ML20216J743
| ML20216J743 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/17/1987 |
| From: | Mccool J, Mcpherson J, Sullivan J TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20216J530 | List: |
| References | |
| SI-130.2, NUDOCS 8707060334 | |
| Download: ML20216J743 (100) | |
Text
?
el TENNESSEE VALLEY AUTHORITY ^ .
SEQUOYAH NUCLEAR PLANT SURVEILLANCE INSTRUCTION SI-130.2 MOTOR DRIVEN AUXILIARY FEE 0 WATER PUMPS Units 1 and 2 ,
Revision 17 PREPARED BY: J.H. Sullivan/J.A. McPherson RESPONSIBLE SECTION: Mechanical Test REVISED BY: J . J . McCool i SUBMITTED BY: CN 0g 1 _
N f%n sb_ ,
Responsible Section Superv r PORC REVIEW DATE: APR T71987 1 APPROVED BY: j 6- 'D .T sv o J DATE APPROVED:
D 1
Reason for revision (include al' 1 Nos.): 1 Revised to correct errors, change format use measuring and test I equipment vice installed instruments and to clarify procedure as 1 a result of SI-1 Appendix F review. This revision satisfies the .1 biennial review requirements, CATS 86-489/SS3 850710 869, NCO' 87-0012-002, DR 86-03-075R, DR-86-319R, and MATS 9052. Revised i Revision log, Revision 16, to add CATS 85227. !
)
The last page of this instruction is number: 70 !
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SEQUOYAH NUCLEAR PLANT l PLANT INSTRUCTION REVISION LOG -
i SURVEILLANCE INSTRUCTION SI-130.2 l REVISION Date Pages REASON FOR REVISION (INCLUDE COMMIT-LEVEL Approved Affected MENTS AND ALL ICF FORM NUMBERS) 12 04/12/85 ALL 1 - 6, 9-18,20, 21,25,26, 28,29,31, 32,34,35 Revised in accordance with ICF No. 85-13 07/18/85 37-40 0694 PORC approved 07/03/85.
Revised in accordance with ICF 85-1261, l 14 11/01/85 3 PORC approved 10/24/85. I Revised in accordance with ICF No.
15 05/27/86 ALL 86-0247, PORC approved 03/14/86.
7,10,11, 13,15,17, 27.30,33, Revised in accordance with ICF 86-0814 16 06/13/86 36 PORC approved 05/27/86 and CATS 85227.
Revised to correct errors, change format use measuring and test equipment vice installed instruments and to clarify procedure, as a result of SI-l Appendix F review. This revision satisfies the biennal review requirements, CATS 86-489/S53 860710-869, NCO-87-0012-002, Added DR 86-03-075R, DR-86-319R and MATS 9052.
Punchlist Revised revision log, Revision 16, to 17 All add CATS 85227.
4 0358L/ tac b
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., 1 TO: CONTROLLED MANUAL HOLDER FROM: Document Control / Records Management, SQN DATE:
SUBJECT:
TRANSMITTAL OF SEQUOYAH INSTRUCTIONS l
Please sign below and return to acknowledge receipt of the following I materia? and affirm that it has been placed in the appropriate manuals, your table of contents has been updated, and the superseded instruction removed and discarded. Return this transmittal to Document Control within 10 days.
SI_130.2 MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS 1 1
Units 1 and 2 l s
Remove and destroy Insert Page Date Revision Page Date Revision i Added Punchlist All Various/Various All 17 Return to: Document Control / Records Management, SQN Signature /Date 0358L/ tac e
- If
1 1
l SQN SI-130.2 I Page 0 Revision 17
.j 4 PUNCHLIST
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This procedure will be establishing new reference values. To comply with ASME B&PV Code Section XI, IWP-3112, the test must be run with the current PORC approved procedure and verified acceptable. When this has been completed, then this SI can be approved by the Plant Manager and the previous SI or applicable revision cancelled at this time. This SI will be performed and the new reference values established. j i
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4 SON 3 SI-130.2 f Page 1 -
Revision 17 1.0 SCOPE '
1.1 Test Description j
i This Surveillance Instruction (SI) is divided into two (2) parts for testing of the motor driven auxiliary feedwater (AFW) pumps.
1.1.1 Part A of this surveillance test will demonstrate that the pumps are OPERABLE. Their operability is verified.
by starting each pump and verifying that the pump inlet pressure, differential pressure, discharge pressure, flow rates, vibration, and the lubrication oil level are i within acceptable range.
1.1.2 Part B of this surveillance test will verify pump' operability and generate new baseline values after maintenance has been completed on a pump which could {
affect its performance.
1.1.3 Both parts A and B will full stroke the pump's miniflow check valves (3-814, 3-815) and part stroke the pump's suction check valves (3-805, 3-806) and miniflow check j valves (3-894, 3-895).
j 1.2 Objectives 1.2.1 Part A of this instruction, AFW Pump Performance, shall verify that the pump being tested adheres to the allowable ranges of test quantitles (Appendix A) specified by the ASME B&PV Code,Section XI, and Technical Specifications (TS) 4.7.1.2.a.1 and 4.0.5.
This SI fulfills TS 4.7.1.2.a.1 and 4.0.5 for the MDAFH pumps.
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- SQN j SI-130.2 Page 2 Revision 17 -
1.0 SCOPE (continued)
NOTE: SON TS 4.7.1.2.a.1 establishes a delta P low limit of 1397 psid. Due to the installation of cavitating venturi in the Unit 1 and Unit 2 motor driven AFW pump discharge piping, more restrictive pump specific delta P limits were established and are provided in Appendix A
.(
Reference:
EN DES Calculations - 844 850620 013 dated 6-12-85 and USQD attached to WP-ll2*,3 revision 2 dated March 7, 1985). These values determine pump operability.
1.2.2 Part B of this instruction, AFW Pump P0st-Maintenance l Test, shall verify that the pump being tested adheres to the requirements of the ASME B&PV Code, Section'XI, Subsection IWP, after maintenance has been performed which could affect its performance.
1.2.3 Parts A and B verify full stroking of the pump miniflow check valves (3-814, 3-815) and part stroke of the suction check valves (3-805, 3-806) and miniflow check valves (3-894, 3-895).
1.3 Requirements NOTE: The motor driven AFW pumps may be tested in any mode.
1.3.1 The following are the requirements of Part A of this instruction for the motor driven'AFW pump performance test:
- 1. 3.1.1 Modes 1, 2, and 3 require three AFW pumps to be OPERABLE per unit, so the motor driven pumps and check valves will be tested once per quarter 1.3.1.2 While in modes 4, 5, or 6 and if the motor driven AFW pumps and check valves are not tested when required,'they will be tested prior to entry into mode 3.
1.3.2 Part B of this instruction AFW Pump Post-Maintenance Test, is only required when maintenance has been performed on either the pump, driver, or controls which could affect the pump's performance.
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Revision 17 1.0 _ SCOPE (continued) 1 i
NOTE:
An AFW pump post-maintenance test will be performed, after preventative maintenance and/or routine servicing of shaft packing that was repacked or tightened. Part A or 8 will be {
performed based on the maintenance' performed and- 3 the judgment of the cognizant engineer.
1.3.3 Sections 6.0, 7.0, 8.0, 9.0, 10.0, 11.0, 12.0, and 13.0 of this any instruction may be performed individually or in sequence.
2.0 REFERENCES
2.1 FSAR Section 6.8.
2.2 ASME B&PV Code Section XI, Subsection IWP and IWV,1974 Edition through Summer 1975 Addenda (Unit 1) and 1977 Edition through Summer 1978 Addenda (Unit 2).
2.3 Technical Specifications (TS) 4.0.5, 4.7.1.2.a.1.
2.4 SI-130.7, Turbine Driven AFW Pumps.
2.5 EN DES Calculations, B44 850620 013, 6/12/85.
2.6 Workplan 11243 R2, 3/7/85 and attached USQD.
2.7 TVA Drawing 47W803-2. I 2.8 TI-103 3.0 PRERE0VISITES 3.1 \
Receive before permission performing from this test.the Unit Senior Reactor Operator (SRO) 3.2 The AFW with system is aligned for standby operation in accordance SOI-3.2.
3.3 Verify the turbine driven AFW pump and the opposite train MDAFW when in modes 1, 2, or 3. pump are operable in the unit the test is being perfo 3.4 Contact Instrument Maintenance to install test equipment in accordance with work request (WR).
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'9 SQN SI-130.2 Page 4 j Revision 17 ,
4.0 PRECAUTIONS 4.1 Do not operate pump against a shutoff head, except with flow directed through the recirculation piping; then carefully monitor for signs of overheating. i 4.2 Do not perform this instruction if an AFW pump is inoperable . 1 unless it is being performed on that pump or unless the j inoperable pump is in the other unit while in modes 1, 2, or 3. ..
J 4.3 Perform the complete instruction for an AFW pump before proceeding to the next pump. If testing shows an AFH pump inoperable, do not test the remaining pump _s on the same unit while in modes 1, 2, or 3. .,
4.4 Do not use the same test equipment on more than one pump.
4.5 Monitor steam generator (S/G) levels to assure no auxiliary feedwater is injected into S/G.
5.0 SPECIAL TEST EQUIPMENT 5.1 The following special test equipment will be required:
5.1.1 Portable vibration indicator 1 5 percent accuracy, and a response range of 1/2 speed to at least maximum speed.
5.1.2 Ultrasonic flowmeter i 3 percent accuracy.
5.1.3 Pressure test instruments 1 2 percent accuracy.
5.1.4 Gauge full-range shall be less than 3 times the reference values, l
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SI-130.2 '
Page 5 .
Revision 17 OATA PACKAGE COVER SHEET Page 1 of 3 MOTOR DRIVEN AUXILIARY FEEDWATER PU!1PS Unit Mode Permission to Perform Test SR0 Performed by:
/ /
Signature Date Signature Date,
/ /
Signature Date Signature Date
/ /
Signature Date Signature Date Date/ Time Started / Date/ Time Completed /
List of data sheets attached.
Instruction No. Data Sheet No. No. of Pages i SI-130.2 I
J NOTE: Refer to Appendix A of SI for definitions of " Acceptable Range" and
" Alert Range."
Did all SI data meet acceptance criteria? Yes No Verified by /
c?qnature/ Title date 1013R/ tis i
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0
. 4 SQN SI-130.2 '
Page 6 '
Revision 17 OATA PACKAGE COVER SHEET Page 2 of 3 Unit Mode NOTE:
If answer next to the above question is "YES," there is no need to answer question.
If no, met? were allYes criteria under either " Acceptable Range" or " Alert Range" No Verified by /
Signature / Title date _
_ NOTE: ..
If answer to this question is "YES." there is no need for the Shift Engineer (SE) to complete the following. If the answer to the second question is "N0," notify the SE who completes the information below.
If the answer to the first question is "NO," but to the second question is "YES," the Mechanical Test Section will have test frequency doubled for this surveillance instruction until the criteria all fall within the acceptable range.
Was a potential reportable occurrence (PRO) initiated? I PRO # Yes No Was a limiting condition for operation (LCO) action required?
Yes (explain in remarks) _ No (explain in remarks)
Verified by SE l Date Time {
j Reason for test:
Required by schedule Maintenance complete on _
Another system ( (Instruction )
)' inoperable .
Plant conditf.on (explain)
Other (explain)
Review of of completion Test Results (SRO's review must be performed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> upon test) i Date Time SRO !
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Revision 17 DATA PACKAGE COVER SHEET I Page 3 of 3 Unit Mode Review and Approval of Test Results
- 1. M&S/S notified to assure SI is rerun within 45 days.
yes no N/A
- 2. M&S/S notified to increase SI frequency to twice per quarter.
yes no N/A _
Pump (s) Affected
- 3. M&S/S notified to return SI frequency to normal.
yes no N/A
/
MS/S Coordinator Date Pump (s) Affected
- 4. MTI-14 summary listing completed Date Mechanical Test Engineer QE&C Review of Test Results QE&C Representative Date Remarks:
1 ANII Review of Test Results '
ANII Inspector Date Remarks:
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, l SON SI-130.2 Page 8 l Revision 17 '
Unit Mode ,
6.0 INSTRUCTIONS FOR PART A - MOTOR DRIVEN AFW PUMP 1A-A PERFORMANCE
6.1 Prerequisites
3.1 /
SRO Signature Date t
3.2 /
Signature Date i
3.3 /
Signature Date l
3.4 /
Signature Date l 6.2 Verify the following test equipment is installed: !
6.2.1 Ultrasonic flowmeter:
/
Range ID Cal Date Cal Due Date Signature Date 6.2.2 Inlet pressure instrument at PI-3-117
/
Range ID Cal Date Cal Due Date Signature Date 6.2.3 Discharge pressure instrument at PT-3-122 )
/
Range ID Cal Date Cal Due Date Signature Date 6.3 Record AFH pump 1A-A inlet test gauge pressure at (PI-3-117) !
psig. !
/
Signature Date 6.3.1 Observe lubricant level for lA-A MDAFW pump. Sat l Unsat
/ i Signature Date l 1
6.3.1.1 If level is unsatisfactory notify the SRO. i i
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Signature Date 1013R/ tis 1
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Revision 17 l
Unit Hode 6.0 INSTRUCTIONS FOR PART A - AFW PUMP 1A-A PERFORMANCE (continued) 6.4 Place the following switches on panel M-4 in Manual and ramp close:
, 6.4.1 HS-3-156A /
Signature Date 6.4.2 HS-3-164A /
Signature Date 6.5 Place the following switches on panel M-4 in Manual bypass and ramp close: . ;
6.5.1 HS-3-156A / 6 Signature Date I 6.5.2 HS-3-164A /
Signature Date j 6.6 Verify the following valves CLOSED:
6.6.1 LCV-3-156 /
Signature Date 6.6.2 LCV-3-156A /
Signature Date 6.6.3 LCV-3-164 /
i signature Date 6.6.4 LCV-3-164A /
Signature Date i
NOTE: Steps 6.7, 6.8, and 6.11 are only required if not performed in Sections 7.0, 8.0, or 9.0. If already performed, N/A these l steps. ;
6.7 Verify VLV-3-927 locked OPEN
/
lst Signature Date
/
2nd Signature Date 6.8 UNLOCK and CLOSE VLV-3-923 /
Signature Date 1013R/tls
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SQN SI-130.2 Page 10 {
j Revision 17 )
l Unit I Mode j 6.0 INSTRUCTIONS FOR PART A - AFW PUMP 1A-A PERFORMANCE (continued)
CAUTION: Observe flow meter as pump is started to prevent dead i heading the pump.
