ML030770425
| ML030770425 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/18/2002 |
| From: | Beltz B, Raasch D Nuclear Management Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| FOIA/PA-2003-0094, IT-300 B | |
| Download: ML030770425 (40) | |
Text
Point Beach Nuclear Plant CO PY PARTIAL PROCEDURE PERFORMANCE Page I of I Procedure Number/Title .. ZTi- _z"" B Unit Revision j Work Order Number Temporary Change Number Purpose/Description/Justification of Partial Performance (attach additional pages if necessary):
Check one of the following which must apply in order to continue:
Ca Equipment out-of-service or inoperable El Equipment not required to be operated F1 Procedure bcing aborted Answer the following for the requested partial performance: YES NO
- 1. Will this request be permanent or more than one-time use? E] P
- 2. Will this request involve a change of intent? (ref. NP 1.2.3)
(The inability to test or operate equipment described in the purpose section of a procedure due to that equipment being "out of service" does not necessarily constitute a change of intent for the procedure)
- 3. Will this request cause a condition on Page 2 to be introduced or created? El
- 4. Will this request alter or affect the applicable initial conditions for equipment being El worked on or evolution in progress? (for test procedures, all initial conditions shall be El established unless the condition is not related to the actions to be performed)
- 5. Will this request change the way the procedure is performed for equipment being El worked on or evolution in progress?
- 6. Will additional clarifying instructions need to be added?
Requested By (print and sign) -p_ 7-,"9 c/ , g,12 A. If the answer to any of the above questions is "Yes", Partial Performance shall not be used and the procedure shall be revised or changed according to appropriate administrative procedures.
B. If all answers are "No" then ensure the following is performed and approval below is obtained prior to implementing the Partial Performance:
I. The sections, subsections or steps required to be performed are included in the procedure package. (This includes as a minimum, the Purpose, Prerequisites, Precautions and Limitations, Initial Conditions' Procedure, Remarks, applicable Attachments or Data Sheets, and any approved currently effective temporary changes)
- 2. If a one time omission of a step or steps has been authorized, mark the unused step(s) N/A.
- 3. If unneeded subsections or sections are retained, mark each unused step in that section NIA.
- 4. The pages, sections, subsections or steps required to be performed (or not performed) are identified in the location provided on the procedure cover page, in the Description Section above, or in the Remarks section of the applicable procedure.
- 5. For Reference Use procedures that do not contain signoffs or record data, a markup of the partial performance is required and may be discarded upon completion.
C. A Group Supervisor (first line supervisors or above) shall review the Partial Performance package and indicate approval below.
'4, Approved By-' pL" EILJ W0 Dat Supervisor (print and sign) j After approvals,this completedform shall be controlled as a recordand remain attachedto procedures requiringsignoffs or data recording. I I PBF-0026m Revision I 2P21101 Reference- NP 1.1.4
Point Beach Nuclear Plant PROCEDURE RECORD AND FIELD COPY TRACKING Record/Field Copy Identification Field Copy Number R-A,.C -R RED - Record Copy, BLACK - Field Copy Procedure Number IT- 300 B n _____it _1 Revision Number 10 Revision Date AUG 22,02 Procedure Title S / G "B" MAIN FEED CHECK V VES (CSD)
Procedure Revision ecke and ent; ac ng ecked or Temporary Changes:
Date 2-*'/
ByI 4TESTOP 0F TOR Record Copy Holder/Locatio _ O
/I FIELD COPY DISTRIBUTION Copy No. Holder/Location Issue Date Return Date 1 CONTROL ROOM 2
3 4
5 6
7 8
9 10 NOTE 1: ANY TEMPORARY CHANGES MADE TO THIS PROCEDURE SHALL BE MADE TO THE RECORD COPY AND ALL OTHER FIELD COPIES THAT HAVE BEEN ISSUED.
NOTE 2: RETURN ALL FIELD COPIES TO THE HOLDER OF THE RECORD COPY UPON PROCEDURE COMPLETION.
PBF-0026i
Reference:
NP 1.1.4 Revision 2 2121101
IT 300B STEAM GENERATOR B MAIN FEED LINE CHECK VALVES (COLD SHUTDOWN)
UNIT 1 DOCUMENT TYPE: Technical CLASSIFICATION: Safety Related REVISION: 10 EFFECTIVE DATE: August 22, 2002 REVIEWER: Qualified Reviewer APPROVAL AUTHORITY: Department Manager PROCEDURE OWNER (title): Group Head OWNER GROUP: Operations Verified Current Copy:
Signature Date Time List pages used for Partial Performance Controlling Work Document Numbers
POIN I' BEACH NUCLEAR PLANT IT 30013 INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I 1.0 PURPOSE 1.1 This procedure partially satisfies TS 5.5.7, by conducting Inservice Testing (IST)
Program bi-directional exercise tests of the "B" S/G Main Feed Line check valves, in accordance with the ASME OM Code 95Ed./96A. Exercising to the closed safety position is demonstrated by the quantifying seat leakage past the check valve, confirming disc closure. Exercising to the open (non-safety) position is demonstrated by normal unit power operations.
1CS-476AA, 1HX-IB SG Check ICS-476BB, 1HX-1B SG Check 1.2 To provide conditions for blowdown of "B" SIG instrumentation, in Mode 5 conditions.
2.0 PREREQUISITES 2.1 Special test rig, Omega flowmeter, Model No. FL-7325, as shown in Attachment B is available.(Stored in U2 TH El. 26' south).
2.2 Test rig pressure indicator (PI's) AND flow cal dates have been checked current.
Test rig:
PINo# i*"fJ -706 Cal Date t____-
FI No # C7ii "AS Cal Date ID-i 2.3 Handheld Pyrometer AND Adapter Cable. (C-59) 000Pl-90') CalDate.. - 1.-03 2.4 I&C Instrument Technicians available to blow down S/G level instrumentation, if required.
3.0 PRECAUTIONS AND LIMITATIONS 3.1 A 20 psig minimum backpressure should be maintained at the test rig to prevent gravity draining of the main feed line.
3.2 The test manifold drain hose should be routed to a local floor drain AND secured to prevent end whip, for personnel safety. These hose shall be rated for greater than OR equal to 500 psig at 250 'F., to minimize risk of injury due to hose rupture.
