ML20212P299
| ML20212P299 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/25/1986 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20212N983 | List:
|
| References | |
| SP-435, NUDOCS 8703160061 | |
| Download: ML20212P299 (26) | |
Text
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l' Rev. 19 08/15/86
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- a m . =-ar=== - - es SURVEILLANCE PROCEDURE SP-435 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 VALVE TESTING DURING COLD SHUTDOWN THIS PROCEDURE ADDRESSES SAFETY RELATED COMPONENTS APPROVED BY: Res onsible Sec ion Superintendent /
Supe vi or GK ,/ . su k W Date S~cl5# SfD 0/03160061 870305 INTERPRETATION CONTACT: Nuclear Inservice Inspection PDR ADOCK 05000302 supervisor p PDR
4 1.0 OBJECTIVE 1.1 Each valve shall satisfy the criteria set forth by the ASME Boiler and Pressure Vessel Code Editions and Addenda of Section XI, subsection IWV, as outlined in Technical Specification (TS) 4.0.5.
1.1.1 Each motor-operated and air-operated valve shall be demonstrated OPERABLE by actuating to the position designated on the data sheets within the maximum
&1lowable stroke time limit.
1.1.2 Each air-operated valve shall upon loss of actuator power procure its fail-safe position.
1.1.3 Each check valve shall. be demonstrated OPERABLE by being exercised to the position to fulfill its func-tion.
1.1.4 Flow demonstrate, thru both EFV-1 & EFV-2, that flow paths exist between condenser hotwell and both EFP-1 &
I EFP-2 suctions.
1.2 TECHNIcar. SPECIFICATION /OTHER REFERENCES LCO/Other Applicable Surv. Perf, Requirements Surv. Freq. Mode References Durina Modes Durina Modes Freq. Notes Notes 4.0.5 1 thru 6 1 thru 4 SP1,SP2,R 23,40,54 4.6.3.1.1 1 thru 6 1 thru 4 SP1,SP2,R 4.7.1.5 1 thru 6 1 thru 3 23,40,54 3.7.1.2 5,6 1,2,3 R 3.7.1.3 5,6 1,2,3 R MODE NOTES: None SP-435 Rev.
192 Page 1
SURVEILLANCE FREQUENCY:
SP1- Special; Surveillance execution shall be determined by the time elapsed since this procedure's last execution and planned duration of the outage. If this outage is planned to exceed 48 hrs. in cold shutdown, or due to unforeseen circumstances the out-age exceeds 48 hrs., then determine the time elapsed since this procedure's last execution. If the period of time between the last execution of this procedure is greater 'than or equal to three (3) months (92 days), execution is required. If the procedure was partially completed, start with those valves not tested during the Surveillance Procedure's performance. (See OP-209, Plant Cooldown, Section 6.2.)
NOTE: The period of cold shutdown does not have to be extended solely for the complete performance of SP-435, but attempt to test as many valves as possible. If the procedure has been fully
completed within the last three (3) sonths, execution is not required.
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l SP-435 Rev.$ b J Page 2 L
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SP2- Special; Immediately prior to returning to service a power-operated valve or check valve that has had maintenance, repair, or replacement of the valve, or actuator, or control / power circuit, a test shall be conducted in which demonstrates the OPERATIONAL READINESS of the particular valve.
R- Refueling; The positions of the valves denoted by asterisks are to be compared to the positions shown by the associated remote indicators.
FREQUENCY NOTES:
23 - Prior to returning equipment to service.
40 - Establish surveillance prior to ascending into the applicable mode.
54 - If cold shutdown is planned to exceed 48 hrs., or due to unforeseen circumstances exceeds 48 hrs., execution of this surveil-lance is required if SP1 condition applies above.
2.0 nrrrarners 2.1 OP-209, Plant Cooldown 2.2 OP-404, Decay Heat Renoval System SP-435 Rev.
19'4 Page 3 t
2.3 CP-102, Inservice Inspection Pump and Valve Data Review and Corrective Action 2.4 HPP-106, Radiation Work Permit Procedure 3.0 DEFINITIONS AND ABBREVIATIONS 3.1 EF - Energency Feedwater l 11 3.2 FW - Feedwater l
3.3 OTSG - Once Through Steam Generator l
3.4 DH - Decay Heat l
3.5 MU - Make-Up l
3.6 CD - Condensate l
4.0 ACCEPTANCE CRITERIA 4.1 The maximum allowable stroke time, as specified on Data Sheet II and III, for each valve is not exceeded.
