|
|---|
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
ML20211K1201999-08-30030 August 1999
Proposed Tech Specs,Adding New Specification That Addresses Use of Interim Provisions Upon Discovery of Unintended TS Action
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
ML20196G8071999-06-22022 June 1999
Revs to Technical Requirements Manual
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
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
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
ML20206E1611999-04-29029 April 1999
Proposed Tech Spec Change 99-04, Auxiliary Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance
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
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
ML20202J6961998-02-13013 February 1998
Proposed Tech Specs Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431)
ML20202J7141998-02-13013 February 1998
Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves
ML20202J7601998-02-13013 February 1998
Proposed Tech Specs Section 3.7.9 Re Relocation of Snubber Requirements
ML20202J7651998-02-13013 February 1998
Technical Requirements Manual
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
ML20094Q2301995-10-30030 October 1995
ASME ISI Valve Testing Program Basis Document, Rev 0
ML20094Q1971995-10-30030 October 1995
Rev 1 to SG Tubing ISI & Augmented Insps, Rev 1 to 0-SI-SXI-068-114.2
ML20094Q1931995-10-30030 October 1995
Rev 1 to ASME Sys Pressure Testing Program Basis Document
ML20094Q1841995-10-13013 October 1995
ASME Section XI Isi/Nde Program Units 1 & 2, Rev 0 to 0-SI-DXI-000-114.2
ML20094Q1761995-10-13013 October 1995
ASME Section XI Isi/Nde & Augmented Nondestructive Exam Programs, SSP-6.10,rev 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
ML20006C0571990-01-18018 January 1990
Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan
ML15264A1571990-01-0202 January 1990
Revised Crisis Mgt Implementing Procedures,Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9,Rev 1 to CMIP-14 & Rev 30 to CMIP-21
ML16152A8951990-01-0202 January 1990
Rev 33 to Public Version of Crisis Mgt Plan for Nuclear Stations.
ML20012A3771990-01-0101 January 1990
Rev 26 to, Offsite Dose Calculation Manual McGuire Nuclear Station
ML20012A3751990-01-0101 January 1990
Rev 25 to, Offsite Dose Calculation Manual,Cawtaba Nuclear Station
ML20012A3801990-01-0101 January 1990
Rev 28 to, Offsite Dose Calculation Manual,Oconee,Mcguire & Catawba Nuclear Stations
ML20012A3791990-01-0101 January 1990
Rev 27 to, Offsite Dose Calculation Manual,Oconee Nuclear Station
ML20012A3691989-12-0505 December 1989
Rev 8 to, Process Control Program,Mcguire Nuclear Station
ML20011D2441989-12-0101 December 1989
Crisis Mgt Implementing Procedures
ML20012A3721989-11-27027 November 1989
Rev 4 to, Process Control Program,Cawtaba Nuclear Station.
ML20012A3731989-11-15015 November 1989
Rev 4 to, Process Control Program Oconee Nuclear Station.
ML19325F1931989-11-0101 November 1989
Public Version of Rev 32 to, Crisis Mgt Plan for Nuclear Stations.
ML19332C8451989-11-0101 November 1989
Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 31 to CMIP-1,Rev 28 to CMIP-4,Rev 32 to CMIP-5,Rev 37 to CMIP-6,Rev 36 to CMIP-7,Rev 25 to CMIP-8,Rev 31 to CMIP-9 & Rev 19 to CMIP-13
ML19332D2241989-09-22022 September 1989
Rev 23 to Odcm.
ML20247H3371989-09-15015 September 1989
Revised Corporate Organization for Nuclear Incidents (Coni) Procedure Manual Including Rev 15 to CONI-1.01, Preparation,Issuance & Control Procedures, Rev 30 to CONI-1.02, Coni & Rev 19 to CONI-1.03, Alerting ..
ML20245H1421989-08-15015 August 1989
Rev 22 to Offsite Dose Calculation Manual Changes
ML20245L7651989-08-0707 August 1989
Rev 0 to Offsite Dose Calculation Manual
ML20247M7921989-07-31031 July 1989
Rev 6 to PWR Operations Guideline Number 12 Simulator Testing Program. Simulator Transient Test Review Data Encl
ML20247M9151989-07-27027 July 1989
Procedure Generation Package
ML20247N0421989-06-19019 June 1989
Rev 5 to SS-1, Braidwood Simulator Steady State Performance Test
ML20247M7581989-05-26026 May 1989
Rev 0 to Test NO-1, Braidwood Simulator Normal Operations Testing
ML20247M7861989-05-26026 May 1989
Rev 0 to SV-1, Braidwood Simulator Surveillance Testing
1999-06-22
[Table view] |
Text
_ _ _
4-\\
m.
b TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT-r lS0iCATEGOlT;'
PORT!0?6 ;;
!.i + n]
A' SYSTEM OPERATING INSTRUCTION
~ ^ - -
J SOI-74.1 I '
RESIOUAL' HEAT REMOVAL SYSTEM Units 1 and 2 l
Revision 40
i PREPARED BY:
C. E. DeWeese RESPONSIBLE SECTION: Operations REVISED BY:
J.sSylvester i
SU8MITTED BY:,
,( l et l
. Re onsfble Section Supervisor PORC REVIEW IATE:
AUG 2 91987 i
~
APPROVED BY:
i
' Plant Mar]ager m,
DATE APPROVED:
3 "N / ! ".'3, 1
4 Reason for revision (include all Instruction Change Form Nos.):
Revised to correct typographical errors, corrected setpoint for U-2 miniflow valve per WP 12536.
Enhanced section H and J (Procedure ~'for swapping RHR pumps, when RCS is drained and when RCS is not drained).
Added procedure for venting RHR system.
The last page of this instruction is number:
57 l[hogDgg $$
g7 P
'$i J
\\?
4 I i, '..
{~
SEQUOYAH NUCLEAR PLANT PLANT INSTRUCTION REVISION LOG SYSTEM OPERATING INSTRUCTION SOI-74.1 REVISION Date Pages REASON FOR REVISION (INCLUDE COMMITMENTS AND LEVEL Approved Affected-ALL ICF FORM NUM8ERS) 9 11/27/79 All 10 03/18/80 8-10,12 11 03/31/80 25-28 I
3,5-7,24, 29,30,32-12 05/19/80 37 13' 10/14/81 4.5,21,33 14 01/26/81 10,21 3-15 04/28/81 10 16 08/19/82 7
17 09/05/81 5,8-10,13 18 09/25/81 36 l
19 11/16/81 5-7 5,7,24,29 20 01/21/82 30,32-34 21 02/03/82 7
5, l'
22 03/10/82 Added SA Coversheet i
2,5,5A,6, 7,24-30, 23 08/05/82 32-37 elte +
0451L/tir I.f L
a
g7
,c y
- ~s SEQUOYAH NUCl. EAR' PLANT' PLANT INSTRUCTION REVISION LOG I
(continued)
Tf SYSTEM OPERATING INSTRUCTION S01-74.1 i,,
REVISION Date Pages REASON FOR REVISION (INCLUDE COMMITMENTS AND LEVEL Approved Affected AND ALL ICF FORM NUMBERS) 25, 24 10/20/82 Added 25A 25 08/15/83 All
- 26 09/06/83 30 l1 6,8,25, I
31,32, 27 10/17/83 34-36 6,8,16-22 25,30-32, s
28 04/23/84 34-36 7-11,14, 27,28,30, 29 10/12/84 37,39 30 12/21/84 35,36 31 01/15/85 All 32 10/04/85 16 Revised to add step to initiate SI-673.
l 12-27, Revised in accordance with ICF 85-1270, g
33 11/19/85 Added 28 PORC approved.10/23/85.
(
Revised in accordance with ICF 85-1306 34 12/03/85 16 PORC approved 11/05/85.
Revised in accordance with ICF 85-1487, s
35 01/17/86 Add 29 PORC approved 11/26/85.
1 Revised to increase minimum RCS level from I
elevation 695' to elevation 695'6" and to add 36 06/18/86 10,11,18 slonoff step to ensure precaution is followed.
2,5,6,8-11,13,14, Revised to correct typographical errors and to 17,20,21, correct license requirements from Technical 37 8/27/86 23-26 Specification references.
1
)
L 3
I 0451L/tir I
J
V:
~
I L4 SEQUOYAH NUCLEAR PLANT PLANT INSTRUCTION REVISION LOG SYSTEM OPERATING INSTRUCTION
~SOI-74.1 REVISION Date Pages REASON FOR REVISION (INCLUDE COMMITMENTS AND i
l LEVEL Approved Affected ALL'ICF FORM NUMBERS) l Revised to correct typographical errors and to-l l-clarify the' procedure to make it technically-Title Chg correct.
This review satisfies the biennial I
38 02/09/87 All requirement.
Revised to enhance the procedure; correct a drawing; made an organizational name change; f
also, Incorporated ICF No.87-205, PORC reviewed i
and approved 03/06/87.
This review satisfies i
39 04/17/87 All the biennial review requirement.
Revised to correct typographical errors, corrected setpoint for U-2 mintflow valve per WP 12536.
