a. All shutdown boards - a. Attempt to restore offsite energized by offsite power per AOI-35 power
- b. Place D/G in standby per SOI-82, Removing D/G From Service After An
., " Emergency Start 6O +
c 4
..r. f -
SQNP ES-0.2 Unit .1 or 2
- t. . . -Page 9 of 18-
- Rev . 1 SI TERMINATION STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTkINED
- 19. Check CST Level-
- a. CST level > 3 ft a. IF' CST level < 3 ft,-
t THEN verify ERCW
, aligned to AFW
- b. CST level > 17 ft b. IF CST level < 17 ft, TIIEN attempt to refill CST while continuing with this' instruction-20- Check Intact S/G Levels
- a. . Narrow range S/G a. Verify AFW flow and levels > '25% intact S/G levels returning to normal. program b." Control S/G 1evels between -
25% and 50%
21 Check'If Source Range Detectors Should Be Energized
- a. Check intermediate range a. WHEN intermediate flux < 10-10amps -10 range flux < 10 amps, THEN ensure source-range detectors !
energized
- b. Ensure source range detectors energized
- c. Transfer NR-45 to one source and intermediate . , -
range -
)
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SQNP ES-0. 2 Unit 1 or 2 Page 10 of 18 Rev. 1 SI TERMINATION STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l CAUTION: Normal T-avg indication and associated interlocks win be inaccurate during natural circulation or when RCS temp is below 530 F.
22 Check RCP Status
- a. At least one RCP running a. Attempt to restart an RCP (loch 2 preferred) f .- per SOI-68.2 IF an RCP can NOT Fe started, THEN verify natural circulation
~
-e RCS subcooling S/G press stable or decreasing T-hot stable or decreasing Core exit T/C stable or decreasing T-cold at saturation temp for S/G press IF natural circulation ITOT verified, THEN increase dumping steam -;.
'e . e
- SQNP ES-0.2 Unit 1 or 2 Par;e 11 of 18 Rev. 1 I( -
SI TERMINATION . i STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED -
23 Realign CCS And ERCW
- a. Stop CCS Pumps that started from SI signal
- b. Stop ERCW Pumps that started from SI signal ,
- c. Reset ERCW valve FCV-67-152
- d. Position FCV-67-152 from >
35% to desired position '
I CAUTION: If a LOCA or loss of secondary coolant has occurred, then evaluate if cntmt isolation valves and ventilation systems should be returned to normal alignm%
24 Realign Cntmt Isolation Valves
- a. Phase A isolation valves per SOI-88.1B
- b. Phase B isolation valves per SOI-88.1C 4
'e s +
[' SQNP J-ES-0. 2 Unit 1 or 2 Page 12 of 18 r, Rev. 2 l, <
SI TERMINATION -
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBT INED 25 Realign Cntmt Ventilation Systems
- a. Reset entmt vent isolation -
- b. EGTS persSOI-65.1 A -
(SOI-G5.2A) and SOI-65.1B (SOI-65. 2B)
I
- c. Cntmt ventilation per SOI-30.2B and SOI-88.1 A l l
- d. Incore inst room per SOI-30.4 '
l
- e. Cntmt vacuum control per SOI-30.3E
(
26 Realign Control' Bldg e
Ventilation Systems
- a. Reset control room isolation
- b. Control bldg ventilation per SOI-30.1B S
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SQNP
.- ES-0. 2 Unit 1 or 2 j Page 13 of 18 l Rev. 1 j f j
)
l\ SI TERMINATION
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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 27 Realign Aux Bldg Ventilation System .
- a. Place aux bldg fans in PULL l TO LOCK '
- 1) Aux bldg general supply
- 2) Aux bldg general exhaust \
i
- 3) Fuel area exhaust
- b. Reset aux bldg isolation
- c. Aux b1dg ventilation per SOI-30.5D
- d. ABGTS per SOI-30.6C and
,e C ~ SOI-30.6B 28 Check Cntmt Hydrogen Ignitors
- a. Turn off hydrogen ignitors if not required 1
29 Realign Ice Condenser System
- a. Align per SOI-61.1 30 Check Main Turbine
- a. Bearing oil pumps running (1500 rpm) y
- b. Bearing lift pump , ,
running (600 rpm)
- c. Place turbine on turning gear after shaft stops SQNP
. ES-0. 2 Unit 1 or 2
. Page 14 of 18 Rev. 1 SI TERMINATION I l
l STEP ACTION / EXPECTED RESPONSE DESPONGE NOT OBTAINED ,
31 , Align MSRs Normal
- a. Press RESET on MSR control panel
- b. Close HP steam to MSR isolation valves
- c. Open starting vents
- d. Close operating vents 32 Check Extraction Steam Valves And Drain Valves
( a. Close heaters 1 and 2
, extraction steam valves
- b. Open turbine drain valves .