4.2 Each check valve is exercised *.o the position required to fulfill its function.
4.2.1 The valve disc in normally open check valves closes on cessation or flow reversal.
4.2.2 The valve disc in normally closed check valves opens when flow is established.
4.3 Valves with fail-safe actuators achieve their fail-safe positions upon loss of actuator power.
SP-435 Rev. ha l' ' Page 4 (Continued on Page 4a)
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4.4 When demonstrating condenser hotwell flow paths between EFP-1 and EFP-2 through EFV-2 and ETV-1, respectively, the water level in CDT-1 shall decrease by approximately one foot per valve.
4.5 The remote indicator positions accurately reflect the actual local indicator positions.
4.6 When verifying operability of EFV-5, 6, 7, 8, 15, 16, 17 & 18, and FWV-43 and 44, flow of approximately 200 l18 gpa to each OTSG shall be obtained to verify the full l stroke of these valves.
Sp-435 Rev. ., LL 9 page 4a
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5.0 SPECT17. TEST EQUIPMENT 5.1 Stopwatches 5.2 Two hundred feet (200 f t. ) of hose for demineralized water and appropriate connections.
5.3 Container to hold a minimum of one gallon of liquid.
5.4 Funnel NOTE: The items mentioned in 5.2 through 5.4 are for performing the test in Section 9.5.
6.0 LIMITATIONS AND PRECAUTIONS 6.1 Verification of valve stroke time may be ma'de at a remote operating station using indicator lights or at j the valve using proper stem motion. Local verifica-l tion should be coordinated with the Control Center.
6.2 The remote position indicators (denoted by asterisks on Data Sheet III) shall be visually observed at least as frequently as scheduled refueling outages with at least one observation being made every two years.
6.3 Prior to operating any valve, permission must be obtained from the Nuclear Shift Supervisor.
l
. a Sp-435 Rev. ' '
Page 5
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6.3.1 Prior to Uperating MUV-253, 258, 259, 260, and 261, operating personnel should be stationed at the local controls to manually open these valves in the event remote reopening is unsuccessful.
6.4 Those valves on Data Sheet II that require time-stroking shall be coordinated with the execution of OP-209, Plant Cooldown, and OP-404, Decay Heat Removal System, during power descent into cold shutdown.
6.5 When the deray heat removal system is in operation, iq aqt close DHV-3, 4, or 41 unless the reactor coolant pumps (RCPs) are available to cool the core.
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CAUTION: Prior to injecting water from CDT-1 into the [19 OTSGs for this test, contact Chemistry l Supervision to ensure efforts have been made [
to provide as high a water quality as l zeasonably possible. This may involve [
tleanup of the CDT-1 via the hotwell and [
condensate de= = ralizers before actual l testing occurs. [
eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeessenesessessessessesse 6.6 Section 9.10 of this procedure will inject water from the Condensate Storage Tank to the OTSGs. Due to possible water quality problems, it is imperative that the amount of water injected be minimized. All personnel involved in this test must fully understand the steps of this procedure and the required data prior to the actual performance of the test.
SP-435 Rev. IS Page 6 (Continued on Page 6a)
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6.7 It is preferred that Section 9.10 of this test be [19 performed on the startuo from cold shutdown prior to [
heating the OTSGs, to limit the concentrating ef fects l of the chemicals / impurities from the CDT-1 in the [
OTSGs. This will allow cleanup of the OTSGs, after [
shutdown and testing, by OTSG blowdown to the hotwell. [
7.0 Praemmerr i-+_1 ru1TIog 7.1 This procedure is designed and written to be performed by Nuclear Operators reporting directly to the Nuclear Shift Supervisor.
7.2 Some assistance may be required from the mechanics to perform Section 9.5 of this procedure, for the attach-ment of hose connections.
7.3 For work located in radiation controlled areas, due consideration should be given to the ALARA program.
This may result in a determination that special preparations and/or precautions are necessary.
