ML030770396

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Procedure IT-300A, Rev. 9
ML030770396
Person / Time
Site: Point Beach NextEra Energy icon.png
Issue date: 09/18/2002
From:
Nuclear Management Co
To:
Office of Nuclear Reactor Regulation
References
FOIA/PA-2003-0094
Download: ML030770396 (38)
v • d • e


Text

Point Beach Nuclear Plant P Y PARTIAL PROCEDURE PERFORMAN CE '1*

Page I of Ptocedure Number/Title _jf-30061 Unit 9 Revision J Work Order Nuniber Temporary Change Number Purpose/Description/Justification of Partial Performance (Vtach ac.diJonal pages if necessary).

UALL~-~

&b~L~ ~cSys k,-- LW- nei-s7I Check one of the following which must apply in order to continue:

XEquipment out-of-service or inoperable Equipmcnt not required to be operated E Procedure being aborted Answer the following for the requested partial performance: YES NO

1. Will this request be permanent or more than one-time use? Li1[
2. Will this request involve a change of intent? (ref. NP 1.2.3) D-A (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? LI '
4. Will this request alter or affect the applicable initial conditions for equipment being,I worked on or evolution in progress? (for test procedures, all initidil conditions shall be 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 instructio/ 4 s need to be added  ? .,."

Requested By (print and sign _ iL j$Jj_ . Date 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:

1. 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 perforined (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 After approvqt~s, this completeeboroýhhlllbe controlledas a recordand remain attachedto proceduresrequiringsignoffs or data recording. I PBF-0026m Revision I 22-1/01

Reference:

NP 1.1.4 7";1

I .

Point Beach Nuclear Plant PROCEDURE RECORD AND FIELD COPY TRACKING Record/Field Copy Identification Field Copy Nfimber RED - Record Copy; BLACK - Field Copy Procedure Number IT- 300 A Unit 1 Revision Number 9 Procedure Title S / G "A" MAIN FEED LINE CHECK VALVES (CSD) Revision Date AUG 22, 02 Proc dure-RevisiqD Checked and et+. Tracingzhecked for Temporary Changes:

By Date _____"

Record Copy Holder/Location LOCAL TEST Ok~RATOR FIELD COPY DISTRIBUTION Copy No. Holder/Location Issue Date Return Date 1 CONTROL ROOM Z/Z.I 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 Revision 2 2/21101

Reference:

NP 1.1.4

1*

IT 300A STEAM GENERATOR A MAIN FEED LINE CHECK VALVES (COLD SHUTDOWN)

UNIT 1 DOCUMENT TYPE: Technical CLASSIFICATION: Safety Related REVISION: 9 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

POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED "Revision9 STEAM GENERATOR A 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 Steam Generator A 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-466AA, 1HX-IA SG Check - cM T7"iT ICS-466BB, 1HX-1A SG Check - .

1.2 To provide the conditions for blowdown of "A" S/G instrumentation, in Mode 5 conditions.

2.0 PRERtQUISITES 2.1 Special test rig, Omega flowmeter, Model No. FL-7325, as shown in Attachment B are available, (stored in U2 TH El. 26' south).

2.2 Test rig pressure indicator (PI's) AND flow cal dates checked current. (Pr's are stored in I&C MTE room).

Test rig: '70(

PI No# iCT t T- Cal Due Date FINo# iCTI -)'2-s CalDueDate IC/,/o07 2.3 Handheld Pyrometer AND Adapter Cable. (C-59)

ID No: c4S,Dý-152- Cal Due Date X2_____

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 Test manifold drain hoses should be routed to a local floor drain AND secured to prevent end whip, for personnel safety. These hoses 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 "A" S/G metal temperature must be greater than OR equal to 70'F before pressurization greater than 200 psig per TRM 3.7.3.

Page 2 of 35 CONTINUOUS USE

"POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I 3.4 Do NOT exceed 840 psig in "A" S/G.

3.5 Do NOT OPEN IMS-2016, lHX-lA SG Hdr Atmospheric Steam Dump Control, when the steam lines are filled except to avoid exceeding 840 psig.

3.6 Do NOT use 1MS-2016, 1HX-lA SG Hdr Atmospheric Steam Dump Control, as a vent path while filling "A" S/G.

Page 3 of 35 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A 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:

The normally scheduled callup.

Work Order No. "-21 NOTE: If this test is being performed to satisfy PMT or off-normal frequency requirements, Shift Management may N/A 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 80-1 10°F.

4.3 At least 1 "A" S/G Main Steam Safety Valve must be operable.

Circle operable Safety valves.

M -2 0T MS IMS-2012 1IM-2013 4.4 Any safety valve removed must have full pressure blank flange installed.

4.5 "A" S/G hand hole covers installed.

4.6 "A" S/G secondary manways installed.

4.7 "A" S/G feed line intact FROM main and bypass feedwater reg. valves inlet isolation TO "A" S/G.

COý PTINUOUS USE Page 4 of 35

fl POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT 1 INITIALS 4.8 All "A7 SIG 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 "A" S/G blowdown as a drain flow path AND for pressure control.