Signature Date 6.9.1 Verify flow on ultrasonic flow instrument. 'If there is no flow, stop pump 1A-A and notify SRO and SE.
/ ,
Signature Date j 6.9.2 If there is flow, this verifies part stroke of VLV-3-805 and full stroke of VLV-3-814 and part stroke of j VLV-3-894 if steps 6.7 and 6.8 are performed. j l
I l Signature Date l
NOTE: The pump shall be run for a minimum of 5 minutes under conditions as stable as the system permits before taking data.
6.10 After required run time, record the following data:
6.10.1 Inlet test gauge pressure at (PI-3-ll7) psig.
1
/
Signature Date 6.10.2 Discharge test gauge pressure at (PT-3-122) psig
/
Signature Date Calculate pump differential pressure AP AP - Discharge pressure - Inlet pressure Discharge pressure psig (6.10.2)
Inlet pressure -
psig (6.10.1)
AP = psid
/
Signature Date 1013R/ tis e
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l SQN SI-130.2 Page il ~
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,l Revision 17 l
Unit ;
Mode {
(continued) l 6.0 INSTRUCTIONS FOR PART A - AFW PUMP 1A-A PERFORMANCE !
NOTE: Refer to Appendix B for vibration locations.
mils (peak to peak 6.10.3 Vibrations: Inboard vertical unfiltered) / I Signature Date
~
., Inboard horizontal mils (peak to peak unfiltered)
/
Signature Date Range ID Cal Date Cal Due Date sat unsat 6.10.4 Observe lubricant level:
/ !
Signature Date 6.10.4.1 If lubricant level is unsatisfactory, notify the SRO.
/
Signature Date gpm 6.10.5 Flowrate on ultrasonic flowmeter
/
Signature Date 6.11 Change valve alignment for part stroke of VLV-3-895:
l 6.11.1 OPEN AND LOCK VLV-3-923 1
/
lst Signature Date
/
2nd Signature Date CAUTION: Observe flowmeter as valve is closed to prevent dead heading the pump.
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SQN i SI-130.2 ~
Page 12 ,
Revision 17 -
Unit Mode 6.0 INSTRUCTIONS FOR PART A - AFH PUMP 1A-A PERFORMANCE (continued) 6.11.2 UNLOCK and CLOSE VLV-3-927 :
. /
Signature Date 6.11.3 Check flow on ultrasonic instrument. If flow is 3 value in step 6.10.5, this verifies VLV-3-895 part.
strokes. Go to Step 6.11.4. .,
/
Signature Date 6.11.3.1 If flow is less than step 6.10.5, STOP 1A-A pump and notify SR0 and SE VLV-3-895 failed to open and go to step 6.11.4. 1
/
Signature Date 6.11.4 OPEN AND LOCK VLV-3-927.
' I lst Signature Date I
/
2nd Signature Date ,
lst Signature Date
/
2nd Signature Date 6.13 Return the following switches to AUTO:
6.13.1 HS-3-156A /
lst Signature Date
/
2nd Signature Date 6.13.2 HS-3-164A /
1st Signature Date
/
2nd Signature Date
R s
i SON SI-130.2 Page 13 -
Revision 17 Unit Mode !
6.0 INSTRUCTIONS FOR PART A - AFW PUMP 1 A-A PERFORMANCE (continued) 6.14 Evaluate data using acceptance criteria in Appendix A:
6.14.1 If data is acceptable, go to step 6.15.
/
Signature Date 6.14.2 If data is unacceptable notify SRO and SE.
~
j
/
Signature Date 6.15 Remove the following test instruments:
6.15.1 Ultrasonic flowmeter
/
lst Signature Date
/
2nd Signature Date 6.15.2 Inlet pressure instrument at PI-3-il7
/
Ist Signature Date
/ t 2nd Signature Date 6.15.3 Discharge pressure instrument at PT-3-122
/ ,
1st Signature Date ;
/ ,
2nd Signature Date I I
6.16 Notify SR0 test of AFW pump 1A-A is complete.
/ !
Signature Date 1
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SQN SI-130.2 i Page 14 !
Revision 17 .l Unit ,,
Mode i 7.0 INSTRUCTIONS FOR PART A - MOTOR DRIVEN AFW PUMP IB-B PERFORMANCE l
7.1 Prerequisites
3.1 /
SRO Signature Date 3.2 /
Signature Date 3.3 /
Signature Date 3.4 /
Signature Date 7.2 Verify the following test equipment is installed:
7.2.1 Ultrasonic flowmeter:
/
Range ID Cal Date Cal Due Date Signature Date 7.2.2 Inlet pressure instrument at PI-3-127
/
Range ID Cal Date Cal Due Date Signature Date 7.2.3 Discharge pressure instrument at PT-3-132
/ ,
Range ID Cal Date ral Due Date Signature Date l 7.3 Record AFW pump IB-B inlet test gauge pressure at PI-3-127 psig
/
Signature Date l
l i
I l
l 1013R/ tis
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Page IS ,.
t Revision 17 Unit Mode 7.0 INSTRUCTIONS FOR PART A - AFW PUMP IB-B PERFORMANCE 7.3.1 Observe lubricant le. vel for 1B-8 MDAFW Pump.
Satisfactory Unsatisfactory
/
Signature Date
[-
7.3.1.1 If level is unsatisfactory notify the SRO.
~
/
Signature Date 7.4 Place the following switches on panel M-4 in Manual and ramp close:
7.4.1 HS-3-148A
/
Signature Date 7.4.2 HS-3-171A
/
Signature Date
7.5 Placeclose
ramp the following switches on panel M-4 in Manual bypass and 7.5.1 HS-3-'148A
/
Signature Date 7.5.2 HS-3-171A
/
Signature Date 7.6 Verify the following valves CLOSED:
7.6.1 LCV-3-148
/
Signature Date 7.6.2 LCV-3-148A
/
Signature Date 7.6.3 LCV-3-171
/
Signature Date 7.6.4 LCV-3-171A
/
Signature Date 1013R/ tis ,
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l SON SI-130.2
-l Page 16 Revision 17 Unit Mode 7.0 INSTRUCTIONS FOR PART A - AFW PUMP IB-B PERFORMANCE (continued)
NOTE: Steps 7.7, 7.8. and 7.11 are only required if not performed in Sections 6.0, 8.0, or 9.0. If already performed, N/A these steps.
7.7 Verify VLV-3-927 locked OPEN
/
ist Signature Date
/ i 2nd Signature Date 7.8 UNLOCK and CLOSE VLV-3-923 / l Signature Date '
CAUTION:
Observe flowmeter as pump is started to prevent dead heading the pump.
Signature Date 7.9.1 ~ Verify flow on ultrasonic flow instrument. If there is no flow, stop pump 1B-B and notify SR0 and SE.
I Signature Date I
{
7.9.2 If there is flow, this verifies part stroke of VLV-3-806 and full stroke of VLV-3-815, and part stroke of VLV-3-894 if steps 7.7 and 7.8 are performed. )
/
Signature Date NOTE:
The pump shall be run for a minimum of 5 minutes under conditions as stable as the system permits before taking data.
7.10 After required run time, record the following data:
7.10.1 Inlet test gauge pressure at (PI-3-127) psig.
/
Signature Date 1013R/ tis
3
. I I
l SQN l SI-130.2 J Page 17 -
Revision 17 ;
I Unit '
Mode 7.0 INSTRUCTIONS FOR PART A - AFW PUMP 18-B PERFORMANCE (continued) 7.10.2 Discharge test gauge pressure at (PT-3-132) psig
/ !
Signature Date Calculate pump differential pressure AP
~
AP = Discharge pressure.~ Inlet pressure i
Discharge pressure psig (7.10.2)
Inlet pressure -
psig (7.10.1) i i
AP = psid '
/
Signature Date NOTE: Refer to Appendix B for vibration locations.
7.10.3 Vibrations: Inboard vertical mils (peak to peak unfiltered)
/
Signature Date Inboard horizontal mils (peak to peak unfiltered)
\.
j Signature Date Range ID Cal Date Cal Due Date 7.10.4 Observe lubricant level: sat unsat
/
Signature Date 7.10.4.1 If lubricant level is unsatisfactory notify the SRO.
/
Signature Date 1013R/ tis 2
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SON I SI-130.2 Page 18 ~
Revision 17 Unit Mode 7.0 INSTRUCTIONS FOR PART A - AFW PUMP 18-8 PERFORMANCE (continued) 7.10.5 Flowrate on ultrasonic flowmeter gpm
/
Signature Date }
7.11 Change valve alignment for part stroke of VLV-3-895:
7.11.1 OPEN AND LOCK VLV-3-923.~.
1
/
lst Signature Date i 1
/ )
Zid Signature Date CAUTION: Observe flowmeter as valve is closed to prevent dead heading the pump.
7.11.2 UNLOCK and CLOSE VLV-3-927 I
/ l
(
Signature Date I 7.11.3 Check flow on ultrasonic flo,vmeter. If flow is i: value in step 7.10.5 this verifies VLV-3-895 part strokes, go to step 7.11.4. i l
/
Signature Date 7.11.3.1 If flow is less than step 7.10.5, STOP 18-B pump and notify SR0 and SE VLV-3-895 failed to open and go to step 7.11.4
/ l Signature Date 7.11.4 OPEN AND LOCK VLV-3-927.
/
ist Signature Date
/
2nd Signature Date 1013R/ tis t
- f SON SI-130.2 Page 19 *-
I Revision 17 Unit Mode 7.0 INSTRUCTIONS FOR PART A - AFW PUMP IB-B PERFORMANCE (continued) 7.12 Stop AFW pump 1B-B /
lst Signature Date
/
2nd Signature Date 7.13 Return the following switches to AUTO:
7.13.1 HS-3-148A /
lst Signature Date
/
2nd Signature Date 7.13.2 HS-3-171A /
lst Signature Date
/
2nd Signature Date 7.14 Evaluate data using acceptance criteria in Appendix A:
7.14.1 If data is acceptable, go to step 7.15.
/
Signature Date 7.14.2 If data is unacceptable, notify SR0 and SE.
/
Signature Date 7.15 Remove the following test instruments:
7.15.1 Ultrasonic flowmeter
/
lst Signature Date
/
2nd Signature Date 1013R/ tis
.o i
a M
SQN SI-130.2 Page 20 -
Revision 17 Unit Mode 7.0 INSTRUCTIONS FOR PART A - AFW PUMP 18-8 PERFORMANCE (continued) 7.15.2 Inlet pressure instrument at PI-3-127
/
lst Signature Date
/
2nd Signature Date 7.15.3 Discharge pressure instrument at PT-3-132
/
1st Signature Date
/
2nd Signature Date 7.16 Notify SRO test of AFW pump 1B-8 is complete.
/
, Signature Date 1013R/ tis 1
-o SQN SI-130.2 Page 21 .
Revision 17 *
. Unit Mode 8.0 INSTRUCTIONS FOR PART A - MOTOR DRIVEN AFW PUMP 2A-A PERFORMANCE
8.1 Prerequisites
3.1 /
SRO Signature Date 3.2 /
Signature Date .
3.3 /
Signature Date 3.4 /
Signature Date 8.2 Verify the following test equipment is installed:
8.2.1 Ultrasonic flowmeter:
/
Range ID Cal Date Cal Due Date Signature Date 8.2.2 Inlet pressure instrument at PI-3-il?
/
Range ID Cal Date Cal Due Date Signature Date 8.2.3 Discharge pressure instrument at PT-3-122
/
Range ID Cal Date Cal Due Date Signature Date 8.3 Record AFW pump 2A-A inlet test gauge pressure at (PI-3-il7) psig
/
Signature Date 8.3.1 Observe lubricant level for 2A-A MDAFW pump.
Sat Unsat
/
Signature Date 1013R/tls t
...w-
. s I
SQN SI-130.2 Page 22 -
Revision 17 Unit Mode 8.0 INSTRUCTIONS FOR PART A - AFH PUMP 2A-A PERFORMANCE (continued) 8.3.1.1 If level is unsatisfactory notify the SRO.
/ 4 Signature Date 8.4 Place the following switches on panel M-4 in Manual and ramp close:
8.4.1 HS-3 156A /
Signature Date 8.4.2 HS-3-164A /
Signature Date 8.5 Place the following switches on panel M-4 in Manual bypass and ramp close:
8.5.1 HS-3-156A /
Signature Date 8.5.2 HS-3-164A /
Signature Date 8.6 Verify the following valves CLOSED:
8.6.1 LCV-3-156 /
Signature Date 8.6.2 LCV-3-156A /
Signature Date 8.6.3 LCV-3-164 /
Signature Date 8.6.4 LCV-3-164A /
Signature Date I
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I Page 23 -
I Revision 17 Unit Hode ;
8.0 INSTRUCTIONS FOR PART A - AFW PUMP 2A-A PERFORMANCE (continued)
NOTE: Steps 8.7, 8.8, and 8.11 are only required if not performed in Sections 6.0, 7.0, or 9.0. If already performed, N/A these steps.
8.7 Verify VLV-3-927 locked OPEN
/
Ist Signature Date ,
.e 2nd Signature Date 8.8 UNLOCK and CLOSE VLV-3-923 /
Signature Date CAUTION: Observe flowmeter as pump is started to prevent dead heading the pump.
Signature Date 8.9.1 Verify flow on ultrasonic flowmeter.
stop pump 2A-A and notify SRO and SE.
If there is no flow.
/
Signature Date 8.9.2 If there is flow, this verifles part stroke of VLV-3-805 l and full stroke of VLV-3-814, and part stroke of VLV-3-894 if steps 8.7 and 8.8 are performed. {
t
/
Signature Date
)
NOTE: The pump shall be run for a minimum of 5 minutes under conditions as stable as the system permits before taking data.