3.3 "B" SIG metal temperature must be greater than OR equal to 70'F before pressurization greater than 200 psig per TRM 3.7.3.
3.4 Do NOT exceed 840 psig in "B" SIG.
Pace 2 of 38 CONTINUOUS USE
?-'UI.N 1BEACH NUCLEAR FLAN I IT 300B I LNSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT 1 3.5 Do NOT OPEN 1MS-2015, 1HX-1B SG Hdr Atmospheric Steam Dump Control, when steam lines are filled except to avoid exceeding 840 psig.
3.6 Do NOT use, 1MS-2015, IHX-1B SG Hdr Atmospheric Steam Dump Control, as a vent path while filling "B" S/G.
Page 3 of 38 CONTINUOUS USE
I, I .UJJU.-)
INSERVICE.TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS 4.0 INITIAL CONDITIONS 4.1 This test is being done to satisfy:
X, The normally scheduled calluu.
Work Order No.
9'q513 T-5Z NOTE: If this test is being performed to satisfy PMT or off-normal frequency requirements, Shift Management may NIA those portions of the procedure that are NOT applicable for the performance of the PMT. The use of N/A is NOT acceptable for Initial Conditions, Precautions and Limitations, or procedure steps that pertain to the equipment requiring PMT, nor is it acceptable for restoration of equipment/components unless the component has been declared inoperable.
Post-maintenance operability test for:
Equipment ID WO No(s).
Special test - no numbers Explain:
4.2 01150, Heating the Condensate Storage Tanks, has been implemented to split CST's AND heat T-24A, South CST to 80-1106F. IL 4.3 At least I "B" S/G main steam safety valve must be operable.
(Circle operable 1HX-1B SG Header Safety valves).
c0LS-008 4.4 Any safety valve removed must have full pressure blank flange installed.
4.5 "B" S/G hand hole covers installed.
4.6 "B" S/G secondary manways installed. v-==A C Page 4 of 38 CONTINUOUS USE
11 .IUUbl INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT 1 INITIALS 4.7 "B" S/G feed line intact FROM main and bypass feedwater reg. valves inlet isolation TO "B" S/G.
6"N 4.8 All "B" S/G tubes that require plugging are plugged on BOTH ends.
(N/A if primary manways are installed)
ISI 4.9 Chemistry notified
"* To determine discharge permit requirements to utilize steam generator blowdown system.
"* To determine chemical addition requirements AND to have required chemicals available at P-38B Chemical Addition Pot.
4.10 Unitl1 inMODE5, 6, ORDefueled.
4.11 "B" SIG Wide Range Level, LT-470A OR LT-470B, operable.
I&C I
4.12 PBF-2051, "B" S1 Blowdown Flow Rate Log Sheet, is available if <2 required.
4.13 P-38B, Aux Feedwater Motor-Driven Pump AND flow path to "B" S/G is available with no outstanding clearances OR associated work is in progress.
WCC 4.14 "B" SIG Blowdown system has no outstanding clearances, no associated work in progress AND is available tb receive drains from steam line B AND "B" SIG blowdown.
WCC 4.15 Permission to Perform Test The conditions requied'by this test are consistent with required plant conditions including ýjuipment operability. Permission is granted to perfp,-o/'thi telt.//
/' ,4.t.-Time Oyý DateE/
S
'/ // ýZ/r(-L-Page 5 of 38 CONTINUOUS USE
S. _, POINT BEACH NUCLEAR PLANT IT 300B "INSERVICETESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS 5.0 PROCEDURE 5.1 PT-478, IHX-IB Steam Pressure Channel in service.
5.1.1 IMS-478, 1HX-1B SG Header PT-478 Root. OPEN ..
5.1.2 1MS-478A, IHX-1B SG Header PT-478 2nd Off Isolation. OPEN 5.1.3 PT-478, 1HX-1B Steam Pressure Channel. OPERABLE .,
I&C 5.2 Ensure one OR both SG Steam Pressure Channels in service PT-479 OR PT-483 (Mark unused channel as N/A).
5.2.1 1MS-479, HiX-1B SG Header PT-479 Root OPEN 5.2.2 1MS-479A, 1HX-1B SG Header PT-479 2nd Off Isolation. OPEN 5.2.3 PT-479, 1HX-1B Steam Pressure Channel. OPERABLE I&C OR 5.2.4 1MS-483, IHX-1B SG Header PT-483 Root. OPEN 5.2.5 1MS-483A, IHX-1B SG Header PT-483 2nd Off Isolation OPEN .L.
5.2.6 PT-483, 1HX-1B Steam Pressure Channel. OPERABLE z4 "1ý I&C 5.3 IF feed line has been drained since shutdown, THEN perform Main Feed Line fill per Attachment A, step 1.0. .' k' Pag~e 6 of 38 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B "rh-SERVICETESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS 5.4 Obtain "B" SIG metal temperatures by performing steps 5.4.1 OR 5.4.2.
(NIA the one NOT used) 5.4.1 Using hand held pyrometer AND adapter cable located at C-59, plug adapter cable into thermocouple junction box located on "B" S/G missile shield wall AND record readings:
- b. TE-2022B, IHX-1B SG Shell Temperature Thermocouple Below. transition cone _ OF
- c. TE-2022C, 1HX-1B SG Shell Temperature Thermocouple Above tubesheet _ OF .4 5.4.2 Using hand held pyrometer, obtain metal temperatures at "B" S/G upper manway OR upper level tap penetration.
5.5 IF "B" S/G temperatures less than 70*F, THEN establish "B" SIG level less than OR equal to 360 inches. iy 5.6 WHEN "B" SIG pressurized greater than 50 psig but less than ORj equal to 100 psig, THEN arrange with I&C to blow down "B" S/G level transmitters, if required.
Pagge 7 of 38 CONTINUOUS USE
- . P0 INT BEACH NUCLEAR PLANT IT 300B INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS 5.7 Record as found positions AND align "B" S/G for filling:.