"* To determine chemical addition requirements AND to have required chemicals available at P-38A Chemical Addition Pot.

4.10 Unit I in Mode 5, 6, OR Defueled 4.11 "A" S/G wide range level, LT-460A OR LT-460B, operable.

I 4.12 PBF-2051, Steam Generator Blowdown Flow Rate Log Sheet, is available if required.

4.13 P-38A, Aux Feedwater Motor-Driven Pump, AND flow path to "A" S/G is available with no outstanding clearances OR associated work is in progress.

"WCC 4.14 "A" S/G blowdown system has no outstanding clearances, no associated work in progress AND is available to receive drains from steam line A AND "A" S/G blowdown.

WCC 4.15 Permission to Perform Test The conditions required by this test are consistent with required plant conditions including equipment operability. Permission is granted to perform this test.

_/

DSS L Time J q S-7 Date Page 5 of 35 CONTINUOUS USE

'POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS 5.0 PROCEDURE 5.1 PT-468, 1HX-IA SG Steam Pressure Channel, in service.

5.1.1 1MS-468, IHX-lA SG Header PT-468 Root. OPEN 5.1.2 1MS-468A, IHX-1A SG Header PT-468 2nd Off Isolation. OPEN 5.1.3 PT-468, 1HX-IA SG Steam Pressure Channel. OPERABLE/ L 5.2 Ensure one OR both SG Pressure Transmitter Channels in service PT-469, OR PT-482, (mark unused channel as N/A) 5.2.1 1MS-469, 1HX-IA SG Header PT-469 Root. OPEN 5.2.2 1MS-469A, IHX-1A SG Header PT-469 2nd Off Isolation. OPEN PT-469, 1HX-IA SG Pressure Transmitter. OPERABLE 5.2.3 OR oc.

5.2.4 1MS-482, 1HX-1A SG Header PT-482 Root. OPEN 5.2.5 1MS-482A, 1HX-1A SG Header PT-482 2nd Off Isolation OPEN {/

5.2.6 PT-482, 1HX-1A SG Steam Pressure Transmitter. OPERABLE since shutdown, 5.3 IF feed line has been drained THEN perform main feed line fill per Attachment A, step 1.0.

Page 6 of 35 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT 1 INITIALS 5.4 Obtain "A" S/G metal temperatures by performing steps 5.4.1 OR 5.4.2.

(N/A 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 "A" S/G missile shield wall AND record readings:

a. TE-2023A, 1HX-1A SG Shell Temperature Thermocouple Above feedwater inlet OF
b. TE-2023B, IHX-1A SG Shell Temperature Thermocouple Below transition cone OF
c. TE-2023C, IHX-1A SG Shell Temperature Thermocouple Above tubesheet OF 5.4.2 Using hand held pyrometer, obtain metal temperatures at "A" S/G upper manway OaR upper level tap penetration.

CAUTION A minimum 70" F test temperature is required to pressurize SG greater than 200 psig. (Secondary to primary leak test) 5.5 IF "A" S/G temperatures less than 70"F, THEN establish "A" S/G level less than OR equal to 360 inches.

efr5 5.6 WHEN "A" S/G pressurized greater than 50 psig but less than OR equal to 100 psig, THEN arrange with I&C to blow down "A" S/G level transmitters, if required.

Page 7 of 35 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS 5.7 Record as found positions AND align "A" S/G for filling:.

As Found Required Valve Component Description Position Position Initials 1HX-81A SG Header Main Steam Stop Control . SHUT IMS-2018 valve "2;/" SHUT 1HX-1A SG Header MS-2017 Main Steam IMS-234 Stop Bypass kj,1q SHUT 1MS-231 IHX-IA SG Header ST-2029 Inlet SHUT (P7

  • OPEN IMS-34 HX-lA SG Header ST-2093 Second Off Isol. ,O. OPEN 4 uc* UNCAPPED 1MS-123A HX-1A SG Header ST-2093 Bypass Drain & OPEN NoeIMS-211 is on top of "A" SIG AND will be left in LO position with red lock and chain LOCKED IMS-211 1HX-1A SG Vent OPEN Note: 1MS-213 is inaccessible. Visual verification from remote area to check rising stem AND red lock is sufficient to satisfy

. position check.

/SHUT &

1MS-213 1HX-IA SG Vent Line Vent Penetration IVTC CAPPED IMS-223 1HX-lA SG Vent, outside containment - OPEN 1MS-219A 1HX-IA SG Blowdown Line Drain, inside L-SHUT &

