ML20137K945
| ML20137K945 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 07/22/1996 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17354B293 | List:
|
| References | |
| FOIA-96-485 JPN-PSL-SEMS-96, NUDOCS 9704070127 | |
| Download: ML20137K945 (1000) | |
Text
{{#Wiki_filter:. t JPN.PSL SEMS-96-051 Rav 0 Page 1 of 6 l I l Engineering Evaluation 2B Charging Pump Seal Leakage Evaluation ST LUCIE NUCLEAR PLANT UNIT 2 JPN-PSL-SEMS-96-051 ; l REVISION 0 j I FLORIDA POWER & UGHT COMPANY NUCLEAR ENGINEERING DEPARTMENT Safety Related 9704070127 970325 bj B DER 6 485 PDR
- JPN PSL SEMS-96-051 Rsv 0 Page 2 of 6
/ REVIEW AND APPROVAL RECORD
. PLANT ST LUCIE UNIT 2 TITLE Engineering Evaluation for 2B Charging Pump Seal Leakage Evaluation LEAD DISCIPLINE Mechanical ENGINEERfNG ORGANIZATION Site Ergineering Grouc REVIEW / APPROVAL:
INTERFACE TYPE GROUP PREPARED VERIFIED APPROVED FPL APPROVED
- INPUT REVIEWg MECH X N/A ELECT X ! N/A N/A N/A I&C X N/A N/A N/A N/A CIVIL X N/A N/A N/A N/A LIC X N/A N/A 73 N/A CSI X N/A N/A N/A N/A NUC FUEL X N/A N/A N/A N/A OTHER X N/A N/A N/A' N/A
- For Contractor Evals As Determined By Projects ** Review interface As A LEn On All 10CFR50.59 Evals and PLAs FPL PROJECTS APPROVAL: M DATE:
OTilER INTERFACES
JPN-PSL SEMS.96-051 Rsv 0 Page 3 of 6
't Engineering Evaluation for 2B Charging Pump Seal Leakage Evaluation l
< 1.0 BackgrourxFPumana This evaluation determines the maximum potential fluid flow past the 2B Charging Pump seals dunng the 7/13/96 I charging pump packing leak event. Based on the observations reported by field personnel dunng the leakage event, two different leakage paths occurred. The maximum leakage path of each path is determined in order to bound the total leakage flow. This evaluation demonstrates the observed leakage could not have exceeded 10 gpm. NRC notification was ; conservative but was not required. 2.0 Assumptions
- 1. Each charging pump sealis cooled by natural co'nvection flow to a seal tank in which level is monitored. During i the event, the 2B charging pump seal tank high level alarm did not actuate. The Mechanical Maintenance planner stated that the leak was " leaking bad enough to fill the seal tank in ten minutes".
- 2. Each charging pump's plunger area is within a casing that is routed to the floor drain. The " plunger pot" did not overfbw during the event. The maintenance planner stated that the middle stuffing box had a steady flow and the east one was dripping. No leak was identified on the west stuffing box. As dripping was observed from the east plunger, the water level within the casing was below the centerline of the plungers.
- 3. As the event had been ongoing for several minutes and the casing area is physically small (-2 cubic ft), the water level due to the packing seal leakage is assumed to have reached equilibrium at a level below the plungers.
3.0 Methodology The maximum flow of each path will be determined and summed to obtain the maximum leakage flow. 3.1 The leakage into the seal tank will be estimated based on the volume of the tank between the normal and high level alarm elevations and a fill time of 10 minutes. s 3.2 The leakage from the packing into the casing area will be estimated based on the elevation of the plunger centerline, the floor drain, and the piping line size assuming gravity drainage (plunger pot is vented to Gas l Vent Header). 4.0 Evaluation See Pages 4 & 5 5.0 Results This maximum potentialleakage is estimated at .40 gpm to the charging pump seal tank and 3.7 gpm to the floor drain in the charging pump room for a total combined flow of 4.1 gpm. 6.0 References
- 1. Isometne 2998-C-124 Sheet CH-126, Rev 3
- 2. Vendor Mariual 2998-15458, Rev 8
- 3. Streeter, Fluid Mechanics,5th Edition 4 Crane Co, Flow of Fluids Through Valves, Fittings, and Pipes, Technical Paper 410. 23rd Printing
- 5. Observations of M.J. Rentz as documented in 7/14/96 ccMail Message (Page 6)
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i . 4 ! JPN PSL SEMS 96-051 Rcv 0 PaQ4 6 of 6 'f a , e i Forward Header ! Subjects UNIT #2 OPERATIONS DEPT. CHRONOLOGICAL LOG Author: Mike Rents at USFPL810 l Date: 7/14/96 11:12 PM I 1' i
- TO: TONY MINOCAL FROM: M.J. RENTE, PLANNING
SUBJECT:
UNIT 82 CEG PP 23, PACKING LIAK ON 07/13/96 l (OPERATIW S DEPT. CERONOIOGICAL I4G 07/14/96, UNIT #2) THIS IS IN MAW 10 THE INCObtRECT IDG WHICH STATES THAT A PLANNER REPORTED A LEAK OF TEN GALIAMS PER MINUTE. I MAR CALLED DOW 1 0 1185 CEARGING PCMP ROON TO OBSERVE "C" THE LEAK ON THE 25 CBG PP, WEEN I OOr 11 TIRE TER PtMP MAS SEtFt DOWN AND 11EE CEG PP, THE CHARGING Pt3tp MAS ItMtING. I OBSERVED M LEAK ON THE *B" MIDDLE STUFFING EOE EAD A STEADY PLOW AND 11tB EAST ONE WAS DRIPPING. l NO LEAK ON 11EE WEST STUFFING BOK. l I ASKED EIN I r*mf.Tmn 11EE UNIT 82 CONTROL ROOM AND TALKED TO J. SANDY. IP ME MANTED ME TO ORIGINATE 11EE W/R FOR REPACK AND BE SAID 00 AEEAp. ER ASKED BOW BAD IT MAS T2arrgG AND I 1012 EIM, "IT IS LEAKING BAD I I ALSO TOIb HIM WEICH ENODGE TO FILL TER SEAL TANK IN TEN MINUTES.* STUFFING DOKES WERE T2ar mra. I BOPE THIS CLEARS UP THE MISUNDERSTANDING. y g = w-
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i Q ' s Operations Department Chronological Log - Unit 1 i 31 M 96 NUMSER: 579 NUC POWER: O DATE: 5/22/96 DELTA T POWER: 0 SHIFT: MID MWE: 0 BOARD RCO: GASSER CEA GROUP #: 0 DESM RCO HOSP POSITION: 0 NWE: LANGNEZ T AVG: 0 l ANPS: SIMPKINS BORON: 2154 < NPS: SANDY Xe WORTH: 0 j MODE: 6 CALCULATED SD MARGIN: >2000 l MAJOR MILESTONES OR ACTMTIES TO BE PERFORMED DURING THE SHIFT: TRAIN SWAP TIME LOG ENTRIES 19.00 ASSUMED THE SHIFT COMPLETED BOARD WALKDOWN 19:20 STARTED HVE 10A AND STOPPED HVE-10B IN PREPARATION FOR
- TRAIN SWAP" 19:23 "A* CCW RAD MONITOR BIS 19:28 HVS-4A BIS 19:30 HVE-10A BIS 20:00 TRANSFERRING DFO FROM 18 DOST TO 1 A DOST LAW OP-2200021 APP."B", TANK LEVELS AT START OF TRANSFER: 1 A DOST 13' 2.5"; 18 DCST 13' 3.5" 19.50 (LATE ENTRY) FREEZE SEAL ESTABLISHED ON LINE SI-113 20:36 SECURED TRANSFER OF DFO, TANK LEVELS AT COMPLETION OF TRANSFER:1 A DOST 14' 8";1B DOST 11' 10" 21:04 SECURED LRPW 1-96-36 21:20 STARTED HVE-8A AND STOPPED HVE-8B IN PREPARATION FOR
- TRAIN SWAP", DECLARED HVE-8A BIS 21:55 CLEARANCE HUNG AND FUSES ARE PULLED ON 182 480V LC LOAD SHED RELAY, THE FOLLOWING EQUIPMENT DECLARED OOS: 1 B FIRE PUMP; HVS-48; HVE-68; HVE-8B; HVE-9B; HVE 100; 1 B CHARGING PUMP 22:00 ANPS (SIMPKINS) HAS COMPLETED PRE-EVOLU~10N tshir!NG ON
- TRAIN SWAP" 22:20 STARTED
- TRAIN SWAP" TRANSFERRING ELECTRICAL LOADS LAW OP10910024 22:30 STARTED HVE-8A CONTAINMENT PURGE 22:35 COMPLETED
- TRAIN SWAP", DECLARED 182 LOAD CENTER AND 185,1B6,187 MCC OUT OF SERVICE, 1B1 LC IS POWERED FROM 1 A1 LC,1B2 LC IS POWERED FROM 1 A2 LC THRU 1 AB LC 1:00 DAMPER D-298 OOS FOR PM1.UBEllNSPECTION 1:20 CHEMISTRY REPORTS SFP Cb @ 2163 ppm, SAMPLED AT 0100 1
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Operations Department Chronological Log - Unit 1 31M96 1 21 DEENERGlZED 182/183 4100V BUSES, OPENED BKRf 20302 FEED FROM 1B S/U TRANSFORMER, DECLARED 182 & 183 4100V BUSES OOS 2:07 FREEZE SEAL ON SI-112, LOOP 1 A1 HEADER, BEING THAWED 2:15 COMPLETED APP"J" OF OP14WNo, PERIODIC SAFEGUARDS TEST, DFO CROSS CONNECTION TEST 2:50 FREEZE SEAL ON 12-SI-150,181 SIT OUTLET, BEING THAWED 4:15 THE FOLLOWING EQUIPMENT DECLARED OOS UE TO 1B DC BUS ALIGNED TO 1C DC BUS THRU 1 AB DC BUS LAW OP10000020: 18 DC BUS; 120 VAC BUS MB; 120 VAC BUS MD; *B" CHANNEL WR NI; "D* CHANNEL WR N1. ENTER TECH SPEC A.S. 3.9.2, NO OPERABLE WR NI CHANNELS, NO CORE ALTERATIONS IN PROGRESS, DEFUELED CONDITION 5:25 SECURED SENDING 1C' HUT TO 1B WMT IAW OP1-0510020, PLACED 1C HUT IN SERVICE 5:30 COMPLETED PUMPlNG 1B DOST TO
- FRAC" TANK; 1B DOST LEVEL g 4*
7.00 NO FURTHER ENTRIES THIS SHIFT TIME REVIEWER 1 COMMENTS 0:02 Reviewed log. J Sandy, NPS 5:56 Rowtowed Log P. lanees NPS 6'06 Reviewed log, C.D. Morpie 6.09 Reviewed log. J Sandy, NPS 6:15 Rewtowed log. H. Johnson l 6:37 Reviewed log, J. Scarole I i l l l l a
I Operations Department Chronological Log - Unit i 1 31 # 96 NUMBER: 580 NUC POWER: 0 DATE: 5/22/96 DELTA T POWER: O SHIFT: DAYS MWE: 0 BOARD RCO: CASSIDY CEA GROUP #: 7 DESK RCO de la Gunnha POSITION: 0 NWE: SMITH /GILES T AVG: 95 ANPS: MARTIN BORON: 2163 NPS: ISAACS Xe WORTH: 0 1 MOOE: 6 i CALCULATED SD MARGIN: >1720 PPM MAJOR MILESTONES OR ACTNITES TO BE PERFORIaED DURING THE SHIFT: GET THE 1 A LPSI PUMP BACK IN SERVICE TIME LOG ENTRES 7:00 COMPLETED BOARD WALKDOWN , ASSUMED SHIFT 8 47 STARTED LRP 1-96-37 IAW OP 1-0510022 10:10 COMPLETED STROKING DAMPER D-298, STROKE SAT 10:15 DECLARED D-29B AND MET TOWER 57.9 METER WIND SPEED BACK IN SERVICE 13.00 SPENT FUEL POOL BORON CONOENTRATION AT 2168 PPM PER CHEMISTRY 17:42 SECURED LRP 1-96-37 18:45 NO FURTHER ENTRIES THIS SHIFT TIME REVIEWER'S COMMENTS 18:30 Reviewed Log P. Isaeca NPS K 1
l Operations Department Chronological Log - Unit 1 31 # 96 NUMSER: 581 NUC POWER: O DATE: 5 @ 96 DELTA T POWER: O l SHIFT: MID MWE: 0 90ARD RCO: MIKE FLINN CEA GROUP #: 0 DESKRCO TIM GASSER POSITION: 0 NWE: MIKE LANGNES T AVG: ANPS: JIM TOTTON BORON: 2168 NPS: CHUCK LADD Xe WORTH: 0 MODE: 6 j CALCULATED SD MARGIN: >2000 i
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MAJOR MILESTOWES OR ACTIVITIES TO BE PERFORMED DURING THE SHIFT: l l TIME LOG ENTRIES 19:00 ASSUMED THE WATCH, COMPLETED BOARD WALKDOWN l 23:15 FREEZE SEAL WATCH REPORTS THAT HCV-3617 NOW HAS INTEGRITY 0:25 STOPPED HVE 16A, HVS 6, HVE 15 HVS 7 AND HVE 17, DECLARED FHB VENT PIG OUT OF SERVICE FOR l&C FUNCTIONAL TEST. ENTERED ACTION STATEMENT NO FUEL MOVEMENT OR CRANE OPS IN SFP. CHEMISTRY INFORMED. 0:45 SNPO REPORTS DEMIN WATER TK LEVEL IS 9 FT. STARTED FILLING DEMIN WATER TANK 1:00 BORON SAMPLES : SFP IS 2168 PPM AND CAVITYIS 2115 PPM. 4 1:30 FREEZE SEAL WATCH REPORTS THAT VALVES HCV-3645 AND HCV-3646 ARE BREACHED 1:35 COMPLETED FILLING DEMIN WATER TANK d 2:10 1B START-UP TRANSFORMER IS OUT OF SERVICE.
- 3
- 30 STARTING CONTROL ROOM PRESSURE PERIODIC TEST IAW OP 1 1900050, STARTED HVE 13A AND
- HVE 138.
3:40 STOPPED HVE 13A AND HVE 138, CONTROL ROOM PRESSURE TEST COMPLETED SAT 4:05 STARTING AREA RADIATION MONITORING SYSTEM ( ARMS) PERIODIC TEST OF CHANNELS # 7 & # 8 (FUEL POOL AREA MONITORS. CHANNEL #7 IS DOS. 4:15 FUEL POOL RAD MONITOR CHANNEL # 7 IS BACKIN SERVICE. 4:15 FUEL POOL RAD MONITOR CHANNEL #8 IS OUT OF SERVICE. 4'20 CHANNELS # 7 & # 8 AREA RAD MONITOR PERODIC COMPLETED SAT. CHANNEL #8 IS BACKIN SERVICE. 5.45 RSC-261 ( PLANT VENT P.I.G. )IS BACK IN SERVICE, 6:50 NO FURTHER ENTRIES THIS SHIFT TIME REVIEWER'S COMMENTS 1
i Operations Department Chronological Log - Unit 1 31 M96 1:30 Row 6ewed log. C.D. Ladd 5:38 Row 6ewed log. C.D. Ladd. . l 6:04 Reviewed log, C.D. marple 6:10 Reviewed log. H. Johnson 1 6:23 Rowtowed Log, J. Scarole i I e 1 4 0 2
CHEMISTRY DEPARTMENT POLICY The Chemistry Dept. expectation is that all procedures and guidelines will be followed verbatim. This expectation will be met by either having the procedure "in hand" or by
" memorization" The criteria for "in hand" procedures is as follows:
- 1. Extensive or complex jobs.
- 2. Infrequently performed.
- 3. Any procedure or guideline that requirer mipulating valves other than sample sink valves.
- 4. Any procedure or guideline that involves placing Tech Spec equipment OOS for any period of time.
- 5. Any procedur.e or guideline that requires signoffs and/or independent verification.
The following page lists all of the Chemistry Dept. procedures and guidelines that are required to be "in hand" All other Chemistry Dept. procedures and guidelines fall into the " memorization" category. Chemistry personnel have been informed of the expectation for verbatim compliance on a regular basis. Chemistry procedures and guidelines are located in every location where analysis is performed. [L s
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4 I I CHEMISTRY PROCEDURES / GUIDELINES THAT REQUIRE HAVING PROCEDURE "IN HAND" SECONDARY CG-13 Calibration of Water Treatment Plant (WTP), Secondary Sample i Panel (SSP), Condensate Polisher (CP) and Steam Generator ; Blowdown Treatment Facility (SGBTF) Conductivity Monitors , 1-CG-54 Secondary Chemical Additions System Operation l 2-CG-56 Secondary Chemical Additions System Operation l C-52" Maintaining Turbine Cooling Water And Blowdown Coolitig Water Chemistry C-81C High Activity In Steam Generator 1-CG-55 Operation And Calibration OfThe Unit 1 Sodium Analyzer l 2-CG-57 Operation Of The Unit # 2 Sodium Analyzer 1 PRIMARY C-37 Determination Of Gases (N2,02,H2) C-55 " Maintaining Reactor Coolant System Chemistry C-56" Maintaining Component Cooling Water Chemistry ; 1-C-80 Determmation Of Hydrogen Gas In Contamment ' 2-C-80 Determination Of Hydrogen Gas In Containment ; l l-C-112 Operation And Calibration Of The Milton Roy Post Accident Sampling System 2-C-113 Operation Of The Combustion Engineering (CE) Post Accident . i Sampling System (PASS) 1-1710020 Pnmary Sample System Valve Alignment ! Being Itpiaced by 1-COP-65.21 Unit 1 Primary Systems Sampling l 2-1710020 Primary Sample System Valve Alignment ! Being replaced by 2-COP-65.22 Unit 2 Primary Systems Sampling j DIESEL FUEL OIL TESTING C-114 Determmation Of Diesel Fuel Oil Flash Point i C-115 Kinematic Viscosity Test, Diesel # 2 Fuel Oil i C-117 Specific Gravity (API) Diesel # 2 Fuel Oil C-121 Determination Of Particulate Contammation; & Check For Clear And Bright Appearance With Proper Color Diesel # 2 Fuel Oil EFFLUENTS / MONITORS 2-C-62A General Atomic PIG Process Monitor Operation 2-C-62B General Atomic Single Stage Gas (SSG) And Steam Line Process Monitor Operation 4 2-C-62C General Atomic Single Stage Liquid (SSL) Process Monitor Operation 2-C-62D General Atomic Wide Range Gas Monitor (WRGM) Process Monitor Operation 2-C-66A Calibration Of General Atomic Gas, Liquid, Steam Line, and WRGM COP-65.02 Effluent Grab Sampling .
*a ONLY REQUIRED WHEN PERFORMING VALVE LINEUPS OR CHEMICAL ADDITIONS.
as OF THE POPULATION OF PROCEDURES / GUIDELINES THAT ARE REQUIRED IN HAND, THE FOLLOWING HAVE SIGNOFFS AND/OR IV STEPS 1-CG-54 Secondary Chemical Additions System Operation 2-CG-56 Secondary Chemical Additions System Operation (Currently in Information Services for 50.59 and typing) C-52 Maintaining Turbine Cooling Water And Blowdown Cooling Water Chemistry C-55 Maintaining Reactor Coolant System Chemistry (Currently in Information Services for FRG and typing) l C-56 Maintaining Component Cooling Water Chemistry , 1-C-112 Operation And Calibration OfThe Milton Roy Post Accident l Sampling System 2-C-113 Operation Of The Combustion Engineering (CE) Post Accident Sampling System (PASS) 2-C-62A General Atomic PIG Process Monitor Operation l 2-C-62B General Atomic Single Stage Gas (SSG) And Steam Line Process Monitor Operation 2-C-62C Genera! Atomic Single Stage Liquid (SSL) Process Monitor Operation 2-C-62D General Atomic Wide Range Gas Monitor (WRGM) Process Monitor Operation 2-C-66A Calibration Of General Atomic Gas, Liquid, Steam Line, and WRGM COP-65.02 Effluent Grab Samplieg (Plant Vent, GDT's, etc.) 1-1710020 Primary Sample System Valve Alignment (Currently used) 1-COP-65.21 Unit 1 Primary Systems Sampling, is currently in Information Services for typing and FRG approval. Contains signoffs and IV's. This procedure will renlace all of the samoline evolutions in 1-1710020. Primary Sample System Valve Alignment (Currently used) 2-1710020 2-COP-65.22 Unit 2 Primary Systems Sampling, is currently in Information Services for typing and FRG approval. Contains signoffs and IV's. This procedure will renlace all of the samalian evolutions in 2-1710020. 1-C-112 and 2-C-113 are currently being rewritten into the new COP format. We are currently writing our procedures using the Ops Dept. Procedure Writer's Guidelines. These tyvo procedures are numbers 1 & 2 on our list of procedures to upgrade. t
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CHEMISTRY DEPT. SCHEDULE FOR UPGRADED PROCEDURES PRIORITY PROCEDURE # DATE SCHEDULED FOR PCR SUBMITTAL 1 1-C-112 9/6/96 2 2-C-113 9/6/96 ;
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3 C-37 9/30/96 4 C-55 9/30/96 5 C-56 9/30/96 6 C-52 9/30/96 7 C-81C 9/30/96 8 C-114 10/31/96 9 C-115 , 10/31/96 10 C-117 10/31/96 11 C-121 10/31/96
- 12 1-C-80 11/30/96 .
13 2-C-80 11/30/96 NOTE: 1 i i t l The Unit 2 Process Monitor Procedures will be turned over to the I&C Dept. by the end i of 1996. We do not plan on upgrading these procedures. Da e Faulkner l Chemistry Dept. Supervisor l l 4 f s
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s . i l Charging Pump Packing Performance O Repack Criteria - Based on Seal Tank Level Change Primary Leak - Rising Seal Tank Level Secondary Leak - Falling Seal Tank Level e PSL Maintenance / OPS Repack Criteria PWO Origination - 6 inch / hour level change (0.05 gal / min leakrate) M/M Action Required - 9 inch / hour level change (0.075 gal / min leakrate) e Industry Standards Packing Leakrate Action - 0.15 gal / min (PSL Equivalent to 18.3 in/hr level change) Acceptable Packing Runtime - 1100 hours Randy Decker 8/15/96
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- 2. Packing Geometry Packing Cross-Section Packing Length 1
- 3. Stuffing Box Packing Geometry Spring Wear - Spring Rate Packing Stackup - Spacer O
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PLAN OF THE DAY WEEK 6 A-TRN [08/05/96 -08/11/96) THURSDAY - AUGUST 8,1996 3RD QTR WORK
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L 8:30 A.M. MTG - LARGE CONFR. RM - ROOM 4011 UNITS 1 & 2 LOAD THREATENING AND LCO ITEMS
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LCOITEMS ; UNIT 1 M LPatSYUCN1L PNL MSR CN1L CN 8 LOAD THREATEMNO19988 UNIT 1 1x,2ru ,_ . b
& UNIT 2 AkT Ge!K,N 5 > x =Wt DEN LOW 00L PREESURE TEST (LOSS OF LOAD 1EST) [
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O St. Lucie Plant Daily Report August 8,1996
- l. Operating Parameters Unit 1 Unit 2 Y-T-D Equivalent Availability (4 August,1996) 57.40 % 92.90 % l Continuous Days on Line 13 55 Gross Megawatts 880 885 Expected Megawatts 888 899 Net Megawatts 836 842 Reactor Power (%) 100 100 Heat Rate (BTU /KWH) 10466 10405
{ Condenser Backpressure (inches Hg) 3.60 3.00 Reactor Coolant System Leakage (GPM) 0.26 0.14 Feedwater Temperature (F) 433 431.5 Condenser Air inleakage (scitM) 1.3 2.9 l Condenser Dissolved Oxygen (PPB) 9 6 Intake Water Temperature (F) 79.5 79.5 Annunciators in Alarm (Off Normal) 3 1
- 11. Daily Status I A. Tech Spec LCOs (Start date, trne/LCO durat on)
B. Hot items: 2A MSR EH fluid leak. i Unit 1, #9 turbine beanng up to 9.0 mils. 1C charging pump oilleak. ; C. Other (ie Reason for MWs lower than expected, etc) lli. Significant Operating Events: (Tnps. etc) C.D. Ladd Nuclear Plant Supervisor Page1
UPDATED /SUBMITTEC , ST. LUCIE NUCLEAR PLANT BY UTAGE MGMT LCO LCO *-5
@ g HOTITEMS UNIT 1 PLAN OF THE DAY mURSDAY, AUGUST 8,1996 - 8:30 A.M. MTG NEXT REFUELING OUTAGE: OCT.1,1H7 HOT ITEMS b I I
%S UNIT DESCRIPTION TIS LCO SUPV DEPT CO M NTS IDENTI ED RMVD. 7/9/96 1335 - RTN N/A W! GRAVITY FEED :
REPR OIL LK - FAILED Ql-11 TEST-AWP-DUE 8/9,'96 1 IB BAM PP N/A D ENGLISH M/M SC# 67060-1 8/15/96 ; 1.2 PSIG - SCE TO PROVIDE VENTING PATH (WORKING 1 CNTMT PRESS HIGH PORTER SCE 8/9/96 ISC 1 TE-1121Y NEED ENG SPT D PITTS TEMP SWINGS (MONITOR) 8/8/96 i SENDING DATA TO CE MR OIL LEAK BETWEEN CRANKCASE & GEAR HOUSING pp SCE RMVD: 8/7/961945 N/A W/ A&B CHG PP'S AVAILABLE l e
- n-ORAUG%0F 10 h [
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UPDATED /SLCMITTEC , BY OUTAGE MCMT ST. LUCIE NUCLEAR PLANT LCO UNIT 2 LCO , b PLAN OF THE DAY & HOT ITEMS TH.URSDAY, AUGUST 8.1993 - 8:30 AM. MTG MTITMS
, NEXT REFUELING OUTAGE: APR.15,1M7 i
UNIT DESCRIPTION T/S LCO y DEPT 8 IDEN BED l 3.12.2 OPS PCR TO FRG TO ALLOW UNISOLATE RECIRC 2 V2169 CHG PP 2A DISCHARGE CHECK N MOTLEY M/M 7/24/96
^
- 8/896 2 FCV-10435 2A MSR REHEAT STOP FAB CLAMP, INSTALL AND FURMANITE SHOOT 8/9/96 O
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UPDATED / SUBMITTED UNIT 1&2 BY WORK COnTROt CONTROL BOARD ANNUNCIATORS SCHEDULED DATE CGMPLETION ANNs COMPONENT SUPV/ DEPT WR# IDENTIFIED STATUS DATE UNIT 1 HJTC #1 DRIFTING -WORKING (SCHEDULE 8/6/96)- J-33 B QSPDS INADEQUATE CORE COOLING FH-l&C 96013217 8/2 SOFTWARE PROBLEM
& S/96 ISOLATED M45 LY-1110 BYPASSED LETDOWN THR VLV AP LCV-21100 ADJUST LIMITER 8/8/96 . . _ . . - - _ . - - - . . -- _ _-8&C-. .. -- -- . - - - - - - - - . .
P-22 RAB HEPA FLTR HVE-10A/100 D/P HI 8/8 REPLACING 24 FILTERS TODAY &9/96 M48 CHG PP 1C CS OFF/SS ISOL 8/8 OIL LEAK CR GENERATED 96-1895 8/9/96 D-15 TURBINE VfBRATION ABNORMAL 8/8 #9 BRNG -INTERMITTENT ALARM 91 MILS 8/8.96 UNIT 2 . - - ._- - J-26 OBSOLETE MOTOR AWP SC #0090806 -(REPAIR MODULE RCP 2A2 OtL PRESS /FLO/LVL Hl/LO AP-l&C 7/31/96 ON DAYS 8/7/96) INSTALL MODULE 8/8/96 8/9/96 M SMITH C-49 CME OFF/ TROUBLE P&C 8/8/96 SYSTEMS NOTIFIED 8/8/96 08AUG96 07 21
ST. LUCIE NUCLEAR PLANT , MUCle i
@. PLAN OF THE DAY 3RD QTR WORK WEEK 6 A-TRN (08/05/96 -08/11/96)
FRIDAY - AUGUST 9,1996
=
y ru. **d'* i 8:30 A.M. MTG - LARGE CONFR. RM - ROOM 4011 ! UNITS 1 & 2 LOAD THREATENING AND LCO ITEMS im AY FRIDAY ~5ATt.mDAY suvuuAT-~~ lh0NDAY ~ TUE5 DAY WEDNESDAY THURSDAY FRfDAY ~5ATURDAY' ~ 5UNDAY' P MiDTP ' NTNTF-1ipIr M l' N T P ' MTDIP MiDIP MIDiP MI IP 'M7 TF uINTP LCOITGMS t UNIT 1 ! C b N 8/9/96 : 8[12 0603 Cb 8/7/96 9450hE BAC8/10/96194h U IT 2 MV-08-3/ VAL /FJTHROTTU1 TRIP VALVE FOR AUX!LinRY FEEDWATER PUMP 2C HVE -41A/ FAN /Pfl0PELLER FA4 FOR INTAK$i STRUCTURE EXHAUST Q i LOAO THREATNNINGITEMS UNIT 1 l
-l UNIT 2 N Q CEA BLOCK CIP E Sf22/96 I
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CUIT CHEC1(SEMI-ANNUAL)
! MODES 182 . O.D.DA1 ,
@ Q DEN LOW OIL P RESSURE TEST (LOSS OF LOAD TEST)lPCR ! REQD - D.D. DA TE 8?f 8/96 t C
PERIODIC - f.D. DATE S596 O l
j St. Lucie Plant Daily Report August 9,1996 I I. Operating Parameters Unit 1 Unit 2 Y-T-D Equivalent Availability (4 August,1996) 57.40 % 92.90 % Continuous Days on Line 14 56 Gross Megawatts 884 885 Expected Megawatts 890 899 Net Megawatts 839 840 Reactor Power (%) 100 100 Heat Rate (BTU /KWH) 10422 10408 Condenser Backpressure (inches Hg) 3.50 2.90 Reactor Coolant System Leakage (GF 0.56 0 Feedwater Temperature (F) 433 431.5 Condenser Air inleakage (SCFM) 1.3 2.4 Condenser Dissolved Oxygen (PPB) 9 6 intake Water Temperature (F) 77 77 Annunciators in Alarm (Off Normal) 3 0
- 11. Daily Status A. Tech Spec L Os (start date. tene/Lco duration)
B. Hot items: 2A MSR EH fluid leak. Unit 1, #9 turbino bearing up to 9.0 rrils. Eight unit 1 CEA's 2-3 steps inserted. Reason unknown. See IHE 96-066. 1C and 2C charging pumps OOS for maintenance. 2B1 waterbox flowgage indicates kne plugged. CTCS balls missing. Unit 1 containment pressure 1.2 PSIG. Need prcadure to reduce. i l C. Other (e Reason for MWs lower than expected etc) l l [ lit. Significant Operating Events:(tnps.etc) l
\
l C.D. Ladd ! Nuclear Plant Supervisor l Page1
UFDATED/ SUBMITTED , ST. LUCIE NUCLEAR PLANT LCO LCO y-'- UNIT 1 b PLAN OF THE DAY & E g HOTITEMS FRIDAY, AUGUST 9,1996 - 8:30 A.M. MTG HOT ITEMS NEXT REFUELING OUTAGE: OCT.1.1997 ,tleS UNIT DESCRIPTION T/S LCO 3 y DEPT IDENT F ED COMMENTS $ RMVD. 7/9/96 1335 - RTN. N/A W/ GRAVITY FEED REPR OIL LK - FAILED Ol-11 TEST-AWP-DUE 8S/96 1 1B BAM PP N/A D ENGLISH M/M SC# 67060-1 8/15/96 12 PSIG - SCE TO PROVIDE VEN TING PATH (WORKING 1 CNTMT PRESS HIGH PORTER SCE ENSWG) 8/9/96 I I&C TEMP SWINGS (MONITOR) REMOVED FROM ERDADS , 1 TE-1121Y NEED ENG SPT D PITTS 8/14/96 , MONITORING AFTER THE CAL (CAL PERFORMED 8/8) LPM CHANNEL 6 1 T NEWHOUSE l&C 8/9/96 DECLARE OOS DUE TO THE LEVEL SWITCH- ALARMS 10W OIL 1 1C CHG PP O!L LEVEL SWITCH D ENGLISH M/R 8/8/96 8/10/96 PLUNGER LEAKAGE 59%iARY & SECONDARY LEAKAGE EXCESSIVE OF M 9M 72 HR TO GET L'4ER A OR C BACK 1 1A CHG PP D ENGLISH U.:t 8/9/96 START 0600 8/986 8/10/96 '
._ DUE 0600 8/12/96 i
09AUG%0715
_ _ _ _ _ ~ . _ . _ _ _ . _ . - - - . _ . _ . _ _ _ _ _ _ _ _ _ t UPDATED /SUBMITTEC , BY UTA E MGMT ST. LUCIE NUCLEAR PLANT j LCO UNIT 2 LCO
& PLAN OF THE DAY &
ERIDAY, AUGUST 9,1996 - 8:30 A.M. MTG HOT ITEMS HOT ITEMS
. NEXT REFUELING OUTAGE: APR.15,1997 LEAD DATE UNIT DESCRIPTION T/S LCO SUPV KPT IDENTIFIED C N NTS Mgi67:
o ; FAB CLAMP. INSTALL AND FURMANITE SHOOT 3 FCV.10-035 2A MSR REHEAT STOP N MOTLEY M/M 8/8/96 8/9/96 , V2339 DIFFICULT TO OPERATE 3 2C CHG PP N MOTLEY MN 8/9/96 EM I 6 t s 1 : l i osauc*oi n w
. UPDATED / SUBMITTED UNIT 1&2 By wORx cONTaOt CONTROL BOARD ANNUNCIATORS SCHEDULED DATE COMPLETION ANN # COMPONENT SUPVIDEPT WR# IDENTIFIED STATUS DATE I
UNIT 1 BSCULTHOR D-15 TURBINE VIBRATION ABNORMAL -PDM 8/8 #9 BRNG -INTERMITTENT ALARM 91 MILS 6/8/96 K-18 CEA POSITION DEVIATION WARNING RS/l&C 8/8/96 IROUBLESHOOTING L CEDS CABINET DC CONT VOLT FAILURE RS/I&C 8/8/96 TROUBLESHOOTING
.-29
_. . .-- . - . ~ _ - - - . _ . - .. _ __ - LCV-2110P DID NOT SHOW DUAL INDICATION O IN USE. P IS M45 8/8/96 ISOLATED-WORKING ON LMT SWITCH FOR LCV-2110P gg LY-1110 BYPASSED LETDOWN THR VLV M TLEY UNIT 2 i 09AUG% 0721
1 y Operations Department Chronological Log Unit 1 SHIFT NUMBER: 748
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NUMBER: 748 NUC POWER: 100 DATE: 8/Bf36 DELTA T POWER: 100 SHIFT: DAYS MWE: 880 BOARD RCO: PAUL FARNSWORTH/HOLZMACHER CEA GROUP #: 7 DESK RCO: TIM GASSER /NICHOLS POSITION: 136 NWE: JEFF STARKWEATHER T AVG: 576 ANPS: WALT DAUGHTRY/SIMPKINS BORON: 1027 NPS: ROGER WELLER/ JOHN SANDY Xe WORTH: 2481 MODE: 1 CALCULATED SD MARGIN: >3600 MAJOR MILESTONES OR ACTIVITIES TO BE PERFORMED DURING THE SHIFT: l q MAINTAIN 100% POWER 1 TIME LOG ENTRIES 07:00 ASSUMED THE WATCH, COMPLETED BOARD WALKDOWN. 08:05 SJAE RAD MONITOR IS OUT OF SERVICE WHILE NPO TAKES AIR IN LEAKAGE (1.8"H20") AND THE SYSTEM SPECIALIST CHECKS FOR SOURCE OF DISOLVED OXYGEN 08 45 h ANN B-27 (480 VOLT SWGR 1A1/1C MCC UNDERVOLTAGE/ GROUND) NPO INVESTIGATED AND FOUND NO ABNORMALITIES, ALARMIS CLEAR. 09:16 STARTED HYPO TO UNIT #1, { 10:10 SNPO HAS PLACED THE WASTE GAS SYSTEM IN OPERATION LAW OP 1-0530020, THE 1 A GAS DECAY TANK IS IN SERVICE (PRESSURE IS 76 PSIG) AND THE 1B COMPRESSOR IS RUNNING FOR POST MAINTENANCE TESTING. WASTE GAS STOP VALVE V6565) IS SHUT. CHEMISTRY HAS BEEN INFORMED.
- 10.00 (LATE ENTRY) JOHN SANDY HAS RELIEVED ROGER WELLER AS NPS.
s 10 45 l&C STARTING RPS RCS LOW FLOW TRIP SETPOINT DETERMINATION IAW ISC 1-0120050, CHANNEL "A" LOW FLOW IS OUT OF SERV 1CEl 10.53 STOPPED HVS-4A AND HVE-10B FOR MAINTENANCE TO CHANGE HVE 10 FILTER BAGS. HVE 10B IS OUT OF SERVICE. NPO REALIGNED SJAE EXHAUST TO ATMOSPHERE.
} 10.55 SNPO REPORTS THAT THE 1B WASTE GAS COMPRESSOR HAS A DIAPHRAGM LEAK, HE HAS SWAPPED TO THE 1 A COMPRESSOR.
, 11:08 COMPLETED HYPO TO UNIT 1 11:13 RPS CHANNEL "A" RCS LOW FLOWIS BACK IN SERVICE. 11:15 RPS RCS LOW FLOW TRIP SETPOINT DETERMINATION CONTINUES LAW I&C 10120050, CHANNEL
, "B" LOW FLOW IS OUT OF SERVICE 11:30 RPS CHANNEL "B" RCS LOW FLOWIS BACKIN SERVICE.