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page 6a Sp-435 Rev. [{ . ,
Initial /Date 8.0 PernrrwISITES 8.1 Prior to commencement of surveillance, review Data Sheets I, II, and III, Step 6.6 and " Caution" prior to (15 6.6 of this procedure. /
[
8.2 , Notify the Nuclear Shif t Supervisor on duty prior to performance of this procedure. /
8.3 The time-stroke measurements of the DH valves on Data Sheet II are to be done in coordination with the execution of OP-404, Decay Heat Removal System, Step 8.1.3.1. /
NOTE: If these valves have been completed within the last three months, N/A this step.
8.4 The time-stroke measurements of the RC valves on Data Sheet II are to be done in coordination with the execution of OP-209, Plant Cooldown, Step 7.2.10.1. /
NOTE: If these valves have been completed within the last three months, N/A this step.
8.5 Prior to performing Section 9.10, contact Chemistry
[19 Supervision to ensure water quality is satisfactory [
for addition to the OTSGs during this test. See l
Caution at Section 9.10. Name of person contacted:
[
/ /
Name Date I
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{ SP-435 Rev. ', d 9 Page 7 (Continued on Page 7a)
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9.0 INSTRUCTIONS NOTE: On Data Sheets II and III, the ' Observed Stroke Time' column will designate the direction in
, which the stroke time is to be measured.
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SP-435 Rev. e yL s Page 7a
Initial /Date 9.1 Complete Data Sheet II during power descent into cold shutdown.
9.2 Isolate MUV-253 's actuator air supply and bleed the isolated air through the solenoid; record observation on Data Sheet III (Page 1 of 3).
9.3 Complete ' Power Loss Verification" and record stroke time for the appropriate valves of Data Sheet III, Part "A*.
NOTE: For all valves in Part 'A', except MUV-253, verification of actuator power loss is fulfilled by stroking of valve.
9.4 Insure MUV-64 is open. /
l 9.4.1 Open DHV-11. /
9.4.2 Record makeup tank (MUT) fluid level indicated on MU-14-LR on Data Sheet III, Part 'C' (Page 3 of 3).
9.4.3 Observe the MUT level indicator for a minimum of 15 l ain.
9.4.4 Record MUT fluid level after the allotted time has expired on Data Sheet III, part 'C' (Page 3 of 3).
9.4.5 If an increase in fluid has not occurred, initial the appropriate data space of Data Sheet III, verifying that check valve MUV-65 is closed.
9.4.6 Close DNV-11. /
4 SP-435 Rev. Page 8
s . :. . . . . ' .: . . _ . . .
Initial /Date 9.5 This portion of the procedure requires approximately 200 ft. of hose for carrying desineralized water and approximately 1 hr. of hold time af ter hose is in place. .
9.5.1 Close DWV-196. /
9.5.2 close CGV-53. /
9.5.3 open DWV-160. /
9.5.4 Connect a desineralized water hose from any convenient source outside containment to any convenient deminer-alized water hose connection inside containment. /
9.5.5 Open DWV-159. /
9.5.6 when water stops coming from DWV-159, pressurize the downstrean side of DWV-162 by valving in the deminer-alized water hose connected in Step 9.5.4. /
9.5.7 Collect the leakage from DWV-159 for 1 hr. Record the initial and final time, and the leakage on Data Sheet III, part "D".
9.5.8 If the leakage is less than 1 gal. per hour, DWV-162 is verified closed.
9.5.9 Isolate and remove the demineralized water hose connected in Step 9.5.4. /
i l 9.5.10 Open DWV-196. /
9.5.11 No additional restoration is necessary.
i 9.6 Stroke test and flow verification of EFV-1 and EFV-2.
l SP-435 Rev. ~- Page 9
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Initial /Date 9.6.1 Initial Conditions
- a. Main Condenser (CDHE-4B).
(1) No vacuum exists in CDHE-4B.
(2) CDHE 4B is available to receive approxi-mately 12,000 gallons of water.
- b. Condensate Storage Tank (CDT-1),
(1) CDT-1 is not supplying water to another tank or system. /
(2) CDT-1 is not receiving water from another source. /
. (3) CDT-1 level is stable (CD-67-L12). /
- c. Valve lineup.
(1) EFV-3 is open. /
! (2) EFV-4 is open. /
(3) EFV-1 is shut. /
(4) EFV-2 is shut. /
(5) EFV-36 is open. /
- d. EFWP's are not running. /
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SP-435 Rev. O Page 10
, c; . .. :_ 2 . _ . . . _ _ . . . . . .