cont. (C- CAPPED IMS-220 IHX-1A SG Blowdown Line Manual Isolation- r OPEN IMS-5958 1HX-1A SG Blowdown Isolation, inside cont. , AIR ON &

~~~~

_______ ~-t SHUT k)'_________________

IMS-2042 IHX-IA SG Header Blowdown Control "1"t-C AIR ON &

, ,,V OPEN IMS-265 1HX-1A SG Blowdown Isolation, outside k OPEN cont. __ _

IMS-271 lHX-1A SG Blowdown to 1T-26 SGBD Tank 0 *i OPEN _

IMS-273 1HX-IA SG Blowdown to 1T-26 SGBD Tank 1/4 turn Outlet V OPEN IMS-278 lHX-lA SG Blowdown to IHX-18AI/2 SHUT SGBD IHX IMS-286 1T-26 SGBD Tank Outlet OPEN I'. NI CONTINUOUS USE Page 8 of 35

POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS INITIALS As Found Required Valve Component Description Position Position Initipls 1MS-288 IT-26 SGBD Tank Outlet MS-2040 Inlet fi OPEN (h, 1MS-2040 IT-26 SGBD Tank Outlet Control-* SHUT 6, 1MS-296 P-49 Blowdown Pump Suction OPEN 6,1 IMS-300 P-49 Blowdown Pump Discharge C OPEN //

Note: Align at leait 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 1MS-303 F-64A Blowdown Filter Outlet Line Drain -2 SHUT '66 IMS-301 F-64A Blowdown Filter Inlet OPEN Oil IMS-304 F-64A Blowdown Filter Outlet OPEN F-64B blowdown filter 1MS-306 F-64B Blowdown Filter Inlet Line Drain .2 SHUT 1MS-307 F-64B Blowdown Filter Outlet Line Drain _ __SHUT 3_

I1MS-305 F-64B Blowdown Filter Inlet _' _OPEN Q14 1MS-308 F-64B Blowdown Filter Outlet & OPEN &

IMS-2099 Blowdown Filter System Outlet Control "-0if AIR OFF& ON BD Filter System to Condensate Demin Flow AIR OFF &

IMS-5954 Ctl, aligned to service water return header Al, OPEN BD Filter Sys Outlet to Service Water Return 1MS-311 Hdr OPEN I

I 5.8 Discharge permit to utilize "A" S/G blowdown flow path for pressure control obtained from Chemistry.

Required NOT Required 5.9 SHUT 1MS-2083, 1HX-1A SG Sample Isolation Control.

5.10 Set IMS-2016, lHX-1A SG Hdr Atmospheric Steam Dump Control, to 17Z 840 psig AND place controller in AUTO.

5.11 Ensure T-24A, South CST temperature 80-1 10°F.

Page 9 of 35 CONTINUOUS USE

'POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS 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 TLB 34).

NOTE: T-24A, South CST may be refilled per 01 150, Heating the CST, via transfer hose as necessary.

5.12 Fill "A" 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 /7 1HX-1A SG 1CS-466 Regulator Inlet t)e/7 SHUT ICS-149 ICS-150 lHX- IA SG I CS-149 Regulator Inlet SHUT SHUT___

Bypass ZIP___

1CS-151 1HX-IA SG ICS-466 Regulator Outlet , ,t OPEN _ _

ICS-151A 1HX-21A/B HP FWH 5AI5B Out SG SHUT &

FW Sample Root Isol CAPPED ICS-153 1HX-IA SG ICS-480 Regulator Bypass , /-7 SHUT Inlet0,__'

ICS-153A 1HX-IA SG 1CS-480 Regulator Bypass SHUT &

Line Drain CAPPED 1CS-154 OutletHX-1A SG CS-480 Regulator Bypass C!7/. OPEN 1CS-480 1HX-1A SG ICS-466 FW Regulator GAGGED

_____Bypass Control 'I(C'15t OPEN/1 ICS-167A 1HX-1A SG Chemical Injection Second SHUT Off Isolation 7 SHUT 1CS-169A ICS_169A 1HX-1A SG Sampling Second Off SHUT &

Isolation CAPPED ICS-218 Feedwater Leakage Check Test Line L. & HU 1CS-219 Feedwater Leakage Check Test Line UNLOCKED I_CS218_ & SHUT Pagre 10 of 35 CONTINUOUS USE

'POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS 5.12.2 Ensure the following valves are locked SHUT AF-30, P-38A/B AFP Discharge Crossconnect.

AF-43, P-38A/B AFP Discharge Crossconnect.

CAUTION To prevent pump motor breaker trip on overload, motor-driven pumps flow rate should NOT exceed 240 gpm. The minimum recirculation flow is 70 gpm 5.12.3 Using OI-62A, Motor-Driven Auxiliary Feedwater System (P-38A & P-38B) START P-38A, Aux Feedwater Motor-Driven Pump. ljq 5.12.4 Establish a 175-200 gpm fill rate to "A" A/G.

NOTE: At 510 inches wide range level, remaining "A" S/G and Main Steam header volume is 11,600 gal. This equates to 58 minutes of run time at 200 gpm.

5.12.5 WHEN "A" S/G wide range level at 510 inches, THEN record times below AND continue filling (175-200 gpm fill rate) "A" S/G for additional 40 minutes Time at 510 in ;___

Time at 510 in.+40 min _____

Time at 510 in.+50 min Al-b 5.12.6 WHEN at Time at 510 in + 40 min, THEN Throttle fill rate to approximately 100 gpm AND establish communication with operator at "A" S/G manual vent within Time at 510 in + 50 min.