11:33 RPS RCS LOW FLOW TRIP SETPOINT DETERMINATION CONTINUES IAW l&C 1-0120050, CHANNEL "C" LOW FLOW IS OUT OF SERVICE 11:40 SJAE RAD MONITOR IS BACK IN SERVICE. 06-Aug96 1
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Operations Department Chronological Log Unit 1 SHIFT NUMBER: 748 a 11:56 RPS CHANNEL "C" RCS LOW FLOW IS BACK IN SERVICE. 12:55 SJAE RAD MONITOR OUT OF SERVICE FOR AIR IN-LEAKAGE DATA GATHERING. 13.00 RPS CHANNEL D RCS LOW FLOW TRIP BISTABLE OUT OF SERVICE FOR TRIP SETPOINT DETERMINATION. 13:21 RPS CHANNEL D RCS LOW FLOW TRIP RETURNED TO SERVICE. I 13:22 1 & C REMOVED TE-1121Y FROM T-COLD INPUT TO ERDADS SCAN. 13:40 STARTED THE 1C CHARGING PUMP FOR OIL LEAK EVALUATION. l 14:02 . SECURED THE 1C CHARGING PUMP. THE SNPO OBSERVED OIL LEAKING FROM THE GEAR BOX AT APPROX. 2 DROPS PER MINUTE. ALSO A PWO SUBMITTED FOR THE OIL LEVEL SWITCH FOR THE ALARM DOES NOT APPEAR TO WORK CORRECTLY. 14:13 STARTED HVE 10A FOR OP CHECK. ALSO STARTED HVS-4A 14:14 STARTED HVE 10B AND SECURED HVE-10A. OP CHECKS FOR HVE 10A & B SAT 14.30 SJAE RAD MONITOR BACKIN SERVICE AND EXHAUST ALIGNED TO PLANT VENT. 16:15 IN AN ATTEMPT TO RESET ANN L-29(CEDS CABINETS DC CONT VOLT FAILURE), ANN K-18 (CEA POSITION DEVIATION WARNING ) WAS RECEIVED. THE INITIATING EVENT WAS RESETTING CEA POWER SUPPLY #14362(LOCATED IN BAY A IN THE CEDS LOGIC CABINET). IT WAS NOTED THAT CEA*S THAT WERE SELECTED ON THE CEA CONTROL PANEL WENT FROM 136.5 INCHES WITHDRAWN TO 132.75 INCHES WITHDRAWN. ENTERED CEA OFF NORMAL DUE TO CEA DEVIATION i ALARM. THE CEA'S SELECTED ARE 26,58,50,2,14,68. O
- 17:00 SJAE RAD MONITOR TEMPORAIRILY OUT OF SERVICE FOR A 3 4-LEAKAGl* READINGS.
)
17:05 SJAE RAD MONITOR IS BACK IN SERVICE. 15:30 ( LATE ENTRY ) JOE MARTIN RELIEVED WALT DAUGHTRY AS ANPS. 17.30 HELD PRE-JOB BRIEF WITH RCO IN PREPARATION FOR PERFORMANCE OF SBCS FUNCTIONAL SURV PER OP 1-0810051, 17:40 DISABLED SBCS BY PLACING CONTROL SWITCH IN "OFF" PER OP 1-0810051. 16:20 (LATE ENTRY) AFTER CONSULTING CEA ONOP (1-0110030)IT WAS DETERMINED THAT THE EXIT CONDITIONS ARE MET. EXITED ONOP 1-0110030, 20:05 PLACED SBCS CONTROL SWITCH BACKIN " AUTO", SBCS FUNCTIONAL IS COMPLETE, HOWEVER SEVERAL VOLTAGES WERE OUT OF SPEC. A NPWO WAS ENTERED FOR THIS CONDITION ON 7/31/96, WR #96013028. O 18:45 PREVIOUS ENTRY SHOULD BE FOR 1805, NOT 2005. G:00 RCO'S HAVE BEEN RELIEVED BY N!CHOLS AND HOLZMACHER. COMPLETED A BOARD WALKDOWN. MARTIN RELIEVED BY S!MPtJNS AS ANPS. 19.21 ANN J-7,1 A1 RCP VIBRATION HIGH CAME IN. NO ALARM IN ON BENTLEY NEVADA. ALARM WAS RESET BY DEPRESSING THE 1 A1 RCP VIBRATION RESET BUTTON ON RTGB-103 16.45 (LATE ENTRY) A REVIEW OF THE DDPS PRINTOUTS FOR THE DAY SHOWS THAT THE SELECTED CEA*S AND CEA 18 MAY HAVE STARTED STEPPING IN FROM UEL SINCE ABOUT 0900. DUR!NG THE
- DAY I&C WAS CHANGING CEDS LOGIC CABNET POWER SUPPLIES AND INVESTIGATING THE SYSTEM FOR GROUNDS. AA PWO SUBMITTED AND l&C HAS BEEN NOTIFIED. STA WRITING AN lHE.
18:45 (LATE ENTRY) NPS COMPLETED PLANT MANAGEMENT AND NRC (MILLER)IHE NOTIFICATION. 08-Aug 96 2
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O SHIFTNUMBER: 748 Perations Department Chronological Log Unit 1 1 I 21:45 COMMENCED PURGING THE VCT OF UNDESIRABLE GASES IAW OP 10210021. 21:23 (LATE ENTRY) HVE-10 A AND HVE-10B DECLARED BIS AT 1500, a 21:25 ENTRY FOR 2145 WAS NOT THE CORRECT TIME. TIME SHOULD HAVE BEEN 2115. j 22:45 NO FURTHER ENTRIES THIS SHIFT. TIME REVIEWER'S COMMENTS 14:31 Renewed log. J Sandy, NPS j: 21:39 Reviewed log. J Sandy, NPS 22:30 Rewewed lor. 't appears that both the dayshift and peakshift are included in shift 748. Pay careful attention to 4 the times. ODL. }
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Operations Department Chronological Log Unit i SHIFT NUMBER: 749 igu F d : 749 NUC POWER: 100 OATE: 8/9/96 DELTA T POWER: 100 i SHIFT: MnDS MWE: 880 BOARD RCO: HOLZMACHER CEA GROUP #: 7 DESK RCO: NICHOLS POSITION: 136 NWE: LANGNES T AVG: 575 l AN*S: SIMPKINS BORM: 1025 NPS: LADD Xe WORTH: -2428 MODE: 1 CALCULATED SD MARGIN: 33600 MAJOR MILESTONES OR ACTMTIES TO BE PERFORMED DURING THE SHIFT: MAINTAIN 100 % AND PERFORM CODE RUN ON 1 A CCW PP AS PER D.S. # 22. ALSO CONTINUE TO PURGE THE VCT OF UNDESIRABLE GASES AND TO INCREASE THE VCT H2 CONCENTRATION. TIME LOG ENTRIES 1 23:00 CONTINUED ON WITH THE SHIFT. HOLZMACHCR AND NICHOLS ARE THE RCO'S AND SIMPKINS IS THE ANPS(A',L FROM THE PREVIOUS SHIFT). 00:35 ANN 0-35, SIT 182 LEVEL HIGH/ LOW CAME IN. LEVE!. lS 89.3%. SIT WILL BE FILLED IAW OP 1-0410021 AS SOON AS POSSIBLE. 00.56 STARTED THE 1B HPSI PP TO FILL THE 1B2 SIT PER OP 1-3410021 01:05 STOPPED THE 1B HPSI PP COMPLETED FILLING THE 182 Sif CHEMISTRY NOTIFIED. SWAPPED TO THE 1C GOT , THE 1 A GDT IS ISOLATED. 01:34 SJAE RAD MONITOR OOS FOR CONDENSER. AIR IN-Leak"GE READING. 01:42 WE HAD TO TC THE PROCEDURE FOR PL'RGING FlSSION GASSES FROM THE VCT AND ALSO PERFORMED A TC TO THE SIT NORMAL OPERATION PROCEDURE. 02:05 COMPl.ETED PURGE OF THE VCT. CHEMISTRY NOTIFIED. 02:56 COMMENCED ADDING H2 TO THE MAIN GENERATOR IAW OG 1-022 03:00 (LATE ENTRY) SJAE RAD MONITOR WAS BIS AT 01:39. 03:18 SECURED ADDING H2 TO THE MAIN GENERATOR. PRESSURE IS 62 PSI. 04:10 COMMENCED THE CODE RUN SURVEILLANCE ON THE 1 A CCW PUMP 1AW D.S. 22 04:20 RCS LEAK RATE IS 0.56 GPM IAW D.S. #1. NPS REQUESTS THAT ANOTHER LEAK RATE BE PERFORMED DUE TO LEAKAGE BEING MORE THAN NORMAL. 04:53 THROTTLED FLOW TO 5000 GPM FOR 1 A CCW PP SURVEILLANCE 05 02 1 A CCW PUMP SURVEILLANCE COMPLETE AND SAT. 05.50 INVENTORY BALANCE INDICATES LEAK RATE IS NOW 1.5 GPM. SNPO REPORTS THAT THERE IS A LEAK ON THE CENTER PLUNGER ON THE 1 A CHG PP. THE NPS HAS BEEN NOTIFIED 05:55 START THE 1B CHG PUMP AND STOP THE 1 A CHG PUMP TO TRY TO REDUCE THE LEAKAGE FROM THE 1 A CHG PUMP. STARTING ANOTHER RCS LEAKRATE LAW D.S. #1. 09-Aug 96 1
s Operations Department Chronological Log Unit 1 SHIFT NUMBER: 749 l 06.00 1 A CHARGING PUMP DECLARED OUT OF SERVICE DUE TO A PLUNGER LEAK.1C CHG PP HAS BEEN OUT OF SERV FOR A OIL LEAK, THEREFORE IN ACCORDANCE WITH TECH SPEC. 31.2.4 WE HAVE ! ENTERED A 72 HOUR ACTION STATEMENT, SUBMITTED AA PLANT WORK ORDER. l 06:02 ISOLATING 1 A CHARGING PUMP AND WILL INITIATE A LEAK RATE TO ASSESS AMOUNT OF WATER BEtNG LOST, 06:22 ENTERED AN UNUSAL EVENT DUE TO THE INVENTORY BALANCE INDICATES GREATER THAN 1 GPM, THE 1 A CHARGING IS SUSPECTED AS THE SOURCE OF THE LEAK. 06:10 (LATE ENTRY) STARTED AN INVENTORY LEAK RATE WITH THE 1 A CHARGING PUMP ISOLATED. ENTERED PROCEDURE 10120031 EXCESSIVE RCS LEAKAGE, NOTIFIED OPS MANAGER C. MARPLE. TIME REVIEWER'S COMMENTS 05:08 NPS Review. CDL.
' l 1
06:11 Reviewed log, C. Marple 06:18 Rewswed log. R. Weller 06:25 Rewowed log R.A. Storke 09-Aug 96 2
s e Operations Department Chronological Log Unit 2 SHIFTNLnHBER: 692 NUMBER: 692 NUC POWER: 100 DATE: 7/16/96 DELTA T POWER: 100 SHIFT: MID MWE: 890 BOARD RCO: SHAWN CASSIDY CEA GROUP #: 5 DESK RCO: GEORGE LOUDAKIS POSITION: 136 NWE: JOHN GILES T AVG: 574 ANPS: BOB DIEHL BORON: 848 NPS: JOHN SANDY Xe WORTH: -2442PCM MODE: 1 CALCULATED SD MARGIN: >5000PCM MAJOR MILESTONES OR ACTIVITIES TO SE PERFORMED DURING THE SHIFT: 2C AFW PERIODIC SURVEILLANCE, TEST THE *B" TRAIN ECCS VENTILATION SYSTEM, MAINTAIN 100% TIME LOG ENTRIES i 19.00 ASSUMED THE SHIFT, BOARD WALKDOWN AND LOG REVIEW COMPLETE. 19 45 WEST BUS B.I S. 20:32 STARTED HVE-9B FOR *B" TRAIN ECCS AREA VENTILATION TEST. 20:52 STOPPED HVE-9B, SURVEILLANCE SAT. 22:25 DECLARED HVE-9B OOS FOR CLEARANCE TO PM/ LUBE DAMPER D-15 AND LOUVER L-78. 20:50 ! (LATE ENTRY) DECLARED LPM CHANNEL #2 OCS. FAILED LOW. NOTIFIED NPS/ GENERATED PWO TO 1/C..T.S. A/S 3.3.3.8,30 DAYS TO RETURN TO SERVICE OR SUBMIT A SPECIAL REPORT. ' 0:11 DECLARED RM-26-11,SJAE RAD MONITOR, OOS FOR AIR IN LEAKAGE READINGS. 0:13 AIR IN-LEAKAGE READINGS COMPLETE, DECLARED RM-26-11, SJAE RAD MONITOR, B.! S. 0:20 NPO EEGAN ADDING H2 TO THE GENERATOR IAW 2-OG-020. PRESSURE IS 59 PSIG. 0:39 COMPLETED ADDING H2 TO THE GENERATOR. PRESSURE IS 62 PSIG. 0 50 RCS INVENTORY BALANCE COMPLETE. RCS LEAKRATE IS .03 GPM.
~ 1:07 STARTED THE 2C AFW PP FOR OUARTERLY CODE RUN LAW OP 2-0700050. - 1:35 LOCALLY TRIPPED THE 2C AFW PP IAW OP2-0700050. 2C QUARTERLY CODE RUN COMPLETE, SAT.
1:55 DECLARED THE 2C AFW PP OOS FOR CLEARNACE FOR PMilNSPECTION. 3 05 DECLARED RM-26-12, PLANT VENT , RAD MONITO, OOS FOR CHEMISTRY TO DBTAIN GRAB SAMPLE. 3.30 CHEMISTRY COMPLETED TAKING PLANT VENT GRAB SAMPLE, DECLARED RM-26-12, PLANT VENT
, RAD MONITOR B.I.S.
3 40 DECLARED RM-26-13. FHB VENT RAD MONITOR, OOS FOR CHEMISTRY TO OBTAIN GRAB SAMPLES. 3 57 CHEMISTRY COMPLETED TAKING FHB VENT GRAB SAMPLE, DECLARED RM-26-13, FHB VENT RAD MONITOR, B.I.S. 16-Jul-96 1 ,
/ /0{
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Operations Department Chronological Log Unit 2 SHFTNUMBER: 692 5.58 STARTED HVE 9B FOR POST MAINT TEST RUN .-- '/
- ~
- 6.01 STARTED 20 AFW PUMP FOR PMT lAVWOP2-070050 6 02 2C AFW PP TRIPPED ON ELECTRICAL OVERSPEED. PP WAS STARTED FOR THE POST MAINT VIA MV-08-12. NOTIFIED NPS.
TIME REVIEWER'S COMMENTS 5.50 Reviewed Log P.B.lsaacs NPS ( i vt If i 4 ].' H'b :: i, t
'l I i'l 53N J, , , . r. ,
, ~ ? 'j, 7 ,.
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QI 3-PR/PSL-1 Revision 40
' a _. .,
May,1996
, ;M.
Page 35 of 38 y. ATTACHMENT 4 i SYSTEAOACCEPTANCE/rURNOVER SHEET (Page 1 of 2) Page 1 of k PC/M No. O34- % novi.ien 6 < t Supent d+1 Unit (s): 71 0 2 O Common SATS: O Parbal Complete
Title:
RPatie S OLE A O)'D if Lt/ RF ptA TrnEnTN , implemented by: Discipline: O Electrical Mechanical O iac 0 Maint. Projects O Sys. Protecbon O 0 ner j E Mode Deferred Testing is requred in Mode b & E*V O This SATS is a parbei tumover. work romaning treados the foiiovnng- .i
- I 1
h i PC/M CLX6DiNATOR5: { All procedures for my department which are requred for tumover are complete and/or procedure changes i f:r my department which are not required for tumover are listed below:
- YES N/A DATE
(/ /# 8 O M Secunty: / i O El Chemistry: Zw.EM Ljfjk O k Fire Protection: ' [bD
/7 fe.f dL/d O G Health Physses: [b 6 /// //6 E O Plant Mamtenance: _[a.,/.,,d.,/1 O G Emergency Preparedness: I M h d-- 4 //*/ #4 j PROCEDURE NO.
(/ DATE REQUIRED CR OR PMAI NO. I' l- IM F ci9. o f / / PM C t G 400 fM P - 04. 02 / / % l
/ /
s
/. /
/ /
j SYmic,M ENGINr.cn OR OPS SUPPORT TEmisedG: YES N/A j System functional tesong has been satisfactonly completed and all test documents used " j have been transmitted to CM. (N/A if test has been mode deferred for this SATS). g [ h t) The updated PODS for which the SATS is being issued adequatWy support the design change. O #\7 q 3) All Department procedures required for tumover are complete and/or SCE Department j
, procedures not required ei for turnover are iisted above.p y g.,14M. ,: ~r e O %g '/
System Engineer or OST: [ /M ~ Date: '7 / 2. / 6 ur ' su-
~
a\ (&
QI 3-PR/PSL-1
' Revision 40 l May,1996 l Page 36 of 38
! ATTACHMENT 4 ' SYSTEM ACCEPTANCE / TURNOVER SHEET ' (Page 2 of 2) PC/M No. 96O34 Page 2 of 1 l SPONSORDNR DEPARTINENT: needs for . 1 The instased modlAcedon it was onginated. ! Sponsonng Department Hood: /. Date: b/N N / l TRAIN 5NB COORDDIATORT YES N/A AE operator trairung commements have been identified in the Tracidng System Action l O j Request Process for review and subsequent incorporadon intop's Trasung May. l TSAR No(s): $$0 N L l$lEbibIjljWfffft. He fj4 ply f4cMMt ! Applicable trairung bulistins are below --dc" W in the Control Room. O Trairung Coordinelor: __
,. e / # Date: f ZT
/ / [96 OPERATIONS COORDINATOR: YES N/A The Master Clearance Order has been updated. D [
j AI requwed eqtspment tag changes are complete. O AB temporary or permanent labeling is complete. O [ { AE apges* plant operating documents are updated and in the Control Room. O I ! As procedures requwed for ass and in the Control Room l and/or procedures Page 1 of this SATS. O Y j Operabons Coordinator. I \ _ Date: 7 / 2- /5 ] j NL@ "AR PLANT SUPERVN DR: AB equipment is g in accordance with ----+ operating procedure. YES NO N/A O O E NO is checked, ensure cornponent is in the Equipment Out of Sonnes Log. l ! Operabigty as defined in the Technmal Specsfloations has been met. O O ! Nd j E No is checked, M ensure component is in the Equipment Out of Sennce Log. Equipment Out of Service Log for this SATS. O l j Nuclear Plant Supervisor: , 7 y' Date: '/ 0, / N', ! m. - .r. e. - - l MODE DEFERRED TESTING TIFICATION 1 Mode Deferred Toshng was performed in Mode (s) .3 The follovnng apply: /R40 l 3 All tesong for this SATS has been satisfactorily completed.
- O The testing was not satisfaciority compieeso and tnis SATS shas be a partial turnover.
l CM Representative: M Date: 7/E//.ff. 2 Nuclear Plant Supenneor: GNvND - Date: 7 / 8d M ! CONFIGURATION MANAGERIENT: " j The PC/M review process for this TS has been satisfactority completed. j CM Representative: [ .~'d : ~ - Date: Il//b i Comments: / 4 e i
/R40 i _ _ . _
Inter-OfEce Correspond nce
@ FPL Q'%a L 1
d Vb_k 1 I JPN-SPSL-96-0135 I To: S. A. Valdes Date: St. Lucie Plant APR 2 3193 From: Hid W D. J. Denver Department: JPN/PSL Nuclear Engmeering Ciihiect? ST. LUCIE IJb 1 l 1 rum nuh ' 4.. c ,"034-196, Rev.1, Supplement 1 ' I S 7 Q""ITTLE: U.I Transmittal of a Unit 1 MEP for the RCGVS Solenoid f,,h [ Valve Replacements, Addition of Flanged Valve / Spool
% '^ O 3 9 b Assemblies and Manual Valve Additions
.s ' - N FEREHCE: REA SLN-93-101-10
' MErW PC/M 034-196 l t
Attached for review, approval and use is Revision 1 to the Minor Engineering Package for the subject PC/M. This engineering package provides the necessary details to implement the following modifications within the j Unit 1 Reactor Coolant Gas Vent System: i
- a. Replacement of the four original RCGVS Target Rock seal-welded primary solenoid valves with a Target Rock solenoid valve having a bolted bonnet design, b- Addition of three 1" system isolation valves just upstream of the primary solenoid valves (two on the Reactor head vent line and one on the Pressurizer vent line), and
- c. Provide flange sets on each primary and secondary solenoid valve to create a unique valve / spool assembly for universal valve replacements in either St. Lucie unit.
These plant changes shall increase solenoid valve reliability and will facilitate maintenance and testing of these same valves at various plant operating ccnditions. Revision 1 i This revision includes updated reference information to remove the holdpoint concerning the stand-alone safety evaluation for the addition of three new manual isolation valves to the RCGVS process lines (as desenbed above) This evaluation is given as Attachment 6 to this MEP and has been issued to support the implementation. Revision 0 discusses the change-out of only the four primary solenoid valves while Revision 1 addresses a scope change to include the change-out of the three secondary solenoid valves as well (seven valves total). Since each solenoid valve assembly with welded tlange connections will be interchangeable between locations in either St. Lucie unit, a unique tracking system is required for configuration control purposes and to eliminate future 1and potentially tedious) drawing changes. Revision 1 includes a scheme for these purposes and also mcorporates other comments noted since the issuance of Revision 0
-- . _. . -= - - - -. - ~ . _ _ .
JPN-SPSL-96-0135 Page 2 of 2 Current Differences Between Unit 2
)
- 1. Valve / Spool Assembly Length for the Secondary Solenoid Valves In order to establish universal replacements between the RCGVS solenoid valves or between these identical valves within either St. Lucie unit, a standard size valve / spool assembly must be configured.
The spool-piece length to be applied as the standard for both units was selected as that used for the primary solenoid valves on Unit 2; the end-to-end length for this assembly was set at 16" NOTE: The valve / spool assembly for two Unit 2 secondary solenoid valves, V1464 and V1465, were configured to a length of 36" This was done for two reasons: (1) since numerous flanges were installed on shon notice prior to power ascension, flange availability was limited, and, (2) due to this parts limitation, the in-line I flanges located 20-1/2" downstream of these two Unit 2 secondary solenoid valves were utilized as the downstream flange end connection. Funhermore, the third Unit 2 secondary solenoid valve, V1466, was not modified at all with flanged connections. Future actions are expected to backfit the three Unit 2 secondary solenoid valve assemblies to conform to the new standard length of 16"
- 2. Configuration Control /D' rawing As-Building ,
Since each solenoid valve assembly with the welded flange connections will be interchangeable between
' locations in either St. Lucie unit, a unique tracking system is required: (1) for configuration control purposes and, (2) to eliminate future drawing changes. A weld number identification scheme has been established for each Unit I assembly in the Unit 1 TEDB change package; however, this enhancement concept was not considered during the lead work for Unit 2. Weld identifications for the existing Unit 2 valve / spool assemblies, any prospective assemblies (with the bolted bonnet valve) and any backup assemblies (configured with a seal-welded solenoid valve) must also be assigned, fabricated and tracked in an identical manner as that given for Unit 1.
A PMAI will be written to ensure these two action items are implemented for the Unit 2 RCGVS design. Should you have any further questions, please contact Larry Lostocco at PSL extension 7137. (R(W DJD/fK/LGL , Copies: R. E. Ball - MEC/PSL H. L. Fagley/DCC - SLC/PSL(w/ Original) i J. E. Price - SCE/PSL D. M. Stewart - SCE/PSL M. A. Tarascio - ENG/PSL D H. West - ENG/PSL
Ol 3-PR/PSLo1 Revision 39 April,1996
- Page 22 of 26 ATTACHMENT 2 PC/M REVIEW FORM (Page 1 of 2)
- PC/M Number 9/o ON Supplement Number I Expiration Date 2/2F/ 9 7 l
! PC/M
Title:
i Rc G V.S solenaw A lve Ree la cam ants, AddiH n oF flanged Va lve /St= A s se m hi:e s ee n d 11? a n u a t VaIve Additie n s PC/M Classification: R Major Modification or , Minor Modification
- Safety ClassWication
- '
4 X Safety Related Quality Related i Not Nuclear Safety Related Administrative
\
! PC/M Category: l l b Normal Either/Or As-Requested Package As Fail Generic 4 .i Does the PC/M contain a Safety Evaluation? O Yes or 5 No is this a proposed change or modification to a unit system or equipment that affects nuclear safety? f
% Yes or O No if either of the above questions is YES, FRG approvalis required.
FRG Review Required? E Yes or O No Un Date: f I E 11 9G
- //,onfiguration Management e -- Date
- I/ /kb Plant General Manager FRG Nurhber: H-l 2 l FRG Secretary: b ate: _5_/ 4 / 9(o ,
f FRG Comments: "d#b'""' Y a I d
l Ol 3-PR/PSL-1 Revision 39 April,1996 ! Page 23 of 26 ATTACHMENT 2 PC/M REVIEW FORM (Page 2 of 2) Implementing Documentation: Department ER/NPWO # W/O # rnM t:, / /6960 95026 46 R I c- s1 /Bl? E 9 G Oto CG& fs1 / 817 C. 9GelIo72 4, 3 / e t 7 2. 9 f,, m i c 7 5 4 5 / 8 / 7Z >& es o e 7 4 63 /8t?2 4 6 01/ b ?& 63/ # 7 2. 9 G O/ t 07 7 PC/M Review and Approval: b N t b / 2 f /_f fe_ Conf % ration nagement AA ' 7Y / Date $ / 30 OC-Comments: qg ' Quality Control O ' l l 1 I Areae Affected: Yes or No Desenption Operator Training Yes As per Training Department Requirements Operating Procedures /gg fe.r Opu ffons [/t/ew Wlas last.//,J) Surveillance Procedures Ye s, fey Cpr $ opp,-t 7b&$ Maintenance Procedures /es F*e //4/,7h 1 fPec4 nr , i ci Spare Parts
/e s Drawings / Technical Manuals ye s Pa 4 e i 2. + 12 SRDs? h N FUSAR Change
)/f5 A n . % , 11, /- t TEDB Change sfHaekme,+ 4
[e s Human Factors (CREDIT) No Environmental Concems No in Service Inspection po Maintenance Rule ao Plant Restrictions [6.5 Maoeal Vo / e.5 /Mee/ /-.oc/c5, Others fyg kb Conhsuraten Management Date f / 2f f 5
AIINOR ENGINEERING PACKAGE (31EP) PLANT PSL UNIT 01 PC/M NUMBER 034-196 SUPPL ]_ ORIGINATING DOCUMENT SLN 93-101-10 EXPIRATION DATE 02/28/97 l PC/M CLASSIFICATION: X SR QR ,__ N N S ADMIN TITLE RCGVS Solenoid Valve Reolacements. Addition of Flanged Valve /Soool Assemblies and Manual Valve Additions A DDITIONAL REQUIREMENTS / INSTRUCTIONS YES NO AS-BUILDING TO COMMENCE UPON ISSUANCE OF PACKAGE? _ X l THIS PACKAGE HAS TIE POTENTIAL TO SIGNIFICANTLY IMPACT PERSONNEL RADIATION EXPOSURE *. IF YES, 1 JPN FORM 72 IS REQUIRED. _ X MARA screenmg performed per JPN QI 3.13 10CFR50.59 SCREENING YES NO
!) DOES TIE CHANGE REPRESENT A CHANGE TO TIIE FACILITY AS DESCRIBED IN THE SAR? X. __
- 2) DOES TIE CHANGE REPRESENT A CHANGE TO l PROCEDURES AS DESCRIBED IN THE SAR? ._ X
- 3) IS TIE CHANGE ASSOCIATED WITH A TEST OR EXPERIMENT NOT DESCRIBED IN THE SAR? __ X
- 4) COULD TIE CHANGE AFFECT NUCLEAR SAFETY IN A WAY NOT PREVIOUSLY EVALUATED IN THE SAR? _ X
- 5) DOES THE CHANGE REQUIRE A CHANGE TO TIE TECilNICAL SPECIFICAT!ONS? _ X.
' ~ r . c e., _ _ . . s. ;e...;~.,;-.........,_.r.__... .... . .t. r , _ .- :
. Signatures on file for Revision 0 l
REVIEW / APPROVAL GROUP INTERFACE TYPE PREPARED VERIFIED APPROVED FPL APPROVED
- INPUT REVIEW N/A , 4 ,
MECll X M. f __ N/A 1 LECT X N/A N/A N/A l&C X N/A N/A N , N/A civil 'X N/A N/A A N/A NUC" ' X N/A N/A //" L d/ N/A CSI X N/A N/A N/A N/A NUC 11TI. X N/A N/A N/A N/A
- For Contractor MEP's As Determmed Hv Projects " Review Interface As A Mmimum On All Non-Adnunistrauve MEP's FPL PROJECTS APPROVAL: -
.ld DATE: 2 WO
/
/
PC/M 034-196 Rev. 1 l Page 2 of 16 ENGINEERING JUSTIFICATION A. Introduction and Reason for Channe Valves V1441, V1442, V1443, V1444 are the primary solenoid valves for the Unit 1. Reactor Coolant Gas Vent System (RCGVS) while valves V1445, V1446, V1449 are the secondary solenoid valves for this system. These safety-related control valves are required to open after an accident to vent non-condensible gases from the Reactor Coolant System (RCS). They may also operate during normal plant startup and shutdown to provide a vent path when filling or drammg the RCS. The original valves were installed as Target Rock valves, Model 80B-001-12 (Y-pattern, globe, solenoid-operated with a scal-welded body-to-bonnet joint). This MEP evaluates the l installation of the replacement Target Rock valve, Model 80B-001BB (similar design with a bolted bonnet) in I each of these seven locations. A change-out to the bolted bonnet design shall simplify maintenance efforts, reduce related costs, increase valve life, and reduce the spare parts inventory requirements. This MEP has been developed and expanded to physically change out all of the existmg RGCVS solenoid valves (fourpnmary and ' three secondary) to the bolted bo.nnet design. Hence, this PC/M addresses the replacement of Valves V1441, ; V1442. V1443, V1444,1445, V1446 and V1449. Additionally, new manualisolation valves (given as V1650, V1651 and V1652) are to be installed on the process lines of the Unit 1 RCGVS iust upstream of the primary solenoid valves (two on the Reactor head vent line and one on the Pressurizer vent line). These valves will allow dualisolation of any RCGVS solenoid valve so that maintenance and/or testing can be performed while at elevated RCS operating temperature and pressure. Prior to the addition of these three manual isolation valves, the RCGVS solenoid valves could only be worked with the RCS depressurized. This design change will provide more latitude for future maintenance of these valves. This ; MEP will evaluate the installation of two Anchor Darling valves in line 1"-RC-B00 and one such valve in Line l 1"-RC-B24. These valves will normally be in a locked open position to preclude inadvertent positioning during power operation. Identical valves were recently added to the Unit 2 RCGVS for similar reasons. Also, each existing Unit 1 primary and secondary solenoid valve shall be provided with a flanged connection set to create a standard size valve / spool assembly. This spool-piece will be developed for universal replacements between these valves or between these identical valves within either St. Lucie unit. The valve / spool assembly length recently established for the Unit 2 RCGVS valves (via Reference 4) shall also be applied as the standard for the Unit 1. valves. This plant change will also facilitate solenoid valve removal / replacement activities and test efforts should a future valve problem develop at hot operating plant conditions. Revision 1 This revision includes updated reference information to remove the holdpoint concerning the stand-alone safety evaluation for the addition of three new manual isolation valves to the RCGVS process lines (as described above). This evaluation is given as Attachment 6 and has been issued to suppon the implementation of this MEP. Revision 0 discusses the change out of only the four primary solenoid valves while Revision 1 addresses a scope change to include the change-out of the three secondary solenoid valves as well. Since each solenoid valve assembly with welded flange connections will be interchangeable between locations in either St. Lucie unit, a unique tracking system is required for configuration control purposes and to eliminate future (and potentially tedious) drawing changes. Revision 1 includes a scheme for these purposes and also incorporates other comments noted since the issuance of Revision 0. With the removal of the holdpoint and these other changes, the implementation of all work in this MEP can now proceed.
PC/M 034l% Rev. 1 l Page 3 of 16 B, Backaround Small-bore piping is provided from the top of the Reactor and Pressurizer heads to enable various vent functions. The RCGVS solenoid valves are configured with four upstream valves in parallel and three downstream valves in parallel for venting to either the Quench Tank, Containment atmosphere or to the Containment Sump. These Target Rock valves have had a history of seat leakage and operational startup problems within both St. Lucie units as evidenced by numerous 1994/1995 STAR's. The piping between the upstream and downstream valves will not be pressurized if the upstream valves are not leakmg. Due to the valve design, the differential pressure across the valve under normal system operation (at elevated pressure and temperature) should assist in seating the valve properly. However, during low pressure service, e.g. when the valve experiences filling / venting during a refueling event or during RCS heatup, the valve may leak by the seat and potentially cause damage to the seat. Historically, the valves have been replaced in lieu ofrepairing the valve due to the seal weld at the body-to-bonnetjoint. The root cause analysis of Reference 5 was developed and provided short term and long term recommendations. One recommendation was to provide a bolted bonnet valve such that maintenance could be improved. Another recommendation was to perform a supplemental low pressure seat leakage test prior to the return-to-service following each outage. A Solenoid Valve Team was formed in January 1995 to review and address problems associated with the existing Target Rock valves. The team detemuned that the Herion valve design should provide a solution to the problems identified with the Target Rock valves. Herion valves were approved for purchase and installed in the four RCGVS primary control valve locations during the 1995 Unit 2 outage (see Reference 4 regarding the replacement of seal-welded Target Rock solenoid valves with Herion solenoid valves). However, many problems were experienced during the Plant's heatup evolution which impacted Plant availability. The problem report of Reference 6 explains the failure modes in more detail, and discusses the immediate design changes that were necessary to get the Plant on-line; additionally, long term actions were provided. This MEP addresses the long term design improvements that evolved from the Unit 2 Herion valve replacement effort (based on the problem report of Reference 6). Based on recent operating plant experiences, the Herion valves are believed to be more susceptible to particulate damage than the Target Rock valves. On this basis together with the lessons learned from the recent Unit 2 work, the alternate Target Rock solenoid valve design (with a bolted' bonnet) will be used for all further RCGVS control valve applications. Other Unit 2 design improvements will be incorporated into this MEP to facilitate remote valve maintenance and valve testing. This includes: (a) the creation of valve / spool assemblies on all critical RCGVS solenoid valves, i.e. the addition of flange sets, and (b) the addition of manual isolation valves upstream of the primary solenoid valves for positive system isolation should valve maintenance be required at elevated RCS pressures and temperatures. e
PC/M 034-196 l Rev. 1 l t Page 4 of 16 l C. Eneincerine Evaluation
- 1. Evaluation for the Target Rock Repiscement Valves The Target Rocl bolted bonnet solenoid valves were procured in 1995 to a later revision of the same specification used to procure the original seal-welded Target Rock valves. The valves were procured such that they are functionally interchangeable with the original model. The bolted bonnet valves have similar operating characteristics and have been certified by Target Rock to be in compliance with the original qualification report given as Reference 16 (see Attachment 1).
Page 3 of Attachment 2 provides a tabular comparison of design parameters for the currently installed seal welded valve and the replacement bolted body valve. The design and design configuration for these two types of valves are nearly identical. Obvious differences for the bolted bonnet valve beyond the bonnet type include: a slightly larger height dimension, a slightly larger solenoid diameter, and a weight increase. Dimensional characteristics have been previously and favorably evaluated in Reference 9 to document the proper fit. The critical evaluated dimensions for the valves as shown in Attachment 2 are the end-to-end dimension, centerline-to-top of valve, centerline-to-disassembly height, and the solenoid diameter. The evaluation of these differences between the existing Target Rock valve (with a seal welded body-to-bonnet joint) and the newer Target Rock bolted body valve are addressed in Reference 9. This reference provides a technical evaluation for the acceptance of the new Target Rock bolted bonnet valve as a direct replacement for their seal-welded design in locations for Valves V1441, V1442, V1443, V1444, V1445, V1446 and V1449. Electrical power and termmal end connections are also identical between the currently installed and replacement valves. This evaluation accepts the appropriate vendor drawings and includes an Item Equivalency Evaluation (IEE) which enables this like-for-like replacement. This IEE provides the necessary review to accept the bolted bonnet Target Rock valve Model 80B-001BB as a replacement for the existing Target Rock valve Model 808-001. Minor design differences were evaluated prior to the procurement of the bolted bonnet valves. Product improvements / upgrades are listed and justified as being equivalent or more superior to the original parts. Specifically, the IEE concludes that the bolted bonnet design has the same design requirements, performance requirements and operating mechanism as the original valve. Based on the above equivalency statements, this PC/M provides acceptance for the replacement of all seven RCGVS solenoid valves (four primary and three secondary solenoid valves - V1441, V1442, V1443, V1444, V1445, V1446 and V1449). Stress calculation RCV-1000C (see Reference 23) and the related stress isometric drawings were revised to l include the weight increase for the replacement solenoid valves at all seven locations. The analysis also considered the addition of flange sets for the valve / spool assemblies at all seven solenoid valve locations as well as the l I addition of three new Anchor / Darling valves installed upstream of the primary solenoid valves. The affected l piping has been evaluated and found acceptable. Pipe supports / restraints and the structures to which they are attached have been reviewed for applicable loads and have been iound acceptable in their as-found condition for i the resised loads. ! I The DCR of Reference 10 adds the design information for the bolted body valves into the FPL drawing control l system. This includes the design / seismic report, the valve technical manual. and other valve / assembly drawings. l The appropriate TEDB change package was included in this DCR. [ NOTE: Reference 10 provides a TEDB change package for only the alternate use of the bolted body valve and enters associated drawings.] I
PC/M 034-196 Rev. 1 l Page 5 of 16
- 2. Evaluation of the Three New System Isolation Valves Should solenoid valve maintenance / testing become necessary at elevated RCS pressure and temperature, adequate manualisolation of the Unit 1 RCGVS is not available. Hence, the RCGVS solenoid-operated valves can only be worked with the RCS depressurized. To facilitate maintenance under elevated RCS pressure and temperature, the addition of manual valves in the RCGVS provides the capability for dual and remote isolation of the Reactor and Pressurizer head vent lines for personnel safety and ALARA purposes.
Currently, only one manual isolation valve (V1450) exists on the Reactor head vent and it is located just above the Reactor Cooling Shroud making access diflicult. Two new valves (V1650 and Vl651) will be installed on the process line just upstream of the primary solenoid valves along the west sidewall of the Pressudzer. Single valve isolation (via V1239) exists within the vent line from the Pressurizer. Since it is located within the Pressurizer cubicle and approximately 5 feet above the head, it is considered to be fairly accessible to an operator. Therefore, only one new valve is required to provide the desired dual isolation. One new valve (V1652) will be similarly installed on the Pressurizer vent line adjacent to the same west sidewall only at a higher elevation. Operation of these new manual valves will be in accordance with the Technical Specification of Reference 2 for RCS vents. It states that, at least one Reactor Coolant vent path consisting of two vent valves and one block valve powered from emergency buses shall be operable and closed from both the Reactor Vessel head and the Pressurizer steam space, while in hiodes I through 4. The physical closing of a new manual valve will isolate an RCS vent path. Thus, the requirements of Technical Specification 3.4.15 must be considered whenever one or more of these valves is to be closed. Therefore, these manual valves shall not be closed except for the performance of approved RCGVS maintenance or testing activities. Funhermore, these manual valves shall be administratively locked open to preclude inadvertent positioning during normal power operation. Accordingly, the installation of these valves will not affect the design basis or operative functions of the RCGVS (see Reference 43 which is given as Attachment 6). I Under current programmatic guidelines for small-size replacement valves, Anchor / Darling has been selected as the vendor-of-choice for the three new isolation valves. The design parameters for these three new 1" manual globe valves are addressed below:
- a. Code Requirements (including year and addenda)
Reference 18 specified AShiE Section Ill,1977 Edition, Winter 1978 Addenda or any later code year / addenda up to and including that approved by 10CFR50.55a. These valves are designed / manufactured to AShiE Section 111,1986 Edition, No Addenda. This code year is approved by 10CFR50.55a, Edition January 1,1992.