As Found Required Valve Component Description Position Position Initials IMS-2017 IHX-IB SG Header Main Steam Stop Control . SHUT valve -,-2,1 1MS-236 1HX-IB SG Header MS-2017 Main Steam SHUT Stop Bypass IMS-241 1HX-IB SG Header ST-2028 Inlet SHUT IMS-242 1HX-1B SG Header ST-2028 Bypass ", SHUT ,*"
JO '1-229" 1HX-1B SG Drain to IT-26 Blowdown Tank SHUT UNLOCKED IMS-237 P-29 AFP/Radwaste Steam Isolation ý,k-" & SHUT HX-1B SG Header ST-2036 First Off Isolation IMS-35 "-_1A- ( OPEN HX-1B SG Header ST-2036 Second Off OE lMS-36 Isolation OPEN HX-1B SG Header ST-2036 Bypass Drain tk.N, UNCAPPED IMS-120A 01_e%- &OPEN Note:lMS-212 is on top of"B" S/G AND will be left in LO position with red lock and chain Lo d4,A LOCKED IMS-212 1HX-IB SG Vent Q?.,- OPEN Note: 1MS-214 is inaccessible. Visual verification from remote area to check rising stem AND red lock is sufficient to satisfy position check.
Ud*,i SHUT &
lMS-214 IHX-1B SG Vent Line Vent Penetration IVTC " CAPPED IMS-248 .- IHX-1B SG VVeot L.,, sk OPEN M ,
1HX-1B SG Blowdown Line Drain, inside s;,,- SHUT & _j7 lMS-217A containment c,,p. CAPPED 1MS-218 IHX-1B SG Blowdown Line Manual Isolation OPEN IHX-1B SG Blowdown Isolation, inside Air, AIR ON &
IMS-5959 containment SHUT AIR ON &
IMS-2045 1HX-IB SG Header Blowdown Control oPEN O_,,
IMS-266 IHX-IB SG Blowdown Isolation, OPEN 1MS-272 1HX-1B SG Blowdown to IT-26 SGBD Tank OPEN IHX-IB SG Blowdown to IT-26 SGBD Tank 1/4 turn IMS-274 Outlet, 1 '-"'- OPEN IMS-282 IHX-lB SG Blowdown to 1HX-18BI/2 I__,,,-_ SHUT Page 8 of 38 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS As Found Required Valve Component Description Position Position Initials 1MS-286. IT-26 SGBD Tank Outlet o--" OPEN IMS-288 IT-26 SGBD Tank Outlet MS-2040 Inlet ,,. OPEN IMS-2040 IT-26 SGBD Tank Outlet Control SHUT lMS-296 P-49 Blowdown Pump Suction OPEN lMS-300 P-49 Blowdown Pump Discharge ,,-i..,-- OPEN Note: Align at least one blowdown filter ..
F-64A OR F-64B (N/A filter not selected) ;
F-64A blowdown filter 1MS-302 F-64A Blowdown Filter Inlet Line Drain - SHUT IMS-303 F-64A Blowdown Filter Outlet Line Drain IJA- SHUT IMS-301 F-64A.Blowdown Filter Inlet OPEN lMS-304 F-64A Blowdown Filter Outlet OPEN F-64B blowdown filter Emu=
IMS-306 F-64B Blowdown Filter Inlet Line Drain <" SHUT IMS-307 F-64B Blowdown Filter Outlet Line Drain -qw.-- SHUT 1MS-305 F-64B Blowdown Filter Inlet Lfs.' OPEN IMS-308 F-64B Blowdown Filter Outlet 4Wv OPEN IMS-2099 Blowdown Filter System Outlet Control A,, o.-. AIR ON IMS-5954 BD Filter System to Condensate Demin Flow f?/
cl- AIR OFF &
Ctl, aligned to service water return header/tf'- OPEN __
1MS-311 BD Filter Sys Outlet to Service Water Return OPEN Hdr I______---_
I I
5.8 Discharge permit to utilize "B" S/G Blowdown flow path for pressure control obtained from Chemistry.
Required NOT Required4 5.9 SHUT IMS-2084, 1HX-1B SG Sample Isolation Control.
5.10 Set 1MS-2015, IHX-IB SG Hdr Atmospheric Steam Dump Control to 4-840 psig AND place controller in AUTO.
5.11 Ensure T-24A, South CST, temperature 80-1 10'F. ,
'C'.-
Page 9 of 38 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS CAUTION Maintain 13,000 gallons of usable volume in T-24A, South CST. Ensures ability to maintain operating unit in hot shutdown condition for at least one hour. (Reference tank level book).
NOTE: The T-24A, South CST may be refilled per 01 150, Heating the Condensate Storage Tanks, via transfer hose as necessary.
5.12 Fill "B" S/G 5.12.1 IF Attachment A has NOT been performed, THEN record As found position AND align valves per
"- required position:
Valve Description As Found Required Initials Position Position ICS-147 IHX-1B SG 1CS-476 Regulator Inlet PCP SHUT It k r ICS-148 1HX-1B SG 1CS-147 Regulator Inlet Bypass ___,__ SHUT .(7T $.(j ICS-145 lHX-1B SG 1CS-476 Regulator Outlet OPEN ICS-144 IHX-1B SG 1CS-481 Regulator Bypass Inlet SHUT 1.,e*r' SHUT & "
1CS-144A 1HX-1B SG 1CS-481 Regulator Bypass Line Drain ¢.,*-* CHPPE CAPPED j, ICS-143 1HX-1B SG 1CS-481 Regulator Bypass Outlet OPEN 1CS-481 IHX-IB SG 1CS-476 FW Regulator Bypass Control GAGGED
____ OPEN ICS_,14A 1HX-21AJB HP FWH 5A/5B Out SG FW Sample OPEN Root Isol 1CS-145B 1HX-21A/B HP FWH 5A/5B Outlet SG FW Sample , SHUT 1CS-145C 1HX-21A/B HP FWH 5A15B Header Drain 5,, SHUT &
__________________________ ~CAPPED 1IC-198 Corrosion Product Monitor Panel FW Sample ICS-145E Isolation Sample OPEN 1CS-180A 1HX-IB SG Chemical Injection Second Off Isol. SHUT I
SHUT &
1CS-178A IHX-1B SG Sampling Second Off Isolation CAPPED S~~UNLOCKED UN t Feedwater Leakage Check Test 0'/ Line 41", & SHUT 0]rt:'*
Feedwater Leakage Check Test Line Z;,k e &
UNLOCKED
__ __ __ __ __ __ __ __ __ __ & SHUT
'-I Page 10 of 38 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT 1 INITIALS INITIALS 5.12.2 Isolate 1C-198, Corrosion Product Monitor Panel by:
- a. Notify Chemistry 1SS-208, 1C-198 Corrosion Product Monitor Panel FW Sample Inlet will be SHUT for -
IT-300B.