Enhanced section " and J (Procedure for swapping RHR pumps, when RCS is drained and when j
AUG 2 a
RCS is not drained). Added procedure for 91v87 40 All ventina RHR' system.
i i
e
~
-s 0451L/tir 4
__.___..m_
.j i
1: F,.
Sold 4,1 PageL1 l
Revision;40 l-,'.
[i;*
i RESIDUAL HEAT REMOVAL SYSTEM' PURPOSE i
To provide. instructions for the;following modes of operation:
A.
Placing RHR system in service: for normal cooldown.
- B.
Changing from Two Train'.Cooldown to One Train;Cooldown After Decay Heat j
4
- Load Permits-j C.
Filling Reactor Cavity for Refuel'ing'-
D._
~Dr_aining Reactor Cavity After Refueling l
E.
. Shutdown of_RHR System j
Changing from One Train Cooldown to Two Train Cooldown F.
G.
Filling RCS with RHR System After Vessel Head is.in Place l
Swapping RHR aumps:with Vessel Level Drained to Hot Legs n.
'J.
Swapping RHR Pumps K..
Filling and Venting the RHR System
_.J
=
i I
l l.
i i
02960/tir i
l
Jj I l
SQN --
50I-74.1 Page 42.
Revision 40 Section H Page 1 of:6 Date Unit
- 0perator SWAPPING RHR PUMPS WITH VESSEL LEVEL ORAINED TO HOT LEGS i
I.
. PURPOSE-l 4
To provide instructions which will prevent losing suction to_RHR pumps
.while. changing.to the'oppostte train with RCS. level drained,to hot
]
legs.
4 l.
II.
. LICENSE REQUIREMENTS TS 3.4.1.3, 3.4.1.4, 3.9.8.1,'3.9.8.2 I'I I. CONDITIONS FOR OPERATION
-A.
RCS larvel drained'to hot legs.
One train of.RHR in service with opposite train available.
B.
IV.
PRECAUTIONS A.
After starting opposite RHR' pump, monitor RCS level.to ensure that it does not fall below 695'6" to ensure adequate. suction to I
RHR pump.
L.
B.
Run only one RHR pump to minimize ~ probability of insufficient suction pressure to RHR pumps which could occur with both pumps running.
C.
RCS temperature shall be equal to or less than 140*F.
j
. i l
l l
I '~
0297U/tir
- l.
.I 1
(
j i
SQN S0 n f,. "
s#'h' g
jh Revision 40 Section H Page 2 of 6 Date Ope'rator Unit q
l
^
V.
INSTRUCTIONS.
I 1
A.
Placing "A" Train RHR in service and removing "B" Train RHR from service.
l 1
1.
Verify Valve Checklist 63.10 complete.
2.
Verify Pow;r Availabil,ity Checklist 63.10 complete.
3.
Verify "A" Train component cooling water in service-in accordance with SOI-70.1.
i 4.
-Ensure RCS level equal to or greater than el. 695'6".
5.
Verify closed FCV-74-16, RHR Htx. A outlet flow control valve.
f 6.
Verify closed FCV-74-28, RHP. Htx. B outlet flow l
control valve.
7.
Verify closed FCV-74-32, RHR Htx. bypass flow control valve.
i 8.
Verify closed FCV-63,93, CL Loops 2 and 3 MOV isol.
+l i.
Verify closed FCV-63-9k, CL Loops 1 and 4 M07 isol.
9.
10.
Verify that miniflow valve FCV-74-24 for RHR pmp B-B f
opens at 500 gpm (693 gpm for U-2).
t L
11.
Stop RHR pmp B-8.
t 12.
Verify FCV-70-156, RHR Htx. A CCS outlet NOV, positioned to obtain desired cooling rate.
CAUTION:
In order to reduce vib/ation across FCV-74-16 and FCV-74-28, the RHR must be aligned to only 2 cold legs when only one train of RHR is running.
l 02970/tir sem i.
.._______.________m.
d
4 l
So n =.kn L4.,
~
8" i'Sid4 CA EGORY n 40 Section H t
~~
Page 3 of 6 l
Oate Unit L
Operator i
V.
INSTRUCTIONS (continued) l I
A.
Placing "A" Train RHR in service and removing "B" Train RHR from l
T service (continued) i
- 13. If aligning RHR cooling water to loops 1 and 4, perform the l
g; following steps.
If not, NA this step.
l l
l a.,
Verify Open FCV-74'33 l
b.
Verify Open FCV-74-35 c.
Verify Open FCV-63-94 d.