8.10 After required run time, record the following data:
8.10.1 Inlet test gauge pressure at (PI-3-117) psig.
/
Signature Date 1013R/cwm
'mw. .-
h
SQN SI-130.2 Page 24 -
Revision 17 Unit Mode 1 8.0 INSTRUCTIONS FOR PART A - AFW PUMP 2A-A PERFORMANCE (continued) 8.10.2 Discharge test gauge pressure at (PT-3-122) psig
~
/
Signature Date ,
Calculate pump differential pressure AP AP - Discharge pressure - Inlet pressure Discharge pressure psig (8.10.2)
Inlet pressure -
psig (8.10.1)
AP - psid Signature Date NOTE: Refer to Appendix 8 for vibration locations.
8.10.3 Vibrations: Inboard vertical mils (peak to peak unfiltered)
/
Signature Date Inboard horizontal mils (peak to peak unfiltered) l Signature Date 1 Range ID Cal Date Cal Oue Date 8.10.4 Observe lubricant level: sat unsat
/
Signature Date 8.10.4.1 If lubricant level is unsatisfactory notify the SRO.
/
Signature Date 1013R/ tis 1%
1
-a SQN SI-130.2 ~
Page 25 .
Revision 17 Unit Mode 8.0 INSTRUCTIONS FOR PART A - AFW PUMP 2A-A PERFORMANCE (continued) 8.10.5 Flowrate on ultrasonic flowmeter gpm
/
Signature Date i 8r11 Change valve alignment for part stroke of VLV-3-895:
8.11.1 OPEN AND LOCK VLV-3-923 l
\
ist Signature Date j
/ I 2nd Signature Date CAUTION: Observe flowmeter as valve is closed to prevent dead heading the pump.
i 8.11.2 UNLOCK and CLOSE VLV-3-927 1
/
Signature Date 1
8.11.3 Check flow on ultrasonic flowmeter. If flow is t value in step 8.10.5 this verifies VLV-3-895 part strokes, go to step 8.11.4.
I Signature Date j 1
8.11.3.1 If flow is less than step 8.10.5, STOP 2A-A pump {
and notify SRO and SE VLV-3-895 failed to open '
and go to step 8.11.4.
I Signature Date j 8.11.4 OPEN AND LOCK VLV-3-927.
/
lst Signature Date
/
2nd Signature Date 1013R/tls
SQN SI-130.2 Page 26 _
Revision 17 -
Unit Mode 8.0 INSTRUCTIONS FOR PART A - AFW PUMP 2A-A PERFORMANCE (continued) i 8.12 Stop AFW pump 2A-A / l 1st Signature Date I k:
2nd Signature Date 8.13 Return the following swl_tches to AUTO:
8.13.1 HS-3-156A / I
_lst Signature Date
/
2nd Signature Date 8.13.2 HS-3-164A /
lst Signature Date
/
~ 2nd Signature Date 8.14 Evaluate data using acceptance criteria in Appendix A:
I 8.14.1 If data is acceptable, go to step 8.15.
/
Signature Date j i
8.14.2 If data is unacceptable, notify SRO and SE. l 1
/
Signature Date 8.15 Remove the following test instruments:
8.15.1 Ultrasonic flowmeter
/
lst Signature Date
/
2nd Signature Date ;
I 1013R/ tis j i
9
.'b.
.o SON SI-130.2 j
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Page 27 .
Revision 17 Unit Mode j 8.0 INSTRUCTIONS FOR PART A - AFW PUMP 2A-A PERFORMANCE (continued) 8.15.2 Inlet pressure instrument at PI-3-117
/ l 1st Signature Date
/
2nd Signature Date 8.15.3 Discharge pressure instrument at PT-3-122 ,
/
lst Signature Date l
/
2nd Signature Date j 8.16 Notify SR0 test of AFW pump 2A-A is complete. l
/
Signature Date i
i 1013R/ tis T
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SON l SI-130.2 Page 28 ,
Revision 17 i
Unit i i
Mode 9.0 INSTRUCTIONS FOR PART A - AFW PUMP 2B-B PERFORMANCE I
9.1 Prerequisites
3.1 /
SRO Signature Date 3.2 /
Signature Date 3.3 /
Signature Date 3.4 /
Signature Date 9.2 Verify the following test equipment is installed: {
9.2.1 Ultrasonic flowmeter:
/
Range ID Cal Date Cal Due Date Signature Date 9.2.2 Inlet pressure instrument at PI-3-127
/
Range ID Cal Date Cal Due Date Signature Date 9.2.3 Discharge pressure instrument at PT-3-132
/
Range ID Cal Date Cal Due Date Signature Date i 9.3 Record AFW pump 2B-8 inlet test gauge pressure at (PI-3-127) !
psig
/
Signature Date l 9.3.1 Observe lubricant level for 28-B MDAFW pump.
Sat Unsat
/ '
Signature Date 1013R/ tis l t
SQN SI-130.2 ,
Page 29 -
Revision 17 Unit Mode as 9.0 INSTRUCTIONS FOR PART A - AFW PUMP 2B-B PERFORMANCE (Continued) 9.3.1.1 If level is unsatisfactory notify the SRO.
~~~ /
Signature Date 9.4 Place the following switches on panel M-4 in Manual and ramp close: .
9.4.1 HS-3-148A /
Signature Date 9.4.2 HS-3-171A /
Signature Date 9.5 Place the following switches on panel M-4 in Manual bypass and ramp close:
9.5.1 HS-3-148A /
Signature Date 9.5.2 HS-3-171A /
Signature Date 9.6 Verify the following valves CLOSED:
9.6.1 LCV-3-148 /
Signature Date 9.6.2 LCV-3-148A /
Signature Date 9.6.3 LCV-3-171 /
Signature Date 9.6.4 LCV-3-171A /
Signature Date 1013R/cwm 4
s
SQN SI-130.2 i
Page 30 Revision 17 Unit Mode j l
9.0 INSTRUCTIONS FOR PART A - AFW PUMP 2B-B PERFORMANCE (continued) J NOTE: Steps 9.7, 9.8, and 9.11 are only required if not performed in Sections 6.0, 7.0, or 8.0. If already performed, N/A these steps.
]
9.7 Verify VLV-3-927 locked OPEN
/
lst Signature Date
/
2nd Signature Date 9.8 UNLOCK and CLOSE VLV-3-923
/
Signature Date ;
CAUTION: Observe flowmeter as pump is started to prevent dead heading the pump.
9.9 Start AFW pump 28-8 /
Signature Date
)
9.9.1 Verify flow on ultrasonic flowmeter. If there is no flow, stop pump 2B-8 and notify SR0 and SE.
/
Signature Date 9.9.2 If there is flow, this verifies part stroke of VLV-3-806 and full stroke of VLV-3-815, and part stroke of VLV-3-894 if steps 9.7 and 9.8 are performed.
/
Signature Date 1013R/cwm
o SQN SI-130.2 Page 31 -
Revision 17 Unit Mode 9.0 INSTRUCTIONS FOR PART A - AFW PUMP 2B-B PERFORMANCE (continued)
NOTE: The pump shall be run for a minimum of 5 minutes under conditions ,
as stable as the system permits before taking data. !
9.10 After required run time, record the following data: ;
9.10.1 Inlet test gauge pressure at (PI-3-127) psig.
~
t
/
Signature j Date {
9.10.2 Discharge test gauge pressure at (PT-3-132) psig l
/ i Signature Date Calculate pump differential pressure AP AP - Discharge pressure - Inlet pressure j
Discharge pressure psig (9.10.2) !
Inlet pressure -
psig (9.10.1) {
AP = psid l l
/ .
Signature Date NOTE: Refer to Appendix B for vibration locations.
9.10.3 Vibrations: Inboard vertical mils (peak to peak unfiltered)
/
Signature Date Inboard horizontal mils (peak to peak unfiltered)
/
Signature Date Range 10 Cal Date Cal Oue Date 1013R/cwm j
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1 SQN l SI-130.2 I Page 32 -
I Revision 17 ,I Unit Mode 9.0 INSTRUCTIONS FOR PART A - AFH PUMP 28-8 PERFORMANCE (continued) l i'
9.10.4 Observe lubricant level: sat unsat
/
Signature Date 9.10.4.1 If lubricant level is unsatisfactory notify the S RO ._
.. /
Signature Date 9.10.5 Flowrate on ultrasonic flowmeter gpm
/
Signature Date 9.11 Change valve alignment for part stroke of VLV-3-895:
9.11.1 OPEN AND LOCK VLV-3-923
/
Ist Signature Date ~
/
2nd Signature Date CAUTION: Observe flowmeter as valve is closed to prevent dead heading the pump.
9.11.2 UNLOCK and CLOSE VLV-3-927
/
Signature Date J 9.11.3 Check flow on ultrasonic flowmeter. If flow is t value I in step 9.10.5 this verifles VLV-3-895 part strokes, go to step 9.11.4.
/
Signature Date 1013R/ tis M
va < ,
n SQN i SI-130.2 j Page 33 '
Revision 17 Unit Mode 9.0 INSTRUCTIONS FOR PART A - AFW PUMP 28-B PERFORMANCE (continued) 9.11.3.1 If flow is less than step 9.10.5, STOP 28-B pump and notify SRO and SE VLV-3-895 failed to open ;
and go to step 9.11.4. l
/ !
Signature Date 9.11.4 OPEN AND LOCK VLV-3-927.
/
s ist Signature Date l
/
2nd Signature Date 9.12 Stop AFW pump 28-8 /
lst Signature Date
~'
2nd Signature Date !
9.13 Return the following switches to AUTO:
9.13.1 HS-3-148A /
l l
1st Signature Date
_ /
2nd Signature Date 9.13.2 HS-3-171A /
lst Signature Date
/
2nd Signature Date 9.14 Evaluate data using acceptance criteria in Appendix A:
9.14.1 If data is acceptable, go to step 9.15.
/
Signature Date 1013R/ tis 0
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SQN SI-130.2 Page 34 -
Revision 17 9.0 INSTRUCTIONS FOR PART A - AFW PUMP 28-B PERFORMANCE (continued) 9.14.2 If data is unacceptable, notify SRO and SE.
/
Signature Date 9.15 Remove the following test instruments:
9.15.1 Ultrasonic flowmeter
/
lst Signature Date
/
2nd Signature Date 9.15.2 Inlet pressure instrument at PI-3-127
/
lst Signature Date
/
2nd Signature Date 9.15.3 Discharge pressure instrument at PT-3-132
/
1st Signature Date
/
2nd Signature Date 9.16 Notify SR0 test of AFH pump 2B-B is complete.
I
/ l Signature Date l
l i
1013R/tls
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SQN SI-130.2 Page 3S Revision 17 .
DATA PACKAGE COVER SHEET Page 1 of 3 i MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS Unit Mode Permission to perform test SRO Performed by:
/ /
Signature., Date Signature Date
/ /
Signature Date Signature Date
/ / I Signature Date Signature Date Date/ Time Started / Date/ Time Completed /
List of data sheets attached.
Instruction No. Data Sheet No. No. of Pages SI-130.2
)
NOTE: Refer to Appendix A of SI for definitions of " Acceptable Range" and
" Alert Range."
Did all SI data meet acceptance criteria? Yes No l
Verified by /
Signature / title date
)
NOTE: If answer to the above question is "YES," there is no need to answer next question.
1014R/peb 4-sy
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- , + ..
2 ;
SQN-SI-130.2 Page 36 Revision 17 -
. DATA PACKAGE COVER SHEET Page 2 of 3 If no, were all criteria under either." Acceptable Range" or " Alert Range" met? Yes No /
Verified by date Signature / title NOTE: If answer to this-question.is "YES," there is no need for the ShiftIf the ans Engineer "NO,". (SE)notify to complete the SE who the following.
completes question the information below. is If the answer to the.first question is "NO," but to the second .
question is "YES." the Mechanical Test Section will have test.
frequency doubled for this SI until the criteria all fall within-the acceptable range.
Yes No If yes, PRO # l Has a PRO initiated?
Has a LC0 action required?
Yes (explain in remarks) No (explain in remarks)
Date _
Verified by SE Time Reason for test:
- Required by schedule )
Maintenance complete on (Instruction Another system ( ) inoperable Plant condition (explain)
Other (explain)
Review of Test Results (SR0's review must be performed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> upon completion of test)
Date SRO Review and Approval of Test Results
- 1. M&S/S notified to assure SI is rerun within 45 days.
yes no N/A
- 2. M&S/S notified to increase SI frequency to twice per quarter.
yes no N/A Pump (s) Affected 4
1014R/peb i
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I s
l SQN SI-130.2 Page 37 Revision 17 -
DATA PACKAGE C0VER SHEET ;
Page 3 of 3 '
- 3. M&S/S notified to return SI frequency to normal, yes no N/A
/
M&S/S Coordinator Date Pump (s) Affected l
- 4. MTI-14 summary listing completed !
Date Mechanical Test Engineer .
QE&C Review of Test Results QE&C Staff Date Remarks:
ANII Review of Test Results ANII Inspector Date ;
i Remarks:
i 1
l I
I 1014R/peb si , 4 c; 4g w I sj p , 3
I SON
{
i SI-130.2 )
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Page 38 )
Revision 17 . (
1 Unit j Mode 10.0 INSTRUCTIONS FOR PART B - MOTOR DRIVEN AFW PUMP 1A-A POST-MAINTENANCE 10.1 Prerequisites: 3.1 /
SR0 Signature Date 3.2 ~
/
Signature Da te j 3.3 /
Signature Date 3.4 /
Signature Date 10.2 Verify the following test equipment is installed:
10.2.1 Ultrasonic flowmeter:
/
Range ID Cal Date Cal Due Date Signature Date 10.2.2 Inlet pressure instrument at PI-3-ll7
/
Range ID Cal Date Cal Due Date Signature Date 10.2.3 Discharge pressure instrument at PT-3-122 i
/
Range ID Cal Date Cal Due Date Signature Date )
10.3 Record test gauge pressure at (PI-3-il7) psig
/
Signature Date 10.3.1 Observe lubricant level for 1 A-A MDAFW pump.
Sat Unsat !
/
Signature Date 10.3.1.1 If level is unsatisfactory notify the SRO.