- c. Open MFW pump turbine drain valves
- d. Locally open extraction drain valves, HS-5-94 33 Shutdown Unnecessary Secondary ;
Plant Equipment
- a. Leave 2 hotwell pumps running
- b. Leave 1 condensate booster pump running .
- c. Stop DI booster pumps ..
- d. Stop heater drain tank pumps and close discharge valves
- e. Open exciter field breaker and place voltage regulator in off position
_____---------_J
I SQNP ,
.. ES-0. 2 Unit 1 or 2. 1 Page 15 of 18 ,
Rev. 1 !
/-
SI TERMINATION I l
l STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l
4 I
34 Flush BIT Injection Lines l
- a. Unlock and open BIT bypass valve 63-697
- b. Monitor flushing flow on FI-63-170
- c. Adjust FCV-62-89 to maintain s 8 gpm RCP seal injection flow
- d. After flushing s 150 gal, close 63-697
- e. Relock 63-697 e C f. Adjust FCV-62-89 to
" maintain s 8 gpm RCP seal injection flow 35 Establish BIT Boron Concentration
- a. Verify BIT recirc closed FCV-63-38, 41, and 42
- b. Open BIT valve to HUT '
HCV-63-573 k
- c. Open BIT inlet recire FCV-63-38
- d. Place BA transfer pump in slow speed
- e. After BAT level has -
decreased by 12% (1000 gal), ,.
then open BIT outlet recirc FCV-63-41 and 42
- f. Close BIT valve to HUT HCV-63-573 1
I
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SQNP
'ES-0.2 Unit 1 or 2 Page 16 of 18
- . Rev. 2 l
1 SI TERMINATION -
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 36 Verify BIT And RWST Within Limits
- a. Locally reset the BIT heaters (Aux Bldg 690 pipe chase)
- b. BIT water temp > 145 F
- c. BIT low flow alarm cleared
- d. RWST level between 370,000
, gal and 375,000 gal I e. RWST temp between 60 F "'
and 105 F 37 Check If Reactor Trip IF reactor trip breakers
[ Breakers Can Be Closed are NOT cycled, f-y a." All SI signals cleared THEN comply with Tech Spec 3.0.3 due or blocked to loss of both trains i
of automatic SI actuation
[ b. Close or cycle reactor trip breakers 38 Reset Following Valves l a, Reset entmt sump isolation u valve l b. Establish RIIR discharge L valve control
- 1) Place FCV-74-16 and 28 controller to 0%
- 2) Reset RIIR discharge valves e
- 3) Ensure FCV-74-16 and 28 - OPEN 7
5 D
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_ _ _ _ _ _ _______.-____--_.-------w
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SQNP ES-0. 2 Unit 1 or 2 Page 17 of 18
{, Rev. 2 le SI TERMINATION r.
M STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 39 Maintain Stable Plant Conditions
- a. RCS press
- b. Pzr level 1 -
- c. RCS temp
- d. Intact S/G levels -
40 Complete Surveillance And Reports
)
- a.81-268, Verification Of P-4 Interlock
}
- b. SI-603, High Flux Adjustment
/ After Shutdown i' c.
- SI-407.2 and SI-415 if reactor power decreased by > 15%
- d. SI-38, Shutdown Margin
~
- e. SI-166.10 if the SI Pumps injected into RCS
- f. AI-18, file package 18 for Reactor Trip Report and NRC notification l l
c l
l 3
l l
_____-______---J
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SQNP
'ES-0. 2 Unit 1 or 2 Page 18 of 18 -
, Rev. 2 ,
,- ,)
_ SI TERMINATION -
h STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 41 Verify ECCS Not Required '
- a. Pzr level > 20% a. Control charging
[50% FOR ADVERSE CNTMT] ~
to restore pzr level I
IF pzr level can NOT E~e maintained, THEN start CCP and/or SI Pumps as necessary. -
Go to
- E-1, LOSS OF REACTOR OR SECONDARY "
COOLANT I -
- b. RCS subcooling > 40 F b. IF RCS subcooling can NOT be maintained,
' l THEN start CCP and/or SI Pumps as necessary.
[ Go to
- E-1, LOSS OF l " REACTOR OR SECONDARY l'- COOLANT
_ 42 Go To Applicable Plant Instruction
- a. ES-0.3, Natural Circulation Cooldown
- b. GOI-2, Plant Startup From Hot Standby To Minimum Load
- c. GOI-3, Plant Shutdown From Minimum Load to Cold Shutdown Conditions
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/a
- END -
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