9.6.2 Stroke of EFV-1 (Data Sheet III, Parts "B" and "E*)
- a. Record initial CDT-1 level,
- b. Open ETV-1. Record start time in Part 'E' and stroke time in Part "B" of Data Sheet
. III.
- c. When CDT-1 level decreases by 1 foot, then shut EFV-1.
- d. Record shut time and final CDT-1 level on Data Sheet III, Part 'E*.
NOTE: A decrease in CDT-1 level . indicates unter flow through EFV-1 to CDBE-48.
9.6.3 Stroke of EFV-2 (Data Sheet III, Parts "B" and "E*).
- a. Record initial CDT-1 level.
- b. Open EFV-2. Record start time in Part 'E' and stroke time in Part "B" of Data Sheet III.
! c. When CDT-1 level decreases by 1 foot, then shut EFV-2.
j d. Record shut time and final CDT-1 level on I
l Data Sheet III, Part 'E*.
[ NOTE: A decrease in CDT-1 level indicates water flow j through EFV-2 to CDHE-48.
i SP-435 Rev. e II O Page 11
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Initial /Date 9.6.4 Restore affected EF valves to positions appropriate for plant conditions. /
9.7 Complete Data Sheet III and verify that each valve is restored to its NORMAL position by completing the
' Restoration position" column with appropriate mark
('O' for open, "C" for closed).
9.8 (DELETED) 9.9 (DELETED) 9.10 VERIFICATION OF FEEDWATER AND EMERGENCY FEEDWATER CHECK YALVES NOTE: The operability verification of the valves in this test is to be performed by flow indication through the EF to OTSG system. Bosever, the energency feedwater pumps must be started by manual operation and not through the EFIC auto-matic actuation.
CAUTION: Prior to injecting water fron the CDT-1 into (19 the OTSGs for this test, contact chemistry l Supervision to ensure efforts have been made j to provide as high a water quality as [
reasonably possible. This may involve l cleanup of the CDT-1 via the hotwell and [
condensate desineralizers 'before actual l testing occurs. l
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, ,. .4 gA page 12 SP-435 Rev. 3
4 Initial /Date d
9.10.1 Ensure the following valves are:
EFV-55 in manual operation ard closed. /
EFV-56 in manual operation and closed. /
EFV-57 in manual operation and closed. /
EFV-58 in manual operation and closed. /
. 9.10.2 Open or verify open the following valves:
EFV-3 Open /
EFV-4 Open /
EFV-7 Open /
EFV-8 Open /
EFV-11 Open /
EFV-14 Open /
EFV-32 Open /
EFV-33 open /
9.10.3 Ensure the following valves are closed:
/
ASV-5/204 Closed FWV-34 Closed /
FWV-35 Closed /
9.10.4 Manually start EFP-1 by using the " pistol-grip" control handle on the main control board, having flow initially recirculating back to the condensate Storage Tank. /
9.10.5 Manually open EFV-57 and EFV-58 until a flow of ~ 200 l18 gpa is obtained on each FI listed in Step 9.10.6. /
l Page 13 SP-435 Rev. 7 d Q'
O -
Initial /Date 9.10.6 Record flow through the following flow indicators:
EF-23-FI gpa > EFV-16 Open /
) FWV-44 Open /
EF-25-FI gym ) EFV-15 Open /
) FWV-43 Open /
9.10.7 Close EFV-57 and EFV-58. /
9.10.8 Shut down and secure EFP-1. /
9.10.9 Flow verification in Step 9.10.6 verifies EFV-6 and EFV-7 opened. /
9.10.10 Manually start EFP-2 by opening the auxiliary steam valves ASV-5/204, having flow initially recirculating back to the Condensate Storage Tank. /
9.10.11 Bring pump speed up to 4030 rpm. /
9.10.12 Manually open EFV-55 and EFV-56 until a flow of ~ 200 l18 gpu is obtained on each FI listed in Step 9.10.13. / l 9.10.13 Record flow through the following indicators:
EF-24-FI gpa > EFV-18 Open /
EF-Js-FI gpu ) EFV-17 Open /
9.10.14 Close EFV-55 and EFV-56. /
9.10.15 Shut down and secure EFp-2. /
9.10.16 Flow verification in Step 9.10.13 verifies EFV-5 and
'EFV-8 opened. /
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l l SP-435 Rev. 1. k).