- b. Code / Safety Classification The valves are located within a Quality Group B (USAS B31.7) Class 2 portion of the piping system (see References 27 and 29). The Anchor / Darling valves being supplied are AShiE Class 1 valves. In accordance with AShfE Section Ill. Subsection NCA-2134. valves classified as Class 2 or 3 in their Design Specifications (original construction) may be constructed and stamped in accordance with the mies of Subsection NB (Class 11 The ASNIE Safety Class will be shown as Class 2 in TEDB (or other drawings such as the P&ID. isometric. ete ) since the new installed valves are of a higher AShfE Safety Class. The ASNiE Safety Class shown in these documents will be retained to indicate the minimum AShfE Safety Class requirement of the piping system.
PC/M 034-l% ! Rev. 1 l Page 6 of 16
- 2. Evaluation of the Three New System Isolation Valves (continued)
- c. Material Reference 18 specifies acceptable materials for both St. Lucie nuclear units. Due to ALARA concerns associated with wear products of cobalt based materials in contact witn reactor coolant fluid, cobalt hard-facing has been restricted by FPL (unless no other hard-facing is available). The Anchor / Darling valves do not employ cobalt hard-facing and the materials of construction meet the requirements of Reference 18.
- d. Seismic Qualification The affected piping and supports have been evaluated and found acceptable for the additional weight of the valves and flanges (see Reference 23).
- e. Procurement Level The correct procurement classification for these manual globe valves in their ASME Class 2 application is Procurement Class PC-1 and they have been purchased accordingly to that requirement (see Reference 44).
- f. Design Pressure and Temperature The ANSI pressure class of the Anchor Darling valves is ANSI 1878 standard interpolated pressure class (see Reference 20). Review of the TEDB and the piping isometrics of Reference 20 indicates that the system design pressure and temperature are 2485 psig @ 700 "F. These valves are designed to operate at 2705 psig @ 700 'F. Therefore, the pressure class of the replacement valves bounds the design and is acceptable,
- g. Spatial Envelope These valves will be located in an area on the west side of the pressurizer that is open faced and have l an end-to-end dimension of 5-1/2" (see Reference 20). Based on a review of the piping isometrics of l Refer'ence 27, there is sufficient room for installation and operation of these valves.
- h. Pressure Drop The C,, or flow coefficient for the Anchor / Darling valve is 8 (see Reference 20). This Cy value imposes a negligible line loss with respect to the entire system resistance. Review of the Reference 3 design basis document indicates that the vent rate is limited by the class break restricting orifices, and addition of these valves will have no impact on the vent rate.
PC/M 034-196 Rev i l ) Pace ~ of 16 1
- 3. Evaluation of the Flanged Valve / Spool Assemblies and Flange Materials
- a. Valve / Spool Configuration J On Unit 1, the currently installed RCGVS Target Rock solenoid valves (located inside Containment) are welded into place. As a consequence, f one should develop future seat leakage problems at hot operating plant conditions, it must be worked in place. The need to improve repair methods was obvious. In order to facilitate solenoid valve removal / replacement activities and subsequent test efforts, and minimize personnel exposure, it will be desirable to modify all RCGVS solenoid valves to incorporate flanged end connections. These flanged connections are not integral to the standard Target Rock bolted-bonnet solenoid valve body design and, as such must be mechanically fitted.
In December,1995, flanged connections were installed on the ends of the corresponding solenoid valves on Unit 2 (see Revision 3 to Reference 4). In order to establish universal replacements between these valves or between these identical valves within either St. Lucie unit, a standard size valve / spool assembly must be configured. The spool-piece length to be applied as the standard for both units will be selected as that used for the primary solenoid valves on Unit 2 the end-to-end length for this assembly was set at 16" (NOTE: The valve / spool assembly for two Unit 2 secondary solenoid valves, V1464 and V1465, were configured to a length of 36" This was done for two reasons: (1) since numerous flanges were installed on short notice prior to power ascension, flange availability was limited. and, (2) due to this parts limitation the in-line flanges located 20-1/2 inches downstream of these two Unit 2 secondary solenoid valves were utilized as the downstream flange end connection. Furthermore, the third Unit 2 secondary solenoid valve, V1466, was not modified at all with flanged connections. Future actions are expected to backfit the three Unit 2 secondary solenoid valve assemblies to conform to the original standard length of 16" The use of flanged assemblies on Unit I will be acceptable since pipe fittings affect neither the design basis nor the desired venting operations of the RCGVS. However, based on the inspection of References 25 arid 26, the selected assembly length of 16 inches may present minor interferences with seismic restraints which are located upstream of Valves V1441 and V1442, and. possibly V1443 The suspected problem areas are pnmarily with Pipe Supports RCGV-58 and RCGV-59 (and, possibly RCGV-15 and RCGV-56), interfering with the upstream flange end of the installed valve / spool assembly. Due to the ease in relocating the pipe supports slightly upstream without impacting other adjacent supports or equipment (rather than relocating the valves slightly downstream), it will be pursued and implemented ! in this PC/M if required. Since it is uncertain whether these relocations will be required, any pipe suppon changes will be submitted as CRN's to this package if deemed necessary.
/MPORTANT REMARKS: Since each solenoid valve assembly with welded flange connections will !
be interchangeable between locations in either St. Lucie unit, a unique tracking system is required: (1) ; for configuration control purposes and, (2) to eliminate future (and potentially tedious) drawing changes. l A weld number identification scheme has been established for each Unit I assembly in the TEDB change package (given as Attachment 4 to this PC/M); however, this enhancement concept was not considered during the lead work for Unit 2. The serial number and valve body number for that valve welded into the assembly is matched to a set of four field weld numbers (see PC/M Drawing JPN-034-196-009) Specific weld identifications have been assigned through the use of the PASSPORT Weld Control System Weld identifications for the existing Unit 2 valve / spool assemblies. any prospective spare assemblies (with the bolted bonnet valve) and any backup assemblies (configured with a scal-welded solenoid valve) must also be assigned, fabricated and tracked in an identical manner as that gwen for Unit 1.
1 PC/M 034196 Rev. 1 l Page 8 of 16
- 3. Evaluation of the Flanged Valve / Spool Assemblies and Flange Materials (continued)
)
- b. Flange Material !
The Unit 2 PC/M of Reference 4 has established the precedence for flange material selection. Flange specifications for Unit I shall be identical to those supplied on the Unit 2 valve / spool assemblies. The j Unit 2 flange specifications that will be applied for all seven Unit I assemblies are given as: ' Flange Specification: AShE Class, 2500 lb rating, socket weld, raised face,1", Schedule 160 bore Material: ASME SA 182, F304 stainless steel l Since valve / spool assemblies will be interchanged between both St. Lucie units, a comparison of these Unit 2 specifications must be made against those flanges supplied on the original Unit 1 RCGVS design (see Reference 27). Unit 1 flange specifications are as follows: Flange Specification: AShE Class,1500 lb rating, socket weld, raised face,1", Schedule 160 bore ' Material: AShE TP 316 stainless steel Major differences include the pressure class (2500 lb. vs.1500 lb.), the type of stainless steel (304 vs. 316) and the thicknesses (the 1500 lb. flanges are slightly thinner but its material has a higher yield value) These differences are in the material code allowances and are not considered to be significant. ' Since flanges are considered to be nearly equivalent to each other, the use of the flanges supplied on Unit 2 will be acceptable for use on Unit 1. Gasket and bolting specifications shall be designated in accordance with the piping specification of Reference 41 (for Pipe Code SS-7,2500 lb. Stainless Steel). Gaskets shall be a spiral wound Type 304 stainless steel with graphite such as Flexitallic Flexacarb Style CG or equivalent. Bolting shall conform l to AShE SA-193, Grade B7 threaded full length with a diameter of 7/8" and an approximate length of 5-1/2", ANSI B16.5, to ensure full engagement of the nuts. Nuts shall conform to ASME SA-194, Grade 2H or Grade 7 semi-finished heavy series hexagonal per ANSI B18.2.
PC/M 034-196 Rev 1 l Page 9 of 16 CONCLUSION This PC/M provides the documentation and justification for the following plant changes to the RCGVS system to increase solenoid valve reliability and to facilitate maintenance and testing of these same valves at various plant operating conditions:
- a. replacement of the seven original RCGVS Target Rock seal-welded primary solenoid valves with l a Target Rock solenoid valve having a bolted bonnet design,
- b. addition of three 1" system isolation valves just upstream of the primary solenoid valves (two on the Reactor head vent line and one on the Pressurizer vent line), and
- c. provide flange sets on each primary and secondary solenoid valve to create a unique valve / spool assembly for universal valve replacements in either St. Lucie unit.
Previous evaluations have approved the bolted bonnet design as an acceptable replacement for the seal-welded design. The bolted bonnet valves will be installed in an approved configuration in accordance with the design documentation. Also, the three new manual valves for system isolation and spool-piece assemblies have been evaluated to be acceptable for in-plant use (see Reference 43 which is given as Attachment 6). l Since the RCGVS solenoid valves are required to operate after an accident, this MEP must be classified as Safety-Related. Each valve is located within'a Quality Group B/ Class 2 portion'of the RCGVS. The modifications presented within this documentation package change neither the design basis nor any operational or performance requirements approved in the FSAR (Reference 1) or in the Technical Specifications (Reference 2). The St. Lucie PASSPORT System was accessed on Apnl 16,1996 and there are no outstanding designs in progress which will l affect or are affected by this MEP. The Active Safety Evaluations List was also accessed and reviewed on April 16,1996, and no safety evaluations are impacted, nor do they impact this MEP. I
)
Although the RCGVS and associated valves are discussed in the FSAR, this modification is not to the level of detail provided in the FSAR. The changes result in no impact or degradation, either directly or indirectly, to any safety functions required for analyzed accidents, and do not increase any radiological hazards. This evaluation together with the stand-alone safety evaluation of Attachment 6 supports the "10CFR50 59" screening on Page 1 of this MEP. For items (b) and (c), the addition oflocked-open manual isolation valves and flanged end connections to all RCGVS solenoid valves is analogous to the addition of a new pipe section within the system. Since the new isolation valves will be locked open and will not be closed except for the performance of approved maintenance or testing activities, they will have no impact on normal or post-accident Plant operations. Thus, it has been shown that this modification is within the scope of the 10CFR50.59 since it is not a change to the facility or procedures as described in the FSAR, nor does i: require a change to the plant Technical Specifications. Furthermore, this modification does not affect Nuclear Safety in a way previously not evaluated in the FSAR. Therefore, the modi'ication provided by this MEP can be implemented without prior NRC approval.
PC/M 034-196 Rev 1 I Page 10 of 16 SPECIAL INSTRUCTIONS \ IMPLEMENTATION REQUIREMENTS 1. Coordinate all work with Operations and Hcalth Physics to obtain appropriate clearances. 2. Cut and remove the existing four primary solenoid valves (V1441, V1442, V1443 and V1444) in accordance with PC/M Drawings JPN-034-196-004 and 005, Sheet 1 of each. Replace these four valves I i with the Target Rock bolted bonnet design and assemble each valve within the standard valve / spool configuration given by PC/M Drawing JPN-034-196-003. Install all four valve / spool assemblies as shown on PC/M Drawings JPN-034-196-004 and 005, Sheet 2 of each. The valve / spool assemblies are expected to be fabricated in the shop; PC/M drawing JPN-034-196-010 shall be used as a fabrication aid. 3. Cut and remove the existing three secondary solenoid valves (V1445, V1446 and V1449)in accordance with PC/M Drawings JPN-034-196-006 thru 008, Sheet 1 of each. Replace these three valves with the Target Rock bolted bonnet design and assemble each valve within the standard valve / spool configuration given by PC/M Drawing JPN-034-196-003. Install all three valve / spool assemblies as shown on PC/M Drawings JPN-034-196-006 thru 008, Sheet 2 of each. The valve / spool assemblies are expected to be fabricated in the shop; PC/M drawing JPN-034-196-010 shall be used as a fabrication aid. !
- 4. At least three additional flange sets have been ordered and should be available to construct standard
{ valve / spool assemblies from the seal-welded (body-to-bonnet joint) solenoid valves that were cut out in i Steps 2 and 3 above. Those valves which are deemed to be most functionally adequate shall be selected ! for spooling. PC/M drawing JPN-034-196-011 shall be used as a fabrication aid. These assemblies will be stored on site as a possible future alternate for the bolted-bonnet valves. A CRN shall be created to ' document the weld number ID's for each valve / spool assembly with a seal-welded solenoid valve. !
- 5. '
The valve /spoollength may present minor interferences with seismic restraints which are located upstream of Valves V1441, V1442 and, possibly V1443. Pipe supports 8770-RCVG-58 and 59 (and possibly j RCGV-15 and 56) may require relocation to facilitate installation of flanged valve assemblies. Should these j supports, or any other supports require relocation, they shall be submitted to engineering via CRN to this i package. Expansion anchors shall be installed in accordance with Reference 39. !
- 6. Gasket and bolting specifications has been designated in accordance with the piping specification of l l Reference 41. Gaskets shall be a spiral wound Type 304 stainless steel with graphite such as Flexitallic l Flexacarb Style CG or equivalent. Bolting shall conform to ASME SA-193, Grade B7 threaded fulllength l with a diameter of 7/8" and an approximate length of 5-1/2", ANSI B16.5, to ensure full engagement of the nuts. Nuts shall conform to ASME SA-194, Grade 2H or Grade 7 semi-finished heavy series hexagonal per ANSI B18.2. Torquing of all flange bolts shall be perfonned in accordance with Reference 42.
- 7. After fabrication of all seven valve / spool assemblies, preliminary testing is recommended (e.g. low pressure l seat leakage test, high pressure seat leakage test, stroke time test and operational test) to assure that each valve is operating correctly prior to installation in the plant. The operational test shall include testing of the position indication system.
l i 8 Cut and remove portions of the existing RCGVS pipe (Lines 1"-RC-B24 and I"-RC-B00)in accordance with PC/M Drawings JPN-034-196-004 and 005, Sheet I of each. Install all three 1" manual isolation valves (V1650, V1651 and V1652)in accordance with PC/M Drawings JPN-034-196-004 and 005, Sheet ; 2 ofeach. Where possible. the stems for Valves V1650 and V1651 should be similarly aligned while Valve V1652 should be installed with the stem in a vertical position.
- 9. All welding shall be in accordance with the FPL Welding Control Manual. Weld numbers are specified on i the PC/M drawings and have been previously identified within the PASSPORT Weld Control System. If additional weld numbers are required, a CRN will be required to this PC/M.
- 10. The three manual valves shall be locked in the open position in accordance with the Plant standards for (a) l mechanically securing the as-supplied handwheel and, (b) the administrative procedure for the control of valves, bcks and switches (see Reference 37).
I 1. Pipe support drawings included in this package are for administrative revision to drawings only and require I no physical modification. I
l l PC/M 034196 Rev. 1 l Page 11 of 16 POST-MODIFICATION TESTING 1
- 1. As a prerequisite to any post-modification testing, all RCGVS lines shall be flushed following the installation of pipe flanges and manual valves, and the completion of all related welding operations. The use of a temporary Y-type strainer (flanged and cut to the standard 16" valve / spool length) is acceptable. ;
- 2. ASME Section XI, Sections IWA-4400 and IWA-7400 exempt 1" and smaller valve replacements from hydrostatic testing. A system leakage test shall be performed to assure leak tightness. ;
- 3. Following installation of the bolted bonnet solenoid valves per this PC/M, they shall be tested to verify l proper operation in accordance with Plant procedures (e.g. Reference 38, as applicable). The tests should I include a low-pressure seat leakage test, a high-pressure seat leakage test, a stroke time test, and an operational test.
- 4. Following installation of the three manual valves per this PC/M, each shall be stroke-tested under pressure ;
to verify proper operation and isolation capability (utilmng the RCGVS Control Room pressure instrument, l ; PI-l117, to document readings). l l I l i i i +
PC/M 034196 Rev. 1 l Page 12 ot' 16 LIST OF AFFECTED DRAWINGS AND VENDOR MANUALS dL JDdud3d.DIA. wings (1) All Affected (2) (3) MEP (4) PC/M Drawing No Rev Description / Title " Plant Drawines Rev P Rev JPN-034-196-001 1 Addition of RCGVS M 8770-G-078, 18 1 1 Spool, Valves & Flanges l-Sheet 110 JPN-034-196-002 1 Addition of RCGVS M 8770-G-215, 2 2 Spool, Valves & Flanges Sheet 8 1 l' JPN-034-196-003 1 Typical Valve Spool M 8770-G-215, 2 2 1 Detail Sheet 8 JPN-034-196-004 1 V1441/V1442 & Pipe M 8770-B-124, 3 2 Sheet 1 of 2 Cut and Removal Sheet RC-225 1 l-JPN-034-196-004 1 Vl441/V1442'& Pipe M 8770-B-124, 3 2 1 l Sheet 2 of 2 Rework Sheet RC-225 JPN-034-196-005 0 V1443/V1444 & Pipe M 8770-B-124, 1 2 0 - Sheet I of 2 Cut and Removal Sheet RC-226 JPN-034-196-005 1 V1443/V1444 & Pipe M 8770-B-124, 1 2 1 Sheet 2 of 2 l Rework Sheet RC-226 JPN-034-196-006 0 Valve V1449 M 8770-B-124, 2 2 0 Sheet 1 of 2 Cut and Removal Sheet RC-229 JPN-034-196-006 1 Valve V1449 M 8770-B-124, 2 2 1 Sheet 2 of 2 l Rework Sheet RC-229 JPN-034-196-007 1 Valve V1446 M 8770-B-124, Sheet 1 of 2 Cut and Removal Sheet RC-231 1 2 1 l-JPN-034-196-007 i Valve V1446 M 8770-B-124, 1 2 1 Sheet 2 of 2 l Rework Sheet RC-231 JPN-034-196-008 0 Valve V1445 M .8770-B-124, 2 2 0 Sheet 1 of 2 Cut and Removal Sheet RC-232 JPN-034-196-008 1 Valve V1445 M 8770-B-124 2 2 1 l Sheet 2 of 2 Rework Sheet RC-232 JPN-034-196 09 & 1 Field Sketches (Weld ID N/A (not to be N/A N/A 1 -JPN-034-196-010 for RCGVS Valves) used for as-building) i l See Page 13 for the List of Notes used above. j j
PC/M 034-196 Rev. 1 l 1 Page 13 of 16 LIST OF AFFZCTED DRAWINGS AND VENDOR MANUALS (continued) i A. Included Drawines (continued) (1) All Affected (2) (3) MEP (4) i PC/M Drawina No. Rev Descrintion/ Title " Plant Drawings Rev E Rev JPN-034-196-101 0 Pipe Support C 8770-RCGV-13, 2 2 0 Sheet 1 of 2 RCGV Sheet 1 JPN-034-196-101 0 Pipe Suppon C 8770-RCGV-13, 2 2 0 i Sheet 2 of 2 RCGV Sheet 2 l JPN-034-196-102 0 Pipe Support C 8770-RCGV-14 2 2 0 RCGV ! JPN-034-196-103 0 Pipe Support C 8770-RCGV-16 1 2 0 RCGV JPN-034-196-104 0 Pipe Support C 8770-RCGV-19 1 2 0 RCGV I JPN-034-196-105 0 Pipe Suppon C 8770-RCGV-20 1 2 0 l RCGV JPN-034-196-106 0 Pipe Support C 8770-RCGV-22 2 2 0 l Sheet I of 2 RCGV Sheet 1 JPN-034-196-106 0 Pipe Support C 8770-RCGV-22 2 2 0 Sheet 2 of 2 RCGV Sheet 2 JPN-034-196-107 0 Pipe Support C 8770-RCGV-26, 2 2 0 Sheet 1 of 2 RCGV Sheet 1 JPN-034-196-107 0 Pipe Support C 8770-RCGV-26, 2 2 0 Sheet 2 of 2 RCGV Sheet 2 JPN-034-196-108 0 Pipe Support C 8770-RC-158-128 1 2 0" RCGV JPN-034-196-109 0 Pipe Support C 8770-RC-161-139 1 2 0 RCGV i Notes to Drawmg Update: 1. Loads shall be removed from all support drawings, however, the restraint directional arrows shall be maintained. ;
- 2. Since the solenoid valve assemblies will be interchangeable between locations in either St. Lucie unit, a weld number identification scheme has been established in the TEDB change package to eliminate future (and potentially tedious) drawing changes.
B. Vendor Mamh MEP(4) l Plant Document Number ** Rev (2) Vendor /Eauinment Remarks Rev None '" ' (1) DISCIPLINE: C = Civil. E = Electrical, I = I&C, M = Mechanical N = Nuclear ; (2) REVISION of anected drawing / vendor manual. Indicate "new"ifthe drawing / vendor manualis being created. The ! engineer is accountable for reserving the new drawing / vendor manual number. (3) DRAWING UPDATE PRIORITY: For PSL. indicate I for (SRD). 2 (Non-SRD), or 5 (Other). For PTN, indicate i i for (POD),2 (CRD),3 (MD),4 (ED), or 5 (Other). (4) MEP REVISION under which last drawing change was made. (5) Vendor manual changes and/or additicns were provided in an earlier Plant document. See Reference 10.
PC/M 034196 Rev. 1 l 1 Page 14 of 16 OTHER AFFECTED DOCUMENTS l Reference Paragraoh/Page or Document Attach Revised Pages 1. Administrative Procedure 1-0010123, Rev.100, entitled Plant review required. Revise Appendix E
" Administrative Control of Valves, Locks and Switches" to include the 3 new locked-open valves
- 2. Design Basis Document DBD-RCS-1, Rev. O, i See Attachment 3 !
entitled " Reactor Coolant System"
- 3. Mechanical Maintenance Procedure 1-MMP-01.04, Rev. 3, Currently includes bolted body valves; entitled " Unit 1 Reactor Head Vent Gas System Valves" However, Plant review is required.
4. Various Plant Procedures for Normal RCS/RCGVS Plant review required to include the 3 new Fill and Vent, Off-Normal and Emergency Operations locked-open valves. Guidance shall be provided as appropriate to Plant operators. ATTACHMENTS Attachment Number Numbgr Descriotion/ Title ofPages 1 Target Rock Bolted Bonnet Valve Certification 3 and Interchangability Statements 2 Comparison of Target Rock Solenoid Valve Characteristics (Models 808-001 an ! 80-B-001 BB) 3 3 Design Basis Document Change Package 3 4 TEDB Change Package 39 I 5 { DELETED FROM REVISION 1) 6 10CFR50.59 Safety Evaluation Which Supports 31 the Installation of Three Manual Globe Valves Notes: (a) Attachments 1 and 2 were unaffected as a result of the Revision 1 issuance. (b) Pages 31-39 of Attachment 4 are new to Revision 1. (c) Attachment 6 was unavailable for the issuance of Revision 0 but is being issued with Revision 1.
i PC/M 034-196 4 Rev. I l, Page 15 of 16 i 4 REFERENCES l 1 1. FSAR for St. Lucie Unit No.1, Amendment 14 dated June,1995, Section 5.7 entitled " Reactor Coolant Gas , i Vent System" l 2. Technical Specifications for St. Lucie Unit No.1, Amendment 141, dated October 27,1995, Section 3/4.4.151 - , entitled " Reactor Coolant System Vents" - 1 3. Design Basis Document DBD-RCS-1, Rev. O, " Reactor Coolant System", Section 7.11 4. f PC/M for St. Lucie Unit 2, PC/M No. 043-295, Suppl. 3 dated December 22,1995 entitled " Replacement of Reactor Coolant Gas Vent System Solenoid Valves (V1460, V1461, V1462, V1463. V1464, V1465 and , V1466)" ,. 5. St. Lucie Repon from MMEG/JPN entitled " Root Cause Analysis for PSL Unit 2 Reactor Head Vent Gas , j System (RHVGS) Inservice Seat Leakage",1995, by Tom Sanders, Joel Kagan, and Mike Little ! 4 '6. St. Lucie Plant Problem Repon for Unit 2, Repon No. 95-108 dated December 3,1995 entitled " Unit 2 Reactor i Gas Vent System Reliability Problems During Unit Stanup"
- 7. FPL Request for Purchase Authorization with Target Rock Corporation, Requisition No. 00020757 for Solenoid-
. Operated Bolted Bonnet Globe Valves, Stock Code No. 0053084-1 ) 8. FPL Purchase Order with Target Rock Corporation, P.O. No. C 95934-90377 dated June 30,1995 for Solenoid-Operated Bolted Bonnet Globe Valves
- 9. Procurement Engmeering Technical Evaluation for St. Lucie Units 1 and 2, Evaluation No. 038155, dated 3 November 19,1995 for Target Rock Solenoid-Operated Bolted Bonnet Globe Valves - includes the required
- Item Equivalency Evaluation for the use of bolted bonnet in lieu of the seal-welded design 1
- 10. DCR for St. Lucie Units 1 and 2, DCR No. DCR-95-0343, Rev. O dated November 16,1995 entitled " Target
! Rock Corp. Documentation for Model 80B-001BB (Bolted Bonnet)" ,
- 11. Target Rock Document for St. Lucie Units 1 and 2, EMDRAC Drawing No. 2998-19633, Rev. O entitled l I j " Design and Seismic Report for the Valve Model 80B-001BB Solenoid-Operated Globe Valve- TRC Repon No. l 1 5851" '
- 12. Target Rock Technical Manual for St. Lucie Units I and 2, VTM No. 2998-19634 entitled "Model 80B-001BB !
i Solenoid-Operated Globe Valve" { j 13. Target Rock Valve Drawing for St. Lucie Units 1 and 2, EMDRAC Drawing No. 2998-19635 entitled " Solenoid- l l Operated Globe Valve - Energize to Open,1", SW, -Model 80B-001BB" !- 14. Target Rock Valve Drawing for St.' Lucie Units 1 and 2, EMDRAC Drawing No. 2998-19636 entitled " Assembly
! ~ ;
Drawing for Target Rock Solenoid-Operated Globe Valve - Sheet 1 of 2" ! 15.. Target Rock Valve Drawing for St. Lucie Units 1 and 2, EMDRAC Drawing No. 2998-19637 entitled " Assembly l l- Drawing for Target Rock Solenoid-Operated Globe Valve - Sheet 2 of 2" l
- 16. Target Rock Solenoid Valve Qualification Test Repon, TRC Repon No. 2375, Rev. E l
, 17. Equipment Qualification Documentation Package for St. Lucie Plant Unit 1, Equipment Qualification Report and l Guidebook, No. 8770-A-451-1000, Rev. 3 - [ l 8. Mechanical Design Specification for the FPL Nuclear Engineering Department, Document No. MN 3.08, Rev. 2, dated October 14,1993 entitled " Steel Station Valves 2 Inch or Smaller - Nuclear Safety Classes 1,2, and 3"
- 19. Mechanical Design Standard for the FPL Nuclear Engineering Depanment, Document No. STD-M-005, Rev.
1, dated ' August 10,1995 entitled " ANSI /ASME Code Reconciliation For Replacement Material, Pans, and
. Components" 20.
) Anchor / Darling Valve Drawing for St. Lucie Unit 1 EMDRAC Drawing No. 8770-12705 Rev. O entitled "1"- 1875 Socket Ends Stainless Steel Globe Valve" j 21. ASME Boiler and Pressure Vessel Code, Section III,1977 Edition, Winter 1978.
- 22. Code of Federal Regulations. Part 10CFR50 55a. Edition January 1.1992
- 23. Stress Calculation for St. Lucie Unit 1. Calc. No. RCV-1000C, Rev. 4 i
l.
[ Attaehment I to PC/M 054-196 Esv. 0 10 06 95 to:43 3516 293 4949 TARGET R0cK CORP p gg3 'Z003 003 Target Rock Corporation, tusE secaonci.c4 Ac. o 0. Som v. carmiegeaie. N.Y t1715 0957
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- REVISED 9/12/95 CERTIFICATE OF CONFORMANCE CUSTOMER: Florida Power and Light Company FOR: St. Lucie Plant CUSTOMER P.O. #: 95934 90377 TRC PROJECT #: 95Z.506 PRODUCT: l' Solenoid Operated Valve P O item- 1 Qty 2 S/N I A 2
. . . . . . . . . - . . ~ . ...
We cenify that the pans noted heretn meet all the requirements of the Purchase Order. D. rMng and Speci6catnns Funher we cenify that the detaiied fabncation, inspection and test reccrds oted in the order and speci6 cations are traceable and are on file. l l TRC Qaality Manual. E(ition 5. Revision 9. Dated 9/30S4 is applicable. We cemfy that items provided with this order are identical to or functionally interchangeable Mth the same items supplied in the original model and as such will not arTect the original quali5 cation covered by Target Rock Quali6 cation Test Repon No. 2375 Rev. E. 1 9lt1.lV R. 'E. Olaner Date Manager, Quality Engineering
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PECCY BRUNO. SR. CONTRACTS ADMINISTRATOR, Exc. 648 i DATE: ' D6d. 3, /kk M TOTAL NUNSER OF PAGES: / INCLUDING tills COVER SBERT l l sv53nCTs Tke VAll/G 2/DbELS &>B-ml-fa [C8-Col - 94 be- 40t -/dR IF YOU DO NOT RECSIVE ALL PAGES, PLEASE CALL SACE AS S005 AS POSSISLE t*MflL} //D& DU1. Abbt11CWAL TGL5CDA) TDbnv'. < - kl of 7M &'26JKc7 n/A l d G H e l G b n)&AA Mb_nnh CA) M SAHE P.O. 0 9070/C& BY cswaysneul SD6/A)fEL.'A)6 ADb R)Eh6 Et2ttr 70 7149A. 4/6c. l 6 Ro 6 LM .LE- 7/l test. l r 79 ASHE ceD6 /477 Gbtriegl
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' Target Rock Corporation.1966E Broadhollow Rd., P.O. Box V, Farmmodale. N.Y.1173b-0917
- wasno, c.n c...w unum i Tel. No.: 407-465-3550 Fax No.: 407-468-4258 L950306 Att384tIMt 7. to Florida Power & Light PC/M 054-196 St. Lucia Plant Kav. 0 P.O. Box 128 Pt. Pierce, FL 34954 pagg g g 3 l
Attention: Ms. Carol Wallace
Subject:
Comparison of So* 4..;dd valve Characteristics l i TRC Proposal No. b 6 037 l I
Dear Ms. Wallace:
Thank you for your continued interest in Target Rock Corporation (TRC). l Please find attached the information you requested. We have tried ! to completed it as fully as possible. If you should need any further information, please do not hesitate to contact us. Very truly yours, ! TARGET R CORPORhTION t .,,, (T . a Ed LoBuglio sales Engineer Nuclear & Industrial Products Div. cc: J. White R. Crawford FO' (516)2934144
~eeer0 e '5'6)293 ~B00
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Target Rock Corporation.1966E Broaanonow Rc., P O. Sor v. Farmmgcase N.Y. *
- 735 0917 1 YP te.. :.n u....c , 2-.o- Attah I to PC/M 0M-196
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SUBJECT:
_7 A C l IF YOU DO NOT RECEIVE ALL PAGES, PLEASE CALL BACK AS 500N AS POSSIBLE : ea d w sea or ro e ana a J4wf ) Acf - CHAA Acfat t! r/ c t l b Me l l:0mFAA tt *N P A & c.r FoA. < as see-ooi 23. l ' inen ct.s s o a - o o i- 12.
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! Pese 2' I
C0AEpl4ASION OF SOLSWOW VALW CNMtACsasas ama i MCEVE VALWE t n .- MANUPACTURER TARGET ROCK CORP. i TARGET ROCK CORP.
""" NUMGM _ 300 00198 800401 12 ASSEhE.Y OWO. NO. 1ajee101 13021104 VALVs Size 1 1- 1*
PUNCTION i ENEROGE TC QPEN ENEAGlZE TO OPEN BONNET TYPE I SOLTED SEALED WELDED
' 4 END CONNECTloN $^*'L8T WELD I $hi WELO BODY TYPE Y PATTERN i Y PATTERN i
ANSIPRggs m_^mg 6 2188 i 2186 i END TO EIS 7.50 INCHES 7.50 INCHES CENT""" TO TOP 16.83* vWmCAL 1s.S" VWITICAL OF WALVE . 30.4* ANGLE I CENT" "8 TO 20.02* VUmCAL 30.5* vuni= CAL DISASS8"_V >WSNT ' I
**""*a MAX. DIA. '
S.se* I 4.5' MotalNG _ i 5.379' PLANGE SEAT La^N
"^****d' TO SEAT 3*
- sei 25.190 set 1st PLOT 70 IEAT 24.250 se6 24.290 see 2nd PILOT TO MAT 30.380 sei 24.250 sei SEAT CONTACT UNg l UNE SEAT u^ha8ACSIG STELUTE S . STELUTE 6 i I DISC M.*mn*ACS89 I NONE8aame IS M anns*"" MAT'u NONt4OISC 3 MAR 0ssGD MAT'u i
Cv 18 i 13 WEIGHT WI , 42 ST I POSm0N *a'a^ TION REED SWITCM j REED SWITCH i PC C Itf"JS-T" m 135VOCA.8 Aars its VDCJ0.8 AMPS i COIL CL'** CLASS M CLASS M l COL EQ LIFE , 10 YEARS I 10 YEARS MLOT OPERAT30 YES YES STROIE T1hd > 2 SEaa* W/ PLueD PLOW > 2 S8C00006 WI Plute PLOW MAIN SEAT Otaw?ERS t ._ t.0. ' 1.200* 6 1.250' O.D. ! NONE NONE l MtM MOLE OtAa4TfA 0.0goa 0. M -
! 6 oid* 0.140'
Attachment 3 to PC/M 034-196 Rev. 1 I Page 1 of 3 DESIGN BASE DOCUMENT CHANGE PACKAGE COVER SHEET l Descriotion of Channes l Three new 1" Anchor Darling valves (given as V1650, V1651 and V1652) are installed on the process lines of l the Unit 1 RCGVS just upstream of the primary solenoid valves (two on the Reactor head vent line 1"-RC-B00 and one on the Pressurizer vent line 1"-RC-B24). These valves will provide manual isolation of the RCGVS to allow dual isolation for the Target Rock solenoid valves so that maintenance and/or testing can be performed while at normal RCS operating temperature and pressure. This design change will provide more latitude for future maintenance of these valves. 1 Basis for Change i See PC/M 034-l%, Rev. I entitled "RCGVS Solenoid Valve Replacements, Addition of Flanged Valve / Spool l Assemblies and Manual Valve Additions" References See PC/M 034-l%, Rev. I entitled "RCGVS Solenoid Valve Replacements, Addition of Flanged Valve / Spool l Assemblies and Manual Valve Additions" Aporovals Prepared by: Ym 4 N " Date 4-M-% Verified by: w5 M Date 4-MP4 Approved by: Date , 2/)A Data Review /Inout (as aoolicable) Reviewed b'y: Date Data Entry by: Date Data Entry Verified by: Date Form 53, Rev 6/94
.._ . _m _ _. . . . _ . . . . _ _ . _ . _ _ _ _ _ - _ _ _ _ ._. _ _ _ . _ . . _ _ . _ _ . _
a :n m ! REACTOR COOLANT GAS VENT SYSTEM Eo 29~ 3 -i oc CD O E' a :n se C E' On o 2. O O -a CONT AfMMf NT PURQt HE ADER
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- Attachme,t $ to j PC/M 054-196 l Rev. i l Page 5 of $
! St. Lucie Unit 1 Document No. DBD-RCS 1 i REACTOR COOLANT SYSTEM Revision O Design Basis Document Page 336 of 336 i ! 1963 I 10.7.38 PC/M 130-81, Reactor Vessel Level Monitor System Pressure Boundary i Modification l 10.7.39 PC/M 136-81, installation of MI Cable for QSPDS I 10.7.40 Palisades Primary Coolant System Design Basis Document prepared for i Consumers Power Co., Revision 0 ! 10.7.41 Document No. 8770-A-451-1000, St. Lucie Unit 1 Equipment Qualification Report and Guide Book, Revision 3, Figure 3-5 I i 10.7.42 Emergency Operating Procedure 1 EOP-15, Functional Recovery, i -. Revision 4 - I 10.7.48 PC/M 0$4-196, Kav. O metttial'KMVS Solodi Yalve Kaplaesmeets, Adetton of Fhmeed Valve / Spool Assembles and Manual Valve Adettons' [ l D
I t Attachment 4 to PC/M 034-196
- i Rev. 1 l j Page 1 of 39 i
TOTAL EOUIPMENT DATA BASE CHANGE PACKAGE COVER SHEET l
- Descriotion of Channes i
1. RCGVS valve and pipehne modifications are being implemented by this PC/M for improving the ability to l i replace / remove / test the primary and secondary solenoid valves. To facilitate maintenance efforts and improve j valve life, the existing RCGVS seal-welded Target Rock solenoid valves in the valve locations for Valves V,1441, j V1442, V1443, V1444, V1445, V1446 and V1449 are being changed to bolted-bonnet Target Rock solenoid
- valves. [ NOTE: Reference 10 to PC/M 034-196 provides a TEDB change package for the alternate use of the i
bolted body valve. However, additional TEDB changes will be necessary to reflect the actual installed condition ] of the bolted bonnet valves in these seven solenoid valve locations and are provided herein.] l
- 2. Since the solenoid valve assemblies will be interchangeable between locations in either St. Lucie unit, a weld l
j number identification scheme has been established in this TEDB change package. This scheme was devised to ' l climinate future (and potentially tedious) drawing changes and for configuration control purposes. Specific weld , . identifications have been assigned through the use of the PASSPORT Weld Control System. 2
- 3. In support of this plant modi 6 cation work, three 1" manual valves are being added to the RCGVS for.better l
- system isolation should a valve problem occur at elevated RCS pressures and temperatures. This TEDB change package adds .hese three valves (V1650, V1651 and V1652) to the electronic vendor data system. ;
- i
- 4. Additionally, this TEDB change package revises four snubber thermal movements.