/
Signature Date 1014R/peb
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SQN SI-130.2 Page 39 Revision 17 -
Unit Mode i 10.0 INSTRUCTIONS FOR PART 8 - AFW PUMP 1A-A POST-MAINTENANCE (continued) 10.4 Place the following switches on panel M-4 in Manual and ramp close:
10.4.1 HS-3-156A /
Signature Date 10.4.2 HS-3-164A /
Signature Date 10.5 Place the following switches on panel M-4 in Manual bypass and ramp close: ;
10.5.1 HS-3-156A /
Signature Date 10.5.2 HS-3-164A /
Signature Date Verify the following valves CLOSED:
10.6 10.6.1 LCV-3-156 /
Signature Date 10.6.2 LCV-3-156A / i Signature Date j i
10.6.3 LCV-3-164 / i Signature Date l l
10.6.4 LCV-3-164A / -
Signature Date NOTE: Steps 10.7, 10.8, and 10.11 are only required if not performed l in Sections 11.0, 12.0, or 13.0. If already performed, N/A these steps.
I 10.7 Verify VLV-3-927 locked OPEN i
/
lst Signature Date
/
2nd Signature Date i 10.8 UNLOCK and CLOSE VLV-3-923
/ '
Signature Date 1014R/peb :
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]
1 1
o SQN SI-130.2 1 Page 40 Revision 17 .-
l j
Unit Mode I
10.0 INSTRUCTIONS FOR PART 8 - AFH PUMP 1A-A POST-MAINTENANCE (continued)
CAUTION: Observe flowmeter as pump is started to prevent dead heading the pump.
10.9 Start AFH pump 1A-A /
Signature Date 10.9.1 Verify flow on ultrasonic flowmeter. If there is no flow, stop pump _lA-A and notify SRO and SE.
/
Signature Date 10.9.2 If there is flow, this verifles part stroke of VLV-3-805 and full stroke of VLV-3-814 and part stroke of VLV-3-894 if steps 10.7 and 10.8 are performed.
/
Signature Date NOTE: The pump shall be run for a minimum of 5 minutes under conditions as stable as the system permits before taking data.
10.10 After required run time, record the following data:
10.10.1 Inlet test gauge pressure at (PI-3-117) psig.
/
Signature Date i
10.10.2 Discharge test gauge pressure at (PT-3-122) psig ;
4
/
Signature Date Calculate-pump differential pressure AP 6P = Discharge pressure - Inlet pressure Discharge pressure psig (10.10.2)
Inlet pressure - psig (10.10.1) 6P - psid l
/
Signature Date 1014R/peb l
t
/, - t
SQN SI-130.2 Page 41
{
Revision 17 .
Unit Mode 10.0 INSTRUCTIONS FOR PART B - AFW PUMP 1A-A POST-MAINTENANCE (continued)
NOTE: Refer to Appendix B for vibration locations. l 10.10.3 Vibrations: Inboard vertical mils peak to peak '
f i
/ l Signature Date i
Inboard horizontal mils peak to peak
/
Signature Date '
Range ID Cal Date Cal Due Date 10.10.4 Observe lubricant level: sat ___ unsat j
/ I Signature Date 10.10.4.1 If lubricant level is unsatisfactory notify the SRO.
/
Signature Date
, 10.10.5 Flowrate on ultrasonic flowmeter gpm
/
Signature Date 10.11 Change valve alignment for part stroke of VLV-3-895:
10.11.1 OPEN AND LOCK VLV-3-923
/
lst Signature Date
/
2nd Signature Date 1014R/cwm -
p 4'
i .k t
5+ s
e i
SQN )
SI-130.2 i 1 Page 42 !
I Revision 17 -
Unit Mode
(. '
10.0 INSTRUCTIONS FOR PART B - AFW PUMP 1A-A POST-MAINTENANCE (continued) [m CAUTION: Observe the flowmeter as valve is closed to prevent '
dead heading the pump. j I
10.11.2 UNLOCK and CLOSE VLV-3-927 {
i
/ j Signature Date {
10.11.3 Check flow on ultrasonic flowmeter. If flow is i: .
value in step 10.10.5 this verifies VLV-3-895 part l strokes, go to step 10.11.4.
I I
)
/ l Signature Date bi 10.11.3.1 If flow is less than step 10.10.5, STOP 1A-A pump and notify SR0 and SE VLV-3-895 failed to open and go to step 10.11.4. ,
l
/
Signature Date 10.11.4 OPEN AND LOCK VLV-3-927.
/
ist Signature Date
/
2nd Signature Date 10.12 Stop AFW pt:mp 1 A-A / l i
lst Signature Date l
/ l 2nd Signature Date ,
10.13 Return the following switches to AUTO:
10.13.1 HS-3-156A /
Ist Signature Date
/ '
2nd Signature Date f
i 1014R/cwm t
t .I.60 4
SON SI-130.2 Page 43 Revision 17 -
Unit Mode 10.0 INSTRUCTIONS FOR PART B - AFW PUMP 1A-A POST-MAINTENANCE (continued) 10.13.2 HS-3-164A /
Ist signature Date
/
2nd Signature Date 10.14 Evaluate data using acceptance criteria in Appendix A:
10.14.1 If data is acceptable, go to step 10.15.
/
Signature Date 10.14.2 If data is unacceptable, notify SRO and SE.
/
Signature Date 10.15 Remove the following test instruments:
10.15.1 Ultrasonic flowmeter
/
lst Signature Date
/
2nd Signature Date 10.15.2 Inlet pressure instrument at PI-3-117
/
lst Signature Date
/
2nd Signature Date 10.15.3 01scharge pressure instrument at PT-3-122
/ -
1st Signature Date
/
2nd Signature Date 1014R/cwm 3 I
i va .u =
SQN SI-130.2 Page 44 .,
Revision 17
- Unit Mode 10.0 INSTRUCTIONS FOR PART 8 - AFW PUMP 1A-A POST-MAINTENANCE (continued) 10.16 Notify SRO test of AFW pump 1A-A is complete. '
/
Signature Date 10.17 Reviewing section complete the following:
10.17.1 Review the results. (Refer to Appendix A in conjunction with the following.) ,
10.17.1.1 A new reference value or set of values shall be determined or the previous values reconfirmed.
10.17.1.2 Deviacions between previous and new sets of reference values shall be identified and verification that the new values represent acceptable pump performance.
10.17.1.3 If new reference values are acceptable, revise Appendix A.
10.17.1.4 If new reference values are unacceptable, repairs shall be redone and the test rerun.
Deviations and Verifications I
1 Mechanical Test Engineer / Date I 1014R/cwm e
., m ' e fa d' , p
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SQN ;
SI-130.2 Page 4S Revision 17 -
Unit Mode 11.0 INSTRUCTIONS FOR PART B - MOTOR DRIVEN AFW PUMP 18-8 POST-MAINTENANCE 11.1 Prerequisites: 3.1 /
SRO Signature Date 3.2 /
Signature Date 3.3 /
_ Signature Date 3.4 /
Signature Date 11.2 Verify the following test equipment is installed:
l 11.2.1 Ultrasonic flowmeter:
/
Range ID Cal Date Cal Due Date Signature Date 11.2.2 Inlet pressure instrument at PI-3-127
/
Range ID Cal Date Cal Due Date Signature Date l 11.2.3 Discharge pressure instrument at PT-3-132
/
Range ID Cal Date Cal Due Date Signature Date 11.3 Record AFW pump 1B-B inlet test gauge pressure at PI-3-127 psig
/
Signature Date 11.3.1 Observe lubricant level for 1B-B MDAFW pump Sat Unsat
/
Signature Date 11.3.1.1 If level is unsatisfactory notify the SRO.
/
Signature Date 1014R/peb l
~
I*
,5., 1 .,4 % 3 4i ;g
q c
SQN SI-130.2 Page 46 ,
Revision 17 -
Unit Mode 11.0 INSTRUCTIONS FOR PART B - AFH PUMP 18-B POST-MAINTENANCE (continued) 11.4 Place the following switches on panel M-4 in Manual and ramp !
close:
11.4.1 HS-3-148A /
Signature Date 11.4.2 HS-3-171A /
Signature Date_
11.5 Place the following switches on panel M-4 in Manual bypass and ramp close:
11.5.1 HS-3-148A / !
Signature Date l 11.5.2 HS-3-171A /
Signature Date 11.6 Verify the following valves CLOSED:
11.6.1 LCV-3-148 /
Signature Date 11.6.2 LCV-3-148A /
Signature Date 11.6.3 LCV-3-171 /
Signature Date 11.6.4 LCV-3-171A /
Signature Date NOTE: Steps 11.7,11.8, and 11.11 are only required if not performed in -
Sections 10.0, 12.0, or 13.0. If already performed, N/A these l steps.
11.7 Verify VLV-3-927 locked OPEN
/
1st Signature Date ,
/
2nd Signature Date j 1014R/peb w .
SQN SI-130.2 Page 47 Revision 17
- Unit Mode 11.0 INSTRUCTIONS FOR PART B - AFW PUMP 18-B POST-MAINTENANCE (continued) 11.8 UNLOCK and CLOSE VLV-3-923
/
Signature Date CAUTION: Observe flowmeter as pump is started to prevent dead heading the pump.
11.9 Start AFH pump 18-B /
Signature Date..
11.9.1 Verify flow on ultrasonic flowmeter. If there is no flow, stop pump 18-B and notify SR0 and SE.
/
Signature Date 11.9.2 If there is flow, this verifles part stroke of VLV-3-806 and full stroke of VLV-3-815, and part stroke of VLV-3-894 if steps 11.7 and 11.8 are performed.
/
Signature Date ;
NOTE: The pump shall be run for a minimum of 5 minutes under conditions as stable as the system permits before taking data.
11.10 After required run time, record the following data:
11.10.1 Inlet test gauge pressure at (PI-3-127) psig
/
Signature Date 1014R/peb
% 6
-a SQN SI-130.2 Page 48 Revision 17 -
Unit Mode 11.0 INSTRUCTIONS FOR PART B - AFW PUMP 18-8 POST-MAINTENANCE (continu 11.10.2 Discharge test gauge pressure at (PT-3-132) psig
/
Signature Date Calculate pump differential pressure AP AP = Discharge pressure - Inlet pressure Discharge pressure psig (11.10.2)
Inlet pressure -
psig (11,10,j)
AP = psid
/
Signature Date NOTE: Refer to Appendix B for vibration locations.
11.10.3 Vibrations: Inboard vertical mils peak to peak
/
Signature Date Inboard horizontal mils peak to peak
/
Signature Date a
Range ID Cal Date Cal Due Date 11.10.4 Observe lubricant level: sat ___ unsat
/
Signature Date 11.10.4.1 If lubricant level is unsatisfactory notify the SRO.
/
Signature Date 11.10.5 Flowrate on ultrasonic flowmeter gpm
/
Signature Date -
1014R/peb r
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o SON SI-130.2 Page 49 -
Revision 17 Unit l Mode i 11.0 INSTRUCTIONS FOR PART B - AFW PUMP 18-8 POST-MAINTENANCE (continued) 11.11 Change valve alignment for part stroke of VLV-3-895:
11.11.1 OPEN AND LOCK VLV-3-923 l
/ {
Ist Signature Date
~
2nd Signature Date !
}
CAUTION: Observe flowmeter as valve is closed to prevent I dead heading the pump.
11.11.2 UNLOCK and CLOSE VLV-3-927
/
Signature Date 11.11.3 Check flow on ultrasonic flowmeter. If flow is E )
value in step 11.10.5 this verifles VLV-3-895 part '
strokes, go to step 11.11.4.
~
/
Signature Date 11.11.3.1 If flow is less than step 11.10.5, STOP 1B-B pump and notify SRO and SE VLV-3-895 failed to open and go to step 11.11.4.
/
Signature Date 11.11.4 OPEN AND LOCK VLV-3-927.
/
1st Signature Date
/
2nd Signature Date 11.12 Stop AFW pump 1B-B /
1st Signature Date 2nd Signature Date 1014R/peb a' ,, 6 gru 4 . '
l SQN l SI-130.2 Page 50 Revision 17 ,
Unit Mode 11.0 INSTRUCTIONS FOR PART B - AFW PUMP 1B-8 POST-MAINTENANCE (continued) 11.13 Return the following switches to AUTO:
11.13.1 HS-3-148A / l 1st Signature Date j
/ .
2nd Signature Date 11.13.2 HS-3-171A I. /
lst Signature Date
/
2nd Signature Date 11.14 Evaluate data using acceptance criteria in Appendix A: i 11.14.1 If data is acceptable, go to step 11.15.
/
Signature Date 11.14.2 If data is unacceptable, notify SRO and SE. q
/ I Date I Signature 11.15 Remove the following test instruments:
11.15.1 Ultrasonic flowmeter
/
lst Signature Date
/
2nd Signature Date 11.15.2 Inlet pressure instrument at PI-3-127 ,
/
Ist Signature Date
/
2nd Signature Date 1014R/peb
l
- f SQN
\
SI-130.2 l Page 51 i
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Revision 17 .{
l Unit i Mode I l
11.0 INSTRUCTIONS FOR PART B - AFW PUMP 18-8 POST-MAINTENANCE (continued) 11.15.3 Discharge pressure instrument at PT-3-132
/ ..
1st Signature Date
/
2nd Signature Date j
~
11.16 Notify SRO test of AFH pump 18-8 is complete.
l
/ !
Signature Date l 4
11.17 Reviewing section complete the following:
11.17.1 Review the results. (Refer to Appendix A in conjunction with the following.) f 11.17.1.1 A new reference value or set of values shall !
be determined or the previous values reconfirmed.
11.17.1.2 Deviations between previous and new sets of reference values shall be identified and verification that the new values represent acceptable pump performance.
11.17.1.3 If new reference values are acceptable, revise Appendix A.
11.17.1.4 If new reference values are unacceptable, repairs shall be redone and the test rerun.
Deviations and Verifications Mechanical Test Engineer / Date 1014R/peb
< 1.4t$: -
c SON SI-130.2 Page S2 Revision 17 -
Unit Mode 12.0 INSTRUCTIONS FOR PART B - HOTOR DRIVEN AFH PUMP 2A-A POST-MAINTENANCE 12.1 Prerequisites: 3.1 /
SRO Signature Date 3.2 /
Signature Date !
3.3 /
Signature Date .