- page 14
Initial /Date 9.10.17 Restore the following valves to their proper operational status:
EFV-55 automatic /
EFV-56 automatic /
EFV-57 automatic /
EFV-58 automatic /
9.11 Inform the Shift Supervisor of the completion of this Surveillance Procedure and of the test results. /
10.0 SYSTDI RESTORATION 10.1 Restoration completed as noted in Section 9.0.
11.0 CONTINGENCIES 11.1 If a valve's stroke time is within the ' Alert Range" i
or exceeds the maximum allowable stroke time, refer immediately to CP-102, Inservice Inspection Pump and Valve Data Review and Corrective Action, for correc-tive action.
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l SP-435 Rev. t- $ Page 15
11.2 If a containment isolation valve is declared INOPERABLE, by either exceeding the maximum allowable stroke time or nonfulfillment of its function, refer immediately to the " Action Statement" of STS 3.6.3.1.
Refer to CP-102, Inservice Inspection Pump and Valve Data Review and Corrective Action, for additional guidance.
12.0 ENCLOSURM Enclosure 1 Data Sheet I
, Enclosure 2 Data Sheet II Enclosure 3 Data Sheet III 4
SP-435 Rev. Page 16
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-DAT7. SHEET I- ENCLOSURE 1 VALVE TESTING DURING COLD SHUTDOWN
-Explanation of Enclosures-Before a non-asterisk denoted valve, shown on data sheets, is manipulated to measure stroke time, the valve's initial (NORMAL) position shall be compared to the associated remote indicator's designated position. The FULL-STROKE position of the valve and the remote indicator shall also be cespared. The top of the valve sten shall correspond to a marking implanted upon the stem housing when in the NORMAL position and in the FULL-STROKE position (or other methods which verify that remote indicators are reflective of valve stem position).
The asterisk-denoted valves' positions shall be compared at least as frequently as scheduled refueling outages with at least one (1) comparison being made every 2 yrs. If comparison is not to be performed, the data space shall be marked 'Not Applicable" (NA).
Each valve shall be restored to its NORMAL POSITION by completing the
" Restoration Position" column with the appropriate mark (0 or C).
If a valve's stroke time is within the " Alert Range" or exceeds the maximum allowable stroke time, refer to Section 11.0, Contingencies.
Performed By Date Time Checked By Date Time 4
SP-435 Rev. +3 page 17
. . . l
- DATA SilEET 11 -
VALVE TESTil1G DURING COLD SiluTDOWN
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NUMBER sie a se w A so H O C <vv wHv M s~ A o A MA NITIAl.S ,
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.' DHV-3 C 52 NA 56.8 60 1A DilV-4 C 54 NA 58.6 120
- IA s DilV-S C 10 I4A 13 15
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DHV-6 C 9.8 NA 13 lb A
DilV-91 C 17.3 flA 22 60 l
RCV-13 0 12 t4A IS 60 RCV-53 C 16 NA 20 60 L' heck valves DilV-93 and RCV-12 are verit ied oper winesi a DilV-93 o' pens /
decrease in pressurizer temperature or pressure occurs. RCV-12 opens /-
DilV-1 opens Checked By
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f low, gpm (Dil-1-fil) DilV-2 opens ,_ ]--- E flow, gpm (Dil-1-F12) _,__
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- All valves are to be full stroked. Containuent isola tion Valve NA - flot Applicatale f, !
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_. Applicable orily to containment isol.ition valves listed in Table 3.6.1 of STS. m t
- DA1 A SilEET- 111 - -
VALVE TESTING DURING COLD Sil0TD0dN r
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EFV-1 C 40.5 NA 50 60 EFV-1 EFV-?
s EFV-2 C 36.6 NA 45 60 Initial COT-1 '
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FWV-29 0 27.5 NA 34 40 l 0 NA ' I FWV-30 28 35 40 Level (CD-67-L12) ,
CD FWV-31 0 59.6 NA 79 120 EFV Open Tline ,
FWV-32 0 57.2 NA 78 120 EFV Shut Time ,
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ENCLOSURE 3 DATA SHEET III (Cont *di ! '
VALVE TESTING DURING CDLD SHUTDOWN PART "C"
HUT-1 Initial Level (HU-14-LR) h Time Initials MUT-1 Final Level (HU-14-LR) Time Initials HUV-65 closed lli PART "D*
Initial Time Approximate Leakage Per Hour Checked By Final Time DW-162 closed / '
Date / Initials Date
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