Page I11 of 35 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS CAUTION Ensure AF-4007, P-38A AFP Mini Recirc Control opens when feed flow to "A" S/G is less than OR equal to 75 gpm.

NOTE: "A" SIG pressure on PPCS will show an increase when almost solid.

NOTE: Individual stationed at vent will have an indication (change in sound) coming from vent just prior to "A" S/G going solid.

5.12.7 Continue filling "A" S/G AND steam line. lrfg-

a. Just prior to going solid, minimize auxiliary feed flow.
b. WHEN water observed from vent, THEN STOP P-38A, Aux Feedwater Motor-Driven Pump.

5.12.8 SHUT 1MS-223, 1HX-1A SG Vent. c, 5.13 Ensure "A" 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) 0 5.13.3 Plug in adapter cable at thermocouple junction box located on "A" SIG missile shield wall AND record readings:

a. TE-2023A, 1HX-1A SG Shell Temperature Thermocouple Above Feedwater Inlet - OF.
b. TE-2023B, 1HX-IA SG Shell Temperature Thermocouple Below Transition Cone OF
c. TE-2023C, 1HX-1A SG Shell Temperature Thermocouple Above Tubesheet OF Page 12 of 35 CONTINUOUS USE

13OINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT ]

INITIALS 5.13.4 Using hand held pyrometer, obtain metal temperature at either "A" S/G upper manway OR at an upper level tap penetration.

(NA point NOT used.)

Upper manway Reading O°F

______" F Upper level tap penetration Reading 5.14 Pressurize "A" S/G to 500 psig.

5.14.1 Place AF-4012, P-38A AFP Discharge Control in MANUAL AND SHUT.

CAUTION To prevent pump motor breaker trip on overload, motor-driven pumps flow rate should NOT exceed 240 gpm. The minimum recirculation flow is 70 gpm.

5.14.2 Start P-38A, Aux Feedwater Motor-Driven Pump, AND ensure AF-4007, P-38A AFP Mini Recirc Control, OPENS.

5.14.3 IF blowdown of "A" 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. ii 5.14.4 Slowly raise "A" S/G pressure to between 75 AND 100 psig by throttling AF-4012 to as low a flow as practicable in MANUAL.

5.14.5 Stabilize "A" S/G pressure between 75 AND 100 psig using AFW flow.

a. Throttle AFW flow as required, using AF-4012.

Page 13 of 35 CONTINUOUS USE

"POINTBEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT 1 INITIALS

b. IF required to hold "A" S/G pressure, THEN establish "A" S/G blowdown flow as follows:

(N/A steps not used).

1. OPEN 1MS-5958, 1HX-1A SG Blowdown Isolation.

--ý/n .

2. OPEN 1MS-2040, 1T-26 SGBD Tank Outlet Control.
3. Throttle 1MS-273, 1HX-IA SG Blowdown to 1T-26 SGBD Tank Throttle.
4. IF required, THEN start P-49, Blowdown Tank Pump.

5.14.6 IF blowdown flow established to stabilize "A" S/G pressure, THEN record flow rate AND time on PBF-2051.

5.14.7 5.14.8 Notify I&C to blow down "A" S/G instrumentation.

Hold until notified by I&C of task completion above.

162I 5.14.9 Slowly raise "A" SIG pressure between 500 AND 520 psig by throttling AF-4012 to as low a flow as practicable in MANUAL.

5.14.10 Stabilize "A" S/G pressure between 500 AND 520 psig. using AFW flow AND, if required, "A" S/G Blowdown.

a. Throttle AFW flow as required, using AF-4012
b. IF required to hold "A" S/G pressure, THEN establish "A" S/G blowdown flow as follows.

(N/A steps not used).

1. OPEN 1MS-5958
2. OPEN 1MS-2040.
3. Throttle IMS-273.
4. IF required, THEN start P-49 Page 14 of 35 CONTINUOUS USE

'POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS INITIALS 5.15 Ensure Flow Indicator Test Rig connected to ICS-151A, IHX-21A/B HP FWH 5A/5B Out SG FW Sample Root Isol.

5.15.1 IF NOT connected, THEN connect per Attachment A, step 2.0.

5.16 Ensure effluent hose connected to 1CS-153A, 1HX-IA SG ICS-480 Regulator Bypass Line Drain.

5.16.1 IF NOT connected, THEN remove cap AND connect hose to 1CS-153A 5.16.2 Route hose to floor drain AND secure to prevent end whip.

5.17 Seat Leakage Test of I CS-466AA, 1HX-IA SG Feedwater Check CAUTION System is pressurized to 500 psig. All drain hoses must be restrained to prevent end whip AND personnel injury.

5.17.1 OPEN 1CS-219, Feedwater Leakage Check Test Line.

5.17.2 OPEN ICS-15IA, 1HX-21AIB HP FWH 5AI5B Out SG FW Sample Root Isol, AND record test manifold pressure.

5 3 5 psig XYJ/ALI4 5.17.3 While observing test manifold pressure perform the following:
a. Throttle OPEN manifold outlet valve until pressure drops rapidly to less than 100 psig, indicating 1CS-466AA, has seated.
b. SHUT OR Throttle manifold outlet valve as required to maintain a 20 to 25 psig backpressure on manifold pressure gauge.

Page 15 of 35 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS INITIALS

c. IF ICS-466AA 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-218, Feedwater Leakage Check Test Line, to restore backpressure to 20-25 psig BEFORE recording data. /1/A )5

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 "A" S/G test pressure is achieved, THEN record on Attachment C:

0 Test Rig Pressure 0 SG A Pressure 0 Measured Leakage 0 Calculated expected 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 1CS-153A, IHX-IA SG ICS-480 Regulator Bypass Line Drain, until manifold pressure drops rapidly to less than 100 psig, indicating 1CS-466AA has seated,
b. SHUT ICS-153A fA 4//V_1
c. IF full flow is established through 1CS-153A AND manifold pressure remains greater than 100 psig, THEN Throttle OPEN manifold outlet valve until I CS-466AA seats.
d. WHEN ICS-466AA has seated, THEN rapidly SHUT ICS-153A AND Throttle with manifold outlet valve, as required, to maintain 20 to 25 psig backpressure on manifold pressure gauge.

Page 16 of 35 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS

e. IF 1CS-466AA 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 1CS-2 18, Feedwater Leakage Check Test Line, to restore backpressure to 20-25 psig BEFORE recording data. a/NITALS

f. WHEN a stable backpressure AND stable "A" S/G test pressure is achieved, THEN record on Attachment C:

0 Test Rig Pressure S SG A Pressure S Measured Leakage 0 Calculated expected valve leakage.

g. IF check valve does NOT seat, THEN SHUT 1CS-153A AND manifold valve AND repeat steps 5.17.3 AND / OR 5.17.4, 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 E.

IF after third attempt check valve has NOT seated, THEN contact test coordinator for further direction.

(In interim, continue with test).

5.17.5 SHUT test manifold outlet valve.

5.17.6 Ensure SHUT ICS-219 Feedwater Leakage Check Test Line. /YXAg L3 5.17.7 Ensure SHUT 1CS-218 Feedwater Leakage Check Test Line.

5.17.8 IF seat leakage test of 1CS-466BB, IHX- 1A SG Feedwater Check, is NOT to be performed, THEN restore Feed Line Drain Valves as follows:

a. SHUT 1CS-151A, IHX-21A/B HP FWH 5A/5B Out SG FW Sample Root Isol.

I Page 17 of 35 CONTINUOUS USE

"POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS

b. Disconnect test manifold at ICS-151A AND install cap.

,li} 111/,

I I c. Ensure SHUT 1CS-153A remove hose AND install cap.

d. Ungag ICS-480, IHX-1A SG 1CS-466 FW Regulator Bypass Control.
1. While depressing ICS-480 reset, start ungagging 1CS-480.
2. Once started, release 1CS-480 reset switch AND fully ungag ICS-480.
3. Ensure ICS-480 is ungagged with a locked handwheel.

IV 5.18 Seat leakage Test of ICS-466BB, 1HX-IA 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 1CS-218, Feedwater Leakage Check Test Line.

5.18.2 Ensure OPEN ICS-151A, IHX-21A/B HP FWH 5A/5B Out SG FW Sample Root Isol, AND record test manifold pressure.

570 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 1CS-466BB has seated.
b. SHUT OR Throttle manifold outlet valve, as required, to maintain 20 to 25 psig backpressure on manifold pressure gage AND record on data sheet.

Page 18 of 35 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS

c. IF I CS-466BB 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 I CS-219, Feedwater Leakage Check Test Line to restore backpressure to 20-25 psig BEFORE recording data. /V/4 ,;'

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 "A" S/G test pressure is achieved, THEN record on Attachment C:
  • Test Rig Pressure
  • SG A 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 ICS-153A until manifold pressure drops rapidly to less than 100 psig, indicating 1CS-466BB, has seated. _/,-__
b. SHUT 1CS-153A.
c. IF full flow is established through 1CS-153A AND manifold pressure remains greater than 100 psig, THEN Throttle OPEN manifold outlet valve until I CS-466BB seats.