3.4 /
Signature Date 12.2 Verify the following test equipment is installed:
12.2.1 Ultrasonic flowmeter:
/
Range ID Cal Date Cal Due Date Signature Date 12.2.2 Inlet pressure instrument at PI-3-ll7
/
Range ID Cal Date Cal Due Date Signature Date
, 12.2.3 Discharge pressure instrument at PT-3-122
/
Range ID Cal Date Cal Due Date Signature Date 12.3 Record AFH pump 2A-A inlet test gauge pressure at (PI-3-117) psig
/
Signature Date ,
12.3.1 Observe lubricant level for 2A-A MDAFH pump Sat Unsat Signature Date 12.3.1.1 If level is unsatisfactory notify the SRO.
Signature Date l
1014R/peb "
4 4 .
1 SON SI-130.2 Page 53 Revision 17 Unit Mode 12.0 INSTRUCTIONS FOR PART B - AFW PUMP 2A-A POST-MAINTENANCE (continued) 12.4 Place the following switches on panel M-4 in Manual and ramp close:
12.4.1 HS-3-156A /
Signature Date 12.4.2 HS-3-164A /
Signature Date I
- 12.5 Place the following switches on panel M-4 in Manual bypass and ramp close:
12.5.1 HS-3-156A /
Signature Date 12.5.2 HS-3-164A / ;
Signature Date 12.6 Verify the following valves CLOSED:
12.6.1 LCV-3-156 /
Signature Date 12.6.2 LCV-3-156A /
Signature Date 12.6.3 LCV-3-164 /
Signature Date 12.6.4 LCV-3-164A /
Signature Date NOTE: Steps 12.7, 12.8, and 12.11 are only required if not performed in Sections 10.0, 11.0, or 13.0. If already performed, N/A these steps.
12.7 Verify VLV-3-927 locked OPEN
/
lst Signature Date
/
2nd Signature Date 12.8 UNLOCK and CLOSE VLV-3-923
/ ,,
Signature Date
!>h s _ ; , 5
- o SON
, SI-130.2 Page 54 Revision 17 '-
Unit Mode 12.0 INSTRUCTIONS FOR PART B - AFW PUMP 2A-A POST-MAINTENANCE (continued)
CAUTION: Observe flowmeter as pump is started to prevent dead heading the pump.
Signature Date
)
i 12.9.1 Verify flow on ultrasonic flowmeter. If there is no l flow, stop pump 2A-A and notify SRO and SE.
/ l Signature Date 12.9.2 If there is flow, this verifies part stroke of VLV-3-805 and full stroke of VLV-3-814 and part stroke of VLV-3-894 of steps 12.7 and 12.8 are performed. ;
/
Signature Date NOTE: The pump shall be run for a minimum of 5 minutes under conditions as stable as the system permits before taking data.
12.10 After required run time, record the following data:
12.10.1 Inlet test gauge pressure at (PI-3-117) psig
/
Signature Date 12.10.2 Discharge test gauge pressure at (PT-3-122) psig
/
Signature Date Calculate pump differential pressure AP AP = Discharge pressure - Inlet pressure Discharge pressure psig (12.10.2)
Inlet pressure -
psig (12.10.1)
AP = psid
/
Signature Date 1015R/cwm t'
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n SQN ,
SI-130.2 i Page 55 l Revision 17 Unit -) !
Mode 12.0 INSTRUCTIONS FOR PART B - AFW PUMP 2A-A POST-MAINTENANCE (continued)
NOTE: Refer to Appendix B for vibration locations. 4 1
12.10.3 Vibrations: Inboard vertical mils peak to peak I
/
Signature Date Inboard horizontal mils peak to peak
~
. /
Signature Date Range ID Cal Date Cal Due Date 12.10.4 Observe lubricant level: sat __ unsat
/
Signature Date 12.10.4.1 If lubricant level is unsatisfactory notify the SRO.
/
Signature Date 12.10.5 Flowrate on ultrasonic flowmeter gpm )
/
Signature Date 12.11 Change valve alignment for part stroke of VLV-3-895:
12.11.1 OPEN AND LOCK VLV-3-923 I'
/
ist Signature Date l
/
2nd Signature Date ;
CAUTION: Observe flowmeter as valve is closed to prevent dead heading the pump. ;
1 l
1015R/ tis k
,* .N.
l1 SQN SI-130.2 l Page 56 Revision 17 Unit -
Mode l
(continued) 12.0 INSTRUCTIONS FOR PART B - AFW PUMP 2A-A POST-MAINTENA f
12.11.2 UNLOCK and CLOSE VLV-3-927 7
Signature Date If flow is 3 12.11.3 Check flow on ultrasonic flowmeter.
value in step 12.10.5 this verifles VLV-3-895 part strokes, go to step 12.11.4.
Signatuhe Date 12.11.3.1 If flow is less than step 12.10.5, STOP 2A-A ,
pump and notify SRO and SE VLV-3-895 failed l to open and go to step 12.11.4. l j
/
Date l Signature f
12.11.4 OPEN AND LOCK VLV-3-927.
/
lst Signature Date
/
2nd Signature Date
/
12.12 Stop AFW pump 2A-A 1st Signature Date
/
2nd Signature Date 12.13 Return the following switches to AUTO:
/ j 12.13.1 HS-3-156A Ist Signature Date
/
2nd Signature Date 1015R/tls 9
AN* .
. 4kkey ,
- Q 1
SQN I SI-130.2 i Page 57 '
Revision 17 -
Unit Mode i 12.0 INSTRUCTIONS FOR PART 8 - AFW PUMP 2A-A POST-MAINTENANCE *
(continued)I 12.13.2 HS-3-164A /
lst Signature Date
- I
/ I 2nd Signature Date e
12.14 Evaluate data using acceptance criteria in Appendix A:
12.14.1 If data is acceptable, go to step 12.15. i
)
l
/ l Signature Date 12.14.2 If data is unacceptable, notify SRO and SE. l
/
Signature Date 12.15 Remove the following test instruments:
12.15.1 Ultrasonic flowmeter
/
lst Signature Date
/
2nd Signature Date I 12.15.2 Inlet pressure instrument at PI-3-117
/ !
Ist Signature Date ,
/
2nd Signature Date '
12.15.3 Discharge pressure instrument at PT-3-122
/
lst Signature Date
/
2nd Signature Date 1015R/ tis
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- SQN j SI-130.2 Page 58 ;
Revision 17
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Unit Mode 12.0 INSTRUCTIONS FOR PART B - AFW PUMP 2A-A POST-MAINTENANCE (continued) 12.16 Notify SRO test of AFW pump 2A-A is complete.
/
Signature Date 12.17 Reviewing section complete the following:
- 12.17.1 Review the results. (Refer to Appendix A in conjunction with the following.) 1 12.17.1.1 A new reference value or set of values shall f be determined or the previous values reconfirmed.
12.17.1.2 Deviations between previous and new sets of reference values shall be identified and verification that the new values represent acceptable pump performance.
12.17.1.3 If new reference values are acceptable, revise Appendix A.
l 12.17.1.4 If new reference values are unacceptable, i repairs shall be redone and the test rerun.
Deviations and Verifications:
i l
l
/
Mechanical Test Date Engineer 1015R/ tis
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9 SQN SI-130.2 Page 59
{
Revision 17 Unit Mode 13.0 INSTRUCTIONS FOR PART B - MOTOR DRIVEN AFW PUMP 28-8 POST-MAINTENANCE 13.1 Prerequisites: 3.1 / l SRO Signature Date 3.2 / l Signature Date ,
3.3 /
Signature Date '
~
3.4 .- / l Signature Date l
13.2 Verify the following test equipment is installed:
13.2.1 Ultrasonic flowmeter:
/ !
Range ID Cal Date Cal Due Date Signature Date l 1
13.2.2 Inlet pressure instrument at PI-3-127
/ !
Range ID Cal Date Cal Due Date Signature Date 13.2.3 Discharge pressure instrument at PT-3-132 l
/
Range ID Cal Date Cal Due Date Signature Date 13.3 Record AFW pump 2B-B inlet test gauge pressure at (PI-3-127) psig
/
Signature Date 13.3.1 Observe lubricant level for 28-B MDAFW pump.
Sat Unsat
/
Signature Date 13.3.1.1 If level is unsatisfactory notify the SRO.
/
Signature Date 1015R/ tis r ay 4
1 l
. 1 SQN I SI-130.2 Page 60 Revision 17 Unit -
Mode 13.0 INSTRUCTIONS FOR PART B - AFW PUMP 28-8 POST-MAINTENANCE (continued) )
J 13.4 Place the following switches on panel M-4 in Manual and ramp close:
13.4.1 HS-3-148A / !
Signature Date j i
13.4.2 HS-3-171A /
Signature Date
{
13.5 Place the following switch'es on panel M-4 in Manual bypass and ramp close:
)
j 13.5.1 HS-3-148A /
Signature Date j I
13.5.2 HS-3-171A / !
Signature Date i 13.6 Verify the following valves CLOSED:
13.6.1 LCV-3-148 /
Signature Date 13.6.2 LCV-3-148A /
Signature Date 13.6.3 LCV-3-171 /
Signature Date 13.6.4 LCV-3-171A /
Signature Date NOTE: Steps 13.7,13.8, and 13.11 are only required if not performed in Sections 10.0, 11.0, or 12.0. If already performed, N/A these steps.
13.7 Verify VLV-3-927 locked OPEN
/
, 1st Signature Date
/
2nd Signature Date 101SR/ tis 7 w t ';: , ' 5 E - es.a
SQN SI-130.2 4:
Page 61 Revision 17 Unit Mode 13.0 INSTRUCTIONS FOR PART B - AFW PUMP 28-B POST-MAINTENANCE (continued) ,
13.8 UNLOCK and CLOSE VLV-3-923
/
Signature Date CAUTION: Observe flowmeter as pump is started to prevent dead heading the pump.
13.9 Start AFW pump 28-B /
Signature Date 13.9.1 Verify flow on ultrasonic flowmeter. If there is no flow, stop pump 28-8 and notify SRO and SE.
/
Signature Date 13.9.2 If there is flow, this verifles part stroke of VLV-3-806 and full stroke of VLV-3-815, and part stroke of VLV-3-894 if steps 13.7 and 13.8 are performed.
/
Signature Date NOTE: The pump shall be run for a minimum of 5 minutes under !
conditions as stable as the system permits before taking data.
13.10 After required run time, record the following data:
13.10.1 Inlet test gauge pressure at (PI-3-127) psig.
/ i Signature Date l 13.10.2 Discharge test gauge pressure at (PT-3-132) psig
/ l Signature Date r
1015R/ tis e-
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- 4 tA$aing s s .e k l
R 4 SQN 1 SI-130.2 Page 62 Revision 17
~
Unit -
Mode 13.0 INSTRUCTIONS FOR PART B - AFW PUMP 28-8 POST-MAINTENANCE (continued)
Calculate pump differential pressure AP j AP - Discharge pressure - Inlet pressure Discharge pressure psig (13.10.2)
Inlet pressure - psig (13.10.1)
AP = psid Signature Date NOTE: Refer to Appendix B for vibration locations.
13.10.3 Vibrations: Inboard vertical mils peak to peak
/
Signature Date Inboard horizontal mils peak to peak
/
Signature Date i
Range ID Cal Date Cal Due Date 13.10.4 Observe lubricant level: sat unsat
/
Signature Date ;
I 13.10.4.1 If lubricant level is unsatisfactory notify I the SRO. l l
/
Signature Date 13.10.5 Flowrate on ultrasonic flowmeter gpm
/
Signature Dhte 13.11 Change valve alignment for part stroke of VLV-3-895:
1015R/tls
'm'afs4p g-.#. e : gag . ,. . , - ,
9 SQN
- j SI-130.2 ,
Page 63 !
Revision 17 .
k Unit . ,
Mode l j
(continued) i 13.0 INSTRUCTIONS FOR PART B - AFW PUMP 28-8 POST-MAINTENANCE f.+.,-
13.11.1 OPEN AND LOCK VLV-3-923 1st Signature Date
/ ;.
2nd Signature Date 1
~
~~
l CAUTION:
Observe flowmeter as valve is closed to prevent dead heading ... j the pump. k i I
.i 13.11.2 UNLOCK and CLOSE VLV-3-927
- 4 f
Signature Date h. u ..
13.11.3 Check flow on ultrasonic flowmeter. If flow is 3: .; 4 4
value in step 13.10.5 this verifies VLV-3-895 part strokes, go to step 13.11.4. i i
Signature Date 13.11.3.1 If flow is less than step 13.10.5, STOP 2B-B pump and notify SRO and SE VLV-3-895 failed to open and'go to step 13.11.4. .y..
l
/-
Signature Date w
13.11.4 OPEN AND LOCK VLV-3-927.
/ ,
Ist Signature Date
/
2nd Signature Date 13.12 Stop AFH pump 28-B
/
lst Signature Date
/
2nd Signature Date .
~
,1015R/cwm 4
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SQN SI-130.2 Page 64 Revision 17 Unit Mode I
13.0 INSTRUCTIONS FOR PART B - AFH PUMP 28-8 POST-MAINTENANCE (continued) 1 13.13 Return the following switches to AUTO: )
13.13.1 HS-3-148A /
lst Signature Date
/
2nd Signature Date ,
13.13.2 HS-3-171A /
Ist Signature Date .I-
/ l 2nd Signature Date 13.14 Evaluate data using acceptance criteria in Appendix A:
13.14.1 If data is acceptable, go to step 13.15.
/
Signature Date 13.14.2 It' data is unacceptable, notify SRO and SE.
/
.. Signature Date 13.15 Remove the following test instruments. 4 13.15.1 Ultrasonic flowmeter
/
lst Signature Date
/ f 2nd Signature Date 13.15.2 Inlet pressure instrument at PI-3-127 .
/
Ist Signature Date
/
2nd Signature Date I
r 1015R/cwm 1*
- du4 5 d A.. 4 14d. .
I
- t l l
SQN SI-130.2 Page 65 Revision 17 _
Unit Mode 1
13.0 INSTRUCTIONS FOR PART B - AFW PUMP 28-B POST-MAINTENANCE (continued) 13.15.3 Discharge pressure instrument at PT-3-132
/
lst Signature Date
/
2nd Signature Date
~
13.16 Notify SRO test of AFW pump 28-B is complete. ,
i
/
Signature Date 13.17 Reviewing section complete the following:
13.17.1 Review the results. (Refer to Appendix A in confunction with the following.) '
i 13.17.1.1 A new reference value or set of values shall be determined or the previous values reconfirmed.