Verify Closed FCV-63-93
- 14. If aligning RHR cooling water to loops 2 and 3, perform the following steps.
If not, NA this step.
a.
Verify Closed FCV-74-35 b.
. Verify Open FCV-74-33 I
c.
Verify Closed FCV.-63-94 d.
Verify Open FCV-63-93 15.
Verify open HCV-74-36, RHR Htx. A bypass isolation valve.
- 16. _
Verify open 74-530, RHR to letdown Htx.
17.
Verify closed HCV-74-37, RHR Htx. B bypass isolation valve.
~
18.
Verify closed 74-531, RHR to letdown Htx.
a 19.
Start RHR pump A-A.
20.
Verify miniflow valve FCV-74-12 opens if flow is
< 500 gpm (693 gpm for U-2).
0297U/tir i
iu
QA' SON UV
// ffs III SOI-74.1 CEEGORY f
M* son 40 Section H Page 4 of 6 Date Unit Operator.
f V.
INSTRUCTIONS (continued)
A.
Placing "A" Train RHR in service and removing "B" Train RHR from service (continued) 21.
Throttle FCV-74-16 and/or FCV-74-32 as required to maintain RCS at desired temp.
l 22.
Verify closed miniflos valve FCV-74-12 when RHR pump A-A outlet flow is
.s 1250 gpm.
B.
Placing "B" Train RHR in service and Removing "A" Train RHR from service.
1.
Verify Valve Ch'ecklist 63.10' complete.
2.
Verify Power Availability Checklist 63.10 complete.
l 3.
Verify "B" Train component cooling water in service
{
in accordance with SOI-70.1.
j 4.
Ensure RCS level equal to or greater than el. 695'6".
5.
. j
[,
Verify closed FCV-74.-16, RHR Htx. A outlet flow control valve.
6.
Verify closed FCV-74-28, RHR Htx. B outlet flow i
control valve.
j 7.
Verify closed FCV-74-32, RHR Htx. bypass flow control valve.
8.
Verify closed FCV-63-93, CL Loops 2 and 3 isol. MOV.
9.
Verify closed FCV-63-94, CL Loops 1 and'4 isol. MOV.
10.
Verify that miniflow valve FCV-74-12 for RHR pmp A-A opens at 500 gpm (693 gpm for U-2).
4 11.
Stop RHR pump A-A.
0297U/tir m
J So ayn L4.,
[m, Page 46 Revision 40 Section H Page 5 of 6 i
Unit Operator V.
INSTRUCTIONS (continued)
B.
Placing "B" Train RHR in service and Removing "A" Train RHR from I
service (continued) 1 12.
Verify FCV-70-153, RHR Htx. 8 CCS outlet MOV j
positioned to obtain desired cooling rate.
CAUTION:
In order to' reduce vibration across FCV-74-16 and FCV-74-28, the RHR must be aligned to only 2 cold legs when only one train of RHR is running.
- 13. If aligning RHR cooling water to loops 1 and 4, perform the following step:.
If not, NA this step.
i a.
Verify Closed FCV-74-33 i
b.
Verify Open FCV-74-35 c.
Verify Open FCV-63-94.
]
d.
Verify Closed FCV-63-93 L
- 14. If aligning RHR cooling water'to loops 2 and 3, perform the following steps.
If not, NA this step.
a.
Verify Open FCV-74-35 b.
Verify Open FCV-74-33 c.
Verify Closed FCV-63-94 d.
Verify Open FCV-63-93
~
15.
VerifyopenHCV-74-37,RHRHtx.$bypassisolation i
valve.
L 16.
Verify open 74-531, RHR to letdown Htx.
l.
17.
Verify closed HCV-74-36, RHR Htx A bypass isolation valve.
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MM Page 47-bh LUV31-Revislon 40 Section H Page.6 of 6 Date.
i Unit
. Operator V.
INSTRUCTIONS- (continued) 8.
Placing "B" Train RHR in service and Removing "A" Train RHR from service (continued) j e
18.
Verify closed 74-530, RHR to letdown Htx.
{
19.
Start RHR pump B-B.
20.
Verify miniflow valve FCV-74-24 opens.
j 21.
Throttle FCV-74-28 and FCV-74-32-as required to
. a.
maintain RCS at desired tem.-
i 22.
Verify closed miniflow valve FCV-74-24 when RHR pump 8-8 outlet flow Is > 1250 gpm.
VI.
REFERENCES
-47H810-1 SQN Technical Specifications CATS 85415 V
i I
s.
l 02970/ttr b
1
--m u
ATTACifMENT 4 TO ENCLOSURE 1
.