- b. Record as found position of ISS-208. ( " '-- )
- c. SHUT ISS-208.
5.12.3 Ensure the following valves are locked SHUT AF-30, P-38A1B AFP Discharge Crossconnect.
AF-43, P-38A/B AFP Discharge Crossconnect.
5.12.4 Start P-38B, Aux Feedwater Motor-Driven Pump, using OI-62A, Motor-Driven Auxiliary Feedwater System (P-38A &
P-38B).
CAUTION To prevent motor breaker trip on overload, P-38B flow rate should NOT exceed 240 gpm. Minimum recirculation flow is 70 gpm 5.12.5 Establish a 175-200 gpm fill rate to "B" SIG.
NOTE: At 510 inches wide range level, remaining '"B" SIG AND Main Steam header volume is 12,200 gal. This equates to 61 minutes of run time @ 200 gpm.
5.12.6 WHEN "B" S/G wide range level at 510 inches, THEN record times below AND continue (175-200 gpm fill rate) filling for additional 40 minutes.
Time at 510 in 1L119 Time at 510in +40.min ",Gq Time at 510 in + 50 min 120 Pagre 11 of 38 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS 5.12.7 WHEN at Time at 510 in + 40, THEN THROTTLE fill rate to approximately 100 gpm AND establish communication with operator at "B" S/G manual vent within Time at 510 in + 50 miin CAUTION Ensure AF-4014, P-38B AFP Mini Recirc Control, opens when feedflow to "B" SIG is less than OR equal to 75 gpm.
NOTE: The '"B" SIG pressure on PPCS will show an increase when
- almost solid.
NOTE: Individual stationed at vent will have indication (change in sound) coming from vent just prior to "B" SIG going solid.
5.12.8 Continue filling "B" S/G AND steam line.
4
- a. Just prior to going solid, minimize auxiliary feed flow.
- b. WHEN water observed from vent, 17.]t THEN STOP P-38B, Aux Feedwater Motor-Driven Pump.
5.12.9 SHUT IMS-248, 1HX-1B SG Vent.
5.13 Ensure "B" S/G Metal Temperature Greater Than OR Equal to 70'F.
5.13.1 Obtain hand held pyrometer / adapter cable from C-59.
5.13.2 Perform either 5.13.3 OR 5.13.4. (Mark steps NOT used as N/A) 5.13.3 Plug in adapter cable at thermocouple junction box located on "B" S/G missile shield wall AND record readings:
- a. TE-2022A, IHX-1B SG Shell Temperature Thermocouple Above feedwater inlet -F Pagre 12 of 38 CONTINUOUS USE
POLNT BEACH NUCLEAR PLANT IT 300B
- INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT 1 INITIALS
- b. TE-2022B, lHX-IB SG Shell Temperature Thermocouple Below transition cone 4/1AL oF
- c. TE-2022C, 1HX-1B SG Shell Temperature Thermocouple 1NIIAL Above tubesheet ,zt/(4/ OF 5.13.4 Using hand held pyrometer, obtain metal temperature at "B" S/G upper manway OR upper level tap penetration. (NA location not used.)
Upper manway Reading A4Ai OF Upper level tap penetration Reading 79 V OF 5.14 Pressurize "B" SIG to 500 psig.
5.14.1 Place AF-4019, P-38B AFP Discharge Control, in MANUAL AND SHUT.
CAUTION To prevent motor breaker trip on overload, P-38B flow rate should NOT exceed 240 gpm AND the minimum recirculation flow is 70 gpm 5.14.2 START P-38B, Aux Feedwater Motor-Driven Pump AND ensure AF-4014, P-38B AFP Mini Recirc Control, OPENS.
5.14.3 IF blowdown of "B" S/G instrumentation is NOT required OR is to be performed AFTER main feed check valve leak test, THEN N/A steps 5.14.4, 5.14.5, 5.14.7 & 5.14.8, otherwise continue.
,ALI-)
y 5.14.4 Slowly raise "B" S/G pressure to between 75 AND 100 psig by throttling OPEN AF-4019 to as low a flow as practicable in MANUAL.
Pagre 13 of 38 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT 1 LNITIALS 5.14.5 Stabilize "B" S/G pressure between 75 AND 100 psig using AFW flow.
- a. Throttle AFW flow as required, using AF-4019.
"1 21
- b. IF required to hold "B" S/G pressure, THEN establish "B" S/G blowdown flow as follows.
(N/A steps not used).
- 2. OPEN IMS-2040, IT-26 SGBD Tank Outlet Control.
- 4. IF'required, THEN start P-49 Blowdown..Tank Pump.
5.14.6 IF blowdown flow is established to stabilize "B" SIG pressure, TIIEN record flow rate AND time on PBF-205 1.
5.14.7 Notify I&C to blowdown "B" S/G instrumentation.
5.14.8 Hold until notified by I&C of task completion above.
'...-'0,'>
5.14.9 Slowly raise "B" S/G pressure between 500 AND 520 psig by throttling AF-4019 to as low a flow as practicable in MANUAL.
5.14.10 Stabilize "B" SIG pressure between 500 AND 520 psig using AFW flow
- a. Throttle AFW flow as required, using AF-4019
- b. IF required to hold "B" SIG pressure, THEN establish "B" S/G blowdown flow as follows.
(N/A steps not used). (iC I. OPEN 1MS-5959, 1HX-1B SG Blowdown Isolation cxL*
POINT BEACH NUCLEAR PLANT IT 300B INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS INITIALS
- 4. IF required, THEN start P-49 Blowdown Tank Pump. 6k4-5.15 Check Flow Indicator Test Rig connected to ICS-145C, 1HX-21A/B HP FWH 5A/5B Header Drain, 5.15.1 IF NOT connected, THEN connect test rig per Attachment A, step 2.0.
5.16 Check effluent hose attached to 1CS-144A, 1HX-lB SG ICS-481 Regulator Bypass Line Drain.
5.16.1 IF NOT connected, THEN remove cap AND attach hose to 1CS-144A
- a. Route hose to a local floor drain.