13.17.1.2 Deviations between previous and new sets of reference values shall be identified and verification that the new values represent acceptable pump performance.
13.17.1.3 If new reference values are acceptable, ,
revise Appendix A.
1 13.17.1.4 If new reference values are unacceptable, repairs shall be redone and the test rerun. }
i Deviations and Verifications:
l l
l
/ j Mechanical Test Engineer Date j
., I 1015R/ tis j_
/\ rm +.k e r w
l
. .' l SQN SI-130.2 !
Page 66 Revision 17 -
Appendix A Page 1 of 4 ACCEPTANCE CRITERIA MOTOR ORIVEN AFH PUMP 1A-A ALLOWABLE RANGES OF INSERVICE TEST QUANTITIES TEST ACCEPTABLE ALERT RANGE' REQUIRED ACTION RANGE * '
QUANTITIES RANGE LOW VALUES HIGH VALUES LOW VALUES HIGH VALUES Pi > 11 psig N/A N/A < 11 psig N/A AP = P.-P i 1486.9 to N/A 1568 to < 1486.9 psid > 1583 psid 1568 psid 1583 psid (4) <4> c4) (4) (4) 9 Inboard Vibration 0 to 1 mil None 1.0 to 1.5 None > 1.5 mils Horizontal mils Inboard i I
Vibration 0 to 1 mil None 1.0 to 1.5 None > 1.5 mils Vertical mils If any value of the test quantities falls in the " Alert Range," notify the Mechanical Test Section. The Mechanical Test Section will'make an evaluation as to which of-the following steps shall be taken:
- a. Have M&S/S double the test frequency.
or
- b. Request that the instruments involved be recalibrated and the test rerun. The test shall be rerun within 45 days.
)
If any value of the test quantities falls in the " Required Action Range," the SE should take the following actions:
- a. Declare the pump inoperable and take the appropriate actions per TS 3.7.1.2.
- b. Notify the Mechanical Test Section as soon as possible to correct the deviation, s c. It is suggested that the instruments involved be recalibrated and ;
the test rerun as soon as possible. l New AP low limits established by EN DES calculations. Ref: j B44 850620 013 dated 6/12/85 and USQD attached to Workplan 11243 R2, i March 7, 1985. There is no low alert range due to this evaluation. ]
This acceptance criteria is more restrictive than existing TS !
criteria. PCVs have been replaced by cavitating venturies which have !
a higher system resistance.
(*'
These values will be established after initial baseline data is collected (see Punchlist).
1015R/bhh M
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.. Y$ 4s 'ac s , m'
'{,. 4 SQN SI-130.2 Page 67 Revision 17 ,
Appendix A Page 2 of 4 ACCEPTANCE CRITERIA MOTOR ORIVEN AFW PUMP 1B-B ALLOWABLE RANGES OF INSERVICE TEST QUANTITIES TEST ACCEPTABLE ' ALERT RANGE' . . REQUIRED ACTION RANGE
- QUANTITIES RANGE LOW VALUES HIGH VALUES LON VALUES HIGH VALUES Pi > 11 psig N/A N/A < 11 psig N/A AP-Po-P i 1503.5( to N/A 1589 to < 1503.5 psid(*) > 1604 psid -,
1589 psid 1604 psid (4) (4) (4) (4) (4) g Inboard ;
Vibration 0 to 1 mil None 1.0 to 1.5 None > 1.5 mils i' Horizontal mils Inboard Vibration 0 to 1 mil None 1.0 to l'.5 None > 1.5 mils Vertical mils ;
(')
If any value of the test quantities falls in the " Alert Range," notify i the Mechanical Test Section. The Mechanical Test Section will make an evaluation as to which of the following steps shall be taken:
- a. Have M&S/S double the test frequency. l or
- b. Request that the instruments involved be recalibrated and the test-rerun. The test shall be rerun within 45 days.
(2)
If any value of the test quantities falls in the " Required Action Range," the SE should take the following actions:
- a. Declare the pump inoperable and take the appropriate actions per TS 3.7.1.2.
- b. Notify the Mechanical Test Section as soon as possible to correct the deviation.
- c. It is suggested that the instruments involved be recalibrated and the test rerun as soon as possible.
New AP low limits established by EN DES calculations. Ref:
844 850620 013 dated 6/12/85 and USQD attached to Workplan 11243 R2, March 7, 1985. There is no low alert range due to this evaluation.
This acceptance criteria is more restrictive than existing TS '
criteria. PCVs have been replaced by cavitating venturies which have a higher system resistance.
(*)
These values will be established after initial baseline data is collected (see Punchlist).
1015R/bhh H I
- 'h%. . . I h'. Magggh 4 '
1 J
,,. ... 1 SQN SI-130.2 i Page 68 Revision 17 ,
Appendix A Page 3 of 4 ACCEPTANCE CRITERIA MOTOR ORIVEN AFW PUMP 2A-A ALLOWABLE RANGES OF INSERVICE TEST QUANTITIE',
2 TEST ACCEPTABLE ALERT RANGE' REQUIRED ACTION RANGE QUANTITIES RANGE LOW VALUES HIGH VALUES LOW VALUES HIGH VALUES j Pi > 11 psig N/A N/A < 11 psig N/A AP P.-P i 1478.3"' to N/A 1578.5 to <1478.3(') psid > 1594.0 psid a 1578.5 psid 1594<0 psid g (4> c4> (4) c4> (4)
Inboard I Vibration 0 to 1 mil None 1.0 to 1.5 None > 1.5 mils Horizontal mils Inboard )
Vibration 0 to 1 mil None 1.0 to 1.5 None > 1.5 mils j Vertical mils !
If any value of the test quantities falls in the " Alert Range," notify the Mechanical Test Section. The Mechanical Test Section will make an !
evaluation as to which of the following steps shall be taken: )
- a. Have M&S/S double the test frequency. j or
. b. Request that the instruments involved be recalibrated and the test
"* rerun. The test shall be rerun within 45 days.
If any value of the test quantities falls in the " Required Action Range," the SE should take the following actions:
- a. Declare the pump inoperable and take the appropriate actions per TS 3.7.1.2. .
- b. Notify the Mechanical Test Section as soon as possible to correct the deviation.
s c. It is suggested that the instruments involved be recalibrated and I
")
the test rerun as soon as possible. l New oP low limits established by EN DES calculations. Ref:
844 850620 013 dated 6/12/85 and USQD attached to Horkplan 11243 R2, March 7, 1985. There is no low alert range due to this evaluation.
This acceptance criteria is more restrictive than existing TS criteria. PCVs have been replaced by cavitating venturies which have a higher system resistance.
(*'
These values will be established after initial baseline data is collected (see Punchlist).
r 1015R/bbh
- _g.; f' . .hk O , gi y .
a.h u' si
o SON SI-130.2 Page 69 .
Revision 17 -
Appendix A Page 4 of 4 ACCEPTANCE CRITERIA MOTOR DRIVEN AFW PUMP 28-8 ALLOWABLE RANGES OF INSERVICE TEST QUANTITIES 2
TEST ACCEPTABLE ALERT RANGE' REQUIRED ACTION RANGE QUANTITIES RANGE LOW VALUES HIGH VALUES LOW VALUES HIGH VALUES Pi > 11 psig N/A N/A < 11 psig N/A AP=P -P i 1487.2 to N/A 1565.4 to < 1487.2(') psid > 1580.7 psid 1565.4 psig , 1580.7 psid (4) (4) (4) (4) (4) g Inboard Vibration 0 to 1 mil None 1.0 to 1.5 None > 1.5 mils Horizontal mils Inboard Vibration 0 to 1 mil None 1.0 to 1.5 None > 1.5 mils Vertical mils
If any value of the test quantitles falls in the " Alert Range," notify j the Mechanical Test Section. The Mechanical Test Section will make an '
evaluation as to which of the following steps shall be taken: l
- a. Have M&S/S double the test frequency. , j or -
I
- b. Request that the instruments involved be recalibrated and the test rerun. The test shall be rerun within 45 days, e
(*' If any value of the test quantities falls in the " Required Action Range," the SE should take the following actions: !
- a. Declare the pump inoperable and take the aporopriate actions per l TS 3.7.1.2.
- b. Notify the Mechanical Test Section as soon as possible to correct the deviation.
- c. It is suggested that the instruments involved be recalibrated and the test rerun as soon as possible.
New AP low limits established by EN DES calculations. Ref:
B44 850620 013 dated 6/12/85 and USQD attached to Workplan 11243 R2, March 7, 1985. There is no low alert range due to this evaluation.
This acceptance criteria is more restrictive than existing TS criteria. PCVs have been replaced by cavitating venturies which have a higher system resistance.
(*'
These values will be established after initial baseline data is collected (see Punchlist).
1015R/bhh N' ,
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SQN SI-130.2 Page 70 Revision 17 _
Appendtx B Page 1 of 1 VIBRATION TESTING LOCATIONS MDAFWP 9t@
co'"ht#
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1 1
ENCLOSURE 3 Unreviewed Safety Question Determination for Initial Postmodification Testing 1
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1
TVA 10551 (EN DES 3 81)
UNREVIEWED SAFETY QUEST!ON_DFTERMINATION s J .; O SHEET 01 To: ,. - -w Nucte r Plant, DoiSYi IN {[. "h $& Il07 .Il-[ Q R. y 1/i
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a" F1 6 S N P, s 'oENn lea u,p .mou.
- MEDS ACCESSION NO.
PREPARED REVIEWED APPROVED TE DPM e pp pD p ,.
12 a
$e .I n 1%64,/ ryM..iPonh4hJ5/ahs 325 ,85 0973 509 x) s I w, lksen'! zwfJ, Lkw j'
$4s sn 3
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+ 6 1 51 yl \ l, l ,f l 'R -
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- R0 =ltitTI AL ISSUE onCute: _50A gh AF#EETED UNIT (S) -
yg 7 gg ECN NO. EC.7 CATE FC RlNC HI -
k MC R /DC R NO. DATE '
SPECIAL REQUIREMENT (S) l OTHER f M Ill O DATE POTENTIAL TECH SPEC CH ANGE ERENCES: bM EbO 2. Cha0bs D k $. Ski use \ f(. k Mkm (R om Lt.h& b Aeb fik .' AM,n,A 1. wad" buss;,ns ',aA AL bb l htPd' k emh 1 bJ, L Idar. PO , h Lk LM . % >&Xi ( @ c6N M n % dT. b '
bmiN(kEd I hM E6M ' ' '
h DESCRIPTION OF CHANGE !l's Ill AEN F4 D Q ATffl b $T&d m
% DctAA )((k O oA 4 C rcha_t ,
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' - d' d,i 0 94459en S - Inte.f pdt vonb d an 'mlepokM nrddien id(mea h Ne>b ed em ,subb wb.1 W cee% a< J!bd LA uA AAAn.
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. Unreviewed hafety Question: *
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s '1.15 the probability of occurrence or the consecuences of an an.cident or malfunction of ecuipment important to safety previously evaluated in
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- 2. 15 the possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report created? . . . .. . .. .. Yes No Justification: h14e b& C t1 e) so e rif 9Ya $bn . n b SSt > f an
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T)ESCRIPTION OF CHANGE:
A t'X I t ". A RY - EED'vA TJ?. SY ST_"Jf }' M N Following. installation of the cavitating venturis downstream of the motor-M Nh Ilk 227 driven auxiliary feedwater pumps (MDAFP), reference ECN L5842. TVA began k.) performing Postmodification Test-53 to verify that the installation of the .
venturis would not degrade the MDAFP ability to provide the required flow rate to the steam generator. Based on results obtained during low pressure testing of the system, it was concluded that MDAFP "A" may not be capable of developing the required 440 gpm flow rate at a pressure of 1,
1100 psia to the steam generator as required by the PMT. This USQD vas -
written to address an assumed 400 gpm flow rate (40 gpm reduction) from
~
MDAFP "A. " Because the PMI had not been completed at the time the USQD
, was prepared, a 40 gpm reduction was assumed for purposes of the evaluation. After the USQD (RO) was issued and the PMT completed, the flow rate from MDAFP "A" was, determined to be approximately 430 gpm at 1100 psia.
l 1 The AFW pu=p design point of 440 gpm at 1100 psia steam generator pressure meets the design parameter identified in the tech .ical (
specification (i.e., 440 gym at steam generator presures less than 1133 psia). The Westinghouse basis documented in TVA calculation (MEB 830527 301) pages 6 and 7 and shown in the FSAR, page 10.4-33, is that 440 gpm is acceptable at steam generator pressures less than 1133 psia if it can be shown that the steam generator safety valves can ;
relieve at least 11 percent nominal main steam flow at that pressure. '
This has been shown for a steam generator pressure of 1100 psia in the above referenced calculations.
SQEP - Sep. 9,1985 JW506 5.03 ,. 11243
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' '. SAFETY EVALUATION: ' W U:
i
, ()'AQ okfk IM.h D f This evaluatiion will address the safety implications of an assumed flow )
l
$ rate of- 400 gpm (40 gpm reduction) at a pressure of 1100 psia from MDAFP "A." All other design parameters associated with the AFW system are vali'd. -
- q. The plant conditions that impose safety-related performance requirements on the auxiliary feedvater system are defined on page 10.4-32 of the FSAR.
. These are:
i (a) Loss of Main Feedwater Transient -t
- Loss of main feedwater with offsite power available
- Station blackout (i.e., loss of main feedwater without offsite power available)
- . (b) Secondary System Pipe Ruptures
- Feedline rupture
, - Steamline rupture (c) Loss of all Alternating Current Power (only for diverse power source consideration)
(d) Loss-of-Coolant Accident (LOCA)
- k. .
(e) Cooldown Thetransientslistedabovevillbeinvestigatedtodetegineifthe reduced flow will result in the AFW system being unable to provide sufficient feedwater flow over the required pressure ranges when assuming the worst single failure.
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WF' 1.: Loss of Main Feedvater Without Stat,ic- i;nckeet "' -
- ,; . MD O The postulated initiating event for this transient does not result in the loss of any auxiliary feedwater pumps. The FSAR analysis presented in Chapter 15 conservatively assumed only one MDAFP would be available
- one minute after the accident (reference FSAR page 15.2-31) and analyzed the transient assuming a flow rate of 440 gpm. With this flow rate the results were acceptable.