d. WHEN ICS-466BB has seated, THEN rapidly SHUT 1CS-153A AND Throttle with manifold outlet valve, as required, to maintain 20 to 25 psig backpressure on manifold pressure gauge. A/1 Page 19 of 35 CONTINUOUS USE

"POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS

e. IF 1CS-466BB 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 1CS-219, Feedwater Leakage Check Test Line, to restore backpressure to 20-25 psig BEFORE recording data. ._____"__

f. WHEN a stable backpressure AND stable "A" S/G test pressure is achieved, THEN record on Attachment C:

"* Test Rig Pressure

"* SG A Pressure

"* Measured Leakage

"* Calculated expected valve leakage. ,'/! *5

g. IF check valve does NOT seat, THEN SHUT 1CS-153A AND manifold valve THEN repeat Steps 5.18.3 and / or5.18.4, 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 lCS-218, Feedwater Leakage Check Test Line. ,', 6dr.

5.18.7 Ensure SHUT 1CS-219, Feedwater Leakage Check Test Line. ___,_____

5.18.8 IF seat leakage test of 1CS-466AA is NOT to be performed, THEN restore Feed Line Drain Valves as follows:

a. SHUT lCS-151A, 1HX-21A/B HPFWH 5A/5B Out SG FW Sample Root Isol.
b. Disconnect test manifold at 1CS-151A AND install cap.

Pace 20 of 35 CONTINUOUS USE

'POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT 1 INITIALS

c. Ensure SHUT ICS-153A remove hose AND install cap.

I

/d. Ungag ICS-480, 1HX-IA SG ICS-466 FW Regulator Bypass Control.

1. While depressing 1CS-480 reset, start ungagging 1CS-480.
2. Once started, release I CS-480 reset switch AND fully ungag 1CS-480.
3. Ensure ICS-480 ungagged with a locked handwheel.

I%

IV 5.19 When Testing is Complete 5.19.1 IF "A" S/G instrumentation blowdown is NOT required OR previously performed, THEN NIA step 5.19.2 5.19.2 IF "A" S/G instrumentation blowdown required for I&C, THEN perform the following:

a. Slowly lower "A" S/G pressure to between 75 AND 100 psig by throttling AF-4012 in MANUAL.
b. Stabilize "A" SIG between 75 AND 100 psig using AFW flow.

"* Throttle AFW flow as required, using AF-4012. PIP~

" I.F required to hold "A" S/G pressure, THEN establish "A" SIG blowdown flow as follows.

(N/A steps not used).

(a) OPEN IMS-5958, 1HX-1ASGBlowdown Isolation.

(b) OPEN 1MS-2040, IT-26 SGBD Tank Outlet Control.

Page 21 of 35 CONTINUOUS USE

'POINT BEACH NUCLEAR PLANT IT 300A SAFETY RELATED INSERVICE TESTS Revision 9 August 22, 2002 STEAM GENERATOR A MAIN FEED LINE CHECK VALVES (COLD SHUTDOWN) UNIT I INITIALS (c) Throttle 1MS-273, IHX-IA SG Blowdown to lT-26 SGBD Tank Throttle.

(d) IF required, THEN start P-49, Blowdown Tank Pump.

c. Place IMS-2016, 1HX-1A SG Hdr Atmospheric Steam Dump Control, to MANUAL.
d. Notify I&C to blowdown "A" S/G instrumentation.

r-'JA

e. Hold until notified by I&C of task completion.
f. Place IMS-2016 to AUTO.

5.19.3 WHEN test is complete, THEN reduce flow AND STOP P-38A, Aux Feedwater Motor-Driven Pump, using OI-62A.

5.19.4 WHEN test is complete, THEN secure "A" S/G Blowdown as follows:

(N/A if not used for pressure control).

a. SHUT 1MS-5958 *
b. Stop P-49
c. SHUT 1MS-2040. -
d. Position 1MS-273 to 1/4 turn OPEN.

5.19.5 IF condensate transfer hose is no longer required, THEN perform restoration steps of 01150. Ž4-i-5.20 Recovery from Leak Check 5.20.1- Contact Chemistry to determine if discharge permit required for drainiig steam line AND "A" SIG.

Required NOT Required 5.20.2 IF required, THEN drain "A" S/G to desired level using 01-124, Draining Steam Generators, Unit 1. ML Page 22 of 35 CONTINUOUS USE

IT 300A

'POINT BEACH NUC7LEAR PLANT SAFETY RELATED INSERVICE TESTS Revision 9 August 22, 2002 "STEAMGENERATOR A MAIN FEED LINE CHECK VALVES (COLD SHUTDOWN) UNIT I UNI11t\L INIT1IAL..,

CAUTION Do NOT open 1MS-2016, 1HX-1A SG Hdr Atmospheric Steam Dump Control UNTIL steam line have been drained.

5.20.3 Drain "A" S/G steam line to blowdown tank as follows:

a. 1MS-275, lHX-1A SG Header Drain to 1T-26 SGBD Tank Throttle. OPEN
b. 1MS-229, IHX-1A SG Header Drain to 1T-26 SGBD Tank.

OPEN c2W-,,1 7

c. 1MS-228, lHX-lA SG Header Drain and Trap isolation.

OPEN

d. 1MS-223, 1HX-1A SG Vent. OPEN W, M
e. Operate the following as required to maintain SGBD Level.

N/A steps NOT used.

1. 1MS-2040, 1T-26 SGBD Tank Outlet Control.