- b. Secure to prevent end whip.
5.17 Seat Leakage Test of ICS-476AA, 1HX-D-B SG Feedwater Check CAUTION System is pressurized to 500 psig. All drain hoses must be restrained to prevent end whip AND personnel injury.
I 5.17.1 Ensure OPEN 1CS-221, Feedwater Leakage Check Test Line.
5.17.2 OPEN the following valves:
- c. Record test manifold pressure. psig.
(10*1*
Page 15 of 38 CONTINUOUS USE
- , POINT BEACH NUCLEAR PLANT IT 300B INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS INITIALS 5.17.3 While observing test manifold pressure perform the following:
- a. Throttle OPEN manifold outlet valve until pressure drops / " 1 2
rapidly to less than 100 psig, indicating ICS-476AA seated.
- b. SHUT OR Throttle manifold outlet valve as required to maintain 20 to 25 psig backpressure on manifold pressure gauge.
- c. IF ICS-476AA backpressure is less than 20 psig OR pressure drops to less than 20 psig (as a result of trying to seat check valve) AND does NOT recover to 20 psig (due to check valve leakage),
THEN momentarily Throttle OPEN 1CS-220 to restore backpressure to 20-25 psig BEFORE recording data.
- d. IF test manifold flow is less than 25 gpm, THEN continue with step 5.17.3.e while marking step 5.17.4 as N/A. (Otherwise mark Step 5.17.3.e as N/A)
- e. WHEN a stable backpressure AND stable "B" S/G test pressure is achieved, THEN record on Attachment C:
0 Test rig pressure 0 SG B Pressure 0 Measured Leakage 0 Calculated expe'ted valve leakage.
5.17.4 With test manifold flow of approximately 25 gpm AND while observing test manifold pressure perform the following:
- a. Throttle OPEN ICS-144A, -HX-1BSG ICS-481 Regulator Bypass Line Drain, UNTIL manifold pressure drops rapidly to less than 100 psig, indicating 1CS-476AA, has seated.
- b. SHUT 1CS-144A r
- c. IF full flow established through ICS-144A AND manifold pressure remains greater than 100 psig, THEN Throttle OPEN manifold outlet valve until ICS-476AA seats.
Pagre 16 of 38 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS INITIALS
- d. WHEN ICS-476AA has seated, THEN rapidly SHUT ICS-144A AND Throttle with manifold outlet valve, as required, to maintain 20 to 25 psig < .
backpressure on manifold pressure gauge.
- e. IF ICS-476AA backpressure is found less than 20 psig OR pressure drops to less than 20 psig (as a result of trying to seat check valve) AND does NOT recover to 20 psig (due to check valve leakage),
THEN momentarily Throttle OPEN ICS-220 to restore backpressure to 20-25 psig BEFORE recording data.
- f. WHEN a stable backpressure AND stable "B" S/G test pressure achieved, THEN record on Attachment C 0 Test Rig Pressure.
0 SG B Pressure 0 Measured Leakage S Calculated expected valve leakage.
g IF check valve does NOT seat, THEN SHUT 1CS-144A AND manifold outlet valve THEN repeat steps 5.17.3 and/or 5.17.4, as required.
(Provide a set of initials for applicable steps performed on Attachment D.)
96'ýý
- h. IF after second attempt check valve has NOT seated, THEN perform Attachment E.
IF after a third attempt check valve has NOT seated, THEN contact test coordinator (for further direction).
In interim, continue test.
5.17.5 SHUT test manifold outlet valve.
5.17.6 Ensure SHUT 1CS-221.
5.17.7 Ensure SHUT 1CS-220.
Page 17 of 38 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT 1 INITIALS 5.17.8 IF seat leakage test of 1CS-476BB, IHX-IB SG Feedwater Check is NOT to be performed, THEN restore Feed Line Drain Valves as follows.
- b. Disconnect test manifold at ICS-145C AND install cap. Ci>
- c. Ensure SHUT 1CS-144A remove hose AND install cap.
- d. OPEN ICS-145B.
- 2. Once started, release 1CS-481 reset switch AND fully ungag ICS-481.
- 3. Ensure 1CS-481 is ungagged with a locked handwheel. CZ14I IV
- f. Restore IC-198, Coribsion Product Monitor Panel FW Sample, alignment as follows:
- 1. Notify Chemistry ISS-208, IC-198 Corrosion Product Monitor Panel FW Sample Inlet will be returned to "As found" position.
Page 18 of 38 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS INITIALS 5.18 Seat leakage Test of I CS-476BB. IHX-IB SG Feedwater Check CAUTION System is pressurized to 500 psig. All drain hoses must be restrained to prevent end whip AND personnel injury.
5.18.1 Ensure OPEN I CS-220, Feedwater Leakage Check Test Line.
5.18.2 OPEN the following valves:
- c. Record test manifold pressure. psig.
5.18.3 While observing test manifold pressure perform the following:
- a. Throttle OPEN manifold outlet valve until pressure drops rapidly to less than 100 psig, indicating I CS-476BB, has seated.
- b. SHUT OR Throttle manifold outlet valve as required to maintain 20 to 25 pslg backpressure on manifold pressure gage.
Page 19 of 38 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT 1 INITIALS
- c. IF ICS-476BB backpressure is found to be less than 20 psig OR pressure drops to less than 20 psig (as a result of trying to seat check valve) AND does NOT recover to 20 psig (due to check valve leakage),
THEN momentarily Throttle OPEN ICS-221 to restore backpressure to 20-25 psig BEFORE recording data.
22ŽI
- d. IF test manifold flow is less than 25 gpm THEN continue with step 5.18.3.e while marking step 5.18.4 as N/A. (Otherwise mark Step 5.18.3.e as N/A)
- e. WHEN a stable backpressure AND stable "B" S/G test pressure is achieved, THEN record on Attachment C:
- Test Rig Pressure,
° SG B Pressure
- Measured Leakage
- Calculated expected valve leakage.
5.18.4 With test manifold flow of approximately 25 gpm AND while observing test manifold pressure perform the following:
- a. Throttle OPEN 1CS-144A, 1HX-1B SG ICS-481 Regulator Bypass Line Drain until manifold pressure drops rapidly to less than 100 psig, indicating 1CS-476BB has seated, 11
- b. SHUT ICS-144A.