l l 1
- Basis for Channe
{ See PC/M 034-l%, Rev. I entitled "RCGVS Solenoid Valve Replacements, Addition of Flanged Valve / Spool l l j Assemblies and Manual Valve Additions" 4 o References See PC/M 034-l%, Rev. I entitled "RCGVS Solenoid Valve Replacements, Addition of Flanged Valve / Spool l
- Assemblies and Manual Valve Additions"
! Acorovals i . Prepared by: b d. d Date 4 J7-% Verified by: 5M Date 4 '/8'M Approved b : -- Date I Data Review / input (as aoolicable) f I 1 Reviewed by: Date i Data Entry by: Date Data Entry Verified by: Date Form 53,Rev 6/94
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l i l l PEcility PSL Units 01 LMD: ' l , Components V1441 l { ( Aerociates l lAtti 4 l l l lRev: l I Date Prtnted l lPage & olf $$ l 11 I TOTAL EQUIPMElff DATA &ASE SKErr EQ Tag V1441 EQ Revt 27 SQ Doc Pace 21.0 Systees 01 RAACTOR COOLAlrf STETBI Seientes ! Safety Clase _ Eng Fefe Q Groups S EQ Sury Note: 0 SQ Speers RG197: W EQ Related: Y EQ Scsws 2*03 RG197 Cats , Q Beste: _ EQ Remarket AG197 Types ,
;3mp Type VL Sub Typer FB Safety Channel _ Pce: 430 191 Neesa SOLENOID VALVE FOR REACTOR HEAD VElff KEADER A TO RCVGS Lcen Codes RCB/75/S 20/E 26 Startup System 0348 Locn Deect *nstl MFG 8: TAR TAAGET ROCK VALVES Engineering Verified Y j
s j
- ssti Modeli s0s 001 S S Reve 0 orig Pos C 9g934-90377 l
_ 1 Comp Groupt NPRDS: N Acct Nos $30 I SQ Tabr _ Insulation Revi . Traina , scaffold Regt . Critical Compi , Control Room Comps , Kerk Groups IST Reqd Y RWP Reqds Y j M2 int pgues , , , , , , , , , I I e S
rectittys PSL untts 01 LMD: 1 Components V1441
, l lPC/A o34-196 'l l l l 8 Aer$ctates t
l lAtt 4 l i IRevi 1 l l Date Printeds l lPage 4 of 3h l . i l i I TOTAL EQOIPMErr DATA SASE SHEff OESIGN CODE YEAR N/A A.B GENERIC NUMBER N/A SPECIFICATION NUMBER N/A REAN TYPE 1 REQ N/A ACTIVE OR PASSIVE N/A EEAM TYPE 2 RSQ N/A STEM DIAMETER INCE NRC RELIEF REQUEST 4 N/A PEMOTE INDICATION N/A SONNET TORQUE FT LBS LENGW INCN PACKING TORQUE FT LSS MAI ALLOW STROKE TIM SEC AEMARE31 N/A "R1FICE DIAMSTER INCN KSMARKS2 N/A MIN REQD STROKE TIME SEC NORMAL MODE N/A TEST FREQUENCY MOS FLON OVER/UNDER SEAT N/A TEST REQUIRED N/A FAILURE MODE - N/A
- EST PROC SHEET [ 7 N/A rEIGNT / 37 1 Las VALVE THRUST RATING 1 M LSS VALVE TORQUE RATING FT Las
' VENDOR STEM FACTCR N/A 3ENERIC FIQ N0/ TYPE N/A 1 l I I i
P!ctlity: PSL Units 01 !RD: , l l Components V1442 l l l
. AeIociates l lAtt 4 l l lReva j i Data Printed: l lPage $ of N i i
l l s TOTAL EQUIPMENT DATA SASE SHIFT EQ Tag V1442 EQ Rev 27 EQ Doc Pact 21.0 Systems 01 REACTOR COOLAlff SYSTEM Salonics I Safety Clases _ Eng Refs Q Group B 50 Surv Note: 0 50 Speers R0197: N IQ asiated: Y TQ Scews 2-04 RG197 Cati , Q Bastes EQ Remarken RG197 Type: , Comp Typet VL Sub Type PB Safety Channels _ Pes: 430-191 Name SOLENOID VALVE POR RSACTOR HEAD VEWT HEADER S TO RCVGS Loca Codes RCS/73/S-20/8-26 Startup Systemt 0348 Locn Descs Init! MPQ fa TAA TAAGBT ROCE VALVBS Enghneering Verified: Y
- nett modet; sos 00t SB Rov 0 Orig Pos C $$$34=$C)77 Coop Group NPRDS: N Acct N 550 EQ Tabs _ Insulation Revls . Train ,
scaffold Req , Critical Comp: , Control Room Comp , l Nork Groups IST Reqd Y RNP Reqde Y ' mint Pgmes ,,, , , , , , , e 4 k s
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,A .. 4 i i l lRev j l l D.te Printeds l lP.ge 6 of 3$ l i l i ! I i
TOTAL EQUIPMENT DATA RASE SERET Dr.wingi Sheet, Coordinatee l l 8770*C 124 RC-235 8770.A*4SO 8770 0 078 (C+4) ,k d 8770-0 215 110 4 ( $ $$s%k [n e pgh g yg
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$11E 1.0 INCH TYPB GLOSE N/A CPERATOR TYPE SOLND N/A BODY MATERIAL 31658 N/A BONNr? DESIGN N/A END' CONNECT!ON 5W N/A COEFF FLOW N/A ANSI CLASS 2500 N/A ASMR CLASS N/A SAFETY C1. ASS 2 N/A ESASCO OPERATOR No. 442 N/A PIPS CATEGORY 2 N/A
$CEEtfJL3 / Tit!CKNRSS W/A DESIGN CODE N/A DESIGN CODE YEAR W/A A 8 GENERIC NUMBtR N/A
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/M RISTORY: 56 80s 043 188 _
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Description:
Ncidel s- Rev. Inst 1. Eng Ver. TAA TAAGET ROCE VALVES 800 001 000 Y Parameter Names valuei UON: 5125 1.0 !NCH TYPE 3LOSF N/A OPERATCR TYPE SOLND N/A 9007 MTERIAL 31655 N/A SCNNET CESIGN N/A END CONNECT!CN SW N/A COBPP PLON N/A ANSI CLASS 2500 N/A ASME CLASS N/A SAFETT CLASS 2 N/A ESASCO OPERATOR NO. 444 N/A PIPS CATBOORT 2 N/A SCNEDUL5/TH!CDrESS N/A e
Ficalityt PSL Units 01 LMD: ~
, i coe ,onenti vse4a l l l ; As meneter i IAtti 4 l 1
1 laevi l l Data Printed I lPage 7 o't $ $ l l I 1 TorAL EQUIPMENT DATA SASE SHEET SPECIFICATION NUMBER N/A EEAM TYPE 1 REQ N/A ACTIVE OR PASSIVE N/A ESAM TYPB2 REQ N/A ETEM D1AMETER INCH NRC 2.BLIEF REQUEST S N/A RBOOTE INDICATION N/A SONNET TORQUE FT LSS
'ENGTH . INCH PACKING TORQUE FT LSS MAX ALLOW STROKE TIM SEC REMARKS 1 N/A CRIFICE DIAMETER INCH RIMARKS2 N/A MI3 REQD STROKE TIME SEC NORMAL MODE N/A *EST FRSQUENCY NOS FLOM OVER/UNDER SEAT N/A TEST REQUIRSD N/A FAILURE NODE N/A TEST PROC SNBET O N/A wErowr / 37 J Las VALVE TERUST RATING b d LBS VALVE TORQUE EATING FT LSS ' VENDOR STEM PACTOR N/A 3ENERIC FIG NO/ TYPE N/A e
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I lrc111tt,Pst, unit, at tat . l l Pt.//A 034-196 l l Component V1443 l l l l Associates l lAtt 4 l l l 1 Revs l ' Cite Printeds l lPage $ elt 3$ I i i l I i TOTAL EQUIPMEarf DATA BASE SRBET EQ Tags V1443 SQ Rev 27 EQ Doc Pacs 21.0 Systees 01 SAAC'!VR C001. ANT SYSTEM j Seteeles ! Safety Clases _ Eng Ref: 1 Q Groupe B BQ Surv Notes O RQ Speers RG197: N J i EQ Related Y EQ Scewi 2-05 R3197 Cati . I I Q Seelei _ EQ Rosartes RG197 Type: , ; 1 Csep Type VL Sub Types FB Safety Channels _ Pes: 430 191 j Name: SCLENOID VALVW FOR PRESSUR12BR VENT TO RSACTOR HEAD VENT Locn Codai RCS/99/5 20/E 24 Startup Systeet 0348 Locn Deses
- n:El MPQ 8: TAR TARGET ROCK V)*, YES Engineering Verified: Y
- nssi Model: 805-001 S S Revi 0 Orig Poi C 95934 - 90377 w _
Comp Group: WPRD3s N Acct No: Sto EQ Tabe _ '.neulat&cn Revle , Train: , ic2ffold Reg . Critical Coops , Control Room Compi , Estk Groups IST Reqdi Y RWP Reqde Y 0 O WI . a. . . . . . . . 9 8 e
l l l l Fec&lity: PSL tJnits 01 LMD: , i Components vtaas l l PC/M C34*i I Assoc *ete 1 [Ats: 4, 1 i l l**ve I i l l Date Printed l l peg, $ og g l I l l l TOTAL SQUIP,mrF DATA SASE SMEFT Drav1D91 Sheets Coosdinntes enemmenergpr's on..A..s. rl.v.tu.g r(4.s.-W r C a.., 3
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- ~
l Nrs: Desertptioni Modeli Rev. Inst 1. Eng ver. TAR TARGRT ROCK VALVES 808 001 000 Y Peremeter Nese: Veluei UOM 3158 1.O INCH 1 I TYPE 3 LOSE N/A CPSRATOR TYPE SQLND N/A 90D7 MAfrRZAL 31.SS N/A BONNET CESIGN N/A END CONNECTION SW N/A OCEFF Flow N/A ANSI CLASS 2500 N/A ASNE CLASS N/A SAFFTY CLASS 3 N/A BBASCO CPERATOR NO. 443 N/A P!!E CATEGORY 2 N/A SolBDULS/TRICENESS N/A CBSIGN CODE N/A OSSIGN C003 YEAR N/A I I
l Ficilitys PSL Units 01 LJ4D s , i l l Components V1443 l l l l Associates I lAtts 4 l 1 i isovs I 1 i Dste Printed, l JPase 10 et 39 ! i t i i TCFTAL BQUIPMEtrF DATA SA$5 SHEET A-5 CBWERIC NUMBER N/A SPSCIF3 CATION WUMBER N/A ESAM TYP51 REQ N/A ACTIVE OR PAS $1VB N/A EXAM TYPE 2 REQ N/A STEM DIAMSTBR INCH NRC RELIBF REQUEST 5 N/A REMOTE INDICATION N/A BONNET TCRQUE FT Les LENGTH INCH PACKING TORQUE FT L38 max ALtou STROrs TIM ssC REMARKS 1 N/A ORIFICE DIAMETER INCH REMARRS2 N/A MI3 RSQD STROKE TIME SBC NORMAL MODE N/A TEST FREQUENCY MOS FLOW OVER/UNDBR SRAT N/A TEST RSQUIRED N/A FAILURE MODE N/A TEST PROC SKRET M N/A wstruT T 37 ) Ls3 VALVE THRUST RATING V LSS VALVE TORQUE RATING FT LBS
' VENDOR STEM FACTOR N/A GBWERIC FIG NO/ TYPE N/A 1
l l I 1 1 4
_, . .. . , _ . . ~ _ _ . - ~ - . _ _ .. -. .- _.. _ . Pscality: PsL Uniti 01 we, 1 Component: V1444 llS$/#bOI4"khl l l l Aaractates , j lAgge f g I l laevi l 1
' DSte Printed s l lPagell og $$ l l 1 1 TOTAL EQUIPMEarf DATA BASB $3357 EQ Tage V1444 SQ Rev 27 BQ Doc Pac 21.0 Systees 01 RSAC"FOR COOLAff? SYSTWI 5essetci 2 safety Claes: _ Eng Ref:
O Groups a 30 surv motsi o sQ speeri R0197: w EQ Relatodi Y EQ Scows 2*04 RG197 Cat , Q ...... EQ R. r... R.,9, T,pe. . 1 Coop Type VL Sub types FB Safety Chazzeli _ Pes 430-191 l I Wase: SOLEWOID VALVE FOR PRESSURIZER VDrf TO REACTOR HEAD VEFT ' Locn Codes RCB/77/8 20/E-26 Startup System 0349 Lcen Desci instl MF0 9: TAR TARGET ROCK VALVES Engineering Verifieds Y In:El Model 80B+0018% Revi : Orig Pos C $f$34=$O)77 j
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Focility: PSL Unit: 01 L99: N /M ObN~ 8% Component: 231 CcoocI:te Att: Y Rev: l Octa Printed: 02/28/96 , Pe** 2 5 af 59 TOTAL EeulPMENT DATA SASE SteEET E3 isg: N/A E9 Rev N/A EO Doc Pec: N/A System: T3 PIPE Amo SUPPORT SYSTEns 511emics l Safety Clace: _ Eng Ref O Grotp: D Ee Surv #cto: N/A E0 speer N/A RG197: , E3 RIltted: u te Scow: N/A RG197 Cat , O Seele: Ee Reserke: N/A RG19T lype: , Comp Type: SU 5th type: Safety Charmel: Pce: 062-191 3:w: SMUBSER 04 I-1-RC-SOO tlwE IRPV VENT - A 1RAlk) Locn Code: RCS/63/5-18/E-25 stortte system: 128 tecn Desc: Instl mfg #: PAC PAClflC SCIENilfl0 Engineering Verified: Y instl Model: PSA 0.25 eev 000 oris Po: N/f Camp Groep: NPe05: N Acst No: 530 E8 feb: _ insulation Revt: _ irein: _ h effald seq: _ Critical Comp: , contret moam Comp: _ Work Grosp: 151 Reqd: N SWP Reqd: Y maint Pome: _ _ _ _ _ _ _ _ _
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facility: PSL tAnit: 01 to: , M 06 'I Ceepenent: 232 Aseeclete: Att: 4 eev: 1 Data Printed: 02/28/96 , Page 25 "' 59 TOTAL EEUIP9EENT DAIA SA5E $NEET E3 Teg: N/A fe Rev: N/A te Dec Pac: N/A system: 73 PIPE AND SUPPORT SYSTEMS Salemics I Safety Clase: _ Eng Ref 8 Grong: D Ee Surv Note: N/A to speer N/A RG197: _ E3 Cstated: N Ee Scow: N/A RG19T Cet: _ e Basis: Ee temerke: N/A RG197 Iyper _ Camp lype: SU 54 Types _ Saf ety Chemet: Pte: 062 191 Name: SaR20ER ON 3-1-RC 300 tlNE (RPW VtNI - A TRAIN) tocn Code: BCS/68/5 10/E-25 5tertip system: 128 Locn Desc: snstl mfg #: PAC PACIflC SCIENilfl0 Engineering Verified: Y Instl Model: PSA 0.25 Rev: 000 Orig Po: N/f Camp Group: NPROS: M Acct No: 530 ES leb: Insulation Aswl: Irain: Sccffald Req: _ Critical Comp: _ Control Room Comp; _ e Work Groep: IST Reqd: N RWP Reqd: T meint Pome: _ _ _ _ _ ___ _ r t I i
Facility: PSL Unit: 01 tee: O ~b component: 232 A.. i. .: At1 4 eevs 1 Date Printed: 02/28/96 Pesegy of 39 - lotAL EeulPMENT DAI A SA5E $NEET Drawing: sheet: Coordinates 8110-8-052 8T70-8-122 STTO s-124 RC-22S STT0 G-123 1 leth Manuela: N/F Pr oc edares: 1-M-0006 Notes: PCM/DCR NISIORT: 56-80 Approved Alternete Mfg:
Description:
Model: Rev. Insti. Eng ver. PAC PAttfl0 5CitullflC PSA-l/4 000 W T Parameter Nome: Walue: UOM: MARK Numett RCGV-14 N/A CAPACllT N/A COLO 5tillWG .4" N/A CAIC INERM & ~ 0.1** N/A INCN SIRost , CALC toad (EIPS) *$P _O O T _ f N/A DRAG ACCEPIANCE ttSS filAN OR EOUAL 17.58 W/A TRAvtl RANGE N/A IRAN 51IlON fuRE Kil N/A RIMARK51 N/A RIMARK52 N/A RIMA #L53 N/A
tecility: P5t unitz et to: _ FC/NI OSO -l% Ca w t: 234 (seeclete: Att: h Gew: j Cete Printed: 02/28/96 Pagegg of 39 - TOTAL E0ulPMENT DATA SASE $NEET te leg: N/A te Rev N/A te Dec Pac: N/A System: T3 PIPE ANs suPPont ST5f tses solemics I Safety Cteses _ Eng Ref: O Gresp: D E0 Surv Note: N/A E0 Speer: N/A 3G197: , te Related: N to Scew: N/A RG197 Cet: , O Seeis: _ to Reserks: N/A R$197 Type , (wp lype: Su Sth type: _ safety Channet: _ Pce: 062 191 Name: $Nuetta ON 3 RC 824 t lNE (RPV VENT - A IRAIN) tecn Code: ste/83/5 18/E-25 Stortte systee: 128 tocn Desc: Instt MfC #: PAL PACifl0 SCitNilfl0 Engineering verifled: V ave.it Model: 844 0.25 new: 000 orte Po: N/F (sep Group: _ MPR05: N Acct No: 530 to lab: , insulation R el: _ train: ,
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Description:
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. I i TOTAL EQUIPMEarf LATA BASE SKEET EQ Tagi V1445 EQ Revs 27 EQ Doc Paci 21,0 l Systems 01 REACTOR COOLANT SYSTEM Setsmici ! Safety classi ,,, Eng Ref Q Groups a EQ Sury Notes 0 SQ Speera RG197: W i
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Osme Typet VL Sub Types FS Safety Channeli _ Pem 430 191 Namei 3CLENOID VALVE FOR REACTCR HEAD VENT TO QtTENCH TANK Lacn Codei RCB/75/8-24/E 26 Startup systems c34A Locn Desca Instl MFC si TAR TAAGET ROCK VALVES Enganeering Vernfied: Y i m e-_ _ - j Insti Model. 40s.0019$ #evi 0 Orig Pos C $%$N*$O)Y7 00Kp Groups NPRDSI N ACCC No, 630 ^ ~ l IQ *abi ,,, Insulation Revlt , Traini , iaaffold Regt . Orttt:al Comp: , Control Room Compt , I dork Groupe IST Reqds Y RwP peqd e Y I Msant Pgess , ,,,,,,,, s i l l l 1 I i I i l l I l l
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*T PE OLCBE N'A OPEAATOR TYPE SOLND NA BODY MTER!A;. 3;655 N A SONNET CE31GW Ns A END CONNECTION SW NA
;*ETF FLCW NA ANSI C1. ASS 2500 N/A A3ME CLASS N/A SArrfT CLASS 2 N/A ERASCO CPERATOR NO, 445 N/A PIPE CATEGORY : N/A SCHEDULE /THICENESS N/A OESIGN C00E N'A t
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i Attachmeet 6 to PC/M 054-196 Revision 1 Page1of31
- 10CFR50.59 Safety Evaluation l for the s
Addition of Three Manual Isolation Valves
- within the RCGVS Process Vent Lines i
j i i - i
- Florida Power & Light Company
- St. Lucie Units 1 and 2 i
i 4 l JPN-PSL-SEMS-96-007 Revision 0 SAFETY RELATED i
1
! Attaduneet 8 to PC/M 054-10 JPN-PSL SEMS-96-007 Ravision 1 Revision 0 Page 2 of $1 Page 2 of 20 DESIGN INTERFACE l REVIEW AND APPROVAL RECORD j FPL PLANT: St. Lucie Units 1 and 2 1
TITLE: Addition of Three Manual Isolation Valves { within the RCGVS Process Vent Lines ] ENGRG. ORGANIZATION: JPN/PSL LEAD DISCIPLINE: Mechanical REVIEW / APPROVAL:
- INTERFACE TYPE FPL GROUP PREPARED VERIFIED APPROVED APPROVED *
; INrer .nmrw wr g f) ,
MECH X d f i N/A ELECT X N/A ! N/A N/A N/A l , I&C X N/A N/A N/A N/A j CIVIL X N/A N/A N/A 'N/A LIC" X N/A N/A /4 N/A i CSI X N/A N/A N/A N/A NUC X N/A N/A N/A N/A
- FITI I
- For Contractor Eval's As Determined By Projects " Redew Interface As A Minimum On All 10CFR50.59 Eval's and PLA's 1
i FPL PROJECTS APPROVAL: e-MNM# ~ DATE: 26!4/>
' l i . EXTERNAL INTERFACES: None DATE:
i i 11
1 Attachmert 4 to Pc/M 0s4-1:3 KMaism 1 JPN PSL SEMS %-007 Pagt 3 of $1 Revmon 0 Page 3 of 20 J TABLE OF CONTENTS I
)
i Frtion No. Section Description Eage l
)
1 COVERSHEET 1 , 1 DESIGN INTERFACE REVIEW AND APPROVAL RECORD 2 TABLE OF CONTENTS' 3 1 ABSTRACT 4 1.0 PURPOSE OF CHANGE AND TECHNICAL DESCRIPTION 5 l 2.0 REVIEW OF EXISTING LICENSING REQUIREMENTS 7 l i
3.0 TECHNICAL ANALYSIS
OF EFFECTS ON SAFETY 9 j 4.0 EFFECTS ON TECHNICAL SPECIFICATIONS 13 ) 5.0 FAILURE MODES AND EFFECTS ANALYSIS / i HUMAN FACTORS ANALYSIS 13 l 6.0 UNREVIEWED SAFETY QUESTION DETERMINATION 14 7.0 PLANT RESTRICTIONS 17 8.0 REQUIRED ACTIONS 17
9.0 CONCLUSION
S 18
10.0 REFERENCES
19 i l 1.0 ATTACHMENTS 20 I l
. .. . . . _ _ . _..m _. m _ _ _ _ _ _ _ . - . _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _
i wa* . . l. PC/M 094-1*3 gaMm 1 JPN PSL.SEMS %-007 l Fact 4 of $1 Revmon 0 t Page 4'of 20 l l St. Lucie - Units 1 and 2 10CFR50.59 Safety Evaluation ] Addition of Three Manual isolation Valves within the RCGVS Process Vent Lines l i ' ABSTRACT i During the 1995 Fall refueling outage for St. Lucie Unit 2, three 1" manual valves were installed in the
- Reactor Coolant Gas Vent S j stem (RCGVS) process lines (two manual valves on the Reactor head vent l line and one on the Pressurizer vent line). These locked-open globe valves were added to enhance
- maintenance and/or test efforts associated with the primary solenoid-actuated vent valves and secondary i solenoid actuated block valves in that system. Should solenoid valve rework become necessary at elevated
( Reactor Coolant System (RCS) pressure and temperature, manual isolation of the RCGVS from the RCS l could be performed by closing these manual valves. A Minor Engineering Package (MEP) screen.ed from j 10CFR50.59 was used to justify their inclusion into the system. A similar plant change is being planned for Unit i during the 1996 Spring Refueling Outage. Valves will be identically located just upstream of i the primary solenoid valves. i i- A Company Nuclear Review Board Subcommittee review of the Unit 2 change package questioned the , need for a 50.59 evaluation and a St. Lucie Action Report (STAR) was generated (see Reference 10.1). This safety evaluation is written in response to this STAR. This evaluation will more formally assess the safety significance of adding these three manual valves to the RCGVS and provide a generic review for their installation. This safety evaluation will be applicable to both St. Lucie nuclear units and will supplement the engineering justification for each unit's plant change / modification package. For this evaluation, a review of the FSAR, the Technical Specifications and the Design Basis Documents (DBD) was again performed to determine any possible impact. The review demonstrates that the , proposed activity for installing manual valves in the Unit 1 RCGVS (and the previous related activity for
]
Unit 2) does not involve an unreviewed safety question or require a change to the Technical Specifications. l Since each concem posed by the 10CFR50.59 can be appropriately answered, prior NRC approval is not j required. ; It is concluded that the installation of these isolation valves will have no affect on plant safety or operation.- l The permanent valve additions to the RCGVS are acceptable from the standpoint of nuclear safety in that ! it does not affect the original design basis nor impact the safe operation of the Plant. This evaluation has indicated that these new valves provide a backup to the existing line valves and actually offer additional system isolation capability. These modifications are considered to be a maintenance aid in the event that RCGVS solenoid vent valves need replacement, refurbishment or additional testing at elevated RCS pressure and temperature. Hence, these changes do not affect the primary safety related function of the RCGVS during post-accident situations or other secondary functions of the system. The subject valves are located within a Quality Group B. Seismic Category 1 portion of the piping system and are designed to ASME Section III, Class 2. Therefore, this evaluation is classified as Safety-Related. i
Affashment 6 fe Ft/M OS4-l*3 Reddue 1 JPN-PSL-SEMS.%-007 Pagt 5" of $1 Revision 0 Page 5 of 20 1.0 PURPOSE OF CHANGE AND TECHNICAL DESCRIPTION 1.1 Pumose of Change The MEP's given by References 10.8,10.9 and 10.10 were developed in support of St. Lucie Plant maintenance activities to facilitate the procedures . for replacement, refurbishment or testing of the RCGVS solenoid vent valves at hot operating conditions. As part of these plant changes, manual locked-open isolation valves were added to the process vent lines and similarly located within each St. Lucie unit (implemented via Reference 10.9 for Unit 2 and proposed in Reference 10.10 for Unit 1). These manual valves were located just upstream of the primary solenoid-actuated vent control valves (two manual valves on the Reactor head vent line and one on the Pressurizer vent line - see the sketches within Attachments 11.1 and 11.2). The purpose of this safety evaluation is to more formally assess the safety significance for adding these manual isolation valves to the RCGVS process lines and provide a generic review for the acceptability of their installation. As such, this safety evaluation will be applicable to both St. Lucie nuclear units and will supplement the engineering justification for each unit's plant change / modification package. 1.2 Technical Descriotion l.2.1 ' Solenoid-Actuated Control Valve Replacements Small-bore piping is provxied from the top of the Reactor and Pressurizer heads to enable various vent functions. The RCGVS solenoid valves are configured with four upstream vent valves in parallel and three downstream block valves in parallel for venting to either the Quench Tank. Contamment atmosphere or to the Contamment Sump. The primary and ,s secondary solenoid vent valves within the RCGVS for both St. Lucie units are defined as the following (see Attachments 11.1 and 11.2 for seven system locations per unit): St Lucie Unit No. Primary Solenoid Valve Tag Nos. Secondary Solenoid Valve Tag Nos. i 1 V1441, V1442, V1443 and V1444 V1445 V1446 and V1449 2 V1460, V1461,' V146'! and V1463 V1464, V1465 and V1466 These safety related control valves are required to open after an accident to vent non-condensible gases from the RCS. They may also operate during normal plant stanup and shutdown to provide a vent path when filling or draining the RCS. The original valves in both Units were installed with a seal-welded body-to-bonnet joint. The MEP's of References 10.8 and 10.10 evaluate the installation of replacement valves with a bolted bonnet in each of the seven locations for Units 1 and 2, respectively. A change-out to the bolted bonnet design was highly desirable as it will simplify maintenance effons, reduce related costs, increase valve life, and reduce the spare pans inventory requirements.
. - - ~- . - - - . - . . . - . - - . ~ - - - - - . - ~ . . - . . - ~ . .
j l i- Atta d uu s t 4 fe 1' l' M/M 004-12 JPN.PSL.SEMS.%.007 1 Emhlm 1 Remion 0 Paes 6 of fl Page 6 of'20 i l i
- 1.2 Technical Descrintion (continued) 5 i I.2.1 Solenoid Actuated Control Valve Replacements (continued) i I During the Fall 1995 Unit 2 refueling outage, bolted bonnet valves were installed in the j primary solenoid valve locations. Other system design modifications were also
- incorporated to achieve case in maintaining the solenoid valves through procedure. One ,
such feature was the addition of manual isolation valves upstream of the primary solenoid l l valves for positive system isolation should valve maintenance be required at elevated RCS l pressure and temperature. The primary maintenance goal associated with the improvement !
- j. items was to facilitate both the solenoid valve removal / replacement and the remote test l
effons under those RCS conditions. j 1 The Unit i MEP of Reference 10.10 addresses the long term design improvements that l 3 evolved from the Unit 2 solenoid valve replacement effort (based on the problem report i of Reference 10.13). On this basis together with the lessons learned from the Fall 1995 ! Unit 2 outage work, the identical design improvements were incorporated into the Unit I
- MEP for improved maintenance practices.
l l ) l.2.2 Manualisolation Valve Additions I I Should solerioid valve maintenance / testing become necessary at elevated RCS pressure and temperature, the provision for adequate manual isolation of either the Unit 1 or Unit 2 RCGVS was not originally considered as part of the system design. Hence, the RCGVS solenoid-operated valves could only be worked with the RCS depressurized or if the upstream isolation valve did not leak. To facilitate maintenece under elevated RCS l pressure and temperature, the addition of manual valves in the RCGVS provides the capability for dual, localized isolation of the Reactor and Pressurizer head vent lines for personnel safety and ALARA purposes. Currently on Unit 1, only one manual isolation valve (V1450) exists on the Reactor head vent line and it is located just above the Reactor Cooling Shroud making access difficult. Previous to the implementation of Reference 10.9 for Unit 2, two manual valves (V1212 and V1470) were installed but their location was near the Reactor head area. For the RCGVS redesign effort v/hich requires the dual isolation feature for each St. Lucie unit, the scheme maintains two new manual valves (V1650 and V1651) to be located on the process line just upstrean. c f the primary solenoid vent valves along the west sidewall of the Pressurizer. Single valve isolation previously existed within the vent line from the Pressurizer on both St. Lucie units (via V1239). Since this valve is located within the Pressurizer cubicle and approximately 5 feet above the head,it is considered to be fairly accessible to an operator. Therefore, only one new valve is required to provide the desired dual isolation upstream of the solenoid vent valves. This new manual valve (V1652) has been identified as part of the RCGVS redesign and shall be located on the Pressurizer vent line adjacent to the same west sidewall only at a higher elevation. Per the redesign, all three 1" manual valves in each unit will be in a normally locked-ops position to preclude inadvertent positioning during power operation.
Attachmet 8 to PC/M 094-l~] JPN PSL-SEMS-%-007 E Maim 1 Revmon 0 1 Pagt 7 of $1 Pace 7 of 20 1.2 Technical De scriotion (continued) l.2.2 ManualIsosation Valve Additions (continued) Under current pmgrammatic guidelines for small size replacement valves, the Anchor / Darling valv. design will be used for the three new isolation valves. The manual valves and associcx1 piping are safety-grade and meet the same requirements as the RCS. All piping is designated as Quality Group B, Seismic Class I, and designed to ASME Section III, Class 2. As such, this evaluation is classified as Safety-Related. 2.0 REVIEW OF LICENSING REQUIREMENTS l References 10.2 through 10.5 present the licensing documents, i.e. FSAR and Technical Specification, for the Unit 1 and Unit 2 RCGVS designs, and the applicable sections for review. The discussions for each St. Lucie unit are identical. The major difference is the presentation of the FSAR flow diagram; Unit I shows the RCGVS integrated onto the RCS flow diagram (see U1 FSAR Figure 5.1-3 referenced from U1 FSAR Section 5.7) while Unit 2 depicts the RCGVS in the RCS section as FSAR Figure 5.1-4b as well as on its own separate diagram (see U2 FSAR Figure 9.3 7 from U2 FSAR Section 9.3.7). Redundancy is not required and one RCGVS figure will be eliminated within the Unit 2 FSAR change package to avoid confusion with respect to future FSAR updates. Figure 5.1-4b addresses an FPL referenced drawing and Figure 9.3-7 does not show any reference drawing. Therefore, from a contrc' standpoint, Figure 9.3-7 shall be eliminated from the Unit 2 FSAR. For simplicity and clarity, the remainder of this evaluation will address the manual valve additions generically for the Unit 1/ Unit 2 RCGVS design. All statements, actions and conclusions shallapply to both units. 2.1 FSAR Reauirements The basic purpose of the RCGVS is to remove the non-condensibles (primarily hydrogen) from the RCS in a reasonable time period over a wide range of reactor coolant pressure and temperature during post-accident conditions. The affected RCGVS vent lines containing these three manual valves are connected off the Reactor and Pressurizer heads. A technical review must be made to ensure that these manual valves do not affect the original design function. Per the discussions in FSAR. the RCGVS performs a safety-related function under post-accident conditions. This system is designed to perform the following:
- 1. The primary safety-related function of the RCGVS is to allow for remote venting of the RCS via the Reactor Vessel head vent or the Pressurizer steam space during post-accident situations when large quantities of non-condensible gases may collect in these high points. [Aside: A quality-related function appearing in the DBD's of References 10.6 and 10.7 is to maintain the integrity of the RCGVS pressure boundary.)
- 2. As a secondary (not-nuclear safety) function, the RCGVS may also be used in normal RCS venting procedures required for a plant outage.
l Attachment 8 to j FC/M 094-1:3 JPN PSL-SEMS 96-007 EMalen 1 Resmon 0 < Pagt 8 of fl Page 8 of 20 2.1 ESAR Reauirements (continued) i i l . l The FSAR figure which depicts the RCGVS flow diagram shows all existing, normally-open, manual valves on the process vent path to be locked-open to effect these design bases. Pertinent design criteria has been established with respect to the system flowrates, controls and piping. The RCGVS parallel piping configuration assures redundancy for the RCS vent path and , flow restricting orifices in each vent path limit excessive RCS mass loss in event of a line break. l Active components such as the solenoid valves are supplied with emergency power and are l designed for a single active failure; this active failure will not prevent venting to the Containment. l Vent controllability is available in the Control Room and all controls are designed to allow ven6ng , under accident conditions. This system must be operable following all design basis events except ) those requiring evacuation from the Control Room. l The RCGVS is not intended for use during normal power operation and administrative controls ) are provided to mmmuze the possibility of inadvertent operation. Power is removed from all l solenoid control valves during normal plant conditions. During accident conditions, the RCGVS will be operated as an on-off system to remove gas from the RCS. The volume of gas to be removed is determined by Reactor Vessel or Pressurizer monitoring and the venting time is dependent'upon this v.olume, RCS pressure and RCS temperature. 2.2 Technical Soccification Reauirements The Technical Specification identifies the vent paths and necessary valving for ensuring the ability to vmt the RCS. At least one vent path consisting of two vent valves and one block valve I pe ded fron; smergency sources shall be operable and closed at locations from the Reactor Vessel head and the Pressurizer steam space. The applicability is during plant operating Modes 1 thru 4. ! If one of these vent paths is inoperable, it must be restored to the operable statur within 30 days, or be in Hot Standby (HSB) within 6 hours and in Cold Shutdown (CSD) within the following 30 hours. If both RCS vent paths are inoperable, at least one path must be restored to the operable status within 72 hours, or be in HSB within 6 hours and in CSD within the following 30 hours.
1 -l 1 l Attesheet 8 to ! Ft/M 004-r3 j JPN.PSL-SEMS 96-007 Radelet I Revmon 0
, Page 9 of 81 Page 9 of b0 9 ;
- i t
j
3.0 TECHNICAL ANALYSIS
OF EFFECTS ON SAFETY In order to justify the use of the three new manual valves within the process vent lines of the RCGVS, a reconciliation of the system and valve designs as well as the normal and post-accident operative capabilities will be necessary. 3.1 RCGVS System Desion Analvsis j Key system design interfaces are presented below for review and analysis. 3.1.1 RCS Pressure Boundarv i i The RCGVS piping between both the Reactor and Pressurizer heads and the RCS j pressure boundary barrier valve, i.e. the primary solenoid vent valves, is rated for full RCS design pressure and temperature (2485 psig and 700 'F - see References
- 10.14 and 10.15). The manual valves will be located in between these components
- and will have design rating in excess of these parameters (see Section 3.2.3 below).
l The RCS pressure boundary will not be affected by the installation of the three j manual valves. Hence, the piping / valving configuration given by this evaluation does not alter the RCS pressure boundary and is compatible with the system
- requirements.
3.1.2 Seismic Quahfication The affected piping and supports have been evaluated and found acceptable for the additional weight of the valves (see Reference 10.16 and 10.17). 3.1.3 Leakage Control To control leakage from fluid systems inside Containment, it is good practice to normally weld the components of the RCGVS into the piping system and muumize the use of flanged connections where practical. It follows that all installed valves . should be the packless-type to mirumize leakage. However, there are many flanged j' connections within the RCGVS to provide case for routine maintenance efforts. Additionally, the three new manual valves will be welded into the system and they will not be packless. Furthermore, all RCGVS valves which have been installed as process, vent and drain valves are not the packless type. This conflicts with the j information that exists within the FSAR's of St. Lucie Unit 1 and Unit 2 (see j Sections 5.7.3.3 and 9.3.7.3.3). The concepts of welded components and packless valves are system design features and used where practical but they are not bona fide system requirements. Sufficient equipment exists within the Plant to monitor and detect leakage from the RCS and connecting auxiliary fluid systems. Additionally, the ASME Code (see ; Reference 10.19) allows the usage of flanged connections and non packless type valves. As such, the FSAR will be changed to reflect the current St Lucie l installations. FSAR change packages are given as Attachments 11.3 and 11.4.
Affashmert 4 C , PC/M 054-C3 JPN PSL SEMS-96-007 ) h1 Revision 0 l Pags 2 of 71 page to of 20 l l 3.1 RCGVS System Design Analysis (continued) l 3.l.4 Design Integration A review of both the St. Lucie PASSPORT Active Safety Evaluations List and DCTS did not locate any safety' evaluations or outstanding change documents which would affect the scope of this safety evaluation. ; 3.2 Manual Valve Design Analysis Critical design parameters associated with the three new 1" manual globe valves have been reconciled and are addressed below. 3.2.1 Code Requirements (including year and addenda) Reference 10.18 speci6ed ASME Section III,1977 Edition, Winter 1978 Addenda (Reference 10.19) or any later code year / addenda up to and .ncluding that approved by 10CFR50.55a (Reference 10'20). . These valves are , designed / manufactured to ASME Section III,1986 Edition, No Addenda. This code year is approved by 10CFR50.55a Edition January 1,1992. 4 3.2.2 Code / Safety Classification The valves are located within a Quality Group B (USAS B31.7) Class 2 portion of the piping system (see References 10.14 thru 10.15 and 10.21 thru 10.24). The Anchor / Darling valves being supplied are ASME Class 1 valves. In accordance with ASME Section III, Subsection NCA-2134, valves classified as Class 2 or 3 in their Design Specifications (original construction) may be constructed and stamped in accordance with the rules of Subsection NB (Class 1). The ASME Safety Class will be shown as Class 2 in TEDB (or other drawings such as the P&ID, isometric, etc.) since the new installed valves are of a higher ASME Safety l Class. The ASME Safety Class shown in these documents will be retained to l' indicate the minimum ASME Safety Class requirement of the piping system. 3.2.3 Design Pressure and Temperature The ANSI pressure class of the Anchor Darling valves is ANSI 1878 standard interpolated pressure class (see Reference 10.28). Review of the TEDB and the piping isometrics of References 10.14 and 10.15 indicates that the system design pressure and temperature are 2485 psig @ 700 *F. These valves are designed to operate at 2705 psig @ 700 'F. Therefore, the pressure class of the manual valves bounds the design and is acceptable. 2 .l
Atteshment 6 fe l PC/M OH-1T3 JPN-PSL-SEMS-96-007 l MI Reusion 0 l Pagt11 d M Page i1 of 20 l 4 I 3.2 Manunt Valve Design Analvsis (continued) i i 3.2.4 Material Reference 10.18 specifies acceptable materials for both St. Lucie nuclear units. Due to ALARA concems associated with wear products of cobalt based materials in contact with reactor coolant fluid, cobalt hard facing has been restricted by FPL < (unless no other hard-facing is available). The Anchor / Darling valves do not employ cobalt hard-facing and the materials of construction meet the requirements ; of Reference 10.18. !