2. P-49 Blowdown Tank Pump.

Page 23 of 35 CONTINUOUS USE

' POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS INITIALS 5.20.4 WHEN "A" steam line drained to blowdown tank, THEN, realign following valves.

Valve Description Restoration Initials IV position Initials LOCKED csk -, (¢_ro IMS-223 IHX-IA SG Vent SHUT k65" 7m 1HX-IA SG Header Drain to 1T-26 SGBD One Turn Qlk I.

1MS-275 Tank Throttle OPEN 1)-S 1HX-1A SG Header Drain to 1T-26 SGBD CD -0" IMS-229 Tank SHUT 5.20.5 Perform the following valve restoration alignment.

Valve Description Restoration Initials IV position Initials 1CS-153 1HX-IA SG 1CS-480 Regulator Bypass Inlet OPEN Ot ,- P-D 1CS-149 1HX-IA SG ICS-466 Regulator Inlet OPEN P.B IMS-271 1HX-1A SG Blowdown to 1T-26 SGBD Tank SHUT SHUT&& * .r, 1CS-218 Feedwater Leakage Check Test Line LOCKED o CXt.

SHUT & /4'r--:, O LOCKED L j 1CS-219 Feedwater Leakage Check Test Line. _______

LOCKED )

IMS-235 P-29, AFP/Radwaste Steam Isolation (B-1) OPEN 5.20.6 Maintain pressure / temperature per Shift Management direction.. /K2 5.20.7 IF NOT needed for "B" S/G testing THEN special test rig(s), as shown in Attachment B, removed AND stored in U2 TH El. 26' south.

5.20.8 Ensure Pr's in step 2.2 removed AND returned to I&C MTE room.

( 5.21 SRO to record TIMEIDATE test completed at step 6. 1.1.

4J1\r Page 24 of 35 CONTINUOUS USE

  • POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT 1 INITIALS 6.0 ANALYSIS 6.1 Operations 6.1.1 Comparisgns with allowable ranges of acceptance criteria test va ues -pe-tSARND-alltichments are ct 7rnp ar co DateTete.

"- -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.

6.2.2 Any requirements for corrective action?

(LF yes, THEN give details in the IST remarks section.) J2 (Circle one) YES 6.2.3 IF acceptance criteria needs updating, THEN initiate a procedure revision. .WA/,

.Zo.olD .2t04i Data An.-zed By Date/Time IST Remarks:

Page 25 of 35 CONTINUOUS USE 'A

' POINT BEACH NUCLEAR PLANT IT 300A LINSERVICE-TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I OPS Remarkst ":S-z 7-( 1- tL9[-27 ,

Y,*

eC e~z- C)'*-2~ h~

1:,v A x_.,-r-( 6*UCc/(

,--), wed

'sccA Tr-7.

e_ [ /M' 1 C,.-/c- 1 oY f~co(

It)& }.- , lt ,--

/ _

Performned By*

Performer (Print d te rime ials IKJ 31,/Pe*9former (Pfriffaj p Jate Time S /"1 N 6 o / a I A ,, a1 t ,~Performer (Print and S ignYX) Date Time U4J'.A I'L1.A.4 i, -

IM .

t 4 -d\

... T Performer "F rmr int u

adSi Sian) Date/Time Date Time 4rffa Vnii isi Date Time Initials t4'Ze MltclAfff(I 02,;AZ / 5f.

Page 26 of 35 CONTINUOUS USE

'POINT BEACH NUCLEAR PLANT IT 300A "INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I

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 FSAR Figures 5.2-3 and 5.2-4 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 TRM 3.7.3. Steam Generator Pressure and Temperature (P/T)

Limits 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.

I 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 Pace 27 of 35 CONTINUOUS USE

'POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I 7.6 Miscellaneous Procedures And Forms 7.6.1 CL-13A, Main Steam Valve Lineup Unit I I

7.6.2 PBF-205 1, Steam Generator Blowdown Flow Rate Log Sheet.

7.6.3 TLB-34, Condensate Storage Tank (T-24 A/B).

8.0 BASES B-I, SCR 99-1106, Administrative Red Locks of closed system boundary valves.

Page 28 of 35 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT 1 INITIALS ATTACHMENT A I MAIN FEED LINE FILL AND FLOW INDICATOR INSTALLATION 1.0 Fill Main Feed Line "A":

1.1 Record As Found positions AND align the following valves:

As Valve Component Description Found Position Position Initials 1CS-149 1HX-1A SG 1CS-466 Regulator Inlet SHUT ,/A ICS-150 1HX-1A SG 1CS-149 Regulator Inlet SHUT Bypass ICS-151 1HX-1A SG 1CS-466 Regulator OPEN Outlet 1CS-151A 1HX-21A/B HP FWH 5A/5B Out SG SHUT &

FW Sample Root Isol CAPPED ICS-153 1HX-1A SG 1CS-480 Regulator SHUT Bypass Inlet 1CS-153A IHX-1A SG 1CS-480 Regulator SHUT &

Bypass Line Drain CAPPED 1CS-154 lHX-1A SG ICS-480 Regulator OPEN Bypass Outlet ICS-480 1HX-1A SG 1CS-466 FW Regulator GAGGED Bypass Control OPEN 1CS-167A 1HX-1A SG Chemical Injection SHUT Second Off Isolation ICS-169A 1HX-1A SG Sampling Second Off SHUT &