- c. IF full flow is established through 1CS-144A AND manifold pressure remains greater than 100 psig, THEN Throttle OPEN manifold outlet valve until 1CS-476BB seats.
e1v/
- d. WHEN 1CS-476BB has seated, THEN rapidly SHUT 1CS-144A AND Throttle with manifold outlet valve, as required, to maintain 20 to 25 psig backpressure on manifold pressure gauge.
Page 20 of 38 CONTINUOUS USE
"POINTBEACH NUCLEAR PLANT IT 300B INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT 1 INITIALS
- e. IF ICS-476BB backpressure is found to be less than 20 psig OR pressure drops to less than 20 psig (as a result of trying to seat check valve) AND does NOT recover to 20 psig (due to check valve leakage),
THEN momentarily Throttle OPEN ICS-221 to restore INITIALS backpressure to 20-25 psig BEFORE recording data.
- f. WHEN a stable backpressure AND stable "B" S/G test pressure is achieved, THEN record on Attachment C:
S Test Rig Pressure 0 SG B Pressure 0 Measured Leakage 0 Calculated expected valve leakage. 01- eýýP_
- g. IF check valve does NOT seat, THEN shut ICS-144A AND manifold valve AND repeat steps 5.18.3 and / or 5.18.4, as required.
(Provide a set of initials for applicable steps performed on Attachment D.)
- h. IF after second attempt check valve has NOT seated THEN perform Attachment F.
IF after third attempt check valve has NOT seated, THEN contact test coordinator for further direction.
(In interim, continue with test).
5.18.5 SHUT test manifold outlet valve.
5.18.6 Ensure SHUT ICS-220.
5.18.7 Ensure SHUT 1CS-221.
Page 21 of 38 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS 5.18.8 IF seat leakage test of 1CS-476AA is NOT to be performed, THEN restore Feed Line Drain Valves.
- b. Disconnect test manifold at ICS-145C AND install cap.
- c. Ensure SHUT ICS-144A remove hose AND install cap.
- 1. While depressing I CS-481 reset, start ungagging ICS-481.
- 2. Once started, release 1CS-481 reset switch AND fully ungag ICS-481.
- 3. Ensure ICS-481 is ungagged with a locked handwheel.
II IV
- f. Restore IC-198, Corrosion Product Monitor Panel FW Sample alignment as follows:
Notify Chemistry ISS-208, IC-198 Corrosion Product Manual Panel FW Sample Inlet will be returned to the "As found" position. 6 -*1 Restore 1SS-208, to "As found" position recorded in step 5.12.2 OR Attachment A as applicable. DIV __y I 5.19 When Testing is Complete 5.19.1 IF "B" S/G instrumentation blowdown is NOT required OR previously performed, THEN N/A step 5.19.2 Pag~e 22 of 38 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS 5.19.2 IF required for I&C "B" S/G instrumentation blowdown, THEN perform the following:
- a. Slowly lower "B" SIG pressure to between 75 AND 100 psig by throttling AF-4019 in MANUAL. 44-ciŽV
- b. Stabilize "B" S/G pressure between 75 AND 100 psig using AFW flow.
"* Throttle AFW flow as required, using AF-4019.
"* IF required to hold "B" S/G pressure, THEN establish "B" S/G blowdown flow as follows.
(N/A steps not used).
.4 i4iLA:'/
(a) OPEN IMS-5959, IHX-lB SG Blowdown Isolation.
(b) OPEN 1MS-2040, IT-26 SGBD Tank Outlet Control.
(c) Throttle 1MS-274, 1HX-1B SG Blowdown to IT-26 SGBD Tank Throttle.
(d) IF required, THEN start P-49 Blowdown Tank Pump.
- d. Notify I&C to blowdown "B" S/G instrumentation.
- e. Hold until notified by I&C of task completion.
/V),i/1!/ &L/
5.19.3 WHEN the test is complete, THEN reduce flow AND STOP P-38B, Aux Feedwater Motor-Driven Pump using 01 62A.
Page 23 of 38 CONTINUOUS USE
POLNT BEACH NUCLEAR PLANT IT 300B ISERVICE TESTS
""; SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS INITIALS 5.19.4 WHEN test is complete, THEN secure "B" S/G Blowdown.
(N/A if NOT used for pressure control).
¢5V
- b. Stop P-49 Blowdown Tank Pump.
- c. SHUT IMS-2040, IT-26 SGBD Tank Outlet Control.
5.19.5 IF condensate transfer hose is no longer required,
- THEN perform restoration steps of 01150.
5.20 Recovery From Leak Check 5.20.1 Contact Chemistry to determine if discharge permit required for draining steam line AND "B" SIG.
2 Required NOT Required X 5.20.2 IF required, THEN drain "B" SIG to desired level using 01-124, Draining "B" SIGs, U1.
Page 24 of 38 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS CAUTION Do NOT open IMS-2015, 1HX-1B SG HDR atmospheric steam dump control, until steam lines have been drained.
5.20.3 Drain "B" S/G steam line to blowdown tank as follows:
- b. IMS-239, lHX-lB SG Drain to IT-26 Blowdown Tank.
- e. Operate the following as required to maintain SGBD Level.
(NIA steps NOT used).
- 2. P-49 Blowdown Tank Pump.
Page 25 of 38 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B fINSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS INITIALS 5.20.4 WHEN steam line has been drained to Blowdown Tank, THEN, realign valves.
Valve Description Restoration Initials IV position Initials LOCKED 1MS-248 IHX-lB SG Vent SHUT " 9.i"3 1HX-1IB SG Header Drain to 1T-26 SGBD One Turn .
1MS-276 Tank Throttle OPEN IHX-1B SG Header Drain to IT-26 SGBD IMS-239 Tank SHUT 5.20.5 Perform the following valve restoration alignment.
Valve Description Restoration Initials IV position Initials 1CS-144 1HX-1B SG 1CS-481 Regulator Bypass Inlet OPEN /2?