. i 3.2.5 Pressure Drop The C, , or flow coefficient for the Anchor / Darling valve is 8 (see Reference i 10.28). This C, value imposes a negligible line loss with respect to the entire {
system resistance. Review of the Reference 10.6 and 10.7 design basis documents indicate that the vent rate is limited by the class break restricting orifices, and addition of these valves will have no impact on the vent rate. i 3.2.6 Spatial Envelope These manual valves will be located in an area on the west side of the pressurizer that is open faced and have an end-to-end dimension of 51/2" (see Reference 10.28). Based on a review of the piping drawings of Reference 10.14 thru 10.15 as well as 10.25 thm 10.27, there is sufficient room for installation and operation Yf these valves. 1 3.2.7 Procurement Level i The correct procurement classification for thes.e manual globe valves in their ASME Class 2 application is Procurement Class PC-1 and they have been purchased accordingly to that requirement (see Reference 10.23). 3.3 RCGVS Onerative Cannhility Operation of these new manual valves will be in accordance with the Technical Specifications for RCS vents. As stated in Section 2.2 of this evaluation, at least one l Reactor Coolant vent path consisting of two vent valves and one block valve powered from emergency buses shall be operable and closed from both the Reactor Vessel head and the Pressurizer steam space, while in Modes i through 4. The physical closing of a new manual valve will isolate this RCS vent path. Thus, the requirements of Technical Specifications must be evoked whenever one or more of these valves is to be closed. Therefore, a system requirement exists.whereby these manual valves shall not be closed except for the performance of approved RCGVS maintenance, surveillance or testing activities. Furthermore, these manual valves shall be administratively locked open to preclude inadvertent positioning during normal power operation.
. . _ . _ . . .- - = . -. - _ . -- -. .
Attashu sef 8 to PUM 094-180 JPN-PSL-SEMS-96-007 hI Revision 0 Pagt R d SI Page 12 of 20 3.3 RCGVS Ooerative Canability (continued) The ability of the RCGVS to perform its intended quality-related or not-nuclear safety functions as discussed in the above Section 2.1 is not affected by the installation of three new manual globe valves. The intermediate pressure instrument, PI-l117 for Unit 1 (on Attachment 11.1) and PI-l140 for Unit 2 (on Attachment i1.2), remains unchanged and provides control room indication as well as an alarm to assure that the primary solenoid vent valves are not leaking. As discussed above, the new manual valves will be locked-open in order to provide the necessary vent path. Section 3.2.5 (above) has shown that the
- modi 6ed RCGVS vent paths will remain unrestricted and the vent flowrate through both vent lines will not be affected. Also, these new valves provide a backup function to the existing line valves by offering additional RCGVS System isolation capability.
f Accordingly, the installation of these valves will not affect the RCGVS design basis or operative functions. 4 e 1 d e J d j
- - - - - ~ . - . . . - - . - - .. - . . . - . - - - . - . - . . . - . . . ~ - . - - - . - - - .
1 . Affadusset t to
- PC/M 094-1D JPN PSL SEMS-96-007 l EaMut 1 Revision 0 Pags 13 'of $1 Page 13 of 20 l
i 4.0 EFFECT ON TECHNICAL SPECIFICATIONS 1 Since the new manual valves have been designated as having a locked-open requirement during normal plant operating modes, there will be no impact on the ability to meet the Technical
- Specification denoted above. It is noted that p'rior to implementing the aforementioned plant j changes associated with these new manual valves, locked-open valves (V1450 and V1239 for Unit
- 1
- V1212. V1470 and V1239 on Unit 2) already exist in each of the Reactor and Pressurizer process vent paths just upstream of the primary solenoid vent valves.
l Other St. Lucie operating, off-normal and emergency plant procedures must be revised per this l
- safety evaluation and per the MEP that installs the three manual isolation valves. As a minimum,
! this includes the FPL procedures of References 10.31 and 10.32. These plant procedures provide j the instructions for placing valves, locks and switches under administrative control when that component is critical to the safety of personnel or equipment. Administrative control means that i the component shall not be operated without specific authorization. The device for all locked j valves shallbe such that it prevents significant rotation of the handwheel. The new manual valves i will be placed within Appen4 E of Reference 10.31 and 10.32 entitled "Cor ainment and Shield Building Integrity Valve List" where the locked + pen valves (mentioned in the previous paragraph) currently exist. With the planned documentation changes and associated valve lock put in place, no changes are required within the Plant Technical Specifications. 1 5.0 FAILURE MODES AND EFFECTS ANALYSIS / HUMAN FACTORS ANALYSIS A physical plant modification is required as a result of the need for additional system isolation valves. Also, these desired changes require the updating of the FSAR drawing which depicts the system configuration. However based on the conclusions of Section 3.0 above, there are no new failure modes or system interactions as a result of this evaluation. This safety evaluation justifies the acceptability of modifying the RCGVS vent path valve arrangement. This safety evaluation does not involve any changes to the Control Room or Alternate Shutdown Panels nor impose any new operator actions other than verifying that the locked-open feature exists per administrative procedures. Hence, a human factors review is not required.
1 Attadunst 8 ft . 1 ~ Ft/M 094-188 JPN.PSL-SEMS.%007 j Emdelen 1 Revision 0 l Fags W of fl Pace 14 of 20
~
6.0 UNREVIEWED SAFETY QUESTION DETERMINATION
- The Code of Federal Regulations Title 10. Chapter 50.59, allows holders of a license authorizing operation of a utilization facility to make changes in the facility and procedures as described in the a Safety Analysis Report (SAR) and to conduct tests or experiments not desenbed in the SAR j without prior NRC approval provided the proposed changes, tests or experiments involve neither j a change to the Technical Specifications (incorporated in the license) nor an unreviewed safety l - question.
l As defined in 10CFR50.59, an unreviewed safety question exists if: (i) the probability of ; occurrence or the consequences of an accident or malfunction of equipment important to safety 1
- previously evaluated.in the SAR may be increased, or (ii) a possibility for an accident or malfunction of a different type than any previously evaluated in the S AR may be created, or (iii) ,
the margin of safety as defined in the basis for any Technical Specification is reduced. l s 1 1 In accordance with 10CFR50.59, the following evaluation serves to determine whether the l permanent installation of the three RCGVS manual valves as evaluated in this safety evaluation I
- constitutes an unreviewed safety question or requires a change to the Technical Specifications, i Based on the comparison review of licensing documents in the above Section 2.0, all ,
- statements, actions and conclusions shall apply to both units. l 6.1 Does the propowd chance increne the probability of occurrence of an accident previousiv evaluardin the SAR?
l 1 The pnmary purpose of the subject manual valves is to isolate the RCS from the RCGVS l solenoid vent valves to allow maintenance under elevated RCS pressure and temperature. The addition of manual valves in the RCGVS provides the capability for dual, localized isolation of the Re~ actor and Pressurizer head vent lines for personnel safety and ALARA purposes during this maintenance effon. Each manual valve will have a lock-open system requirement to assure that the vent path cannot be isolated during plant operating modes. As stated in Section 3.0 above, manual valves are seismically-qualified and will not inhibit the operative c~apabilities of the RCGVS. Thus, the performance ability of downstream solenoid valve vent valves (which are required after an accident) will not be affected by the placement of manual valves in the two vent lines. These manual valves are considered as passive devices and are not relied upon to perform any safety-related, active function. The installation of new valves into the system is funher accepted since they are designed to the same codes and standards as the existing RCGVS piping. Accordingly, these new valves are designed to maintain the RCS pressure boundary and ensures that the probability of an accident is not increased. Since the proposed valving configuration does not affect any accident mitigating components of the RCGVS, the probability of occurrence of an accident previously evaluated in the S AR will not be increased.
Attasheet 4 to PCM OH-13 Jps.PSL SEMS 96-007 hI Re w on 0 Fae W d il Page 15 of 20 6.2 Does the prooosed change increase the consecuences of an accident oreviousiv evaluated , in the SAR? i The addition of manual valves in the RCGVS process vent lines has been evaluated without any negative effects on the system. The design of the manual valves is satisfactory with respect to the service requirements. RCGVS venting operations will not be impacted in the post-accident situation. As long as the valves are locked open during normal plant operating modes, their presence in the lines cannot impair the ability to vent off the high-point gases in the RCS following an accident. Based on the above and the analysis presented in Section 3.0 of this safety evaluation, the addition of the three subject manual valves will not increase the consequence of an accident previously evaluated in the SAR 6.3 Does the orooosed change increase the probability of an occurrence of a malfunction of couinment imnortant to safety oreviously evaluated in the SAR? 1 There is no change to the process line function, length, routing or supports. Therefore, the l original design basis for the two RCS vent lines is maintained. System operation and component functionality will not be affected by the addition of three manual v4ves. No new failure modes for active equipment are introduced by the new valving configuration. RCGVS active equipment, whkh includes the primary and secondary solenoid vent valves, l will remain operable and be capable of RCS post accident venting in accordance with i Technical Specification requirements. No other existing RCGVS equipment that is l imponant to safety has been affected by the addition of these three manual valves. These l 1 manual valves will not alter the function of this equipment and will not increase the probability of their failure. With respect to a malfunction of the manual valves themselves, , it is highly unlikely since they are passive devices in the line. , The affected piping and new manual valves within the RCGVS have been specified at the RCS design pressure and temperature; hence, the RCS pressure boundary integrity will continue to remain intact. The installation of three valves in this portion of the RCS vent , lines will actually enhance the ability to manually isolate the RCS in the event of a vent line j break further downstream. Thus, based on all the above, the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the SAR will not be increased. i , 6.4 Does the crocosed change increase the consecuences of a malfunction of couinment imnortant to safety oreviously evaluated in the SAR? The manual valve additions will not change the design, safety class or safety functions of 1 the system and no new failure modes have been created. Since the ability to vent the RCS 4 high spots during a post accident event is maintained via the solenoid control valves, the potential for worsening the consequences of equipment malfunctions due to manual valve additions will be held in check. The only other accident consequences that could be affected by this new valve scheme are those from a pipe rupture or seismic event. However, these valves are designed to Seismic Class I and the piping system remains seismically-qualified per the statement in Section 3.1.2 above. Pipe stress calculations were performed due to the weight increases and have shown that the structures, systems and components will continue to meet original design criteria and limits in compliance with the FS AR. 4
3-- Atteshment 6 fe PC/M 084-188 JPN-PSL SEMS-96-007 RaMan 1 Revmon 0 , Pats 16 of fl Page 16 of 20 6.4 Continued These new valves are designed to maintain the RCS pressure boundary. Should a failure of a subject manual valve be postulated, it could lead to a small-break LOCA inside Containment. However, this failure cannot produce a consequence that is not bounded by existing accident analysis since the system's flow restricting orifices (which limits blowdown flow from the break) are located upstream of the new valves. As such, the RCGVS will continue to . maintain its critical function as given in the Technical Specifications and no changes to the Technical Specifications will be necessary. I It is concluded that the new manual valves will neither affect nor change to the condition , of the RCS or RCGVS and equipment within these systems can still be used in mitigating j the consequences of an accident. As a result, the safety analysis will not be affected. ! Therefore, the consequences of a malfunction of equipment imponant to safety previously evaluated in the SAR are not increased. 6.5 Does the pronosed channe create the nossibility of an accident of a different tvoe than any oreviousiv evabus*A in the SAR? The addition of new manual valves in the RCS vent lines does not change the operation of the RCGVS. Furthermore, no new hazards or failure modes have been identified that could be postulated to cause an accident different from any previously analyzed in the FSAR. The valving configuration does not add or affect any equipment cah 'J initiating an accident. . Since no RCGVS design basis changes have resulted from the valve additions and system integrity will not change, the possibility of an accident of a different type than any previously evaluated in the S AR will not be created. 6.6 Does the pronosed chance create the nossibility of a malfunction of eauioment imnorvant to safety of a different tvoe than any oreviousiv evaluated in the SAR? These- new 1" valves are seismically-designed, passive components. Section 3.1.2 demonstrates that the RCGVS piping system with the newly installed manual valves is seismically adequate. Additionally, the new valving and affected piping are designed to full RCS pressure and temperature to ensure that the RCS pressure boundary remains. intact. Once installed, the new manual valves meet the same original RCGVS design basis requirements and design criteria of the RCGVS and perform the same design isolation function of similar adjacent manual valves. A postulated failure of a new locked-open i valve is not likely and, if it did occur, would be probabiliscally no different than a failure of the connecting pipe to which it is installed. Also, based on the FMEA discussions within ! Section 5.0 of this safety evaluation, no new failure modes or new system interactions are
- introduced. As a result, the manual valve additions do not create the possibility of a malfunction of equipment important to safety of a different type than any previously evaluated in the SAR.
k Attasbuset 4 fe PC/M OM-l') JPN PSL SEMS.%-007 RMelenI Revision 0 Pags17 of $1 Page 17 of 20 l: 6.7 Does the pronosed change reduce the margin of saferv as defined in the basis for any ' Technical Snecification? As a result of the new valve installations and the information presented above within this safety evaluation, the original design basis, design enteria and operability of RCGVS 4 System imposed by the FS AR are unaffected. Additionally, no changes are required in any safety analysis, accident analysis, assumptions or Plant Technical Specifications. Consequently, the margin of safety as defined in the basis for any Technical Specification are preserved and will not be reduced. 7.0 PLANT RESTRICTIONS j With three new manual isolation valves installed on the RCGVS process vent lines, the intent of the existing plant design an' d licensing commitments has not been altered for either St. Lucie unit. Since these changes have been previousl; sh~en en not impact the Plant, no additional restrictions i on the plant operating modes are required as a result of this evaluation. No new operator actions ! or periodic surveillance need to be implemented due to the Plant or FS AR documentation changes. ) However, see Section 8.0 below for necessary actions. j t 8,0 REQUIRED ACTIONS i The following actions are required as a consequence of this safety evaluation and apply to both St. . Lucie units: ! 8.1 The three new RCGVS manual valves (V1650, V1651 and V1652) to be installed on each St. Lucie unit shall be locked in the open position in accordance with Anchor / Darling
; recommendations.
8.2 The St. Lucie admirustrative procedures for " Administrative Control of Valves, Locks and Switches" (see References 10.31 and 10.32 for Units 1 and 2, respectively) shall be reviewed and appropriately revised to include the three new locked open valves. As a minimum. Appendix E to these administrative procedures will need to be revised. 8.3 Various operating, off-normal and emergency plant procedures for St. Lucie Units 1 and 1 2 require review and, if necessary, revision to ensure compliance with this safety evaluation. 8.4 Provide appropriate guidance' to St. Lucie Plant operators regarding the new installation of the three locked-open valves in.the RCGVS vent lines (two manual valves on the , Reactor head vent line and one on the Pressurizer vent line). 8.5 A revision to the FSAR's for St. Lucie Unit I and Unit 2 is presented within Attachments 11.3 and 11.4. These change packages eliminate both the discussion on leakage control and a duplicate figure for the Unit 2 RCGVS (and provides appropriate references to the RCS diagram given as Figure 5.1-4b within Section 5.1.2). a
. -. ._ = _- - - ._.
Attashnunt 4 c PC/M OH-188 JPN-PSL-SEMS-96-007 Raddet 1 Revision 0 Pass 18 of $1 Page 18 of 20
9.0 CONCLUSION
S ' This evaluation provides a stand-alone 50.59 safety evaluation which provides the bases for the desired RCGVS manual valve additions within St. Lucie Units 1 and 2. Based on the inferences given by the effects analysis on safety within the above Section 3.0, the Technical Specification review in the above Section 4.0 and the 10CFR50.59 safety evaluation presented in the above Section 6.0, the following conclusions can be made with regard to the addition of three new locked-open manual isolation valves on the RCGVS process vent lines. The permanent valve additions to the RCGVS are acceptable from the standpoint of nuclear safety in that it does not affect the original design basis nor impact the safe operation of the Plant. This evaluation has indicated that these new valves are a backup to the existing line valves and actually offer additional system isolation capability. This plant modification is considered to be a maintenance aid in the event that RCGVS solenoid vent valves need replacement, refurbishment or additional testing at elevated RCS pressure and temperature. This change does not affect the pnmary safety related function of the RCGVS during post-accident situations or other secondary functions of the system. This safety evaluation confirms that the RCGVS manual valve additions as given by the MEP's e within References 10.9 and 10.10 will not pose an unreviewed safety question, nor require a change to the Plant Technical Specifications for St. Lucie Units 1 and 2. Therefore, prior NRC approval f6r this plant change is not required. l l 5 e
Attashuset 8 to PC/M 064-188 JPN.PSL-SEMS 96-007 EmWei 1 Revmon 0 Pagtit of $1 Page 19 of 20 s
10.0 REFERENCES
10.1 St. Lucie Action Repon for Unit 2. STAR No. 9600331 dated February 22,1996 entitled "CNRB Committee Review of PC/M 247-295 - 10CFR50.59 Screening" 10.2 FSAR for St. Lucie Unit No.1. Amendment 14 dated June,1995, Section 5.7 entitled
" Reactor Coolant Gas Vent System" 10.3 FSAR for St. Lucie Unit No. 2, Amendment 9 dated October 20,1994 Section 9.3.7 entitled " Reactor Coolant Gas Vent System" 10.4 Technical Specifications for St. Lucie Unit No.1, Amendment 141, dated October 27,
- 1995, Section 3/4.4.15 entitled " Reactor Coolant System Vents" 10.5 Technical SpeciScations for St. Lucie Unit No. 2. Amendment 80, dated October 25,1995, Section 3/4.4.10 entitled " Reactor Coolant Sy, stem Vents"
- 10.6 Design Basis Document DBD RCS-1. Rev. O, " Reactor Coolant System". Section 7.11 10.7 Design Basis Document DBD-RCS 2, Rev. 0, " Reactor Coolant System". Section 7.11 10.8 PC/M for St. Lucie Unit 2, PC/M No. 043-295, Suppl. 3 dated December 22,1995 entitled
" Replacement of Reactor Coolant Gas Vent System Solenoid Valves (V1460. V1461.
V1462, V1463, V1464. V1465 and V1466)" 10.9 PC/M for St. Lucie Unit 2, PC/M No. 247-295, Rev. O, dated December 22,1995 entitled
" Addition of Reactor Coolant Gas Vent System Isolation Valves" 10.10 PC/M for St. Lucie Unit 1. PC/M No. 034-196, Rev. O dated February 28,1996 entitled "RCGVS Solenoid Valve Replacements, Addition of Flanged Valve / Spool Assemblies and Manual Valve Additions" 10.11 Code of Federal Regulations Title 10, Chapter 50.59. Pan 10CFR50.59b
{ 10.12 St. Lucie Repon from MMEG/JPN entitled " Root Cause Analysis for PSL Unit 2 Reactor 1 Head Vent Gas System (RHVGS) Inservice Seat Leakage",1995, by Tom Sanders, Joel Kagan, and Mike Little 10.13 St. Lucie Plant Problem Report for Unit 2, Repon No. 95-108 dated December 3,1995 entitled " Unit 2 Reactor Gas Vent System Reliability Problems During Unit Stanup" 10.14 Piping Isometric Drawings for St. Lucie Unit 1. Drawing Nos. 8770 B-124, Sheets RC-225 and RC-226. Rev. 3 and I respectively, both entitled " Reactor Coolant Vent" 10.15 Piping Isometric Drawings for St. Lucie Unit 2, Drawing Nos. 2998-C-124. Sheet RC-99, Rev. 9 entitled " Reactor Coolant Vent" 10.16 Stress Calculation for St. Lucie Unit 1 Calc. No. RCV-1000C, Re 10.17 Stress Calculation for St. Lucie Unit 2, Calc. No. RCV-4700C. Rev. 2 10.18 Mechanical Design Specification for the FPL Nuclear Engineering Department, Document No. MN 3.08 Rev. 2, dated October 14,1993 entitled " Steel Station Valves 2 Inch or Smaller - Nuclear Safety Classes 1,2, and 3" 10.19 ASME Boiler and Pressure Vessel Code, Section III,1977 Edition, Winter 1978 10.20 Code of Federal Regulations, Title 10. Chapter 50.50 Part 10CFR50.55a, Edition: January 1,1992 10.21 Piping and Instrumentation Diagram for St. Lucie Unit 1 Drawing No. 8770-G-078, Sheet 110, Rev.18 entitled " Flow Diagram - Reactor Coolant System" 10.22 Piping and Instrumentation Diagram for St. Lucie Unit 2, Drawing No. 2998-G-078 Sheet 107, Rev. 4 entitled " Flow Diagram Reactor Coolant System" 10.23 Piping and Instrumentation Diagram for St. Lucie Unit 2, Drawing No. 2998-G-078 Sheet 108, Rev. 2 entitled " Flow Diagram - Reactor Coolant System"
Affaduuset 6 (D PC/M 094-100 JPN PSL-SEMS-96-007 Radelet 1 Reusion 0 Paesto of 71 Pace 20 of' 20
10.0 REFERENCES
(continued) 10.24 Piping and Instrumentation Diagram for St. Lucie Unit 2, Drawing No. 2998-G-078, Sheet 110, Rev. 4 entitled " Flow Diagram - Reactor Coolant System" 10.25 Piping Drawing for St. Lucie Unit 1. Drawing No. 8770-G-215, Sheet 8, Rev. 2 entitled
" Reactor Containment Building - 2" and Under Piping - Reactor Coolant Gas Vent System" 10.26 Piping Drawing for St. Lucie Unit 2 Drawing No. 2998-G-215, Sheet 6. Rev. 9 entitled
" Reactor Containment Building - 2" and Under Piping - Reactor Coolant Gas Vent System" 10.27 Piping Drawing for St. Lucie Unit 2. Drawing No. 2998-G-215, Sheet 8. Rev. 2 entitled ,
" Reactor Containment Building - 2" and Under Piping Sections - Reactor Coolant Gas Vent System" 10.28 Anchor / Darling Valve Drawing for St. Lucie Unit 1 EMDRAC Drawing No. 8770-12705 Rev. O entitled "1"-l875 Socket Ends Stainless Steel Globe Valve" 10.29 FPL Request for Purchase Authonzation withTarget Rock Corp., Req. No. 00020757 for Solenoid Operated Bolted Bonnet Globe Valves, Stock Code No. 0053084 1 10.30 FPL Purchase Order with Target Rock Corporation, P.O. No. C 95934-90377 dated June 30,1995 for Solenoid-Operated Bolted Bonnet Globe Valves 10.31 Administrative Procedure for Unit 1, Procedure No. 1-0010123, Revision 100 entitled
" Administrative Control of Valves, Locks and Switches" 10.32 Admmistrative Procedure for Unit 7. Procedure No. 2-0010123. Revision 69 entitled
" Administrative Control of Valves,ists and Switches" 10.33 FPL St. Lucie Electronic Catalog Listing for Stock Code No. 0052472 Anchor / Darling Valves 11.0 ATTACIBfENTS 11.1 Simplified Flow Diagram for the Unit 1 Reactor Coolant Gas Vent System (manually enhanced version)- 1 page 11.2 Simplified Flow Diagram for the Ucit 2 Reactor Coolant Gas Vent System (manually enhanced version) - 1 page 11.3 FS AR Change Package for St. Lucie Unit 1 - 2 pages j 11.4 FS AR Change Package for St. Lucie Unit 2 - 5 pages l
St. Lucie Unit 1 Attaehmert 6 to Document No. DBD RCS 1 i REACTOR COOLANT SYSTEM WM 6 Revision O Design Basis Document p h 3g Page 4 of 336 4 Attachment 11.1 to JPN-PSL-SEMS-96-007 j . _ Kevision 0
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Attashment 8 O PC/M OS+-lM Attachment i1.3 to I p gg JPN-PSleSEMS-96077 Revision 0 Page 1 of 2 FSAR CHANGE PACKAGE (FCP) Plant St. Lucie Unit i FSAR Page(s) Affected Page 5.7-5 FS AR Figure (s) Affected None Comments The justification for this change is provided within 10CFR50.59 safety evaluation given as JPN-PSL-SEMS 96-007. . Accrovals Prepared bv: M. Date bl9-4 Verifie'd by: m5 M Date J"dMS A,,-ed ,, - W,
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! A e d s a t a to i WM 004-13 Attachment il3 to ! "'"*" 1 JPN PSL-SEMS-96-007 I Pas M d M I Revision 0 ! Page F. of 2. l 1 i vent and reacter vessel head vent, both sised to meet the flow requirements of i i r systes design criteria. l 1 l ' j 5.7. 3 - SAFEff IVALDAT105 4 I 5.7.3.1 performance teteirements. Capabilities. and Re11 abilities I i The ability to vest the RC$ - either reactor vessel or pressuriser - under l accident conditions is assured by providing reduedsat flow paths from each l l vaating source, redundant discharge paths, and energency power to all power ! operated valves. A slagle active f ailure of sither a power operated velve er i power espply will set prevent venting to contaissent (either directly or i through the quench taak dependent upon failure mode) from either source. ! 5.7.3.2 Pipe gresk Analysis i
- Consistent with NRC requirements. the RCCVs is designed to limit mass less to
- less than a 14CA as defined in 10Cy150 Appendis A and thus a separate i
analysis of laadvertest system operation er pipe breakage is set required to east 10Cy150.46. l t l The pressure bevadary of the aersally pressurised porties of the head went l systes is protected'from the effects of postulated pipe breaks la the mets
; loop cold les piping, or branch lines to the cold lege, or non-Rcpt piping.
i The pressure boundary of the normally unpressurised portion of the vest systes
- is protected free the effects of postuisted pipe breaks in non-tCp5 lines for which vesting weeld be required.
I j i The flow fumeties of the vest syntes le protected free the effects of failures { for which venting would be required. ___ } 5.7.3.3 Leahane Detection b decrel
- ^
! The components of the RCCTS are provided with welded ceanections wherever
- possible to minimise leakage to the staespbere. Eswever, flanged seeaecties l q are provided es the reactor vessel vest line to allow disassembly for 1 i refueltag mainte===es. Sva ra= wm1 == = a rs =f *h= ==
- h 1 = = = +=== ** mini =tse l L laakmaa p anage past see systes isolaties valves into the aermelly -
- unpressurised porties of the systes is detected by pressure lastruneatation.
l t 5.7.3.4 Retural phenomena I
- l RCCVS components are located in containment and, therefore, are not subjected j to the natural phenomens described in Osapter 3 other than seissic. piping
- has been analysed and supported in accordance with St Lucie' Unit 1 seismic
- criteria. All valves have been analysed and tested for operability during a
( seismic event by manuf acturers. d . ) .
! De.leke.
1 , 4 i 1
- 5.7-5
Attaehneet 4 to l PC/M OM-13 Attachment 11.4 to hI JPN-PSI,SEMS-96007 I"" " N N Revision 0 ; Page 1 of 5 ! ESAR CHANGE PACKAGE (FCP) Plant St. Lucie Unit 2 i l l l FS AR Page(s) Affected Page 9.3-45f, Page 9.3-45g and Page 9.3-45h FSAR Figure (s) Affected Figure 9.3.7 Comments The justification for the all FSAR changes are provided within the 10CFR50.59 safety evaluation given as JPN-PSL-SEMS-96-007. l' NOTE: Duplicate RCGVS figures appear in the Unit 2 FSAR (see Figure 5.1-4b and Figure 9.3-7). This is unnecessary and can lead to possible confusion regarding future FS AR updates. Figure 5.1-4b addresses an FPL referenced drawing and Figure 9.3 7 does not show any reference drawing. I Therefore, from a control standpoint, Figure 9.3-7 shall be eliminated from the Unit 2 FSAR. Text changes will provide appropriate reference to the RCS Piping and Instrumentation Diagram given as Figure 5.1-4b (within Section 5.1.2). Accrovals Prepared by: d 4. 4 Date 3* 89 **4' verined by: <NU- Date FMM Approved by: Date 29 [
/ '
/
Attasiunerf 6 to pem wa Attachmott 11.4 to wama 1 JPN-PSL-SEMS-96-007 P u t u of 71 Kev h 0 Page 1 of 5 1
)
i active ' i'1ure proof with active component s powered form emergency power j ( sources. Parallel valves powered off alternate power sources are provided at bot h ver ; sources to assure a vent path exists in the event of a single f ailure ,f either a vs1ve nr the power source. The system prov' des a redundant vent path either to the containment directiv or to the quench tank. The quersh tank route allows removal of the gas f rom the RCS without the need to rete.tre the highly radioactive fluid into containment. Use of the quench ! tank provf des a discharge 1ocation which can he used to store small quantities of gas without influencing containment hydrogen concent ration level s. However, venting large quantities of gas to the quench tank will result in rupt u rer of the quench tank rupture disc providing a second path to containment for vented gas. 8"oolina of gas vented to the quench tank is provided by introducing the gas below t he quench volume. *he direct vent path is located to take advantage of mixing and cooling in the containment. The system is designed with a flow lisittina orf fice to limit flow such t hat the mass flow rate of resetor cooiant system fluid out of the vent is less than the makeup capacity of a single coolant charging pump. Thes effectivelv limit s the flow to less than the I.OCA defInft'on of 10CFR50, Appendix A. The vent rate 1imitat f on siso assures t hat RCS pressure control is not compromised by venting operation. 'he system has the capahtlity to vent larae quant f t f es of hydrogen gas f rom the Rf*S. Although designed for acetdent condit tons, the system may he used to afd in the pre or post-refueling venting of the Reactor Coolant System. Ventina of the Individual CEDMs and Br7s wf11 still he necessarv. however, pressurf ter {, and reactnr vessel venting een be accomplished with the system f f desired. Vent fiow can be df reeted to the quench tank nr through a charcoal f(1 ter to the contaf rament purge header for thin operation to prevent i nad ve rtent release of radioactive fluid to the- containment. c.ksm % 5.1-M As shown on Figure 9.h- non-condensible gases are removed f rom ei t her t he pressurizer or reas essel through the flow rest ricting orif ice and one of the parallel isolation valves aW delf vered to the quench tank or containment via their isolatton valves. Venting under accident conditions would he aceneplished using only one tource f reactor vessel or pressurf teri and one sink f euench tank or conta tnment atmospherei at a given time.
".l.7.2.1.1 Normal Ope ra t i on This system is not intended f or use during norma! power operst f on and administrative controls are provided to m'nf eite the pnsst hf11ty of j ' 9a d ve r t e n t ope ra t i on . Adiftfona11v. power it removed ' rom all valves during normal plant conditions.
UVrfng 90rma1 oper4 tion. leakage detection is maintained by use of the pressur+ nstrument. A rise in pressure will indicate leakage pagt any of the j system 'soiation valves. Em411 leakage ratea can be determined by conducting j PCS teak rate calculations. Larger leakage rates can be determined hv j directi9t leakage to t he quench tank and mon'tnring tank level change or to t he a cc umul a t o r and monitoring sump inst rumentat inn. 9.3 45f l l
l Attaeheert 8 to I 4 rem on.tse Attachment H.4 to i wem 1 #N-PA-SEMS-96-007 Paes a of s1 Kevision 0 i Page 5 of 5 0907W-4 9.3.7.2.1.2 Accident Operation l Operation of the RCCVS during accident conditions will vary depending on the j rate of gas generation. For low gas generat tun rates, gas f rom within the reactor vessel or pressurf zer is vented to the quench tank. Reactor and /or pressurf rer vent valves are lined up and the gas released to the quench tank. Monitorlag of quench tank pressure is necessary during this mode of operatinn. From this point the gas could be df scharged to the gaseous waste management system if it is available for use. i For high gas generation rates, gages may he vented to the containment atmosphere. Should this valve fatl, vent to enntainment atmosphere can et t 11 he acco *plished through the quench tank rupture disc. 1
- When ve iting to either the quench tank or containment, the system operating procedures will require that the operator open the pressurf ter or reactor !
vessel solenoid valve whf eh is powered f rom t he alternate emergency bus (f e, I two valves in series will he open, one powere t f rom hus A, and the other free ! t he bu s 8 ) . This will allow temination of venting' for the uni fkely situation j where one of the valves should electrically f afl open. The RCCVS will be operated as an on-of f system to remove gas f rom the RCS. Thai volose of gas to he removed is determined by reactor vessel or pressurf ser l j instruw .ntation and then t he venting time f s ietermined dependent upon t his , volume ind system temperature and pressure. 9.3.7.2.2 Component Description [
- There .i e no major component s in the .V The entire system consists of piping, valvet, and pipe fittings. 11 p ing and valves are constructed of ,
austM tic stainless steels, ucle Safetv qualtf ted according to the j 4 Cla ss as ind iepted on Figure 9. . Pip - tem supports and valves are - seisal. ally qualified as who .gure . -,. Power ope rated valves are solo.ofd operated type designed to f ail c to mintaf te inadvertent ope ra t i on . The solenoid valves control circuitry and position Indicator switchew are class IE qualified to IEEE-3R2-1'372 for inside containment, IEEE-3t1-1975 for sef setc and IEEE-321-1974 for envf ronmental quaiffIcatfon. Redund,.ncy in valve arrangement and power supply is desf gned to meet t he single f ailure criterion. Part of the piping system includes offfices at the . pressurf rer vent and resstor vessel head ven' , both stred to meet the flow requirements of the system design criterf s. 1 l 9.1.7 Safety_ Evaluation 1 9.3.7.1.1 Performance 8tequi rement s, Capabilf t f es, and eel f ahf 11t tes l The ability to vent the RCS either resetor vessel or pressurtzer - under I acefdent conditions is assured by providing redundant flow paths f rom each vent i n: source, redundant d ischarge pat hg, and emergency power to all power operat.d valves. A single active f ailure of ef ther a power operated valve or power supply will not prevent venting to containment (ef ther directly or t hrough t he quench tank dependent upon failure mode) f rom e t t he r source. I 9.3-45g I l
l Attaebnett 4 to PC/M 084-13 Attachmett 11.4 to
*1 '
Pagt18 of $1 JPN-PSL-SEMS-96407 Kevlalon 0 Page 4 of f 09071-5 1 .- 9.3.7.3.2 P1 pe Break Analysis j r:ons! stent with NRC requirements, the RCCVS is designe= required . J
'.3.7.3.1 Leak, age Dn -ctio and Controt d j 2 1 hau enmpnents of the PCCVS are' grovided with welded connections wherever l
ross!Ltc en minialze Icab re to the atmos #Nre. however, f san;,ed connectionn I , i are r uv!ded nn the reactor vesac1 vent line to allow disassembly for re fueling maintenance. Systes valv,e are ofthe r. ek l es s e v ow to miniatu leakic s LeaLage pa s t thu mystem isolation valves into the normally ungr.<issurized prt ton o f the system is detected by grwssure instrumentation. ( ' O . 3 . 7 .1. f. ::atural P senomena PC CNS c no ronent s a re l oc a t ed i n con ta i nmen t a ni.', there fu are nnt subject to the natural phenomena described in Chr.ger 3 c,cher than seismic. Pl %ng has
- been analysed and suppree 1 in .iccordance w 'th St. Luclu 2 seimmic cr;teria. ,
All v ilves have been analyzed and tested for opusability during a swinnic event by manufacturers. Ta ble 9.3-11 troviden a tabulation o f scismic P , ite,ory 1 valves whose a p tation is rel!=d u;nn to mitigstu the consequences of an accident. 1.3.7.1.5 Fa ilure Modus and E f fce ts An.ilysis j Tabl. 9.3-12 unown a failure mode and e f fect s an slyuis for the RCCVS. At leebt one failure i s rentu!ated for c aco s.. wt y-rela teJ com psnent o f the RCCV S . In uach case the passible cause o f muen a failure 16 presented es well i s the Incal e f fects, dsts tion met;mdm. mc mrtnsitinf truvisions. 4
".3.~4 Insteetion 4 , ting Requ ; rne nt .
#..ie. .ompenent 16 i ns pe r t v ! a nd e iraned rri -
ta .ustallit;on lato tne RCCVS. 1
.9e in trumc r.c will be r al . bca ted dur. nc Tr -u ;t ra t iona l t wa ting;. The valven W controls w!!! te ti%te.: f ar a rti e! !i t y f4 ;-,want inst.11.ition.
1
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Attasheet 8 to PC/M 094-C] 4
@ FPL Itmem i Paet30of$1 Ir.ter-Office Correspondence l
l 1 1 JPN SPSL 96-0084 To: S. A. Valdes Date: WAR 2 91996 St. Lucie Plant From: hWW D. J. Denver Department: JPN/PSL Nuclear Engineering I
Subject:
ST. LUCIE UNIT 1 DOCUMENT: JPN PSL SEMS 96 007 .
)
1 TITLE: Transmittal of a Unit 1/ Unit 2 Safety Evaluation for the Addition of Three ManualIsolation Valves within the RCGVS Process Vent Lines ! l
REFERENCE:
STAR 2 960331 1 FILE: PC/M 247 295, PC/M 034196 and SE File l l i
References:
(A) PC/M for St. Lucie Unit 2, PC/M No. 247-295, Rev. 0, dated December 22,1995 , entitled " Addition of Reactor Coolant Gas Vent System Isolation Valves" (B) PC/M for St. Lucie Unit 1, PC/M No. 034-196, Rev. O dated Feb. 28, 1996 entitled "RCGVS Solenoid Valve Replacements Addition of Flanged Valve / Spool Assemblies and Manual Valve Additions" ! (C) FPL St. Lucie Action Report for Unit 2. STAR 2-96-0331 dated Febmary 22,1996 l entitled "CNRB Committee Review of PC/M 247-295 - 10CFR50.59 Screening" J References ( A) was developed in support of St. Lucie Unit 2 maintenance activities to facilitate procedures for replacement, refurbishment or testing of the RCGVS solenoid vent valves at hot operating conditions. As part of these plant changes, manual locked-open isolation valves were added to the process vent lines. l l Following the installation of the three Unit 2 manual valves, a CNRB Subconunittee review of Reference (A) l questioned the need for a 10CFR50.59 evaluation and the STAR report of Reference (C) was generated. Enclosure (1) is the 10CFR50.59 safety evaluation which was written in response to this STAR. A simdar plant change is being planned for Unit 1 RCGVS during the 1996 Spring Outage also through the use of the MEP (see Reference (B). Manual valves will be identically located just upstream of the pnmary solenoid-actuated vent control valves. Therefore, the purpose of this safety evaluation is to assess the safety significance of adding these manual isolation valves to the RCGVS process lines and to provide a generic review for the acceptability of their installation. As such, this safety evaluation will be applicable to both St. Lucie nuclear units and will supplement the engineering justification for each urut's PC/M
Attadamert 4 to JPN SPSL 96-0084 M #12 Page 2 of 2 hp This evaluation demonstrates that the installation of manual valves in the Unit 2 RCGVS (and as proposed for Unit 1) does not involve an unreviewed safety question or requires a change to the Technical Specifications. Since each concern posed by the 10CFR50.59 can be appropnately answered, prior NRC approvalis not required. The permanent valve additions to the RCGVS are acceptable from the standpoint l of nuclear safety in that it does not affect the original design basis nor impact the safe operation cf the Plant. It is concluded that the installation of these isolation valves will have no affect on plant safety or operation. Action items have been identified in Section 8.0 of this evaluation and apply to both St. Lucie units. Should you have any further questions, please contact Larry Lostocco at PSL extension 7137.