Isolation CAPPED UNLOCKED ICS-218 Feedwater Leakage Check Test Line &NOPEN

& OPEN UNLOCKED ICS-219 Feedwater L I Leakage Check Test Line I& OPEN 1.2 Perform the following: \

N 1.2.1 Remove cap from ICS-153A.

1.2.2 Connect a DI water hose between DI-91, Demineralized Water Hose Connection AND 1CS-153A 1 Page 29 of 35 REFERENCE USE

POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I ATTACHMENT A I MAIN FEED LINE FILL AND FLOW INDICATOR INSTALLATION INITIALS 1.3 To commence fill of "A" main feed line perform the following:

1.3.1 OPEN DI-9 1.

1.3.2 OPEN 1CS-153A.

1.4 WHEN level increase noted in 1LT-460A OR 1LT-460B THEN SHUT 1CS-218 AND ICS-219 to partially stroke OPEN 1CS-466AA.

1.5 WHEN second level increase observed in 1LT-460A OR 1LT-460B, THEN SHUT DI-91 AND ICS-153A.

1.6 Disconnect hose at DI-91 1.6.1 Route to local floor drain.

1.6.2 Secure to prevent end whip.

NOTE: Step 2.0 may be performed concurrently if desired.

1.7 Return to step 5.4.

NOTE: The same test manifold may be used on each feed line if feed lines are to be tested sequentially.

2.0 Attach Flow Indicator Test Manifold 2.1 Remove cap from ICS-151A Pig 2.2 Attach flow indicator test manifold to ICS-151A using Attachment B as a guide. -,V1A'Rd tj 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 is SHUT.

Page 30 of 35 CONTINUOUS USE

  • '"POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I B

ATFFACHMENT ATTACHMENT B 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.

F 2

N-F5 FD ICS-151A Page 31 of 35 CONTINUOUS USE

' POINT BEACH NUCLEAR PLANT IT 300A

  • INSERVICE TESTS SAFETY RELATED Revision 9 August 22, 2002 STEAM GENERATOR A MAIN FEED LINE CHECK VALVES (COLD SHUTDOWN) UNIT I INITIALS ATTACHMENT C TEST DATA SHEET 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. 5.17/5 8" 2.1 Record test data AND calculations results in table below: 5.17/5.18 NOTE: D/P= Steam Generator pressure - Test Rig Pressure.

1000psig x Measuredeakagevalue Leakagcat 1000psid 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 "A" Steam Test Rig Generator Steps Valve No. Pressure Pressure (psig) t I 5.17.3.e :a,,i-,oa{* 5-0 T a C -,.#

OR 1CS-466AA VL.tý J440 5.17.4.f 5.18.3.e 5o09 OR 1CS-466BB 1U 184_ f_ .5 __ __

Pag,,,e 32 of 35 CONTINUOUS USE

  • 'POINT BEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I ATTACHMENT D I MULTIPLE STEP PERFORMANCE ATTACHMENT 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 performing the procedure steps and recording the required data.

Valve Number/Step sequence: Date:

Step Initials Initials Initials Initials Initials Initials Initials Page 33 of 35 CONTINUOUS USE

"POINTBEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS ATTACHMENT E ICS-466AA D/P REESTABLISHMENT 1.0 SHUT 1CS-154, 1HX-lA SG 1CS-480 Regulator Bypass Outlet.

2.0 OPEN ICS-153A, 1HX-1A SG ICS-480 Regulator Bypass Line Drain, AND drain line between 1CS-154 AND ICS-153, IHX-1A SG 1CS-480 Regulator Bypass Line Drain.

3.0 SHUT ICS-153A.

4.0 Rapidly OPEN 1CS-154 to seat check valve.

5.0 Repeat steps 5.17.3 and / or 5.17.4, as required.

(Provide a set of initials for applicable steps performed on Attachment D.)

Page 34 of 35 CONTINUOUS USE

"POINTBEACH NUCLEAR PLANT IT 300A INSERVICE TESTS SAFETY RELATED Revision 9 STEAM GENERATOR A MAIN FEED LINE CHECK August 22, 2002 VALVES (COLD SHUTDOWN) UNIT I INITIALS ATTACHMENT F I I CS-466BB D/P REESTABLISHMENT 1.0 SHUT ICS-154, 1HX-IA SG ICS-480 Regulator Bypass Outlet.

2.0 OPEN ICS-153A, 1HX-1A SG 1CS-480 Regulator Bypass Line Drain, AND drain line between 1CS-154 AND 1CS-153, 1HX-1A SG ICS-480 Regulator Bypass Inlet.

3.0 SHUT 1CS-153A.

4.0 Rapidly OPEN ICS-154 to seat check valve.

5.0 Repeat steps 5.18.3 and / or5.18.4 as required.

(Provide a set of initials for applicable steps performed on Attachment D.)

Page 35 of 35 CONTINUOUS USE

wisconsin hiectric orompany Point Beach Unit 1 Speed Load Report For IT-300 9/20/2002 20:32:45 VALVEID TEST DIR DATE , LOWER VALUE DB UPPER LAST  % PASS ICS-00466AA CV-C C 9/18/2002-1 5.00 1.436 N/A Yes ICS-00466BB CV-C C 9118/2002,/ 5.00 N/A Yes I

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