1CS-147 IHX-1B SG ICS-476 Regulator Inlet OPEN IMS-272 lHX-1B SG Blowdown to 1T-26 SGBD Tank SHUT SHUT &
ICS-220 Feedwater Leakage Check Test Line LOCKED ______-_
SHUT &
1CS-221 Feedwater Leakage Check Test Line. LOCKED JD4 LOCKED 1MS-237 P-29, AFP/Radwaste Steam Isolation (B-1) OPEN 5.20.6 Maintain pressure / temperature per Shift Management.
5.20.7 Special test rig(s), as shown in Attachment B removed AND stored in U2 TH El. 26' South.
5.20.8 Ensure PI's in step 2.2 are removed AND returned to I&C MTE room.
5.21 SRO to record TIME/DATE test was completed at step 6.1.1.
Page 26 of 3:8 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B "INSERVICETESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS INITIALS 6.0 ANALYSIS 6.1 Operations 6.1.1 Comparisons with allowable ranges of acceptance criteria test valiqes complete AND all Attachments are complete.
SRO Date/Time 6.1.2 Forward completed procedure to IST Coordinator/Cognizant Engineer via Operations Specialist.
NOTE: To be completed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> of test completion by IST coordinator or his representative.
6.2 IST Coordinator 6.2.1 Ensure all acceptance criteria comparisons are made AND all attachments are complete. SN/A ,'P 6.2.2 Any requirements for corrective action?
(IF yes, THEN give details in the IST Remarks section.)
(Circle one) NO 6.2.3 IF acceptance criteria needs updating, THEN initiate a procedure revision. jvIA Data Analyzed By Date/Time IST Remarks:
.. L'G &,k :& JLj.
A*A4 . is- .,Oi7YW',V',)*'
C(14- 7 Page 27 of 38 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B "INSERVICETESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT 1 Ops..Remarks:/
4z',%
6,./_.., m,*.*/*
"" ,,'vimsi 7 0?
AI,.*,.
T- I)eJ S. . Per P'*nt. Sign) 5 Irnvas Performei (P d Si initials Performer (Pijnt and Si n itials
- ,<." Pr-o-,',,'°rnt and Sign) Date Time I s Lr-,RýI X -9; zcv! 'r57 Revievw'r (Print and Sign) Date Time Initials Page 28 of 38 CONTINUOUS USE
,' POINT BEACH NUCLEAR PLANT IT 300B INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT 1
7.0 REFERENCES
7.1 WEP-91-102, Attachment, "Point Beach Units 1& 2 Safety Evaluation and Report Consolidation" Minimum Temperature for Pressurization.
7.2 Technical Specifications and FSAR figures.
7.2.1 TRM 3.7.3. Steam Generator Pressure and Temperature (P/T) Limits 7.2.2 TS 3.6.3, Containment Isolation Valves 7.2.3 TS 3.7.6, Condensate Storage Tank 7.2.4 TS 5.5.7, Inservice Testing Program.
7.2.5- FSAR Figures 5.2-3 and 5.2-4 7.3 ASME OM Code 95Ed. /96A, Code for Operation and Maintenance of Nuclear Power Plants.
7.4 Procedures.
7.4.1 OI-62A, Motor-Driven Auxiliary Feedwater System (P-38A & P-38B).
7.4.2 01-150, Heating the Condensate Storage Tanks.
7.4.3 01-124, Draining Steam Generators, Unit 1.
7.5 Drawings 7.5.1 M-201 Sheet 1, Main and Reheat System.
7.5.2 M-201 Sheet 3, S.G. Blowdown System.
7.5.3 M-202 Sheet 2, Feedwater System.
7.5.4 M-217, Sheet 1, Auxiliary Feedwater System, Unit 1.
7.5.5 M-222, Sheet 1, Secondary sample system 7.6 Miscellaneous procedures and forms 7.6.1 CL-13A, Main Steam Valve Lineup Unit 1 Page 29 of 38 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B "INSERVICETESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I 7.6.2 PBF-2051, Steam Generator Blowdown Flow Rate Log Sheet.
I 7.6.3 TLB-34, T-24A/T-24B Condensate Storage Tanks 8.0 BASES B-i, SCR 99-1106, Administrative Red Locks of closed system boundary valves.
Page 30 of 38 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I ATTACHMENT A Main Feed Line Fill And Flow Indicator Installation 1.0 Fill of Main Feed Line B:
I 1.1 Record As Found Position AND align the following valves:
Valve Component Description As Found Required INITIALS Position Position ICS-147 1HX-1B SG ICS-476 Regulator Inlet SHUT MIA I 1CS-148 IHX-IB SG 1CS-147 Regulator Inlet Bypass SHUT 1CS-145 IHX-1B SG 1CS-476 Regulator Outlet OPEN T" ICS-144 1HX-IB SG ICS-481 Regulator Bypass Inlet SHUT 1CS-144A I SG 1CS-481 Regulator Bypass Line nHX-1B SHUT &
Drain CAPPED ICS-143 1HX-1B SG 1CS-481 Regulator Bypass Outlet OPEN 1CS-481 1HX-1B SG 1CS-476 FW Regulator Bypass GAGGED Control OPEN ICS-145A I1HX-21A/B HP FWH 5A/5B Out SG FW OPEN Sample Root Isol ICS-145B IHX-21A/B HP FWH 5A/5B Outlet SG FW SHUT Sample .__
ICS-145C IHX-2 1A/B HP FWH 5A/5B Header Drain SHUT &
"" CAPPED */P ICS-145E 1C-198 Corrosion Product Monitor Panel FW OPEN WIN T Sample Isolation 1CS-180A iHX-IB SG Chemical Injection Second Off SHUT SHUT &
IHX-IB SG Sampling Second Off Isolation CAPPED ICS-178A CAPPED UNLOCK ICS-220 Feedwater Leakage Check Test Line ED &
OPEN UNLOCK '
ICS-221 Feedwater Leakage Check Test Line ED &
OPEN Page 31 of 38 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B LNSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I ATTACHMENT A I MAIN FEED LINE FILL AND FLOW INDICATOR INSTALLATION (Cont.)