Enclosures:
(1) FPL Safety Evaluation for St. Lucie Units 1 and 2. Evaluation No. JPN-PSL-SEMS-9M)07, Rev. O, dated March 29,1996 entitled " Addition of Three Manual Isolation Valves within the RCGVS Process Vent Lines" - includes 4 attachments (29 total pages) DJD
$t GL Copies: H. L. Fagley/DCC - SLC/PSL(w/ Original)
D. M. Stewart - SCE/PSL L. G. Lostocco - ENG/PSL l t
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NOTE: FOR SIMPLICITY, DNLY AFFECTED AREAS ARE SHOVN) , l. FLORIDA P ER UGH COMPANY JPN-034-196- 8 APPROVAL 002 Dh/ DR. UNIT 1
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NOTES:
' 1. SOLENOID VALVE ASSEMBLIES ARE INTERCHANGEABLE AND !
MAY PE INSTALLED IN ANY RCGVS SOLENOID VALVE ' OCATION _ VITHIN EITHER ST. LUCIE UNIT. l
- 2. WELD NUMBERS WILL NOT RELATE TO THE CORRESPONDING )
4 LINE NUMBERS. FOR SPECIFIC VELD IDENTIFICATIONS AT ANY ! a DESIRED LOCATION, SEE THE PASSPORT VELD CONTROL SYSTEM. ! l i 1 i a 1
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CH: d' D PIPING ISOMETRIC SHEET 5
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e v NOTES; i
/
/ 1. SOLENOID VALVE ASSEMBLIES ARE INTERCHANGEABLE AND MAY BE INSTALLED NOj QTYj 2ESCRIPTION \
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- 2. VELD NUMBERS VILL NOT RELATE TO THE ilo i 1 1 l' !
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f Y NOTES:
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- 2. VELD NUMBERS VILL NOT RELATE TO THE .
! !, DICE. SCH 160 TP304 CORRESPONDING LINE NUMBERS. FOR SPECIFIC 10 l VELD IDENTIFICATIONS AT ANY DESIRED l l VALVE LOCATION, SEE THE PASSPORT VELD - . -
CONTROL SYSTEM. ,_ ' ' I'l* i , Y- *% CLEAR 35c.mg g , y1 ' 7 63k I/g [ NOTE \ 04 l'/.'# " NOTC\ Cg [\2 6 [NOTk o s /NOTC\ \2! Bad 5 8 ' [
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- m_- y NOTES
- 1. SOLENOID VALVE ASSEMBLIES ARE l NOj CTYj INTERCHANGEABLE CND MAY BE INSTALLED EESCRIPTION IN ANY RCGVS SOLE NOID VALVE LOCATION !151 4 I l' 2500m FL ANGE,$V RI SS h VITHIN EITHER ST, LUCIE UNIT. x
- 2. VELD NUMBERS VILL NOT RELATE TO THE ,6i i1 ! I' DIPE, SCH 160 Tc304 )
CORRESPONDING LINE NUMBERS. FOR SPECIFIC I : VELD IDENTIFICATIONS AT ANY DESIRED # VALVE LOCATION, SEE THE PASSPORT VELD I l l )
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- 1. SOLENOID VALVE ASSEMBLIES ARE NOj QTYJ DESCRIPTION INTERCHANGEABLE AND MAY BE INSTALLED !l g ,
IN ANY RCGVS SOLENOID VALVE LOCATICN l, ~3500m
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VITHIN EITHER ST. LUCIE UNIT. 12 l l l' DIPE. S> 160 To304 )
- 2. VELD NUMBERS VILL NOT RELATE TO THE I CORRESPONDING LINE NUMBERS. FOR SPECIFIC g i
' g VELD IDENTIFICATIONS AT ANY DESIRED {
VALVE LOCATION, SEE THE PASSPORT VELD l~ i k ; 1 CONTROL SYSTEH.
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' n , ,, rd'e- , PER PCM 034-196
. REW R<
(REF. DWG. 8770-B-124 SH. RC-23D NOTE: FOR SIMPLICITY, ONLY AFFECTED AREAS ARE SHOVN ( FLOROA P " " #^N t S LUC E LA T JPN-034-196- l DPf DR: bW APPROVAL CH: NO.N D UNTI 1 007 I DATE: 4 -* *8-IMA
~
PIPING ISOMETRIC SHEET 5 { l REACTOR COOLANT VENT 2 0F 2 1 5 A LDST m Duc
m v N '
- 1. SOLENOID VALVE ASSEMBLIES ARE
' ' INTERCHANGEABLE AND MAY BE INSTALLED NOjOTYj DESCRIPTION \ l IN ANY RCGVS SOLENOID VALVE LOCATION 10 l 4 l 1' 2500m FL ANGE,$V,RF.SS \ VITHIN EITHER ST. LUCIE UNIT. l11l l 1' PIPE, SCH 160 TP304
- 2. VELD NUMBERS VILL NOT RELATE TO THE )
CORRESPONDING LINE NUMBERS. ] FOR SPECIFIC l l ( VELD IDENTIFICATIONS AT ANY DESIRED j j VALVE LOCATION, SEE THE PASSPORT VELD q CONTROL SYSTEM. f [NOTEk 12._ _ _.
\
!/NOTEk l
- I o /BW\ 2 ;i .
\e5Y0/ E = - . l g- l
' ' / NOTE \
fais 2/ 14 r ap3'e s k \a/ s/ 10
/es\
1-y;4& 43 28We/ C'Bo3 rfp' Os l*~a c ,Bo y 17 s lee . s "QP PER PCM 034-196 m-REW R< (REF. DWG. 8770-B-124 SH. RC-232) l NOTE: FOR SIMPLICITY, ONLY AFFECTED AREAS ARE SHOVN l i g ! ROROA P R " WP M AT JPN-034-196- ! DIV: DR: OW APPROVAL s UC E wn1 l CH: IM NE 008 - 1 DATE: 4 - N-
$ ~f M PIPING ISOMETRIC SHEET 5
'l l REACTOR COOLANT VENT 2 0F 2 1 5 A umocos.ono
v ! FIELD VELD NUMBER IDENTTFlCATIONS FOR 'HE ORIGINAL , INSTALLATION CF THE RCGVS ' BOLTED-3CNNET' SOLENOIE VALVES (FOR FIELD' FABRICATION ONLY-NCT TO 3E AS-BUIL ' I J h .
\
- , .~~_
- ::
BOLTED-BONNET VALVE RELATIVE LOCATION i 1 OF FIELD VELD VALVE / SPOOL SER,lAL NO./ ASSEMBLY LOCATION VALVE BODY NO. (SEE ABOVE SKETCH) FIELD VELD NUMBER V1441 3/393788 1 RC-VALV/FV2000 2 RC-V AL V/F W2001 3 RC-VALV/FV2002 4 RC-VALV/FV2003 V1442 4/393789 1 RC-VALV/FV2004 2 RC-VALV/FV2005 3 RC-VALV/FV2006
- , 4 RC-VALV/FV2007 4 4 V1443 5/393790 1 RC-VALV/FV20d8 l 2 RC-VALV/FV2009 3 RC-V ALV/FV2010 4 RC-V AL V / FV2011 j V1444 6/393791 1 RC-VALV/FV2012 2 RC - V AL V/ F V2013 3 RC-V AL V/FV2014 4 RC-V ALV/FV2015
, V1445 7/393792 1 RC-V AL V/FV2016
' l 2 RC-VALV/FV2017 l 3 RC-V ALV/FV2018 4 RC-V AL V/FV2019 ! V1446 8/393793 1 RC-VALV/FV2020 2 RC-V AL V/FV2021 3 RC - V ALV/FV2022 4 RC VALV/FV2023 V1449 9/393794 1 RQ- V AL V/FV2024 2 RC-VALV/FV2025 3 RC-VALV/FV2026 4 RC-VALV/FV2027 g E FLORIDA POWER & UGHT COWPANY ST. LUCIE PLANT JPN-034-196- 8 DIV: DR:_QV_ APPROVAL uun i 009 ! CH: b# _--3 FIELD SKETCH-WELD ID FOR THE ORIGINALLY b DATE: 87- M " [ l INSTALLED RCGVS
- BOLTED-BONNET" SOLENOID YALVES l 5 A LosTocos.ouc
i FIELD VELD NUMBER IDENTIFICATIONS FOR THE JRIGINAL CUT DUT RCGVS ' SEAL-VELDED' SOLENDID VAL VES (FOR FIELD FABRICATION ONLY-NOT TO BE AS-BUILT' 1 .i ' 2 a
\ 3
~
i ' t ;g ' , . ;', 'CS 9 j
.- i
~
- 'idd SEAL-VELDED VALVE I RELATIVE LOCATION ORIGINAL OF FIELD VELD VALVE LOCATION (SEE ABOVE SKETCH) FIELD VELD NUMBER (ALT 1) 1 RC-VALV/FV2028 SEE NOTE 2 2 RC-V ALV/FV2029 y
3 RC-VALV/FV2030 4 RC-V ALV/FV2031 (ALT 2) 1 RC-VALV/FV2032 SEE NOTE 2 2 RC-VALV/FV2033 3 , RC-VALV/FV2034 1
> 4 RC-VALV/FV2035 4 !
1 (ALT 3) 1 RC-VALV/FV2036 SEE NOTE 2 2 RC-V ALV/FV2037 l 3 RC-VALV/FV2038 ! 4 RC-VALV/FV2039 l NOTES:
- 1. THESE THREE ' SEAL-VELDED' (BODY-TO-BONNET JOINT)
SOLENDID VALVES VERE ORIGINALLY INSTALLED INTO THE i RCGVS AND CUT DUT PER PCM 034-196. l
- 2. AT LEAST THREE FLANGE SETS VILL BE AVAILABLE TO CONSTRUCT STANDARD VALVE / SPOOL ASSEMBLIES FROM THOSE VALVES VHICH ARE DEEMED TO BE THE MOST FUNCTIONALLY ADEQUATE.
- 3. THESE ASSEMBLIES VILL BE STORED ON SITE AS A POSSIBLE FUTURE ALTERNATE FOR THE BOLTED-BONNET VALVES.
- 4. A CRN SHALL BE CREATED TO DOCUMENT THE VELD NUMBER IDENTIFICATIONS FOR EACH VALVE /SP00L ASSEMBLY (ABOVE).
E FLORIDA P ER UGH CCMPANY JPN-034-196-DIV: DR: f6[ APPR_ OVAL UNff 1 010
- OH: IdM D g-Q flELD SKETCH-WELD ID FOR THE ORIGINAL 4-W-h MTE:
f l CUT OUT RCCVS
- SEAL WELDEtf SOLENOID VALVES l 3 A LOST 10.DwG
l QI 3-PR/PSL-1
' ~~~ l , R vision 39 '
April,1996 i Page 26 of 26 W l ATTACHMENT 5 l CHANGE ' REQUEST NOTICE CRN No. #'4"~*#93 Page I of PCM No. NPWO No. WO No.
@ sp, implemented Dy:
i O OR
&h- }0h NlA N/A 0 NNS O ADu Affected Document (See page ,_ for addreonal affected oocuments) TEDO Affected: 63 Yes O No
/Je e d B ec_ Rev. 1 Rev. Rev. _,,,
Rev. Rev. Rev. J Rev. Rev. Rev. PCM Title fc6VS 5. lc ei st Va lw 2eg # , CRN Affects Work Control Document (s):
/?ald. H. .C Flame ol/Sp..I shse, hkn WCD Rev. Step (s)
! Reason for Chance
) / e s e- r t p rmse.J- va tn w e ; q *t *- hs t e TF b8 O M. .h k 'pe /A el , . w .% r -b'e r s e rt A .., I.3 4 ix c e f 54.e s 2 - 4 (Spec:.l laatJ ns .
Change Request /Skaten (if necessary) fp o J pc/g t) Valve in.de i A/. . BOB-colS8 e;3ks 4- 2 l' 5
. j" U fra 3 e S . -F Pcirs 4++acs~e.,+ 2'
,2e vi,5 e T~~E D 8, upd a te sAsets a 'n Pcm ,4-t-ta e h m ess + 4 b e. 7~G. D 6 s he e t $ s k e I of be Ckwged rk o+r 3 "I ld>> ' o k $ W j 4 s ,e,.t I Ad , , P.y to .c a. ee/m , si.p 2 , 3 . . 4 : Ar, .w e.,,.e d O Pb/A For St.p s 2 b N-ber has bem d=4-ul u A3: 7P N - c 34- tm. - os o s witfka_b e.
lad /.M ol' 4kese (6cet skps , Iv- SW o 4 3 P N - 0 3 4 - t *% - cs l 4 3 h em be TPN -03 4 - 19(e 009
'r p M - o 14 - 1 %. - a f o ACTION BY ENGINEERING: (Pretirninary)
O in Person @ Proceed Thss CRN has been discussed with , L. L*5foeeo of Engineenng. ETelephone C Hold SOURCE OF CHANGE: APPROVALS: W. tru vensence d a li /-[a rmea O Engr. Error w D.s.gn Evo unon Prepared By- Date f. /N Mat'l Subsetuton Dept b ei [.o M a m f-phone '7078
.; .s 5
SCOPE OF WORK: impi. Dept. Supv. Date ] Olnc,.as. Dec,oas. Mchang.d ENGINEERING APPROVAL (Final) IMPACT OF REVISION CHECK SHEET Yes No 2 APPROVED NOT APPROVED 0 3P4 - PS L. Cogng Org. (CDO) 1. Design Basis or Analyses Affected OE
- Prepared by- bd _1 Date.f)_9./% 2. Safety Evaluation Affected OE W
Venfled by- Mra[MM n Date_[J/8).7[f 3. PDMDs or SRDs Funcnonalty Affected E 4 Approved . T Id-s- W. Lk11Lt). Dategj.fi.Jg.g 4. Start-Up, Opersoons or Ma#ntenance JPN (if not CDOh Date_, / ] ,_ Requirements Affected OE
- g Remarks / Basis for Olspostuon. AAt no r c ore echns a t c., a) vers en Pa.c.c 2 A e m L9 W of +L7s CRM 4e au re Mr M r. nesel 4rmanadM e rro rs .
4 1
TIMD034 COMPONENT / ASSOCIATE /UTC PARAMETERS 10/27/96 10:25 Help Data Print Roadmap Exit Options Facility - PSL Unit = 01 System = 01_ Comp. Type = VL Sub-Type = FB _ Component- V1441 Associate- UTC: Name : SOLENOID VALVE FOR REACTOR HEAD VENT HEADER A TO RCVGS
===========================================--u=================================
- POrameter Name Type Value UOM V Date By j
_ TEST PROC SHEET M N/A 1 WEIGHT M 37 LBS _E 07/16/96 PAB0HIZ_ _ VALVE THRUST RATING M LBS ~ [ VALVE TORQUE RATING [ M FT LBS _
- VENDOR STEM FACTOR _ M N/A _
_ GENERIC FIG NO/ TYPE _ M N/A _ ~ - - More: - F9 TO VIEW LOCATION OR UTC' HISTORY. Fl= Help F4= Prompt F5= Search F6= Refresh F7-Bkwd F8= Fwd F12= Cancel l l l
6 4 CKN OM-196-6095
- y. .
i i Revision 0 l PC/A o34- 196 ii reettteye est units on imD I i I i compnenti visst I i i pgggg9 1 Assoc &etsi 1 l [Att, 4 l l laevi 1 l l Date Printeds l lPage 4 of 3$ l 4 I 4 l l t TOTAL SQUtpeerr DATA SASE SE3rr DESIGN CODS TSAR g/A A B GENBEIC WUMBER N/A
$PBC1FICATION NUMBER g/A REAN 77791 280 s/A ACT1VE OR PASSIVE g/A
, ELAM TYPE 2 REQ g/A STWE DIAMFFER INCR , NRC RELIBF REQUBST 0 g/A REMOTS INDICATION g/A seemser 70sQus n Las . '8NGTR
- tsCu PACE 250 1980UR yt g33 mas ALanu sTac n Trn suc
. REMAAssi g/A i ORIFICS DIAMETER INCE j samanes2 N/A i usw asOD sTnOx T:ms sC NORMAL MODS u/A TEST FR8QUENCY seOs FLOW CVER/UNDSR SEAT g/A TEST 180UTBSD s/A FAILDR3 MDOS - 3/A "587 790C 83337 f 7 _ _ g/A M51GET [M } 47 * ' Lag . VALvs Tunost mArtuo 1# tas vALvs Tomous aATING E n Las
- ev5NDOR STEN FACTOR T s/A 3sNERIC PIO so/TTPS E m/A f
i 1 1
- Change perthis ORN
=
i i g~ - CKN 0$4-196-6093 , tl l lpc/* on-i, Maa 0 '
~ l fagt 3 Of 9
. Components vase g i i l Aseocaates t l Ate, 4 i I
l l nevi 1 l l l Date Printeds [ g rege 7 og $ $ l 3 I I i i l d TOTAL B00!PoERWT DATA BASS SEB37 l ! SPSCIFICAft03 pt2EBBR 3/A = l SEAft TYPE 1 R50 5/A
.' ACTIVB M PASSIVB 3/A J
RIAM TYPS3 RSO N/A , 8798 DIA85TER !WCW NRC SSLISP RSOURST e s/A l RBIOf5 IMICAT!cer 3/A . I y SOIdWBT 708005 Ff Las
*534F75
. INCM PACKIIBO 708005 FT L&s MAI AL145 STROKE TIM SBC RalAREst u/A CR2P!CB DIAftBTER INCE l RE34AAES2 N/A 3
l MI3 R8@ STROE3 TIME ssC ! ! 88088EAL IEDDS N/A a M8T PRSOUENCY 900 5 PMMI 0 4 R/UNDER SEAT N/A TEST 8800123D m/A j FAILURE Is005 g/A 1 Tas? rooC saar? A . w/A estos? /- J"2 tas 4 vALvu Tumost aAfrwa b d ** Las VALVE Toa005 RAT 1HG E rf Las
'v3Beot 373E FACTOR 7 N/A )
Oswaarc rio so/TTes I s/A i , 4 a Change perthis ORN ;
CRbt 034-19S-co93 PC/M o34-l% o R eviste n 0 Rev 1 l
. P9 9 .t 9 Page 10 of 16 SPECIAL INSTRUCTIONS \ IMPLEMENTATION REQUIREMENTS 1.
Coordinate all work with Operations and Health Physics to obtain appropriate clearances. 2. Cut and remove the existing four primary solenoid valves (V1441, V1442, V1443 and V1444) in accordance with PC/M Drawings JPN-034-196-004 and 005, Sheet 1 of each. Replace these four valve with the Target Rock bolted bonnet design and assemble each valve within the standard valve / configuration givert by PC/M Drawing JPN-034-196-003. Install allTour valve / spool assemblies as show on PC/M Drawings JPN-034-196-004 and 005, Sheet 2 of I assemblies are expected to be fabricated in the shop; PC/M drawing JPN-034-19 a fabrication aid.
- 3. Cut and remove the existing three secondary solenoid v 445, V1446 and V1449)in accordance
- with PC/M Drawings JPN-034-196 006 thru 008, S' I of each. Replace these three valves with the Target Rock bolted bonnet design and assemble eact I alve within the standard valve / spool configuration i given by PC/M Drawing JPN-034-196-003. Install { all three valve / spool assemblies as shown on PC/M
- Drawings JPN-034-196-006 thru 008, Sheet 2 of e;
' W=not assemblies are expected to be fabricated in the shop; PC/M drawing JPN-0 s
- 4. At least three additional flange sets have S a fabrication aid.
n ord should be available to construct standard l valve / spool assemblies from the seal-welc d (body-to-bonnet joint) solenoid valves that were cut out in Steps 2 and 3 above. Those valves whict e tg most functionally adequate shall be selected l for spooling. PC/M drawing JPN-034-196%g Mas a fabrication aid. These assemblies will be stored on site as a possible future alt j r the bolted-bonnet valves. A CRN shall be created to document the weld number ID's for e valve / spool assembly with a seal-welded solenoid valve.
- 5. The valve /spoollength may present r interferences with seismic restraints which are located upstream of Valves V1441, V1442 and, po bly V1443. Pipe supports 8770-RCVG-58 and 59 (and possibly RCGV-15 and 56)may require tel 'on to facilitate installation of flanged valve assemblies. Should these supports, or any other supports req e relocation, they shall be submitted to engineering via CRN to this package. Expansion anchors shall stalled in accordance with Reference 39.
j 6. Gasket and bolting specifications een designated in accordance with the piping specification of l Reference 41. Gaskets shall be a spiral ound Type 304 stainless steel with graphite such as Flexitallic Flexacarb Style CG or equivalent. Bolting hall conform to ASME SA-193, Grade B7 threaded fulllength with a diameter of 7/8" and an approximat length of 5-1/2", ANSI B16.5, to ensure full engagement of the ' nuts. Nuts shall conform to ASME SA-1 , Grade 2H or Grade 7 semi-finished heavy series hexagonal per ANSI B18.2. Torquing of all flange bo s shall be performed in accordance with Reference 42.
- 7. After fabrication of all seven valve / spool lies, preliminary testing is recommended (e.g. Iow pressure l l seat leakage test, high pressure seat le ge test, stroke time test and operational test) to assure that each
! ation in the plant. e ope, rational test allinclude testing of the 4 valve is operating correctly position indication system. g gg7 p(rior to 'h eg N i 8. Cut and remove portions of the existm GVTpipe (Lines 1"-RC B24(and C-B00)in accordance
- with PC/M Drawings JPN-034-196-004 and 005, Sheet 1 of each. Install all three 1" manual isolation i
valves (V1650, V1651 and V1652)in accordance with PC/M Drawings JPN-034-196-004 and 005, Sheet
- 2 of each. Where possible, the stems for Valves V1650 and V1651 should be similarly aligned while Valve
- V1652 should be installed with the stem in a vertical position.
1 9. All welding shall be in accordance with the FPL Welding Control Manual. Weld numbers are specified on
; the PC/M drawings and have been previously identified within the PASSPORT Weld Control System. If additional weld numbers are required, a CRN will be required to this PC/M.
j 10. The three manual valves shall be locked in the open position in accordance with the Plant standards for (a) l mechanically securing the as-supplied handwheel and, (b) the administrative procedure for the control of valves, locks and switches (see Reference 37). I 1. Pipe support drawings included in this package are for administrative revision'to drawings only and require i no physical modification. 4
l CKN 0$4-196-6098 pi i i i Kevision 0
' , rasistyi esL PC/M 034- 196 '
( 1 Cea,eneau Viss) Um e, et ue, _ i i l l l Page 4 of 9 l Ase.ctate: I lAts: 4 I i l i laev. 1 l
- i mets Printed. I IPese 10 or 39 i j i l l I f
TOTAL BOU1pMENT DATA BASE SEBST
- A.S GENEkT25tR$3R N/A
! $PECIFICATION WEDGER 5/A EEAft TYPt1 ma0 8/A i ACTTTE M PASSIVE N/A EEAft TYPS2 130 N/A 5798 DIAMBTER INCE
; inc RELIEF R30058T S -
5/A Rasurrs Im ICAT10st 3/A DCIEWT Tea 005 FT LDS m IIICE
- PACEIES TOROUR FT 138 IEAR ALLAS FTROKB TIM SSC mamanreg g/A
} 311FICE 01AMETER INCE , namaannes p/A MIN R200 STROE3 TIME SD" MERMAL MODE N/A TB87 PR800ENCY Mos l Plas Ortk/Ulest SEAT N/A 7:s? an00taso s/A FAILURE DESS 5/A TSST PROC SERrf M i- N/A esterr r - > SX tas 1 VALV5 TW957 RATIBIG h IAS 1 vnLV5 T0000s SATIaIG M FT 138 l mvummon stem FAerca I s/A auramIC rse so/TTrs I s/A i l 4 Change perthis CEN 4
+
4 CKN 054-196-6099 , /li co-ponenti
,=sta ,,, ,s, .t., .1 -, ~ i l Pc/* ox-i,6 l Re*i= 0
) viese l l l fggg 5 Of *) i Aseectates l lAtti 4 i j i i laev g I l Dato Printedi l Itas. Q et 39 l l 1 l 1 Torn sootrusmy oATA aAss saast osstas caos s/A , nester Cops TSAA N/A d A-3 Sust2C IRaest N/A sF9C!r1 CAT 10ff Wtsest s/A sIAft TTPat Rao s/A 4 ACTIVs at Pass!Vs N/A s/A sEAft TTPas kao ~ a s198 D1AusfsR INCs unc asLzst asocast e s/A R910fs Iso! CAT!oel N/A l so.s.T ronous n tas LaulFFs INCs l PACEINo ToRQUs M Las j w nLos sTnors Trn sse j nammaast s/A
- omstres armarran tscs amanaem3 g/A i sen anon sTaoss T2ms see massen ascos s/A
, tsst rasocawcr nos
- etAll OVsR/tRfDat SEAT N/A T5sf RDOUTRED s/A rAILas noos s/A Tsst emoc saast A 2 - u/A vezeer /' 6 ) " T E -
tas v nys Tunast mATruo V tas v uvs tomar natsuo I rt tas evswoom sTam rACToa I s/A asmanze tro wo/Tves I w/A Change perthis CRN o=
. - ..-- - . . ~ - - .
CKN 054-1964095
/ ,,.uity, ,si. unit, oi uos _ l l PC/ A 0 4 4 1 % ! KMslon 0 Compon.nti vie 45 l t I f g 9 Aareciat.2 l lAtti 4 ! l 1
j lt.v ) i l
- c. . ennt..: i ie.. 35 .: 39 i
l $ l l l TOTAL BQUIPMEarr DATA RASE SEBrf DSS!QW C005 YEAR N/A A 8 GENERIC 3RREBER N/A SPSC1FICATION WUMBER N/A j BEAM TYFS1 REQ N/A ACT!YE OR PASStVE N/A
' N/A EXAM TYPE 2 REQ
' INCE STWE DIAMETER WRC R5t.1tr REQUEST S N/A RsnoT3 INDICATIOef N/A j 90serET TCRQUE FT !.SS LEMEFTK lleCE
._ _ T.R l SBC
%AI ALLott STROM TIM J RSMARE31 N/A 1
INCR ! OR1FICE DIAMETER mensaa reg y/A SEC K17 REQD STROKE TIME ; -; m/A woRMAL secos ; T.8T _ n/A Flow ovsR/UWDER SEAT W/A TEST RSQUIASD rAILURS se005 N/A I 4 TRST PROC SERET M a - N/A WEIGNT { M { Of-
- LSS VALys TuRUs? RAT 1pc U I.as J- ,T LS8 VALVE TORQUE RATiteG
, - R .,A
.. - R S, causRIC rze wo/Typs I w/A 1
l k Change perthis ORN eue
s CKN 0$4-196-6099 I
/ ru ,1, t v , est. un,t, .1 mo , . l lPC/M 034-196 l Revision 0
? Componentt V1446 t i i g}[$ Ateoc,ete l lAtts 4 l
. I lRevi I l este tr,ntedi i Irage 34p or 3 $ I j . 1 I i TUTAL SQUIPetENT DATA BASE $NSFT OEstGN CODE TBAA N/A ,
A.E GENERIC NLtdBER N/A l SPECIFICATION NUMBER N/A EIAst TTP51 RSQ N/A Aeffvs ca PASSIVE N/A EXAM TYPB2 RIQ N/A STDI DIAMBTER INCH ! WRC REL15F 1800EST 8 N/A REM 0fB INDICATION N/A 30sers? ToaQEss rf Las "8NGTE
. INCR PACEING TORQUE FT L&S 8
MAI AIAAlf STRolt3 TIM 8BC } REMAAE31 N/A ORIFICE DIAMETBR INCH , s ama r s2 N/A 4 KIN REQD STROEI TIME $8C 1 wCRMAL 8400E N/A TsST rasgosNcf w0s TLOW OVER/UNDER SEAT N/A i T337 RSQUIRED N/A l FA.!LUR3 MOOS _ N/A TEST PROC SEBST F 1 4 - N/A vetGer /' m J 6 *Z~ Las VALVE TERUST RATING N l LS8 vALys TomoUs mATsNG E rr Las
'1CNDOR 8734 FACT 0a F N/A GE3fB11C FIG 300/TTPB / N/A l 1
Change perthis ORN
CKN 054-196-6095 l
/ rumir, m ;... , a u., _ l lPC/A 034-196 Kevision 0 l Component i V144 9 l l g 9 i A r.ei.i., i iAct, 4 l I l iteve [
] I D.te Printedi l lPage % of N
! ! I l
.I' l TOTAL EQUIPMEarr DATA BASE SitBST I SCREDUL5/151CN W/A } 05319 CDOS N/A j DESI W C003 YEAR N/A A B G N ERIC WUmst W/A , SPSCIFICATION WUlGER N/A i 11AM TYPE 1 REQ W/A j ACT!vt OR PASSIVE W/A i N/A l j EXAM TYPS2 88Q STEM DIAaWTER IWCW WRC RELIBF REQUEST 4 N/A REMOTE INDICATION N/A 90eart? TORQUE FT LAS LENGTW INCW PACE 2IIC TORQUE FT LS$ ) MAI A&MMI STROKE TIM SSC REMAAES1 N/A ORIFICE 01AMETER INCE l ne.saare2 N/A
, M1W R200 STROEE TIME SBC j NORMAL Is005 N/A TEST PS200518CT seos
, FWllw OVER/tnIDER SEAT W/A
- TEST RagEr!RSD N/A a FAILURE 3I008
- N/A TEST PROC SHEST .[ h . - N/A l varaurr t F2 t,as i VALVE TERUST RAT 118G U
- LSE VALV3 Toe 0UR RAT!880 E FT US l 'VEarDOR STDI FACTOR P W/A 4 GENERIC FIG WO/TYPS -# N/A i
1 l Change perthis CRN i i 4 0 4 m 1 1 2
l CHANGE REQUEST NOTICE CRN NO.oH t%4MOPage i Of 2 PCM No. NPWO No. WO No. k SR implemented by-034-196 N/A N/A NS O Piant O ADM er N Affected Docurnent (See page _ _ for addrbonal affected documents) TEDB Affected: 0 Yes E No 3Ett.04-196 oci Rev. 1 Rev. Rev. _ _ . . Rev. Rev. Rev.,__ Rev. Rev. , Rev. M4b CD NA R v. Step (s) Reason for Chanoe: Pt/A es4-69(. Jc4bes e i.A A,,en we(c. reeeremeat 4s,r Ae fhne new RCGV5 m .! valver(vit.sa vs6SI ,4 vitef2L %rs ec wemi ;s : bir6 ed (er a4L: ken to r. meress effended cleeda4sle.g. BOD, or.cM, ek.h 6.4 was ri.t AckJed er. (Ac ses P(ID (D%* erm- c.-cys, Change Request / Sketch (It'necessary) 3 Wed. J t o) . F re solve +L:s everstpf, Ass P d ID +=51 also sk.w +L:s uform.O en 1 g See P.p 2 .4 +40s CRN (.r- (Le. cpp,. ped as Lilw3 ;Jerm.3:en, O Q . PSL INFO SYC . z a
! h O !
E ACTION BY ENGINEERING: (Preliminary) 8
- N O S In Person E Proce4 d
- This CRN has been discussed with T. Zudmas of Engineering. O Teiephone O Hold DCC SOURCE OF CHANGE
- APPROVALS:
Impi. Dept. Error Convenience Prepared By- laers G. Losleccse Date IDh Engr. Error Design Evolution ' Emsting Cond. C Other pg g, Dept. S d e. E g n e s.e W Phone '7I 3 7 Mat'l Substtuton " # SCOPE OF WORK: Date bM2,6 Impi. Dept. Supe, .
/
increase Decrease E Unchanged ENGINEERING APPROVAL (Final) IMPACT OF REVISION CHECK SHrdT Yes No 3 APPROVED NOT APPROVED 0 JPMS i Design Org. (CDO) 1. Design Basis or Analysis Affected E Prepared by: d 4- Date 6/3.Z/.9.st 2. Safety Etalualon Affected E Venfied by:- (NM _ Dated _/M2d 3. PD/MDs or SRDs Functionally Affected O W Approved by- M4uA2/ll. -- - Date.(d.f2A/ Sip 4. Start-Up, Operations or Maintenance z g JPN (if not C c Date _f_ / __ Requirements Affected g Remarks /Basas for Dispositon: %e alraww. *.nfermh ne e.dr.d unn Pa e 2 J (kra C RM '. s W carres_f d a n. ,*,,,.A L E#---wa l'a c- e's-ku l& Am s ur,AICa t . a y s s -
y CRM No.034196-6390 Rwe 2 .f 1 j L _
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e::y e-s.: ! = = t*-ec-sos % y i ry, , b l (REF. CDORD. G-8) (REF. COCRD. F-8) R W]RK (RE . JWG. 8770-G-078 SH. '.:.0) NOTE: FOR SIMPLICITY, ONLY AFFECTED AREAS ARE SHOWN g RoRIDAS P ? . C ET JPN-034-196-om on f62. APPROVAL t*at i 001 ! CH: IU - -- Y- - FLOW DIAGRAW 5 DATE: 4 3T-% '[ l REACTOR COOLANT SYSTEM 1 5 A terocor o.c
n 4 . , I Intel'-Office Correspondence 8 @L JPN-SPSL-96-0346 To: S. A. Valdes cate 7 (17 [9 4 St. Lucie Plant From: bD. Y-, 4-4 J. Denver h Department: JPN/PSL Nuclear Engineering
Subject:
ST. LUCIE PLANT UNIT 1 , RCS Hot Lacr T==nerature Alarm Satcoint. REV. 1 PROJECT #: REA-SLN-96-040 FILE: PCM 96117 Attached for review, approval and use is the Minor Engineering Package (MEP) for the subject PCM. This Minor Engineering Package (MEP) provides authorizatien and instructions for increasing the RCP hot leg temperature alarm setpoint. If you have any questions, please centact Pat l'endrick at 447 ~479 l l C0C CTi.
.-d
- pies: J. Harmon- OCC-CS/PSL (w/ original) E .g D. M. Stewart - SCE/PSL G,_,
I *: A. S. Suggs - JPN/JB (w/dwg list) U l R. Olson - ICM/PSL (w/dwgs) D. Howard - ICM/PSL _
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4 QI 3-PR/PSL-1 $i Revision 40 May,1996 )* Page 32 of 38 l ATTACHMENT 2 i PC/M REVIEW FORM (Page 1 of 2) l
- PC/M Number 9 G / / 7 Supplement Number / Expiration Date 6 /30/ 9 7 i
PC/M
Title:
i Kc.s Hot La3 . % peratum Ala rm se +poin t c h ns e. i l PC/M Classmcation:
- Major Modification or Minor Modification f
{ Safety Classification: Safety Related /Ouality Related Not Nucisar Safety Related Administrative 4 ! PC/M Cego.f: -
- ./ Normal Either/Or As-Requested Package As-Fail Generic i
l Does the PC/M contain a Safety Evaluation? O Yes or FNo i ! Is this a proposed change or modification to a unitfsem or equipment that affects l nuclear safety? [F Yes or O No { if either of the above questions is YES, FRG approval is required. FRG Review Required? L s or O No M Date: 7 / / 7 /__9.fe , G6nfiguration Management [W /:S b J SaksDate: 9/NIYd Plant General Manager FRG Number: 9 / -/ 5' 9 FRG Secretary: MMM Date: 7/ /8/ 9 ( FRG Comments:
.- __ ~ ,_. -_ - . . - . . . ._ . _ . - _ - --. - . - . . . . _ . -. _
3 QI 3-PR/PSL-1 Revision 40
' May,1996 lb
<i Page 33 of 38 1 ATTACHMENT 2 PC/M REVIEW FORM ' (Page 2 of 2) implementing Documentation: Department ER/NPVy0 # WO# 2C G E / 594-3 C?& al79+3 PC/M Renew and Approval: k A-- Date 7 / /619G-ration Management . N' Date i / IV /% Wrty Control Comments: 3 l Arese Affected: Yes or No Desenption Pro implementatxm Requirements /R40 (if YES, ensure all affected. documents are , revised pnor to implementation.)
)
Operator Trainmg Yes As per Training Departmert Regtarements Operating Procedures /e.s Openh s twie e C < ,peculw* cLaSes Surveillance Procedures ye3 /e c n siew #. r sc.c. d m e L.y.s Maintenance Procedures Ye5 iet et view b Mrocad*'t ckaafe5 _ Spare Parts /Vo Drawings /Technscal Manuals No PODS? Y /O FUSAR Change NO TEDB Change Pes Human Factors (CREDIT) No Environrnental Concems , No in-Service inspection No Maintenance Rule No' Plant Re'strictions NO Others Al 0 b Date 7/ /6 /_ffe Configutdition Management
MINOR ENGINEERING PACKAGE (MEP) PLANT PSL UNIT 1 PC/M NUMBER 96117 SUPPL 1 ORIGINATING DOCUMENT __ EXPIRATION DATE 6/30/97 PC/M CLASSIHCATION SR X QR NNS __ ADMIN , TITLE RCS Hot Leg Temnerature Alarm Setnoint Chance ADDITIONAL REQUIREMENTS / INSTRUCTIONS YES NO AS-BUILDING TO COMMENCE UPON ISSUANCE OF PACKAGE? _ _X_ THIS PACKAGE HAS Tife POTENTIAL TO SIGNIFICANTLY _ _X_ IMPACT PERSONNEL RADIATION EXPOSURE (See Q13.13). IF YES, JPN FORM 72 IS REQUIRED. , 10CFR50.59 SCREENIhC YES NO
- 1) DOES THE CHANGE REPRESENT A CHANGE TO THE FACILITY AS DESCRIBED IN THE SAR7 ___ _X_
- 2) DOES THE CHANGE REPRESENT A CHANGE TO PROCEDURES AS DESCRIBED IN THE SAR7 _ _X_ i
- 3) IS THE CHANGE ASSOCIATED WITH A TEST OR EXPERIMENT NOT DESCRIBED IN THE SAR? _ _X._
- 4) COULD THE CHANGE AFFECT NUCLEAR SAFETY IN A WAY NOT PREVIOUSLY EVALUATED IN THE SAR7 _ _X_
- 5) DOES THE CHANGE REQUIRE A CHANGE TO THE TECHNICAL SPECIFICATIONS? _ _X_
NOTE: IF TIIE ANSWER TO ANY OF TIIE ABOVE 10CFR50.59 SCREENING OtlESTIONS IS YES IllE MEP CANNOT BE USED REVIEW / APPROVAL: IN1ERFACE TYPE GROUP PREPARED VERIFIED APPROVED FPL APPROVED
- MM -
MECH / ELECT / . , , . . /I 1&C / ff $$. h CIVIL / NUC" / kW10 CSI I
/
NUC WEL /
- For Contractor Evals As Determined By Projects " Review Interface As A M.inimum On All Non-Admin MEPs FPL PROJECTS APPROVAL: A L. DATE: 7 17 hl, f
PCIM 96117 14 Revision 1 Page 2 of 3 Engineering Justification This Minor Engineering Package (MEP) provides authorization and instruction for changing the RCS hot leg high temperature alarms frorn 605 *F to 608 'F. He purpose of the RCS hot and cold leg temperature indication is to determire RCS fluid temperature and to assure core heat is being removed by assuring aT between hot and cold leg temperatures. Each of the two hot legs contains five narrow range RTD channels to measure coolant temperature leaving the reactor vessel. Four of these channels are used as hot leg temperature signals to tae reactor protective system (TE-1112MA, MB, MC, MD for the 1 A1 loop l and TE-1122 MA, MB, MC, MD for the 1B1 loop). The fifth hot leg temperature measurement channel provides a signal to the average temperature computer which is a part of the reactor regulating system (TE-I l l IX for the 1 A 1 loop and TE ll21X for the IBl loop). The temperature from this channel is indicated in the control room in addition to being recorded. A high temperature alarm is provided on this channel to alert the operator to a high temperature condition. As evaluated in Reference 8, the fraction of plugged steam generator tubes for Cycle 14 operation will be approximately 23.4%, ) increased 12% from the level of steam generator plugging in Cycle 13. Assuming an average steam generator tube plugging l level of 25.5%, the Safety Evaluation concluded the bulk value of Tw for cycle 14 will be 600.9 "F with an expected indicated Tw, due to the Hot Leg Thermal Stratification Factor, to be 604.9 *F (Ref. 8 Att.1). The existing higit temperature alarm setpoint is set at 605 'F (increasing). The measurement instrumentation has an accuracy of 0.5 'F. Since the expected temperature indication of 604.9 'F is within the serpoint tolerance, the alarm setpoint will be raised to 608 'F. TEs alarm setpoint was selected to provide for operational margin and prevent spurious alarms. Operator actions for annunciators H-7 l and H-8 were reviewed for impact. , i i The RCS hot leg high temperature alarms are located on RTGB 103 annunciators H-7 and H 8. These alarms are controlled by Temperature Indicating Alarms TIA-llllX and TIA-ll21X which are respectively fed from the TE-1 IllX and TE-l l21X 4-20 mA loops. The TIA's are Sigma model 9222-10ED with a range from 515 to 615 'F. This PC/M will raise the setpoint ; to 608 'F, which is within the range of the instruments. l Conclusion The RCS Hot Leg temperature instrumentation is discussed in Unit i FSAR section 5.6.1 and the Reactor Regulating System is discussed throughout FSAR section 7. Reactor Core Thermal Power is discussed in Technical Specification 2.1.1. This PC/M will modify the alarm setpoints for RCS hot leg temperature, which is beyond the level of detail discussed in the FSAR or Technical specifications. This modification results in no degradation, either directly or indirectly, to any safety functions required for analyzed accidents or introduce any unreviewed system interactions. A design integration review was performed and it has been concluded that this modification does not affect nor is affected by other designs in progress. TIA-1lllX and TIA-ll21X are identified in TEDB as Quality Related components. Therefore, this PC/M is classified as Quality Related. OTHER AFFECTED DOCUMENTS Reference Paragraph /Page or Document Attach Revised Pages TEDB See Attachment 1 SPECIAL INSTRUCTIONS \lMPLEMENTATION REQUIREMENTS
- 1. Coordinate all work with Operations to obtain appropriate clearances.