The SQN auxiliary feedwater design is such that the system complies to _
single failure criteria (reference FSAR page 10'.4-31). Therefore, if the single f ailure criteria were applied during this transient, two auxiliary feedwater pumps would be available providing at least 840 gpm with the reduced flow rate (reference FSAR Table 10.4.7-9) . This would be an acceptable flow rate.
In summary, the AFW System will provide adequate flow for this
%): transient assuming single f ailure criteria.
- 2. Loss of Main Feedwater with Station Blackout
~
As stated in the Westinghouse letter (Attachment 1), a station blackout results in the trip of the reactor coolant pumps. This is i
approximately 12 MWT of pu=p heat not being put into the reactor l coolant system. This 12 MWT is equivalent to 48 gpm of auxiliary feedwater flow. This is sufficient to bound the reduced flow rate
' (i.e. , 440-48 = 3 92 spm 4 400 gpm). In additien, single failure criteria as justified in No. I above is applicable to this transient.
Therefore, if the single fcilure criteria were applied during this 1
trans ient , two auxiliary feedwater pumps would be available providing I at least 840 gpm. %9 N -
"'.A. C f
- O 3 ? & O S In summary, this transient is not affected by the reduction in flow.
SQEP - Sep. 9,1985 JW5065.03 -
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- 3. Feedline Rupture
. g g M Y. h M ) D The postulated initiating event for this transient does not result in
-g the loss of any auxiliary feedwater pumps. The FSAR analysis presented in Chapter 15 assumes no flow until 10 minutes after the break. At '
that ti=e it is assumed the operator has isolated the AFW system from the break and a =inimum flow of 440 gpm to the two intact steam generators, co==ences. At this flow rate the results were acceptable.
l The SQN auxiliary feedwater design is such that the system complies -
4 to single failure criteria. Therefore, if the analysis is performed
_ assuming a single f ailure of the MDAFP not affected by the break, two pumps would be available. One of these pumps would be the TDAFP which would deliver 880 gpm within 10 minutes af ter the trip. This is an acceptable flow rate. The availability of two pumps is documented in the attached memorandum (Attach =ent 2) and FSAR Table 10.4.7-9.
If the analysis were performed assuming the single active failure as the TDAFP, two MDAFPs would be available providing 840 gpm within _
ten minutes after the trip. (The 10 minute assumption is based on the operator isolating the AFW system from the break.) This is an ;
acceptable flow rate. As an additional conservatism, auxiliary feedwater to the two intact steam generators would automatically initiate in one minute (ref erence FSAR p.10.4-40) vs. the ten minute assumption. The attached Westinghouse letter (Attachment 1) indicates the FSAR analysis is conservative with respect to this scenario.
In sum =ary, the AFW system vill provide adequate flow for this transient assuming single failure criteria.
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' d. j '2H C?hN SQEP - Sep. 9,1985 JW5065.03
- 4. Steamline Rupturg Ncci *:' Ye W %L iM5 f.)
The postulated initiating event, when its location is selectively chosen, can result in the loss of TDAFP. Such a scenario is 3 ,
discussed below. Other locations for the initiating event were-
- identified which would result in the loss of a TDAFF; it was concluded, however, that these locations would be bounded by the scenario discussed below.
Steseline Rupture - Steam Supply Line to the Turbine-Driven Auxiliarv ,.
^
Feedwater Pump Downstream of FCV 1-15 or 1-16 ..
The postulated initiating event for this transient would be a break in the steam supply line to the TDAFP at a location common to the primary and backup steam source. The TDAFP is lost as a result of the break.
If a MDAFP failure is postulated as the single active failure, then only one MDAFP is operable.
NL Assu=e MDAFP "A" is the . single active failure. The TDAFP steam supply logic automatically isolates steam generator 1 from the break and- .
switches to steam generator 4. The isolation is initiated by TDAFP pressure not exceeding 100 psia within one minute of a start signal to the TDAFP due to the line break upstream of the TDAFP. The MDAFP "B" is feeding depressurizing steam generator 4. This continues until 10-minute operator action isolates steam generator 4 from the break.
MDAFP "B" then provides the required 440 gpm to the two intact steam generators. l i 1
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wt 1 Assume MDAFP "B" is the single active failure. . -
s" whic.n f eeds I Qbef) k steam generators 1 and 2 vill feed two unfaulted steam generators within one minute since TDAFP steam supply logic automatically isolates
'N
(~ steam generator I from the break. The 400 gpm flow rate initiating -one ,
minute into the event vould result in an equivalent total flow to the steam generators for the first 100 minutes of the transient.
Westinghouse has indicated that this is an acceptable assumption.
After 100 minutes, heat in the reactor coolant system has reduced to a level that 400 gpm would be capable of removing decay heat. (Reference
,B OE calculation TI-ANL-186 (B45 850405 235) .}
In summary, this transient is not affected by the reduction in fluid.
- 5. Loss-of-Coolant Accident The reduced auxiliary feedvater flow does not cause the large or small break LOCA analysis results to be unacceptable. The LOCA accidents do o
(,', ' not impose additional flow requirements on the auxiliary feedwater system (ref erence Westinghouse letter, Attachment 1) .. _
l
- 6. Loss of All AC Power For this transient, only the TDAFP is assumed available. The MDAFPs are inoperable as a result of a less of all AC power (nor=al and emergency). Ther ef ore , this transient is not applicable to a degraded )
MDAFP condition.
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' This operation defines the basis for tankage size while the minimum and maximum flow requirements are established from the previously discussed k]. transients (FSAR page 10.4-41). Therefore, this transient is not applicable to the degraded MDAFP.
Independent Evaluation by Westinghouse i
Reference a letter from E. A. Novotnak to J. A. Raulston dated May 6,
~
l.985-(345 850508 612). i TVA requested that Westinghouse perform a sensitivity analysis for the-Loss of Normal Feedvater and Feedline Break events assuming an auxiliary feedflow of 413 gpm (total flow) to two intact steam generators. The Westinghouse analysis was performed utilizing design basis and codes used for the Sequoyah FSAR.
[ For the Loss of Normal Feedvater, the 413 gpm AFW flow resulted in a more li=iting transient than the 440 gpm, but had a very small ,_
M sensitivity on the system parameters. The calculated point where the AFW heat removal capability catches the USSS heat generation rate'are virtually indistinguishable. The RCS pressure and subcooling margin are essentially unchanged. The pressurizer water volume reached during the'heatup portion of the transient is only a few cubic feet greater I
than the FSAR analysis. This sensitivity indicates that the FSAR conclusion vould not be cffected by the degraded AFW flow rate.
For the Feedline Break, the.413 gpm AFW flow is assumed to initiate one
' 'j (Justification for this assumption is disecused minute into the event.
N above'in item 3, "Feedline Repgure.") The earlier initiation of the ATW i~7 1/ 7:P 1993 _
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flow results in significantly better heat sink charactu istics i
throughout the transient-this results in a less severe transient than presented in the FSAR. .
1 Westinghouse has concluded that based on sensitivities performed with the design basis codes of the actual configuration of the plant, the b reduced flow, 413 gpm, represents no significant impact on the conclusions of the SQN FSAR Chapter 15 Feedline Break and Loss of Normal Feedwater analysis. The Feedline Break analysis is bounded by the FSAR,' -
and the Loss of Normal Feedvater is only slightly more limiting than the
~
FSAR analysis. For both accidents, the conclusions provided in the FSAR
, remain valid.
Conclusion:
The TVA safety evaluation and the independent evaluation by Westinghouse has shown that the AFW system can perform its intended design function with p.)
l an assumed flow rate of 400 gpm (413 gpm Westinghouse evaluation) from MDAFP "A". This conclusion is based on assumptions which are within the requirements of single failure criteria and the operating parameter of the system. l i
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1 SQEP - Sep. 10, 1985
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Response to Question No. 3, pare 2 l
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(' Technical Specification basis 3/4.7.1.2, " Auxiliary Feedwater System" ' .
states that, "The _ operability of the auxiliary feedwater system ensures 1 l
that the reactor coolant system can be cooled down to less than 350 F from nomal operating operating conditions in the event of a total loss of offsite power." This is further stated on FSAR page 10.4-33, "The station blackout transient serves as the basis for the minimum flow required for , f the smallest capacity single auxiliary feedwater pump." The safety evaluation has shown that the operability of the auxiliary feedwater system !
can be ensured with the reduced flow rate. The design parameter presented in the basis of the technical specification "440 gpm (initiated 10 minutes into the event) at pressures less than 1133 psia," is a flow rate that vill satisfy the above stated basis. The basis for the 440 gpm requirement is
_ that the safety valve must release 11 percent of the total steam flow at that pressure. The 440 gpm at 1133 psia flow was conservatively chosen.
The actual set point of the first safety valve is at a nominal pres'sure of 1079 psia, and the capacity of the first safety valve is more than 11 i R3 l percent. Test data indicates that MDAFP "A" will probably provide approximate,9 440 gpm at 1079 psia (413 gpm at 1133 psia, 430 gpm at 1100 psia). This is sufficient capacity to cool the reactor coolant system to 350 F as required by the technical specification. Since the Station Blackout transient produces the highest pressure that the ATP =ust operate, the ATP will operate saticf acterily for the other transients. The 440 gpm flow rate is by no means ther only design parameter flow rate that will
~ . .d satisfy the above stated basis. The saf ety evaluation has documented that a ULt l
400 gpm ficw rate initiated minute into the event is a valid design parameter that will satisfy his basis. Therefore, the margin of safety of C) o' the ATW system has not been degraded. Q2.t{ } -
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. >heet $4 Precauh.on: usqp Mk Ltiv4 O
- While not a safety hazard, OE recommends that NUC PR should take action to identify and correct the cause of the reduction in system flow in a timely '
manner.
'Should the cause of the system flow reduction not be identified and corrected, NUC PR shall ensure that FSAR revisions are incorporated to reflect the assumption that two pumps would be available following the
" Loss of Feedvater" and " Station Blackout" transients'and to discuss the mainsteam line break at the turbine driven auxiliary feedvater pump common steam supply line transient. (This was coordinated with M. R. Harding on January 29, 1985.)
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'sneel 1[ ik bG Me4I b Nothpla ll24) R
Subject:
Auxiliary Feedwater System Minimum Performance Fecuirements for aofaI N
k .
In response to your rec;uest, Westinghouse has reviewed the Scouoyah FSAR accident analysis to determine if a potential degragation of 40 gpm in the design flow of one motor driven auxiliary feedwater pump wculd be acceptable. A summary of the results and conclusions of the Westinghouse review for the limiting design basis accidents is attached. If we can be of any further assistance, please advise. -
~
- k. f.>. 3chlonski, engineer Reactor Coolant & Steam Generator Support Systems M'lC 4-35 )
k.
WN EX D. S. Love, Engineer Nuclear Safety Operatir.3 FICnt Analysis MNC 4-09 V.4k k h d (
APPR0"ED, M. P. Osborne, Manager j
Plant Transient Analysis l
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Steam Gen,2 rater Tube Purture
%W An evaluation for the Steam Generator Tube Rupture event indicates t the (5 degraded on ficw of the motor driven p=p would result in a negligible impact this analysis. .
Lors of Nem al Feeawater The Sequoyah FSAR assumes that "Only one meter driven auxiliary feedseter p=p is available cne minute after trip. " Mcwever, as indicated in the AW design basis report, 440 Spa is assumed as a nowrate for this analysis and two p=ps would be available even with a single failure in the AW system.
With two p=ps available and the degradation of the one motor driven p=p, this would ensure a total ficw of ricre than 800 gpm to four steam generators. Since one motor driven p=p is capable of providing sufficient -
ncurate for this analysis, this provides the argument of an increased reliability of the AFd system . The analysis in the FSAR would still bound ;
the actual conditions of the plant when a single failure is included.
Lerr Of Off-Site Power to the Statien Auri1daries (Statten Blackcut).
The analysis of the Station Blackout event is similar to the L'oss of Nomal Feedsater analysis. One majer difference is that the Reactor Coolant Pmps
~
are assumed to trip as a result of the transient. As a result, the removal cf residual heat (cere decay heat) is maintained by natural circulation. '
Hcuever, the AFd design basis report indicates that this event relies upon the capacity of a single AFJ pump for the Sequoyah Nuclear Plant. Since l
C3 the capacity cf the degraded AFd pump is less than the 440 gpn ass =ed to I be available for this analysis, the BAR analysis, as is, does not beund the actual conditions of the plant.
Tne difference between the Station Blackout analysis and the Loss of Nomal Feedaater analys1: justifies that margin is available to offset the Ocw shortccming of the degraded AFd p=p. The Reactor Coolant P=p trip in the Station Blackout analysis reduces the arount of p=p heat which is transferred to the reactor coolant systcm. This pump heat (nominally ass =ed to be ~12 Nt for Sequoyah) is c-quivalent to approximately 48 spii' of AFd Gcu. Since censervative ass =ptiens are made cn the m.ount'of pump heat transferred to the reactor coolant in the Loss of Nc=al Feedaater transient, the benefit which would be availcble for the Station Blackout analysis would mere than ccmpencate for the ficw thcrtecting.
Feed 1 ! re = r@
Tne BAR Feedline Break analysis asc=es no !Fd fica is delivered to the intact steam generator: until cperater acticn is taken after 10 minutes to isolate the ficw to the faulted steam cenerator. Once the operater action is taken, 440 spn is at:=ed ' b be delivered to intact steam generaters.
~~ I
'fso primary scenarios exist for pingle failures in the AW system:
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- 1. A single failure cf the n:otor_ dr; f. V g b . APd pump Which supp) lits .two A- intact steam generators - With this failure, all the fled fremlthe - i remaining mcter driven AFW punp and the turbine driven AFW pump is lost as a con:cquence of the feedline break until operater acticn occur:. Follcuir.g operator acticn, the turbine driven pump would
- j deliver in exce:s of the 440 g;m assta:ed in the analysis to the remaining intact steem generators. Therefore, the FSAR provides a i bouncing analysis fer this single failure. I
. 2. A single failure of the turbir.e driven AFJ pump 'dith this failure, ene motor driven pump flcw is Ics as a conseciuence of the )
break. Tne retaining AF4 pump provides fles to two intact steam generators within one minute. If this retaining pump is the degraded _.
pump, 400 gpm 'ficw is provided for the renninder of the transient.