INITIALS 1.2 Isolate IC-198, Corrosion Product Monitor Panel by:
1.2.1 Notify Chemistry ISS-208, 1C- 198 Corrosion Product Monitor Panel FW Sample Inlet will be shut for IT-300B.
1.2.2 Record as found position of I SS-208 (________
1.2.3 SHUT 1SS-208.
1.3 Perform the following:
1.3.1 Remove cap from 1CS-144A, IHX-lB SG ICS-481 Regulator T--ý Bypass Line Drain.
1.3.2 Connect a DI water hose between DI-9 1, Demineralized Water Hose Connection AND 1CS-144A.
1.4 To commence fill of Main Feed Line B OPEN DI-91 AND I CS-144A I 1.5 WHEN level increase indicated on 1LT-470A OR 1LT-470B, THEN SHUT following valves: (To partially stroke open 1CS-476AA, AND 1CS-476BB)
"* ICS-220, Feedwater Leakage Check Test Line
"* ICS-221, Feedwater Leakage Check Test Line 1.6 WHEN second level increase "B' SIG is indicated on 1LT-470A OR 1LT-470B, THEN SHUT the following valves:
"* DI-91 ii?::'
"* ICS-144A. 2 Pagre 32 of 38 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B
" - hINSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I ATTACHMENT A I MAIN FEED LINE FILL AND FLOW INDICATOR INSTALLATION (Cont.)
INITIALS 1.7 Disconnect hose at DI-91 AND route to local floor drain AND secure to prevent end whip.
NOTE: Step 2.0 may be performed concurrently if desired.
1.8 Return to step 5.4. Milli NOTE: Same test manifold to be used on each feed line and feed lines to be tested sequentially.
2.0 Attach Flow Indicator Test Manifold 2.1 Remove cap from 1CS-145C, IHX-21A/B HP FWH 5A/5B Header Drain 2.2 Attach flow indicator test manifold to 1CS-145C using Attachment B as a guide.
2.3 Route test manifold effluent hose to a local floor drain AND secure to prevent end whip.
2.4 Ensure test manifold outlet throttle valve SHUT.
Page 33 of 38 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B "INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I ATTACHMENT B I FLOW INDICATOR TEST RIG 1.0 3/4 inch ICS Union 2.0 Omega flow meter, Model No. FL-7325; Max pressure: 3000 psig; Max temperature: 240'F; Flow range: 2.0-25 gpm (water) 3.0 Pressure gauge, 0-600 psig 4.0 3/4 inch Throttle valve 5.0 Drain hose rated for greater than OR equal to 500 psig at 250 oF.
0 FD I0S-1450 Pace 34 of 38 CONTINUOUS USE
- POINT BEACH NUCLEAR PLANT IT 300B LINSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS ATTACHMENT C TEST DATA SHEET 5 17/58-1.0 Record measured valve leakage at test AP from sections 5.17 & 5.18.
5.17/5.18 2.0 Calculate valve leakage expected at 1000 psid by dividing normal operating pressure by test pressure differential pressure (AP) and multiplying square root of value times measured leakage value at test AP.
2.1 Record test data AND calculations results in table below:
5.17/5.18 NOTE: DP="B" S/G pressure minus Test Rig Pressure.
F1000psig x Measured leakage value = Leakage at 1000 psid DP NOTE: A leak rate of about 3.5 gpm at 500 psid will calculate out to about 5 gpm at 1000 psid 3.0 IF calculated leakage rate of any check valve at 1000 psid exceeds administrative limit of 5 gpm, THEN declare applicable valve inoperable AND notify engineering.
5.17/5.18 Measred Measured Calculated Leakage < 5gpm Steps Valve No. Test Rig S/G "B" '4" (psig) Leakage (1000 psid) (circle one)
Pressure Pressure (gpm) (1 pm) 5.17.3.e G
- OR ICS-476AA [W1:. Sat/Unsat 5.17.4.f 5.18.3.e S4-/ 0 ORl ICS-476BB WI.A- I * ." Sat/Unsat 5.18.4.f 1_
Page 35 of 38 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 300B "INSERVICETESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I ATTACHMENT D MULTIPLE STEP PERFORMANCE 1.0 This attachment shall be completed to document multiple step performance. A separate copy of this attachment shall be prepared for each step series requiring multiple performance. All copies of this attachment shall be attached to this procedure when the procedure is complete.
2.0 Refer to procedure steps when performing this attachment.
3.0 List procedure steps by number, including adequate spaces to record initials, as appropriate. For components requiring independent verification or concurrent checks, provide for such checks on the attachment.
4.0 Complete the attachment by peorming the procedure steps and recording the required data.
Valve Number/Step-sequence: Date:_
Step Initials Initials Initials Initials Initials Initials Initials Pagre 36 of 38 CONTINUOUS USE
"., ' POINT BEACH NUCLEAR PLANT IT 300B INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT 1 INITIALS ATTACHMENT E I ICS-476AA D/P Reestablishment 1.0 SHUT ICS-143, IHX-1B SG ICS-481 Regulator Bypass Outlet.
2.0 OPEN 1CS-144A, IHX-lB SG ICS-481 RegulatorBypass Line Drain, to drain line between 1CS-143 AND 1CS-144, 1HX-lB SG ICS-481 Regulator 0w Bypass Inlet.
3.0 SHUT 1 CS-144A. o iw-.
4.0 Rapidly OPEN ICS-143 to seat check valve.
5.0 Repeat steps 5.17.3 and / or 5.17.4, as required. 4N1 1.V (Provide a s&t of initials for applicable steps performed on Attachment D.)
Page 37 of 38 CONTINUOUS USE
"POENTBEACH NUCLEAR PLANT IT 300B INSERVICE TESTS SAFETY RELATED Revision 10 STEAM GENERATOR B MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS INITIALS ATTACHMENT F I ICS-476BB D/P Reestablishment 1.0 SHUT ICS-143, 1HX-IB SG ICS-481 Regulator Bypass Outlet.
2.0 OPEN 1CS-144A, IHX-1B SG ICS-481 Regulator Bypass Line Drain, to drain line between ICS-143 AND ICS-144, 1HX-1B SG 1CS-481 Regulator Bypass Inlet.
o 3.0 SHUT 1CS-144A.
O 4.0 Rapidly OPEN ICS-143 to seat check valve.
5.0 Repeat steps 5.18.3 and / or 5.18.4, as required. 6? jZ' (Provide a s~t of initials for applicable steps performed on Attachment D.)
Pagre 38 of 38 CONTINUOUS USE