- 2. Set TIA-IlllX and TIA-ll21X to alann at 608 'F increasing in accordance with plant procedures.
l l 3. Operations and ICM review this modification for impact on plant procedures.
4 PC/M 96117 o Revision 1 Page 3 of 3 POST MODIFICATION TESTING
- 1. Verify proper calibration of temperature indicating alarms.
4 REFERENCES
- 1. St. Lucie Unit 1 FSAR through Amendment 14.
- 2. St. Lucie Unit i Technical Specifications through Amendment 142.
- 3. St. Lucie Active Safety Evaltation database reviewed 7/15/96.
- 4. Nuclear Engineering Drawing Index,7/15/96.
- 5. 8770-G-078 Sh 110 Rev. 20 Flow Diagram Reactor Coolant System
- 6. Control Wiricg Diagram 8770-B-327 Sh.136 Rev. 24
~
Control Wirsg Diagram 8770-B-327 Sh.137 Rev. 27
- 8. Safety E valuation JPN-PSL SENP-96-065 " Operation With increased Steam Generator Tube Plugging" Rev. 2 l
- 9. Plant Ancunciator Summary, OP No. 1-0030131, Rev. 66 i ATTACHMENTS Number Number Descrin iortrJj'k of Pages i
- 1. TEDB Update Package 3 DRAWINGS
, (I) ALL AFFECTED (2) (3) MEP(C DC/M DRA%TNG NO. " E DESCRIPTIONfrITLE PLANT DRAWINGS REX E BEY None VENDOR MANUALS Q MEP (4) Plsnt Document Number Egy Vendor / Fouinment *', Remarks Eg1 None (1) DISCIPLINE: C = CIVIL: E = ELECT; I = IAC; M = MECil; N = NUCLEAR (2) REVISION of affected drawing / vendor manual. Indicate "new" if the drawing / vendor manual is being created. The engineer is accountable for reserving the new drawing / vendor manual number. 9 (3) UPDATE PRIORITY: Indicate 1 (SRD),2 (non-SRD), or 5 (other) for PSL. Indicate I (POD),2 (CRD),3 (MD). 4 (ED), or 5 (other) for PTN. (4) M,EP REVISION under which last drawing change was made. d a
n j , Facility PSL Unit.L. PCM 96117 4 Attachment No. I Revision No. Xi '" 4 7/"I* Page 1 of 3 ! TOTAL EOUIPMENT DATA BASE CHANGE PACKAGE COVER SHFET Description of Change: gp Change RCS Hot Leg Temperature Alarm Setpoints from 605 to4Wdeg. F. i Basis for Change: PC/M %117 1
References:
f 5 Engineering Prepared by , Date 7//f/f( Verified by #d[ /' Date F//MM ! Approved Date /f4 , ipline Sgvh Engineer) 1 Confleuration Manmoement Reviewed by: . Date: Data Entry by: Date: Data Entry Verified by: Date: For instructions, see QI 2.8 1. IPN Form $3. Rev i0/92
4
. 4' l !Feestity: PSt imit: 01 us: _
j j PCM 9csi7 l l Cassionants TIA*1111X j l l 1 lAseeciates l latt: ; I l l lRev gs M/t 7h7/'4 l l Date Printed: 07/15/M l lPepe 1 of 3 l 1 I i i I j TOTAL EeulMEuf DATA SAst SNEET a 1 I { Drmring: Sheets Coordinates ) 877D s 327 136 8779-s 075 (C 7) 110 8779-3637 8779 3438 l Tech saanuetes l . 8779 5817 l Proceeree:
- 1400065 metes
Approved Attornate j Efe: Descriptions stedets sev. Instl. Erg Ver. j 0015 vtaSATILE 81EAsuuluG luSTR 2000-10-4 (50 08018) 000 ,, T j j Parameter J Bases Vetus: UOut Pe0 CESS BAm0E #1 515 615 m/A
- PSOCESS LAllTS #1 NGF N/A SleIAL INPUT #1 6 20 N/A I e4 DC N/A IMPUT LAllTS #1 l SI M AL SffPUT #1 N/A mirPUT tallTS #1 N/A i SCALE RANGE #1 515 615 m/A SCALE LAIITS '#1 DEG F N/A i CauTWOL CLASS #1 1 06 N/A
! ACTION #1 1 IIICHEAStuG N/A MJuCTION #1 1 _ K1 A N/A ! N/A Pe0 CESS Pe0 CESS RESET fieSETPT #1-(lSOd ] _ N/A ! Pe0 CESS LAllTS #1 1 NGF N/A l ACTUATIOu SETPT #1 1 N/A ACTunTIou RESET #1 1 N/A j ACTUATIOu tullTS 81 1 N/A i i l 1
i . l Facility: PSL tmit 01 We s _ llPCM 96/17 l l Ceepenent: TIA 1121X l l l lAseeclete: l lAtt l mA l l l [tev: g'/ 7/I7/Tb ll lDatePrinted: 07/15/96 l lpese 3 of 3 I l 1I I i TOTAL EeUIPUENT DATA SASE SufET
- Dreerig Sheet Coordinates i 8T70 B 327 137 i 8770 4 078 (C 3) 110 l 8770 3637 j 8770 3638
$ Tech Manuales
- 8770 $417 8
! Preca h ee 1A00065 .l l i metes: Approved Alternate Kft: Descriptions models tev. Instl. Eng Ver, 0015 WERSATILE sEAmalm Intia 200010-G (50 cages) 000 T Parameter genes Vetus: 1N31: Pe0GSS BAgoE #1 515 615 m/A PacGS$ WITS #1 DES F g/A SIMAL fuPUT #1 4-20 N/A luPUT tallTS #1 M DC g/A SIERAL CUTPUT #1 __ g/A GJTPUT tallTS #1 N/A SCALE RAuct #1 515-615 g/A SCALE tallTS #1 DES F m/A CONTuGL CLAS$ #1 1 06 g/A ACTION F1 1 lutaEAllus e/A FUNCTl3 #1 1 ' " ' * - N/A Pe0GSS SETPT #1 1 (OS g/A Pe0 CESS RESET #1 1 N/A Pe0 CESS tallTS #1 1 DEG F N/A ACTUAflos SETPT #1 1 g/A ACTUAflel RESET #1 1 N/A ACTUATION UulTS #1 1 N/A
. _ m .
QI 3-PR/PSL-1 1
~
Revision 40 May,1996 ) Page 35 of 38 l ATTACHMENT 4 l l SYSTEM ACCEPTANCENURNOVER SHEET l (Page 1 of 2) Page 1 of f PC/M No. 9[D l O Revleion OtI St-;-;' me O+I { Unit (s): G'1 02 O comrnon SATs: O Partial M Complete l Tltte: ROS lkTf lM~~T-T=f0P. A LM($) 3 h T T- D j/ [ l Implemented by: i Decipline: O Electncal O Mechanical lac O Maint. Propx:ts O Sys. Proteccon O Otner ; l 0 Mod. Deferred Testing is required in Mode "le I l O This SATS is a partial tumover. werx remaining inciudes the following-i I
- i. l
! PC/M COORDINATOR 8: I All procedures for my department which are required for tumonr are complete and/or procedure changes I j for my deptonent which are not required for tu are listed below: l YES N/A DATE: O @ Security: en. )s e 7 / / f /f_(_. , O E chemetry: XM d 7/ /9/f_!;. O O Fire Protection- M Ad e '7 / l9 / 9' O Q Health Physics . - 7 //k /K 8 O Plant Maintenancei I I 7 //f /M O @ Emergency Preparedness k.b 7 / /9 /96
- PROCEDURE NO. DATE REQUIRED CR OR PMAI NO.
/ /
/ /
, / /
/ /
/ /
, SYSTEM ENGINr.ari OR OPS SUPPORT TESTING: YES N/A i System funcbonal testing has been satisfacterity completed and all test documents used j have been transmitted to CM. (N/A if test has been mode deferred for this SATS). E D The updated PODS for which the SATS is behg issued adequately support the design change. E 7/c /, All Department procedures required for tumover are complete and/or SCE Department
; procedures not required for turnover are listed above. E O System Engineer or OST: [ M Date: 7 / // / 96
- /R40 a
QI 3-PR/PSL-1
- Revision 40
/ May,1996 Page 30 of 38
. ATTACHMENT 4 l SYSTEM ACCEPTANCElTURNOVER SHEET i (Page 2 of 2) ! PCM No. %lM Page 2 of fc., ! SPONSORING DEPARTMBft: l The instaAed modmcetion meets gf it was ongmated.
- Sponsoring Department Head
- bd/ N o' A & /2Co Date: "7 / f/ /.ffs.
j TRAINB00 COORDWATOR: YES N/A 1 All operator training commRments have been identitled in the Tracidng System Achon l Request Process for review and =*=arpnt incorporation into PSL's Trarung Matenals. 7O j TSAR No(e): /89.5 7.T N Mo. l Appilcable trarung below and available in the Control Room. ' S .V O l Training Cocedinator: _ _ _ _
/- Date: 7 /$$
- OPERATIONS COORDINATOR
- 'YES N/A j The Master clearance Order has been updated. O Ef
! M requesd equipment tag changes are mmplete. O Ef M temporary or permanent labeimg is complete. O CI l ! M em plant operating documents. are updated and in the Control Room. O I i All procedures required for tumover are and in the Control Room l and/or procedures not req tor lisyt 1 of this SATS. [O Operations Coordinator: - V Date: 7 / 50/ f5 j NUCLEAR PLANT SUP5tVISORf j g YES NO N/A l All equipment is aligned in accordinnoe with appropriate operating procedure. .O [O
- E No is chocied, Egger omponent is in the Eqtapment Out of Service Log.
I Operabety as defined in the Techrucal Speedications has been met O [O E NO is checked, Egg ensure component is in the Equipment Out of Service Log. l j Equement Out of Sennce been todated for this SATS. O D- ! Nuclear Plant Supennsor:[ _ Date: 7/M , The secean regwoo oroy unen moon assenso esens I MODE RED TESTING NOTIFICATION Mcde Deferred Testing was performed in Mode (s) The followng apply: /R40 l l ! O M testing for this SATS has been satisfactority completed. 3 ! O The testing was not satisfactorpi completed and this SATS shall be a partial tumover. 5 CM Representative: A// a Date: / / Nuclear Plant Supervisor: Y ^ Ad Date: / / 5 CONFIGURATION MANAGEMENT: i The PCM review process for this SAT has been satisfactorily completed. l CM Representative: h Date: B / / 3 /M - . Comments: 1 f f I /R40 j - 5 1
- ~
u _ CONDITION REPORT (C.R.) LOG MODE TRANSMITTED TO LOGGED IN DATE/ TIME ORIGINATOF: CONDITION SYSTEM
^ "
- LAST NAME AND REPORT NUMBER SIGNATURE OF PLANT NUMBER YIN ENTRY SIGNATURE OF LOGGING INDIVIDUAL EXTENSION INTO TRANSMITTING MODE INDIVIDUAL Qvrt.s:Tiodrsecc ~6cvTp4G ms:sil ' ' 31 '% 8'II dA of Io-3o %
E 2689 d d f
~7 '-{(o l P-ocle (2e /~h /o/31/$c /b 't. wl."bb ] 39r gg ,t, gj %.
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,0 r Y mner 8 LACK'A) ASS ffW/NV c)J//f4 /'{} S S/npff/A/S E 2692 977
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CONDITION REPORT TRACKING DATA CONDITION REPORT DATA FACILITY: PSL CR NO: 96 2696 SUPPL: PGM/JBCRRP APPROVAL: 11/04/96 i OPERABILITY /REPORTABILITY DETER: C. No Operability Concern /Not Reportable i SEVERITY LEVEL: 30 Calender Days ORIG DUE DATE: 12/04/96 I l SYSTEM #/NAME: 99 MISCELLANEOUS i UNIT: 01 COMPONENT ID: DDPS MANUAL I COMPONENT NAME: DDPS MANUAL l LOCATION (BLDG /EL): UNIT 1 CONTROL ROOM I DISCOVERY DATE & TIME: 10/31/96 08:00:00 AM EVENT DATE & TIME: 10/31/96 08:00:00 AM l CR ORIGINATOR (S): STEVE SUMNERS l ORIG DEPT: OPS EXTENSION: 3268 I CONDITION DESCRIPTION: NRC INSPECTOR INQUIRED OF THE STATUS OF SETPOINTS AS LISTED IN THE DDPS MANUAL WHEN THE DDPS MANUAL WAS REFERRED TO IT WAS NOTED THAT THE SETPOINTS FOR PT 317 AND 318 WERE LISTED AS THE PRE-S/G PLUGGING l i VALUES. CAUSE: THE DDPS MANUAL WAS NEVER UPDATED AFTER THE S/G PLUGGING. IMMEDIATE ACTIONS TAKEN: NOTIFIED ANPS. CR WRITTEN. RECOMMENDED ACTIONS / SUGGESTED ASSIGNEE: UPDATE THE DDPS MANUAL TO REFLECT THE CURRENT STATUS OF THE PLANT. AND MAKE IT A CONTROLLED DOCUMENT SO THAT THE INFORMATION WILL ALWAYS STAY CURRENT. ADDITIONAL
REFERENCES:
ORIGINATOR REQUESTS COPY OF CLOSED CR7: Yes OTHER: OUTAGE RELATED7: No OUTAGE CYCLE: MODE HOLD?: No FOR ENTRY INTO MODE: COMMENTS: OPERATOR WORKAROUND (OWA): No NPS/JBCRRP NAME: HONEYSETT NPS/JBCRRP DATE & TIME: 11/01/96 02:50:00 AM ASSIGNED DEPT: ENG ORIGINAL AS$lGNEE: DENVER ORIG ASSIGNMENT DATE: 11/04/96 ASSIGNEE: ASSIGNMENT DATE: ASSIGNEE: ASSIGNMENT DATE:
, ASSIGNEE: ASSIGNMENT DATE:
COMMENTS: NP 700 REPORT 7: No ROOT CAUSE?: No INVESTIGATE & CORRECT?: Yes QA CORRECT ACTION VERIF?: No NONCONFORMANCE (NCR)?: Yes FUNCTIONAL FAILURE?: No BY: MARK WOLAVER INVESTIGATION ANALYSIS: CAUSE CODES: 1
CONDITION REPORT TRACKING DATA i TYPE ! i MOD i CAUSE , i DOCUMENTATION INITIATED: No REVIEW REQUIRED FOR: PWO: EQ7: No REA: 10CFR50.597: No PCM: 10CFR217: No OTHER: ASME XI?: No NCR DISPOSITION: N/A?: No REWORK 7: No REPAIR?: No USE AS-IS?: No OTHER: FRG/PNSC REVIEW?: No PREPARED BY: CLOSEOUT / PROB
SUMMARY
CAUSE: CORRECTIVE ACTIONS: OUTSTANDING ACTIONS: MODE RESTRICT RELEASED?: N/A NUCLEAR NETWORK 7: No FRG/PNSC MTG #: MTG DATE: COMPLETION APRVL DATE: COMPLETE?: No CROG REVIEW DATA EVENT INITIATOR: A2 POTENTIAL HAZARD?: No LER?: No NOTICE OF VIOLATION?: No ERT?: No NON CITED VIOLATION?: No CROG DATE: 11/04/96 ROUT!NG DATA ROUTED TO: DENVER ROUTED ON: 11/04/96 ROUTING REMARKS: DELIVERED TO COLLEEN 11/4/96. 2
- . _ . _ _ e CONDITION REPORT TRACKING DATA FIRST EXT APPR By*. LEVEL A TO LEVEL C BY RED 11/6/96.
SECOND EXT APPR BY: ) THIRD EXT APPR SY: CURRENT DUE DATE-t CR POD COMPLETE 7: No e 3
Y l Operations Department Chronological Log Unit 2 1 SHIFT NUMBER: 688 o NUMBER: 688 NUC POWER: 100 l DATE: 7/14/96 DELTA T POWER: 100 SHIFT: MIDS MWE: 900 BOARD RCO: CASSIDY CEA GROUP #: 5 I DESK RCO: de la Guardia POSITION: 136 NWE: CASIAS T AVG: 573 ANPS: ALBRITTON BORON: 851 NPS: SANDY Xe WORTH: -2442 MODE: 1 = CALCULATED SD MARGIN: >5000 PCM l i MAJOR MILESTONES OR ACTMTIES TO BE PERFORMED DURING THE SHIFT: l TIME LOG ENTRIES 19-00 COMPLETED BOARD WALKDOWN 1 20.40 F.'ARTED 2C CHARGING PUMP IN PREPARATION TO SECURE THE 28 FOR THE SNPO TO ADD OIL TO ThE 2B CHARGING PUMP 20:42 SECURED 2B CHARGING PUMP q 20:46 STAP.TED THE 28 CHARGING PUMP 20:48 SECURED 2C CHARGING Ps JP 20:50 RECEIVED ANN M-14 CHARGING PUMPS FLOW LOW , CHARGING FLOW DECREASING, STARTED 2A CHARGING PUMP, CHARGING FLOW DOWN TO O BEFORE 2A CHARGING PUMP RECIRC VALVE FULLY CLOSED, ISOLATED LETDOWN, ISOLATED CHARGING . ENTERED CHARGING LETDOWN ONOP 2-0290030.SNPO REPORTS LEAKAGE OUT OF THE 2B CHARGING CENTER PLUNGER AND EAST PLUNGER 21:05 STARTED 2C CHARGING PUMP TO RESTORE NORMAL CHARGING AND LETDOWN. 21:05 ENTERED T.S ACTION STATEMENT 3.2 5 DNB PARAMETERS DUE TO PZR PRESSURE <2225 PSI, STARTED BACK UP HEATERS 21:10 EXITED T.S. ACTION STATEMENT 3.2.5. DNB PARAMETERS , FZR PRESSURE > 2225 PSI SECURED HEATERS 21:30 NPS DECLARED AN UNUSUAL EVENT BASED ON RCS LEAKAGE > 10 GPM IDENTIFIED AFTER CONVERSATION WITH M/M PLANNER ON HOW MUCH RCS WAS LEAKING OUT OF PACKING 21:31 EXITED ONOP 2-02I0030, CHARGING AND LETDOWN RESTORED 21:32 ISOLATED 2B CHARGING PUMP, PUMP DECLARED OUT OF SERVICE 21:3,5 TERMINATED UNUSUAL EVENT,2B CHARGING PUMP BREAKER IS RACKED OUT 21:41 ATTEMPTED TO CALL S.W.P. ON H R.D. DID NOT WORK 21:51 MADE CONTACT WITH S.W P. 21:54 CALL TO S.W.P. COMPLETED 13-Jul-96
.- . _ _ . . -- .- -. . . . - - _ - ~ . . . . . . . . .. - . .- ... _.
i
- Operations Department Chronological Log Unit 2 SHIFTNUMBER
- 680 22:02 ENTERED T.S A.S 3.2.5 ON PZR PRESSURE < 2225 PSI 2210 EXITED T.S A.S 3.2.5, PZR PRESSURE > m PSI
., 2215 STA COMPLETED CALL TO THE NRC i 22:49 DECLARED RIM-26-90 PLANT VENT GAS WRGMS OUT OF SERVICE I , TIME REVIEWER'S COMMENTS ? 2 i i j i 4 I. 1 4 i 1 i d n J l 1 k 4 13 Jul-96 2 E
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- 2ER QUENCH TANK PRESS - - - - --2"sfe PSIG 10.O 100.O , 70.O
{ f b: 8.9 88.9. 68.9
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- lntsr 0ffice Correspondence FPL JPN-sFSL-96-0236 To: S. A. Valdes Dates May 18, 1996 St. Laacio Plant V, .p,. M W b Freen: D. J. Denver Location: JPN/JB Nuclear EP -- 4 subjoet: ST. LUCIE PLANT UhTT 1 RWT VORTEX SUPPRESSOR pt'M FilJ'. GMht(
l Attached for your review, approval and use is PC/M 96-085, Revision 0, Supplement O. Revision 0 installs a vortex suppressor inside the RWT at the location of the outlet. This PC/M does not affect, amend, or change Techincal Specifications or the FSAR. By copy of this letter, St. Lucie Document Control is requested to distribute this package to the normal distribution.
- If you have any quertions, contact T.C. Kendall at 467-7117.
TCK Attachment cc: J. Harmon - TS/PSL (w/ Repro) K.K. Mohindroo - JPN/PSL C.M. Spalter - JPN/JB
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Form 1008 IStockadi Rev 2 :3
i Ol 3-PR/PSL-1 Rsvi2 ion 40 May,1996 \ 4; / h/ ATTACHMENT 2 Page 32 of 38 i PC/M REVIEW FORM . (Page 1 of 2) PC/M Number 96085 Supplement Number _ O Expiration Date JZjBi/%
- PC/M
Title:
i UntT-1 Rl>3T VORTE)G SDPPPEST5% PC/M Classification: I Major Modification or / i Minor Modification
- Safety Classification
! Safety Related
_ Quality Related Not Nuclear Safety Related _ Administrative j PC/M Category: i j -Normal Either/Or _ As-Requested Package As-Fail Generic i Does the PC/M contain a Safety Evaluation? Yes or O No is thissafety? nuclear a proposed change or modification to a ujntt ystem or equipment that a Id Yes or O No if either of the above questions is YES, FRG approvalis required. FRG Review Re quired? IYes or O No
.l$Y Date: 5 l b 3 G>
Configuration hhtnagement
/
Plant General Manager
$rA/044 Date: . fl_/ 9 I 9'd FRG Number: 016>- 159 FRG Secretary: NDkM Date: 6h /%
/
FRG Comments:
.- - - - . _ _ ~- - - .. ._ -.
1 Ol 3-PR/PSL-1 Revision 40 May,1996
< Page 33 of 38
/
ATTACHMENT 2 PC/M REVIEW FORM (Page 2 of 2) implementing Documentation: Department ER/NPWO #
+'/2 o-TT<Il W/O #
Cdr' 9; Inol 0 /51 ' % of 2 NO r4 /losscrs G / / o r^Z D 96eQ~762f'$ PC/M Review and Approval: - N Date b/I k /b [, Configuratio Management Quality Control Date C/ /* /N l Comments:
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AA.0 Y N"C-C&E$ - DO Cd H WA O W LiN Y- L of MT fk oll Tb Ci ^St.OC, 4MDv)/t's S - h)Crf' ffM' D{ /ClA . Y{ SIS'9b Areas Affected: Yes or No Description p' Pre-implementation Requirements ! (if YES, ensure all affected documents are /R40 revised prior to implernentation.) NO i Operator Training Yes As per Training Department Requirements Operating Procedures NO Surveillance Procedures MD Maintenance Procedures I WO Spare Parts NO Drawings / Technical Manuals YES FUSAR Change PODS? Y /h MO TEDB Change NO Human Factors (CREDIT) NO Environmental Concems MO in-Service inspection
}JO Maintenance Rule NO Plant Restric'tions*lMPLFrYEkTT t 34EM RtAJT r5 Mor RE Others*FIAWL Ocubrna\ oF rHE rAME LikmR G4ALL FK 1MSPEdiciD FPL. 3PM COAT 1MTd5 SPEC 1 ALbil5
)/ 2 1
Configuration Mgement Date 1,[2t/ %
FPL NUCLEAR ENGINEERING ENGINEERING PACKAGE PC/M NO: 96-095 REV: O SUPPL: O PLANT: St. Lucie UNIT: 1 TITLE: Refueline water Tank Vortex sunnressor REVISION DESCRIPTION: Initial Issue l LEAD DISCIPLINE: Mechanical EXPIRATION DATE: 12/31/96 REA NO: N/A DWA NO: N/A PC/M CLASSIFICATION: SR X QR NNS DESIGN ORGANIZATION: JPN ! DISC CHIEF REVIEW REQD? YES NO X EXTERNAL INTERFACES: DISC CHIEF SIGNATURE: ! REVIEW / APPROVAL: INTERFACE TYPE GROUP PREPARED VERIFIED APPROVED FPL INPU REVI N/A T APPROVED
- EW N m -
MECH X .(,__ , Mf h, , #8/E __t ^ ' - - ELECT X q v r I&C X .. _ m, # // L CIVIL X e NUC** X C. n 'e ESI X NUC X FUEL
- For Contractor Prepared EPs As Determined By Projects
** Review Interface As A Minimum On All EPs j FPL PROJECTS APPROVAL: %WN DATE: b i
Form 3, Rev 6/94
PC/M No 96-085
. Rev 0 Page l of 1 LIST OF EFFECTIVE PAGES PAGE NO. M 1 0 2 0 3 0 4 0 5 0 6 0 7 0 8 0 9 0 10 0 11 0 12 0 13 0 14 0 15 0 16 0 17 0 18 0 ATTACHMENTS Number Paces Revision 1 2 0 2 1 0 3 1 0 4 3 0 5 1 1 Form 3, Rev 6/94
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I PC/M No 96-085 i . . Rev 0 Page 3 o f _13_._ l ABSTRACT i , This PC/M installs a vortex suppressor in the Unit 1 Refueling Water Tank (RWT) to prevent possible air ingestion by Emergency Core Cooling System (CCCS) and Containment Spray (CS) pumps during a design basis safety injection scenario. l. The RWT is a 50 foot diameter, 40 foot tall vertical cylindrical tank constructed . e.M aluminum. The RWT stores the inventory of borated water required for filling th- 2eactor cavity during refueling activities. During normal operations, the ! RWT is the dedicated standby supply of borated cooling water'to be injected into l the Reactor Coolant System in the event of an accident. The vortex suppressor to be installed is a downward facing box elbow fabricated , from plate aluminum and attached to the RWT wall above and to each side of the i RWT outlet pipe. The sides of the suppressor extend downward to the elevation of the bottom of the outlet pipe. The design increases the effective submergence ; i of the tank outlet while also increasing the area of the effective outlet. This ! reduces the vertex potential while ensuring that the top of the tank outlet is not uncovered during the high flow rates expected during a full ECCS/CS I actuation. { The suppressor is fabricated from aluminum to be compatible with the tank, and { will be mounted by welding it to the RWT wall. ;
- The RWT, ECCS and CS pumps, and the connecting piping are classified Safety J Related. Therefore, this PC/M is classified Safety Related.
l A review of the changes to be implemented by this EP was performed in accordance
'with the requirements of 10CFR50.59. As indicated in the Safety Evaluation i
(Section II), this EP does not involve an unreviewed safety question, nor does it require a revision.to the Plant Technical Specifications. This modification will have no effect on plant safety and operation. Prior NRC approval is not required for the implementation of this EP. Form 3, Rev 6/94
i PC/M No 96-085 Rav 0 , Page 4 of 1 I. DESIGN l '. Structure. System, or comnonent (SSC) Involved: Refueling Water Tank j 2. SSc Purnose/ Function /Desion Basis l Per Design Basis Document DBD-SDC-1 Revision 0: '
! Safety-Related Functions I
- 1. Shall contain a sufficient volume of borated water to operate all engineered safeguard pumps for twenty minutes...
, 2. Shall contain a sufficient volume of borated water to fill the containment sump to a depth that will permit the safeguards i 4 pumps to operate in the recirculation mode. J j Qualit.y-Related Functions
- 1. Shall contain a sufficient volume of borated water, independent of the BAMT, to maintain the core suberitical during normal cooldowns, and make-up for primary coolant contraction.
Non-Nuclear Safety Functions 1 1. Shall contain a sufficient volume of borated water to fill the refueling canal, transfer tube, and refueling cavity to a depth of 24 feet above the, reactor vessel flange. . l l
- 3. Safety classification: SR X QR NNS
- 4. Reason for Desian chance l It was noted during review of procedures to drain the RWT for i maintenance that the RWT is not equipped with a vortex suppression l device. An evaluation of the condition under CR 96-814 determined I that under a design basis Emergency Core Cooling System (ECCS) and ,
Containment Spray (CS) actuation, there may be insufficient I submergence during the final minutes of the injection phase to prevent air entrainment by vortexing and outlet pipe uncovery. Sufficient air entrainment may damage one or more of these Safety i Related pumps, and may lead to their air binding. Air bound pumps-would be unavailable for further coolant recirculation and decay heat removal until time consuming venting had been completed. Under accident conditions, radiation levels within the ECCS pump rooms could preclude being able to adequately vent an air bound pump. 1 1
- 5. Desion chance Descrintion This PC/M installs a vortex suppressor above the RWT outlet penetration. See attached drawing JPN-96085-001 for the following discussion.
The suppressor is essentially a welded box elbow that redirects the inlet downward to the elevation of the bottom of existing outlet pipe. The elbow is fabricated from 3/8" stock aluminum plate, and has an inlet area approximately 3 times that of the outlet pipe. A 1/2" diameter hole in the top of the suppressor ensures that any Form 3, Rev 6/94
PC/M No 96-095
. Rev 0 Page 5 o f _.,1.F _ ~
1 air trapped beneath the suppressor during draining and subsequent refilling of the tank will escape. This will prevent high buoyancy loads on the suppressor during tank fi'. ling, and eliminates the suppressor as a potential source of unvented air pockets in the j ECCS/CS suction header. The hole is located close to the RWT wall ' to minimize the potential for vortex formation, and is sufficiently small that any air entrained due to vortexing or uncovery of the hole will not be significant (i.e. less than 2% void fraction). ~ All materials used will be 6061 T6 aluminum to be compatible with the existing tank material. All attachments and connections will be made using approved welding procedures and processes, and all materials will be procured PC-2 or better. W 1 l J . l l s I i j 4 Form 3, Rev 6/94
o _.. . . . _. _ . . _ . . _ . _ _ . _ _ _ . _ . _ . _ _ _ . _ . . . _ . . - . _ - . . . .- _ . . - - _ . - - _ _ . _ _ . . ....
. +
PC/M No 96-085 Rev 0 Page 6 of 1
- 6. Desion chance checklist Does the Design Change involve / impact / require justification of:
XXS IlQ REFEREt{CX i Internal / External Flooding _X_ } Heavy Load Handling _X_ i j Tornado / Internal Missiles
- Single Failure Criteria
_Z_ _X_ T.9.1
- Human Factors _X_
Paging System Audibility .2L
- Masonry Block Wall Interaction
_L_ Environmental Criteria _X_ Plant Security Capability _X_ HELBA Criteria / Analyses _X_ I Seismic Qualification _Z_ T.9.2 l Seismic Interaction _Z_ T.B.2 l Electrical Separation Criteria _X_ Accessibility /Laydown/ Clearance Requirements _X_ V.1 fnotes)
- Loads.t ) lied to Existing Structures (+ buried) _Z_ T.9.2
- EDG/Bactery Loading / Load Sequencing _Z_
- Hydrogen Generation In Containment _Z_
-Heat Sinks in Containment _X_ j Emergency Plant Operating Pro edures j
(EOPs/ONOPs) _Z_ ' ASME Code ' _X_ , Emergency Lighting Criteria _Z_ J Snubber Criteria ___ _X_
- Material Compatibility / Hazardous Materials _Z_ I 9.3 E3cctr!. cal Equipment Grounding _X_
j Cable Trsy Seismic Loading _X_ ,- Instrument Setpoints _X_ i Hurricane / Tornado Wind Loading _X_ j Thermal / Hydraulic Performance _X_ T7
- Coatings Inside Containment
' _X_
Emergency Response Data System (ERDS) _JL;, Emergency Planning _X_ 1 a NML Property Insurance Requirements _X_ Environmentalt Qualificatio'n _X_ Att. 3 j FireTProtection Capability _Z_ Att. 4 : 4 Safe / Alternate.ShutdowntCapaNility _X_ Att. 4 ALARAiExposureiCriteria _X_ Att. 5 }. r Forms 3E,: 3F, and 71 shall,be attached to justify the conclusion for these items. I Form 3, Rev 6/94
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. . I PC/M No 96-085 Rav 0 t
Page 7 o f 1L,_
- 7. Desien Evaluation / Justification During an ECCS and/or CS actuation, the outflow from the RWT is terminated by
, a Recirculation Actuation Signal (RAS). The nominal setpoint for the RAS is 4' from the bottom of the RWT (Table 3.3-4 of Reference 1). Drawing 8770-i 4548 rev. 2) shows the centerline of the 23" ID outlet nozzle is 2' 6.75" from the bottom of the tank, giving a nominal net submergence to the top of the outlet of only 5.75". The combined instrument inaccuracy and settability i of the instrumentation is 24.2" (Reference 5). Based on this, with the worst care instrument error, the RWT water level at RAS actuation could be as little as 1"-2" above the top of the outlet pipe. Upon actuation, the RAS stops both Low Pressure Safety Injection (LPSI) pumps, and starts to or a the containment sump to the ECCS/CS suction header j valves. The stroke 'ame of these valves is 30 seconds (Section 1.6 of ~ Reference 9). Simultaneously, the RWT outlet valves stroke closed, with a i stroke time of 90 seconds to ensure a continued suction source for the operating HPSI and CS pumps. , Under the limiting DBA conditions, the maximum RWT outflow rate at the time
, of the RAS will be approximately 12,500 gpm (Reference 5). If one of the two a
LPSI pumps fails to stop upon receipt of the RAS, the continued RWT drawdown i l will be approximately 12,000 gpm (Reference 5). Under DBA conditions the ' l containment will be pressurized, causing the RWT discharge check valves to close as the containment sump isolation valves open and start to supply the l ECCS/CS suction requirements. The capacity of the RWT is 14,690 gal /ft 1 (Reference 6). Conservatively assuming that the RWT continues to supply 100% i of the pump requirements for this 30 second duration, the RWT will be drawn I t down an additional 6,000 gallons, or 5 inches. This final RWT level could then be as much as 4 inches ttha the top of the outlet pipe. Therefore, under design basis conditions, the current configuration could I lead to substantial air entrainment by severe vortexing and/or direct open channel flow after the outlet pipe opening is partially uncovered. ' The only reliable means of predicting the severity of these effects is i through extensive flow model testing. The effects can be entirely eliminated however, by removing the free surface in the vicinity of high velocity flo-. 1 This is the approach used in typical vortex preventers consisting of a l' horizontal plate above the tank outlet. Additional effectiveness is obtained ' by extending the tank outlet opening to a deeper submergence point. Both of these techniques are used by the downward turned elbow and enlarged flange required by fire codes for fire water storage tanks (Reference 10). s The suppressor installed by this PC/M uses a similar construction to obtain increased outlet submergence, decreased entrance flow velocity, and to j eliminate the free surface directly above the area of nighest velocity. 4 j The presence of the venting hole in the top of the suppressor precludes
- keeping an absolute water seal to keep the suppressor full should the water level be reduced below the top of the suppressor. However, the amount of leakage possible through the vent hole will not be sufficient to create a significant air void fraction under the design flow conditions. Lower flows will result in decreased vortex severity and air entrainment through vent hole. Normal operational transfers of water out of the RWT (for flooding the refueling cavity, etc.) are performed at sufficiently lot - flow rates to ensure that any air separates and remains in the top of the suppressor or out M pipe, and will not be entrained into the suction stream.
The large flow area of the suppressor and it's short hydraulic length.make it's effect on frictional line losses negligable. A review of applicable calculations determined that the NPSH availei.le in excess of pump requirements for all of the ECCS and CS pumps is more than . 20 feet. Therefore, addition of the suppressor will have negligable impact upon the Net Positive Suction Head available for all affected components. Form 3, Rev 6/94
i PC/M Ho 96-085 1 Rav 0 . Page 9 o f lE., _ l
)
Hydraulic Loads 1 To determine the hydrodynamic reaction loads on the suppressor, only the net vertical and axial (with respect to the outlet pipe) will be considered. The 1 hydrodynamic side loading will be zero due to cancellation from the bilateral l symmetry. The asymmetric hydro-dynamic loadings can be calculated by the net change in momentum of the water traveling through the suppressor. The nominal open area of the 23" I.D. outlet pipe is 415.5 sq. in. However, the existing grating reduces the effective area somewhat. Drawing 8770-4548 indicates that tb- bearing bars of the grating are 3/16" thick, and a typical aluminum gratins i; fabricated with a bearing bar center-to-center distance of 1-3/16" (Attachment 2). Neglecting the area of the cross bars, the open area of this grating is 1" for every 1-3/16", or 84%. Therefore, the effective area of the outlet pipe is 0.84 x 415.5 in = 33 50 in' or 2. 4 f t a , Under maximum flow conditions (full combined ECCS and CS actuation) of 12,500 gpm, the volumetric flow rate is 27.9 f t /sec, giving an avercge horizontal 3 I velocity of 11.6 ft/see at the grating (i.e. tank outlet). I Since water entering the suppressor will have no horizontal component, the net axial force required to accelerate the water is the mass flow rate ; multiplied by the change in velocity- l 1 F = mV min
= ( 12.5009a1)x( 8.34lbe)x( ) x ( 11.6 ft)x Ibfxsec' = 626 /bf min pal 60 sec sec 32.2 ft I
4 This axial force is equivalent to the pressure x area difference acting on the suppressor, and is a compressive load acting to push the suppressor toward the RWT wall. However, when the flow direction is reversed (as when filling the RWT from the reactor cavity), the force reverses direction. Although the filling flow rate is much less than the maximum design draining
' low rate, for conservatism the attachment welds have been sized to tecommodate 626 lbf acting to pull the suppressor away from the RWT wall.