Although the 400 gpm is less ,than the 440 gpm ficwrote assured in the FSAR analysis, the 400 gpm is initiated nine minutes earlier. The i earlier initiation of AFW ficw, without any cperator action relied upon, results in more total ncw than is provided in the FSAR for ever 90 minutes into the transient. Operator acticn to isolate the firs;
., motor driven pump frem the break would result in additicnal Gew being provided to the int,act steam generators.
- 7. ,
A -
Em Of Crol "-t AcWent .
Tne impact of a recueed auxiliary feccaater f1cw rate en calculat'ed'ECCS perfcrmance of the Sequoyah Units has been evaluated. There is no impact en l the existing large break LCCA analysis because the ' auxiliary feedsater systen is not modeled in that analysis. Tne Sequoyah mtall' break LOCA analysis is somedhat affected by the reducticn in auxiliary feedaater ficw rate.
Previcus cafety evaluation checklists have acccmodated operaticn of the Sec.coyah Units with a chcrtfall in p= ped cafety irjecticn. As a recttlt cf there checklirts, the effective peak c clad tc rerature (?CT) hat in:reased fr:m the FS/J.-reported value cf 14E5 f to a value ppreaching ~7Cv : . .ne :ur*her impact cf reducirx, auxiliarv feecsa .ci ficw n11 te . 011. Safety irdccti:r water delivered by the upptr he:d injectica (UHI) system causes the cere to i remain ecvercJ fcr nn extended period cf time in Seaucyah ::11 break'LCCA ,
cases. Tr.f :tet.m generatcrs have therefere beceme a heat source rather ther a !
heat sink at. the time of c:re uncovery. The impact of a 100 recu:e: auxil ia ry feedaster ficw rate . upon the core une:.very trar.sient :nd the rer'.itir.g TC-.1>
censequently miner fcr Scqu3an.
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UNITED STATES COVERNMENT 3 Memorandum Tzwxzssez vAttzy AuPa'o'nirr 1 MEB '85 0 2 27 015 ')
4 To : Mechanical Engineering Branch Files rnoM :L,. C. Smith, Hechanical Engineer, V7A34 C-K DATE : FEB 2 l 1985 SUtuECT:SEQUOYAH NUCLEAR PLANT - AFV BASIS FOR FSAR TAELE 10.4.7-9 The purpose of this memorandum is to document the-basis for the existing note (3) of Table 10.4.7-9, which reads as follows: 4
"(3) Ten minute operator action is required to isolate AFW flow to faulted loop. Prior to operator action, flow is q cpproximately 200'gpm to unfaulted loops; after operator act'io'n, flow is>440 gpm to unfaulted loops." a i
The basis for the > 440 gal / min flovrate in this note is that at least >
j two AW pumps will be operable for all cases to which the note applies J
except for the following specific main steam line break case. If it is assumed that a break occurs in the steam supply line to the ATV turbine-driven pump (TDP) at a location common to the primary and backup steam source,
($ then the TDP is lost at a result of the break. If a
% motor-driven pump (MDP) failure or electric train failure is postulated as the single active failure, then only one MDP remains operable and capable of fulfilling the AFW design function. Thus, only slightly greater than 440 gal / min (greater by the design margin of the pump) would be available for this scenario after ten-minute operator action.
(Note: For the worst case in which 440 gal / min is not available until after ten-minute operator action, it is assumed the train A MDP is the single active failure; thus, when the TDP stec:n supply logic automatically isolates steam from the primary cource, steam generator 1, and switches to the steam generator 4 secondary supply, the train B MDP, which feeds steam generator's 3 and 4, is feeding depressurizing steam generator 4.
This continues until ten-minute operator action isolates steam generater 4 frem the brenh. If, however, the came break is asou=ed but the train B MDP ;
is taken as the single active failure, the train A ISP, which feeds steam generator's 1 and 2 vill be feeding two unfaulted steam generatoro within one minute since the ~DP steam cupply logic automatically isolateo steam generator 1 from the break.) For all other. cases in the subject table, at least two AFW pu=ps vill be operable af ter ten =inutes.
The "tvo pu=ps operable" bacis for this note in the case of a main steam line break is documented in anianalysis (!EB B00408161), which assu=es that the turbine-driven pump dild one motor-driven pu:np are feeding a faulted steam generator simulqancpuoly. This analysis performs a flow balance which determines that k ere operator action is taken, a minimum of 200 gal /minisavailabletothe0%faultedsteemgenerator.
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SEQUOYAH NUCLEAR PLANT - AFW BASIS FOR FSAR TABI.E 10.4.7-9 The 200 gal / min minimum determined in the main steam line break analysis is ;
applicable to the feedline rupture case as well, since a depressurized steam generator has an identical effect on the AFW system whatever the cause of the steam generator's depressurization. Thus, the above carenistion provides documentation for the feedline rupture case that the
~
same ansumptions apply (that is, that the turbine-driven pump and one
~ motor-driven pump are available and feeding the break until it is isolated by operator action ten minutes into the event). After ten minutes the entire rated output of the two pu=ps is assumed to go to the unfauIted steam generator (880 gal / min + 440 gal / min = 1,320 gal / min). ,
2 e LA L. C. Smith l- LCS:SDW f
g'd cc: C. A. Chandley, W7C126 C-K g ,'
g H. R.,Corbett, W7D224 C-K J. C. Key, All Sequoyah ENG b CAC:SDW g ec: MEDS, SL26 C-K' L J. J. Vineyard, A8 Sequoyah Ehr, ]
Principally Prepared By: L. C. Smith, Extension 2386 C85053.03 l
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ENCLOSURE 4 Safety Evaluation for Restart Testing
Standard Practice Attachment 1 Page 7 Unreviewed Safety Question Determination SQA119 Revision 6 A. Change Description Post Maintenance Test, WP12195, Revision 0, " Auxiliary -
Feedwater System Ontimized Cavitating Venturi on MDAFW 2A-A Pump." This test consists of three parts which are discussed separately. See attached caces.
B. Check block (s) below to describe what is being evaluated. i System, component, or structure being changed is described in the FSAR 1
PORC reviewed procedure (including temporary changes) x Special test or experiment X Special activity, abnormal configuration, etc., which is deemed to ^
need a USQD C. Is the probability of an occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report increased? YES NO X Explanation: . Refer to attachment. Technical Specifications 3.7.1.2 and 3.3.3.7 allow conduct of this test without increasing the probability or consequences of n n re vi nn e: 1 v evaluated accident.
D.
Is the possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report created?
iTS NO X Explanation: Refer to attached pages. The possibility of a different type of accident._is not created, since the AFW terry turbine and the Irain b motor-driven AFW pump are operable.
~
E.
Is the margin of safety as defined in the basis of any technical specification reduced? I iTS 'NO X 1 Explanation: The AFW terry turbine and MDAFW 2B-B pump will be operable, with their associated flow monitors, to ensure the ability to cool the RCS f i
to 350'F. Further margin is provided due to the low decay heat load.
W ors /2-29-86 Jti.S (60 Yl4 C/J$ l-20-87 (P'repareY)' SQha'ture/Da.te//Section
- S.,E. For Non CSSE .ocuments/Date l
M D 910g PORC Review Date 4NOEf?%-
Plant Manager /Date l s,
- Note: PORC and Plant Manager signature may be waived if change is to-non-CSSC equipment, however SE must sign in space provided - otherwise N/A.
wp /2.195' PAGE #~I OF w e -
'~
UNREVIEWED SAFETY QUESTION DETERMINATION g MOTOR-DRIVEN AUXILIARY FEEDWATER (AFW) PUMP 2A-A TEST w l This USOD is to consider the effects of performing a post maintenance test on the AFW system. The objective of this test is to obtain data for analyzing the results of replacing the venturi on the MDAFW 2A-A pump with an
" optimized" venturi. This maintenance activity of replacing the venturi was performed under MR A-522793 and was an effort by ONP to restore the train 2A-A flow rate to the steam generators (S/Gs) to a value above 440 gpm at a S/G pressure of 1085 psig. The original post modification test on the venturi revealed a flow rate below the required 440 gpm. The USQD (Rev. 4) for ECN L5842 and the USQD (Rev. 3) for Workplan (WP) 11243 (Post Modification Test PMT-53, Unit 2) document the acceptability of a delivered flow rate of greater than or equal to 400 gpm at a S/G pressure of 1085 psig. This low I flow condition (prior to installing the optimized venturi) was acceptable from a safety standpoint, but undesirable from a plant performance standpoint.
1 Specific items considered in this evaluation are the following:
- l. Temporary connections to plant cafety-related control instrumentation on the AFW system.
- 2. Effects of the test on plant systems (i.e., S/G levels, feedwater controls).
The AFW system serves as a backup system for supplying feedwater to the secondary side of the S/Gs at times when the feedwater system is not available, thereby maintaining the heat sink capabilities of the S/G. As an Engineered Safeguards System, the AFW system is directly relied upon to prevent core damage and system overpressurization in the event of transients such as loss of normal feedwater or a secondary system pipe rupture. It will j supply sufficient feedwater to prevent the release of primary coolant through the pressurizer safety valves and the uncovering of the core. It has adequate capacity to maintain the reactor at hot standby and then cool the reactor coolant system (RCS) to the temperature at which the residual heat removal (RiiR) system may be placed in operation, but it cannot supply suf ficient feedwater for power generation.
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Part I q The first part of this test will be performed in mode 5 (AFW not required "
operable) and will test the MDAFW 2A-A pump to verify:
- 1. The venturi prevents pump runout (i.e., flow must be less than 650 gpm to the S/Gs).
- 2. Acceptable vibration levels in affected AFW piping. !
- 3. The motor is not overloaded (motor current must be less than 40 amps).
The test results will be evaluated following this part to determine pump operability prior to entry into mode 3. Before declaring the pump operable, it will be shown that the three items above are acceptable and that SI-130.2 has been run in the past quarter for MDAFP 2A-A. The " optimized" cavitating venturi modification has no chance of decreasing AFW flow rate. Therefore, there exists a high level of confidence that the pump will continue to deliver greater than the minimum required 400 gpm to the S/Gs at a S/G pressure of 1085 psig. ]
The instruction (including any changes submitted) will be evaluated to ensure that all temporary conditions existing during this part that affects )
OPERABILITY of the pumps (LCO 3.7.1.2) or post-accident monitoring instrumentation (LCO 3.3.3.7) are removed prior to mode 3.
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Part 2 Tug LV a.s r%Ms l The second part of this test is performed in mode 3 with approximately Zoe m 385 psig S/G pressure (LCV switchover point) and will test the MDAFW 2A-A pump to verify 400 gpm can be delivered through the bypass LCVs. If th; AFU. Q'lf g ,
9 %)
j terry turbin:
ha; not b;;nthetested 'SI 130.1' in pthe I kw m.4% !
jg.8 1 relled prics t; declaring actor-driven 2A-A as 1;;t 02 days, inoperable to it nutt-be/ 3 f" .
edequately cn;ur; two ATU ps;s er; operab-It. Qction Statements 3.7.1.2.a 3" Y *i and 3.3.3.7.b will be entered during this part, and their time limitations ,~4 ;;
complied with. These action statements will be entered when the test . _a ;
equipment is connected to CSSC plant equipment and the ERCW supply to the Q _;
AFW pump is made inoperable. ,
Part 3 10 The last part of this test is performed in mode 3 with approximately 1,005 psig S/G pressure and will test the response time to full flow (460 gpm).
This test will start the pump manually; therefore, the required response time of 60 seconds from the blackout signal will be reduced to account for applicable delays (logic actuation, diecel generator start, load sequence).
If the AFW terry turbine has not been tested in the last 92 days, it must be tested in accordance with S.R. 4.7.1.2.a.2 (SI-130.1) prior to declaring the AFW motor-driven 2A-A pump inoperable. Action Statements 3.7.1.2.a and N or 3.3.3.7.b will be entered during this part, and their time limitations "M complied with. These action statements will be entered when test equipment is connected to CSSC plant equipment and the ERCW supply to the AFW is made j,
ijgjg inoperable.
e WP. 12I W PAGEN"3 oy
In the unlikely event that the level control valves fail closed on Train A during part 2 or part 3, the MDAFW B-train and the TDAFW pump will be g
available to maintain flow to at least two S/Gs. .
Effects Of Installing Temporary Test Equipment To CSSC Plant Equipment This test requires obtaining the pump start signal by placing temporary test connections across the IX relay in the 6900 shutdown board for the MDAFW 2A-A pump. Action Statement 3.7.1.2.a will be entered at this time.
A temporary pressure transmitter will be installed in parallel with the instrumentation which locally measures suction pressure of the pump. The worst case situation resulting from the installation of the temporary pressure transmitter is a rupture of the drain line, resulting in an AFW suction leakage path. During test conduct, the temporary pressure transmitter and line will be periodically monitored to ensure no leaks have developed. As a precaution while connecting and bleeding the suction transmitter, during pump starts and while the pump is running, an ERCW supply valve will be closed (breaker racked open) to ensure an injection of ERCW does not occur from low suction pressure. Action Statement 3.7.1.2.a must be entered while the ERCW supply to MDAFW 2A-A pump is isolated. However, this action statement will already be entered due to the pump start cable connection discussed above.
In the backup control room, a data logger will be placed in series with the current loop of the flow modifiers to measure AFW flow rate to the steam generators. It has been proven during previous terating that this setup does not affect the current loop and, therefore, the flow rates. Action Statement 3.3.3.7.b will be entered while the test equipment is connected in the current loop. This flow rate will also be obtained by connecting another data logger to the test points in the auxiliary instrument room at the output of the flow modifiers. This test point connection will have no effect on the process instruments.
Discharge pressure of the pump will be obtained by connecting a data logger across a test point in the auxiliary instrument room and will have no effect on the process instruments.
In summary, this test will not increase the probability of any accident previously analyzed in the FSAR, nor is the possibility of a new accident created. All postulated scenarios have been evaluated and the bases of the technical specifications is not degraded.
CAG:DLR 12/29/86 0243f 1
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PAGE EI-f OF
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