Similarly, the net vertical reaction load is calculated from the change in vertical velocity. 2 The area of the unobstructed suppressor opening (35.25" x 36") is 8.81 ft. Therefore, the average vertical inlet velocity into the suppressor would be 3.2 ft/sec. 12.5009a1 8.34 lba g min g 3.2 ft p lbfxsec8
= 173 lbf min gal 60 sec sec 32.2 ft During draindown, this force decelerates the vertical velocity component in . the entering water to zero, with a reaction force acting upward on the suppressor. During fill, a smaller force (corresponding to the smaller flow rate) also acts upward on the suppressor as the entering water is accelerated downward.
A static vertical load will be imposed on the suppressor if it should partially uncover during an ECCS/CS actuation with sufficiently high flow to keep it full of water (i.e. continuously removes all air entering the vent hole). As previously discussed, the RWT water level may be lowered as much as 4" below the top of the outlet pipe prior to switch-over to the containment sump. This will result in approximately 8" or 0.67' of uncovery on the suppressor. The water volume held up by the suppressor would be 6 ft 3 (0.67 f t x 9 f t )3 . At 62. 4 lb.o 3, this is a load of 375 lbf acting downward and canceling the upward reactaan force. The net vertical reaction force on Fom 3, Rev 6/94
l PC/M No 96-085 Rav 0 Page 9 o f ,,12, ,,, I the suppressor is then 202 lbf. acting downward. However, for conservatism the upward reaction force will be neglected and the net vertical force will be assumed to be 375 lbf down acting at the geometric center of the' top plate. To ensure that all combinations of loadings are bounded, it will be { i
' assumed that the top plate may also be subjected to an equal upward force.
) For stif fness and structural design considerations, the forces determined j above are assumed to be evenly distributed over the corresponding normal surfaces. Therefore, the design pressure for the top plate is 2375/9 = 241.7 ! psf. t-The design pressure acting on the end plate is 2626/(2.3x3) = 290 psf. It is
- i. assumed that the side walls are subjected to the same pressure, although in i
opposite directions at any given time so that the net hydrodynamic lateral , force on the assembly is zero. 1
- 8. Evaluation of any "YEs" resnonses in Desian chance checklist
] I
- 1. SINGLE FAILURE CRITERIA Functional failure of the suppressor could result in air entrainment s
into, or blockage of, the RWT outlet. This outlet supplies both trains l of ECCS and CS. This common failure mode of both trains is inherent to 4 the design of the RWT and ECCS/CS systems, and cannot be resolved by
, any suppressor design. Since the sunpressor performs no active
] functions, active failure is not a considsration.
'The suppressor has been designed conserratively to withstand the 4 maximum design hydrodynamic, deadweight, aid seismic loads. Since it
{ is an open construction, static pressure loading is not a consideration. The RWT remains at ambient temperatures. As such, j t thermal loads are not a concern. l The vortex suppressor is to be fabricated from engineered materials t using approved processes consistent with the materials and processes j used to fabricate the RWT. Therefore, the vortex suppressor is
- considered comparable in quality, design, and construction to the RWT.
2
- 2. SEISMIC QUALIFICATION AND INTERACTION i
l The vortex suppressor has been designed conservatively to withstand the maximum design hydrodynamic, dead weight, and seismic loads (Refernce , 4), and will not adversely interact with any safety related systems, l
- structures, or components.
4 4
- 3. MATERIAL COMPATIBILITY t
i The _RWT is fabricated from 6061 T6 aluminum plate and structural l components All materials used for the vortex suppressor shall also be 6061 T6 aluminum, consistent with the existing RWT materials (References 7 and 8). This ensures chemical, metallurgical, and electro-chemical comparability wi".h the tank materials and the contents. The identical materia'. properties ensure that galvanic interaction, differential thermal expansion, and other causes of degradation or failure due to the use of dissimilar materials will not be a concern.
- 9. nesian verification stat =mant The design bases were reviewed against the DBD, UFSAR, 10CFR50, JPN Quality i' Intitructions, and Nuclear Industry Reference Guides to ensure that the design considers all applicable codes, standards and Regulatory requirements, and that design interfaces were properly assigned.
Form 3, Rev 6/94
PC/M No 96-095
. Rev 0 Page 12_ of 1 ,
I The design analysis was verified by review of the design inpu:s and ) analytical techniques utilized. ! The integration of this modification with other designs in progress and I impact on existing safety evaluations and JCO's was verified by review of the PC/M Log, Drawings Affected by PC/M Report, and the Safety Evaluation Log. ) 1 The rationale provided in assigning the Safety Classification was verified i against the requirements of ENG-QI 2.6 Safety Classifications. l The Safety Evaluation was verified by review of the requirements of 10CFR50.59 and ENG-QI 2.1, 10CFR50.59 Evaluations performed by Nuclear ) Engineering, as criteria for establishing whether an unreviewed safety I 4 question does or does not exist and whether or not a change to the Technical Specifications is required. j
- I Il a
4 4 I J l l 1 Form 3, Rev 6/94
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PC/M No 96-095 Rev 0 Page __,1,1_, of 13 _ i l II. SAFETY
- 1. Descrintion and Purnome This PC/M installs a vortex suppressor to ensure that the RWT can be drawn down to the minimum credible level associated with a design bcsis accident and RAS actuation without entraining unacceptable air into the ECCS/CS suction flow stream.
- j. 2. Analvsis of Effects on Safety This PC/M ensures the continued operability of the ECCS and CS pumps during a design basis accident despite RWT draw-down rates and levels that could otherwise jeopardize their operation. As such, this PC/M enhances safety by resolving a previously unidentified potential failure mode. This PC/M has no l detrimental impacts on safety. j l
l t
- 3. Failure Modes and Effects Analysis (FMEA) l Three modes of system functional failure could be postulated due to the installation of the vortex suppressor:
l
- 1. Benign. Detachment or functional failure of the suppressor that does l not result in any blockage of the RUT outlet or functional failure of l
the RWT to store or supply borated water. In this case, failure results in the RWT reverting to it's previous configuration. This may lead to air ingestion in the ECCS/CS pumps duri'ig a design basis event.
- 2. Blockage. Detachment or collapse of the suppressor results in partial
- j. or complete blockage of the RWT outlet. This is less severe than catastrophic failure of the RWT since the water inventory would be retained, and may be available in limited-flow rates until the blockage is corrected.
- 3. Catastrophic failure of the RWT due to suppressor failure. This could !
be postulated to result from tearing or holing of the RWT sidewall due to a failed attachment point, or holing of the RWT from a separated and loose suppressor impacting the RWT due to the presence of an impinging flow stream. However, due to the similar construction materials and techniques of the suppressor and the RWT, and the robust design utilized, the probability of failure of the RWT is not considered to have been increased by the installation of the suppressor. The vortex suppressor installed by this PC/M is a passive component designed
.to withstand conservatively high leadings due to seismic, operational and i
emergency hydro-dynamic forces, and deadweight. It is compatible with the medium it is to be exposed to (Boric Acid and air at ambient temperatures), and is compatible with the m).terials of the system in which it is installed. Therefore, none of the above postulated functional failures are considered credible. l 4 4
)
d Form 3, Rev 6/94
PC/M No 96-095
. Rev 0 Page 12, of _,1E
- 4. Effect on Technical 90ecifications This PC/M will have no effect on Technical Specifications. The PC/M will however ensure that the operability of the ECCS and CS systems required by i the Technical Specifications is maintained.
l
- 5. Unreviewed safety ouestien (Uso) Determination l I
- 1. Does the proposed activity increase the probability of occurrence of an accident previously evaluated in the SAR? I No. The RWT, ECCS and CS and pumps, and associated piping are not initiators for any accidents previously evaluated in the SAR. Therefore, the probability of occurrence of such an accident will not be increased by the installation of a vortex suppressor in the RWT.
l
- 2. Does the proposed activity increase the consequences of an accident previously eva'luated in the SAR?
No. The ECCS and CS pumps are required to mitigate the consequences of , accidents previously evaluated in the SAR. They do not increase the l consequences of any such accidents. The proposed installation assures , that the ECCS and CS pumps will not become air bound or be damaged by l excessive air ingestion during design basis accident injection phase l scenarios. The proposed installation does not adversely impact the ! functioning of the ECCS and CS pumps. Therefore, the proposed activity I does not increase the consequences of an accident previously evaluated in the SAR. i
- 3. Does the proposed activity increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the SAR?
No. The ECCS and CS pumps are required to mitigate the consequences of accidents previously evaluated in the SAR. They do not increase the 3 consequences of any such accidents. The proposed installation assures , that the ECCS and CS pumps will not become air bound or be damaged by excessive air ingestion during design basis accident injection phase scenarios. As such, the proposed installation reduces the probability of occurrence of a malfunction of equipment important to safety as previously evaluated in the SAR.
- 4. Does the proposed activity increase the consequences of a malfunction of equipment important to safety previously evaluated in the SAR?
No. The proposed activity has no impact on the consequences of malfunction of equipment important to safety as previously evaluated in the SAR. The proposed vortex suppressor enhances safety by resolving a previously unidentified potential failure mode and prevents certain malfunctions of the safety related ECC and CS systems, but would not adversely affect or increase the consequences of a malfunction in one of these pieces of equipment.
- 5. Does the proposed activity create the possibility of an accident of a different type than any previously evaluated in the SAR?
No. The RWT and ECCS and CS systes and components are normally isolated from the,RCS by automatic isolation valves and check valves, and perform no active safety related function until receipt of an Engineered Safeguards Features Actuation Signal (ESFAS). At that point, an accident previously evaluated in the SAR has already occurred. As such, the installation of the passive vortex suppressor cannot initiate or create Form 3 Rev 6/94
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4 PC/M Wo 96-095 5 Rev 0 Page LL of 1 ' b* t 1 the possibility' of an accident of a different type than any previously evaluated in the SAR. a
- 6. Does the proposed activity cre' ate the possibility of a malfunction of '
t equipment important to safety of a different type than any previously evaluated in the SAF7 ! No. The design of the vortex suppressor ensures a. reliable installation l that does not introduce new challenges to the RWT or any other associated P safety related equipment. As such, the proposed activity does not create the possibility of a malfunction of equipment important to safety of a different type than previously evaluated in the SAR. 7.,Does the proposed activity reduce the margin of safety as defined in the basis for any Technical Specification? Ho. The installation of a vortex suppressor enhances the margin of safety by preventing against ECCS and CS pump air ingestion. The borated water . isource, available water volume, and NPJH requirements for Safety Related ECCS and CS pumps are not adversely aft 9cted by this activity, nor is the Inargin of safety reduced for any Technical Specifications. P Form 3, Rev 6/94
PC/M No 96-095
. Rev _. O Page ,,,11_ of 1 4
- 6. Plant Restrictions
- 1. This PC/M must be completed prior to returning the ECCS and CS pumps to operable status for compliance with Technical Specification paragraphs 3.5.2 and 3.6.2.1 (Reference 1).
- 2. Implementation of this PC/M requires the complete draining of the RWT for access and installation of the vortex suppressor. As such, this PC/M cannot be implemented at any time that the RWT inventory is required to provide a required boration flowpath.
- 7. Conclusions The proposed activity does not constitute a test or experiment, or change to the facility or procedures as described in the Technical Specifications or the SAR. As such, it is does not represent an unreviewed safety question, and is acceptable for implementation without prior NRC review.
f Form 3, Rev 6/94
.. . . -. = , . ~ - - . ~ . . - - . - - . _ - - . .- , . .. .- . - -- .. - .
)
PC/M No 96-095
. Rev 0 Page _1jL. of ,_11 _
e III. CONFIGURATION j 1. Affected Documant checklist XEE E Reference FSAR X._ l Technical Specificativas 2L TEDB . 2L ( Security Plan X._ DBDs Z_ Attachment 1 Snubber List 2L l ISI/IST Program (If 'Yes", ESI review 3 quired) 1 Code Stress Reports X._ , 2. Affected Drawinga 4 PC/M Dwe M Descrintion/?itle h Affected Dwas M py* EP Pev . JPN-96085-001 0 RWT Vortex Suppressor C 8770-4548 2 5 0 4
'
- 1 (SRD), 2 (non-SRD), or 5 (other) for PSL, or 1 (POD), 2 (CRD), 3 (MD), 4 (ED), or 5 (other) for PTN.
- 3. Affected Vendor Manuals l
Plant Doc No Egy Vendor /Ecuin D, igg Remarks EP Rev i
- None
- 4. Attachments
! 1. DBD Change Package; 2 pages.
. 2. Excerpt from McMaster-Carr catalog describing typical aluminum floor j grating; 1 page.
, 3. Environmental Qualification (EQ) Checklist; 1 page. q i
4 Fire Protection Review Checklist; 3 pages.
- 5. ALARA Screening; 1 page.
l Form 3, Rev 6/94
. .. . . ~ . - ~ . _ - . . -.....-..~--.-n...-.~. - . ~ . . - - . - . -. ~ . . . - . . . ~ . . _ . . . . . - . l
-g. j PC/M No 96-085 Rev 0 Page l.5__ of 11_
- 5. References
- 1. St. Lucie Unit 1 Technical Specifications, through Amendment 142 dated ,
4/11/96.
- 2. St. Lucie Unit 1 Final Safety Analysis Report through Amendment 14 ;
dated 6/96. !
- 3. Condition Report 96-814 i
- 4. Calcul*2 tion PSL-1FSC-96-009, Revision 0.
- 5. Calculation PSL-1FJM-96-009, Revision 0. ;
I
- 6. Ebasco Calculation NSSS-004, Revision 2.
)
I
- 7. Specification FLO-8770-759, Revision 2. ,
- 8. Drawing 8770-4544, Revision 3.
- 9. Design Basis Document CS-1, Revision 0.
- 10. National Fire Protection Association (NFPA) 22-93: Standard for private l l fire water supplies. )
IV. MATERIAL l
- 1. Ecuinmant and Meterini JfJun Ouantity Descrietion 1 1 48"x96"x3/8" thick 6061-T651 Alum. Plate 2 As Required Weld Rod / Wire per FPL Weld Control Manual
- 2. Scare Parts l
None. Installation is permanent and not subject to routine wear / tear or maintenance. I l l l t, - 4 i i J i f 1 - Form 3, Rev 6/94
. m - . - . . . _ ,__ _ .. ..-m-. -_ _ _ _ - _. _- .-~.-m m. _m _ _ __-
i ' PC/M No 96-095
. Rev s. O Page 17 o f ,.1]L.__
l 4 V. IMPLEMENTATION
- 1. Tmnlementation Instructions /Soecifications CAUTIONS l
(' . Coordinate all work with Operations to ensure proper clearance boundaries are established.
-The RWT is internally contaminated. Coordinate all work within the RWT with. HP. Precautions to minimize the ceneration of airborne i contamination from weld preparation and cleanup may be required when working on the RWT walls.
The RWT is a closed tank, and is likely. to be a heat stress I environment. In addition, welding operations use oxygen displacing purge gases and can generate irritating or noxious fumes. Coordinate all work with the Safety Department and observe all applicable precautions in accordance with procedure AP 0010505 " Confined Work Space Entry", and AP 0010506
- Heat Stress Control".
The lining on the bottom and lower side M.s of the RWT is flammable. Use positive measures to shield or otherwiJe protect the lining from high temperatures and ignition sources. NOTES The lining on the bottom and lower sidewalls of the RWT is susceptible I to damage from impact, abrasion, heavy loads, etc. Positive measures shall be taken to protect the lining as much as practical, including the following minimum measures: A layer of herculite shall be used in all areas requiring casual or infrequent foot traffic during installation. A similar layer shall be draped to cover the liner in the areas immediately adjacent to ; and below the outlet nozzle. Plywood runners or dimensional planks shall be laid over herculite in all areas of heavy routine foot treffic, and in all areas to be used for the laydown of parts, tools, equipment, etc. The legs of any scaffolding, benches, staging, etc., shall rest on blocks or planks as appropriate to protect the tank liner. In areas whare welding and/or grinding is to be performed, one or more layers of protective fabric shall be laid and/or draped to I shield the herculite and liner from spatter, slag, hot filings and l t tools, etc. l
- 1. Install Vortex Suppressor in accordance with drawing JPN-96085-001.
- 2. Where necessary to remove portions of the RWT iiner to make attachment welds, the following instructions apply:
a
- a. Coordinate with FPL JPN Coatings Specialist prior to removal or
, repair of RWT liner.
j b. Remove coatings approximately 6" on both sides are area to be i welded,
- c. Cut through the fiberglass liner with extreme care to pr:: duce a well i
Form 3, Rev 6/94
I PC/M No 96-095 Rav 0 Page l.!L, of ,11
' ]
l defined area to be removed without damaging the tank wall. Use care to make straight cuts without ragged edges.
- d. It is recommended to remove the affected area of coating using I scrapers and/or chisels. Do not scrape or chisel toward areas of the liner that are to remain in place.
- e. Additional instructions for removal and repair of the tank liner are l provided by specification CN-2.27.
l
- 2. Post-Mod Accentance Testina No post modification functional testing required.
All weld inspections in accordance with drawing JPN-96085-001 and the FPL-Weld Control Manual. Final condition of the tank liner shall be inspected and approved by the FPL JPN Coatings Specialist.
- 3. Ooerations and Maintenance cuidelines l This installation will be transparent to operations, and will not affect any operating procedures or practices, or any plant setpoints or system operating characteristics.
The vortex suppressor has been designed to be maintenance free. Should future maintenance be required for any reason, this PC/M may serve as guidance for development of repairs or replacement. I 1 Form 3, Rev 6/94 )
p
- i Document No. P_ Chi 96-085 Revision o Attachment 1 Page 1 of 2
! DESIGN BASIS DDCUMENT (DBD) CHANGE PACKAGE COVERSHEET i l Plant St. Lucie Unit i DBD PAGES ATTACHED: CS-1 Section 8.0 page 143a (Text to be added to existing page 143). t DBD FIGURES ATTACHED: None
- COMMENTS
- See PC/M 96-085 Pre' pared by/Date: '
$b Verified by/D :
Apgfoved by/Date: kWK \ I l Notes:
- 1. All affected DBD pages and tables shall be legibly marked up and attached.- If additional space is required. then additional pages should be provided. New information for inclusion in the DBD shall also be provided.
- 2. If a figure is provided elsewhere in the design package, then it need not be duplicated in the DBD change package. However, a note shouli be provided in the comment section referring to its location in the package. This also applies to l new drawings which should be added to the DBD. If a figure revision is to be l
included in the change package, then a copy of the DBD figure with a bubble l around the affected area is sufficient. I l I
+
Form 62. Rev 6/94
-_-.- -...... - . - -. _ ....~..- - . .. ...- .- - -. . --.
p - l
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Document No. PC/M 96-085 Revision 0 Attachment 1 ; Page __2 _ of 2 Note to Updating: Add the followingatext to4the end of section 8.0, Modification. History 96-085 RWT VORTEX SUPPRESSOR This P/CM installed a welded box elbow inside the RWT covering the l outlet nozzle to suppress vortex formation and potential uncovery of j the outlet piping during the final minutes of an ECCS/CS injection l phase, j o l l 1 1 1 I 1 1 l l 1 _.m .
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- j, Masimum: Spen 24 feet; cross open 34* Also avsina04e we serrated surface and'
' Standard eross spans are 24' and cione bearmg Der construction for adde y f
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's. Staneare besang tw spesing is IV en pege est ser staneare spasm 9 type.
SPECIFY NO., SPAN AND ACTUAL CROSS SPAN OGMENSIONS pesi Q PurNOse \ i Beedne Bar WL. LhaJ Type 304 Type 316 gener% # 8"a*lmg' aM*##8 suited for *'Y aH *P8" M*'N * ***' d Dp. n Th4L,in. $4 FL No. NET'SO. FT. No. NET'SO. FI ' vieveman u Gr 88"se'8 Has two courses of bent grateg'is of estreme re. i \s 1 a 's . 51.. . 4868741 . . 544.54 6454781 848 3 course or e,rr fees,,enseen DeanrN1 oars j ' k #*"8**' 1 m he .. 1% w ks . 7 3 .. 8 9 ..
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I y. PC/M No. 96-085 Revision 0 Attachment 3 ENVIRONMENTAL QUALIFICATION (EQ) CHECKLIST , 1. ELECTRICAL EOtTIPMENT IIS MQ a) Does the PC/M add, modify or replace electrical /I&C equipment s or affect any EQ Doc Pac? If No proceed to Section 2. A b) Is the equipment located in a harsh environment per EQ Doc Pac 1000 (PSL) or 1001 (PTN)? If NO proceed to Section 2. a$. c) Does the equipment perform a safety related function? 75 OR Does the equipment perform a quality related function such that its failure could mislead an operator or adversely affect any safety related function required to mitigate or monitor an accident? X OR 2 Is the equipment classified as Category 1 or 2 by RG 1.977 l If the answer to any question in Section 1.c is YES, then the equipment is subject to 10CFR50.49 and the EP must justify that the equipment is Environmentally Qualified.
- 2. 2NVIRONMENTAL CONDITIONS IER EQ a) Does the modification add, relocate, raise f' low rate of, or I increase radiation levels of any piping containing radioactive !
liquids such that lifetime or accident exposure of electrical equipment may be increased? _Z_ l b) Does the modification add or reroute any high energy piping, the failure of which could impinge upon electrical equipment or increase the post-break local pressure or temperature? _Z_ c) Does the modification alter process fluid characteristics such that the post accident pressure, temperature, pH, or boron concentration to which electrical equipment will be exposed may be changed? _Z_ d) Does the modification alter any barriers that shield electrical equipment from high energy lines or radiation exposure? _Z_ e) Does the modification add equipment to Containment or increase the post-LOCA makeup water inventory such that the design basis Containment Flood Level may be increased? _Z_
** If the answer to any question in Se': tion 2 is YES, then it must be determined if any equipment subject to 10CFR50.49 could be impacted and, if so, that its . Environmental Qualification is still valid. Document the determination in the EP.
/
Prepared by/Date
- 0 Verified by/Date , hl db 1
e-1 I
PC/M No. 96-085 Revision 0 . Attachment 4 FIRE PROTECTION REVIEW CHECKLIST I. RAFE SEUTDOWN CAPABILITY %ER* HQ REFERENCE Does the Engineering Package install, relocate, modify, or affect the operation of: A. Equipment on the Essential Equip. List X B. Safe Shutdown Analyses
- 1. Safe Shutdown Circuits X
- 2. Alternate Shutilown Components X
- 3. Associated Circuits X
- 4. Manual Actions X 1 l
II. FIRE PROTECTION SYSTEMS l Does the Engineering Package install, modify, j or affect the operation of: l l A. Fire Detection Systems _ X B. Fire Water Supply System X C. Water Suppression Systems X i D. Halon Suppression Systems X E. Standpipes or Hose Stations X F. Portable Fire Extinguishers X III. FIRE FA':7.D ASSEMBLIES Does this Engineering Package install, modify or affect the function of: A. Fire Barriers. X B. Fire Doors X
- Indicato "YES" if an item is impacted or requires justification. If "YES", a section in the EP shall disposition or justify the ites, with the EP section number referenced accordingly on this Form 3F, Rev 6/94 form. Sheet 1 of 3
- . _ _ - ._ _ .- . - . . - . . , - . . .._.- .~ _ . .-
l 1
~
PC/M No. 96-095 Revision 0 Attachment 4 ; 4 1 III. FIRE RATED ASSEMBLIES (Cont) i ,; IEA* HQ REFEF MCE
- C. Fire Dampers
' i D. Mechanical Penetration Fire Seals X J E. HVAC Duct Penetration Fire Seals X 4 F. Cable Tray Fire Stops X G. Structural Steel Fireproofing X I H. Conduit or Raceway Support Fireproofing X I I. Conduit or Raceway Fireproofing X .___ 4 J. Internal Conduit Fireproofing (Stuffing) X X , IV. EMERGEML*Y LIGHTING A. Does the Engineering Package install, modify, or affect the operation of?
- B. Does the Engineering Package obstruct the X required light pattern of?
C. Does the Engineering Package add or X relocate essential equipment or components which will require the addition or relocation of? , D. Does the Engineering Package install, X 4 relocate, modify, affect, or require the use of hand held emergency lights? E. Does the Engineering Package relocate, X modify, affect, or obstruct the light pattern ci perimeter security lighting to equipm6nt requiring manual actions? V. RCP OIL COLLECTION X Does the Engineering Package install, modify, or affect the operation of? VI. MISCELL&MEOUS X A. Does the Engineering Package affcet the quantity or protection of insitu combustibles (solids, liquids, or gases) beyond the assumptions in the FHA? X Form 3F, Rev 6/94 Sheet 2 of 3
. . - . . .- . . _ _ _ - . _ . . ___m . _ _ . _ . _ _ . ._ _ .__.._____.___m.______. . .. _ _ _ ~ _ _ _
,VI.
PC/M No. 96-085 MIBCELLAMEOUS (Cont) Revision 0 Attachment 4 B. Does the Engineering Package Cause the %K9* HQ REFERENCE addition of a large combustible inventory within 50 ft. of essential equipment, components, electrical manholes or structures? C. Does this Engineering Package modify or affect curbs or dikes used to contain X combustible liquid spills? D. .Does this Engineering Package cause the removal of a flame retardant material X from non IEEE-383 cables? E. Does this Engineering Package affect fire protection technical specifications or X fire fighting strategies? F. Does this Engineering Package install, modify or affect the operation of X alternate shutdown communications? G. Does this Engineering Package install, modify, or affect hydrogen lines (or any X combustible gas) in areas of the plant containing safe shutdown equipment or components? H. Does this Engineering Package install, modify, or affect any HVAC equipment or X room heat loads in areas of the plant containing Safe Shutdown equipment or components? X PREPARED BY f e ./ -
/
DATE I-//[/' VERIFIED BY . - . DATE O b p i i Form 3F, Rev 6/94 Sheet 3 of 3
PC/M 96-085
- Rav. O Attachment 5
- ALARA BCREENING fgg l )
- 1. Is this PC/M administrative only (no physical modifications)?
yes, Further ALARA screening is not required, i X no, continue screening.
- 2. Does this PC/M involve a location in the Radiation Controlled Area (RCA)?
X_._ yes, Location: REFUELING WATER TANK Continue screening, i no, Further ALARA screening is not required.
- 3. Does the implementation, operation, or maintenance of this PC/M involve NO_ Movement of radioactive material?
_NO_ Modification of systems containing radioactive fluids or resins such that routing or retention characteristics are affected? _NO_ Movement / modification of existing permanent radiation shielding? _NO_ Modification or removal of equipment that results in an uncontrolled opening / penetration into a High Radiation Aree., Locked High Radiation Area, Very High Radiation Area, or Exclusion Area? _NO_ Diving associated with systems containing radioactive macerial? j _NO_ Entrance into containment during power operation? _NO_ Potential for personnel exposure to a radiation field of a Ir/ hour (assuming current area dose rates)? _NO A total lifetime estimated dose due to the modification greater than or equal to one (1) man rem? If any item in section 3 above is checked "yes", indicate "yes" belows yes, This PC/M has the potential to significantly impact personnel radiation exposure. Complete Form 72 to ensure total radiation dose is minimized by design.
._X_ no, This PC/M has little or no impact on- personnel radiation exposure. Form 72 not required, however, normal ALARA precepts should be followed to minimize radiation exposure.
Prepared:
- Verified: , - .
" Leave signatures blank if same as on Pc/M coversheet "
4 Form 71. Rev 6/94
1 6 i i i
# Inter-Office Correspondence i
plll3L JQQ-96-101
/ !
^
To: J. Scarola, Plant General Mgr. ! Date: July 26,1996 From: L. W. Bladow, Quality Manager Department: .NAPSL I
Subject:
Independent Technical Review Rerort # ITR 96-015, " Safety System Walk l down (Partial): Unit 1 Reactor J.ontainment Building (RCB) sections of I , Emergency Core Cooling Subsystems and Pressurizer Code Safety Valves" This Independent Technical Review (ITR) was conducted as part of a program to periodically verify that engineered safety features (ESF) systems and components are installed and operated in accordance with applicable licensing and design bases documents. The High and Low Pressure Safety injection (HPSI/LPSI) and the Containment Spray (CS) systems were selected bas'ed on the receipt of several recent NRC Information Notices (IN) of possible operability concerns and l common mode failure mechanisms. Pressurizer code safety valves were selected to provide an i oversight review and evaluation of the Plant Change / Modification processes with respect to field ) implementation and design bases document control. The intent of this effort is to provide additional assurance that the St. Lucie Plant is being operated safely and in conformance with license and r.egulatory requirements. I The as-installed configuration for the portions of the High and Low Pressure Safety Injection (HPSI/LPSI), Contamment Spray (CS), and the replacement of pressurizer code safety valves were accurately refleded in Selected Record Drawings for the Reactor Coolant, Safety Injection and i Containmer.. spray systems. Deficient items are being routinely identified by plant personnel and j are being brought to the attention of responsible maintenance departments for corrective action j thrcagh the use of the Plant Work Order system. The general cleanliness and material condition of l the systems (portion walked down) and their components were satisfactory. Sufficient levels of l maintenance, preservation and cleanliness are being applied to maintain system operability. The ; plant staff demonstrated a proactive approach in the use ofindustry information to identify and l resolve issues that may effect St. Lucie Plant operation. l 1 Three ITR Recommendations addresses concerns idemified from this review. Condition Reports have been issued for the department affected by the enclosed ITR Recommendations. Per SQM i 18.0, " Nuclear Assurance Review Activities," Department Heads of affected departments, I designated by an asterisk below, are required to respond in writing within 30 calendar days from issuance of this report (i.e., by August 26,1996), regarding actions to address applicable ITR Recommendations. (An "ITR Recommendation Response" form has been attached to the CR for l this purpose.) l l The cooperation of personnel contacted during this activity is appreciated. If you have any questions . regarding this subject, please contact Mr. Robert De La Espriella at extension 7594, or Mr. C. E. Norris at exten; ion 7591. ;
' , [0
,x./y
/.
l l ;" JQQ-96-101 l July 26,1996 , Page 2 LWB/RJD/CEN: sir Attachment Distribution: l T.V. Abbatiello JNA/PTN H. Johnson OPS MGR/PSL R. J. Acosta JNA/JB J. Marchese MAINT MGR/PSL W. H. Bohlke JPN VP/JB M. Miller NRC RESIDENT /PSL
*D. J. Denver ENG MGR/PSL J. A. Stall SITE VP/PSL i
- ITR Re~ )mmendation response action.
i 4
J INDEPENDENT TECIINICAL REVIEW REPORT NUMBER: ITR 96-015 UNIT: PSL1
SUBJECT:
Independent Technical Review Report # ITR 96-015. " Safety System Walkdown (Panial): Unit 1 Reactor Containment Building (RCB) sections of Emergency Core Cooling Subsystems and Pressurizer Code Safety Valves" PURPOSE / SAFETY CONCERN: This Independent Technical Review (ITR) was conducted as part of a program to periodically verify ; that engineered safety features (ESF) systems and components. are installed and operated in ! accordance with applicable licensing and design bases documents. This program, conducted by the Quality Assurance Independent Technical Review Group, is intended to provide additional assurance that the St. Lucie Plant is being operated safely and in conformance with license and regulatory requirements. DISCUSSION: l A walk down of selected St. Lucie Plant's Unit 1 ESF systems that are not accessible during plant operation was conducted. These systems included: High and Low Pressure Safety Injection (HPSI/LPSI), Containment Spray (CS), and the replacement of pressurizer code safety valves in ) accordance with Plant Change / Modification package, PC/M 040-196M (Reference 1). The selection of these particular systems was based on the receipt of several recent NRC Information Notices (IN) involving possible operability problems and common mode failure mechanisms. The significance of the concerns identified in the information notices indicated that additional review by the ITR group was warranted. Pressurizer code safety valve replacement was selected to provide an oversight review and evaluation of the modification !mplementation. The walk down also examined material conditions and attributes of system installation and maintenance, including: I
. Installed orientation of valves and ontu ,
a Identification (labeling, etc.) of major components
- Cleanliness and preservation (of system components and surrounding area)
. Valve condition (packing leakage, handwheel installed, and valve stem condition)
- Condition of hangers and supports
. Pqtential system operability due to the use of supplementary maintenance equipment (ladders scalTolding, etc.)
. Flammable materials and ignition sources within the vicinity of the system
. Accuracy of associated P&lDs, isometric drawings, and other Selected Records Drawings
= Accuracy of associated system procedures
- Use of the corrective action system to identify deficient items
I ~.
)
e ITR 96-015 e Page 2 of 9 Incorporation of PC/M design change information into the design basis documents of record Plant response and evaluation of concerns contained in selected NRC Information Notic The scope of this walk down included portions of selected systems shown on the Selected Recor Drawings (SRDs) listed below. 8770-G-078, Sheet 110, Revision 18," Flow Diagram Reactor Coolant System"(Reference 2) 8770-G-078, Sheet 130, Revision 16. " Flow Diagram Safety injection System (Sheet 1)" (Reference 3) 8770-G-078, Sheet 131, Revision ll, " Flow Diagram Safety Injection System (Sheet 2)" (Reference 4) 8770-G-088, Revision 33," Flow Diagram Containment Spray and Refueling Water Systems" 1 (Reference 5) Walk down Results l Selected Record Drawings, within the scope of the walk downs, were compared to installed plant ! systems. The orientation of valves and orifices was verified to be as shown on the SRDs. No deviations between installed equipment and the SRDs were noted during the walk down. The { labeling of valves, tanks, orifices, control switches and instmments was adequate and nomenclature was consistent with that used in the system operating procedures. This consistency, an important human factors consideration that reduces error by aiding personnel during the identification of components for operation and maintenance activities, is considered a positive attribute of procedures i prescribing the operation ofplant equipment. The equipment label for the 1B1 SIT recirculation line drain valve opstream of HCV-3638, V3911, was noted to be missing during the walk down. The missing label was reported to responsible personnel in the Operations Support and Testing (OST) group and has been scheduled for replacement. A temporary equipment label was noted to be in place prior to completion of the walk down. The general material condition of the systems and their components was satisfactory. General cleanliness, though diminished due to outage work in the areas examined, did not degrade system operability due to general accumulation of dirt or debris. The condition of valves and supports was satisfactory. Packing leakage was not observed, handwheels were properly installed, and stems were straight. Hangers and supports were noted to be properly made up with fasteners installed. Due to outage work, areas in the vicinity of these systems did contain ladders and scaffolding, however, these areas were verified to be clear of this equipment and other hazards, such as flammable material, that could impact the operability of the system prior to containment closeout. Plant Work Orders (PWO) were checked via the PASSPORT system to ascertain if personnel are identifying and reporting items needing repair. Available data contains several hundred plant work ordern effecting Reactor Coolant Safety Injection and Containment Spray systems that have been identified and closed in the last two years. This indicates that plant personnel are actively using the PWO system to identify deficient items. This check also verified that active PWO's are being tracked, along with the current status of the repair activity.
ITR 92-015 Page 3 of 9 The local valve positions for the ponions of Safety Injection and Containment Spray were consistent with operating procedures, clearance orders in effect and the applicable portions of the SRDs. However, because the unit was in an outage some systems were not required to be operable and in many instances valve positions did not correspond to the prescribed normal operating position due to equipment clearance orders issued for work in progress. In lieu of system walk downs, the valve positions prescribed by system operating procedures: OP l-0410020, "HPSI/LPSI - Normal Operation" (Reference 6), OP l-0410021, " Safety Injection Tank Normal Operation" (Reference 7), OP l-0420020, " Containment Spray - Initial Valve Alignment" (Reference 8), and OP l-0230020, "N 2System" (Reference 9), were ccmpared against the positions prescribed by the applicable SRD (References 2 through 5). This review verified that positions prescribed in the 4 - operating procedures were as shown in the SRDs for normal operation. ' ~ Various SIT recirculation line vent and drain valves that effect ECCS subsystem operability are not required to be lined up until after the system is required to be operable by Technical Specifications. However, since the SIT recirculation lines connect directly to the safety injection headers, a mispositioned vent and drain valve could result in an inoperable injection header. PSL Unit 1 Technical Specification 3.5.3 (Reference 10), requires operability of one ECCS subsystem in operational mode 4 with Reactor Coolant System cold leg temperature above 250 F. However, Safety Injection Tank operability is not required until mode 3 with pressurizer pressure 2 1750 psia per Technical Specification 3.5.1 (Reference 11). The affected valves are initially positioned by l operating procedure OP l-0410021, " Safety Injection Tank No mal Operation," which normally l Eccurs in mo'de 4. However, SIT recirculation line vent - M drain valves should be included in the HPSI/LPSI valve lineup to ensure operability of the system is not compromised due to improper valve position. The ITR Engineer submitted Condition Report, CR 96-1630,"ECCS Subsystem i Valve Lineup" (Reference 12) to request corrective action for this item and to evahiate past l operability. As a result, procedure revisions to both unit I and 2 HPSI/LPSI operating procedures j have been completed. Further corrective action will be tracked through the Condition Report i process. With the exception of the vent and drain valve issue, PSL Unit 1 operating procedures j properly implement the requirements of the St. Lucie Unit 1 Updated Final Safety Analysis Report l for the ESF systems examined. The replacement of pressurizer code safety valves was reviewed as part of this walk down project. Installation of the relief valves was accomplished in accordance with the requirements of PC/M 040-196M and associated Plant Work Orders 61/3604,5, and 6. The installed configuration of the valves
. is consistent with that shown in 8770-G-078, Sheet 110, Revision 18, " Flow Diagram Reactor Coolant System." A review of the planned changes to effected design documents revealed that change packages for the Updated Final Safety Analysis Report and the Total Equipment Data Base had been prepared. However, a change package for St. Lucie Unit 1 Design Basis Document, DBD-PZR-1, " Pressurizer System," (Reference 13) was not included. A DBD Change Package should have been included, but it had been overlooked. A review of Engineering Quality Instructions, ENG-QI 1.1," Engineering Packages," (Reference 14) and ENG-QI 1.2, Revision 1, " Minor Engineering Package (MEP)," (Reference 15) revealed differences in the package preparation checklists for Engineering Packages and Minor Engineering Packages. The Minor Engineering
ITR 96-015 Page 4 of 9 i Package (MEP) preparation Form 131, (such as that used to prepare PC/M 040-196M), does not provide an affected document checklist. A list of this type should be included in the Minor l Engineering preparation Form 131 to reduce the possibility of omissions. l (Recommendation 1 & 2) l Selected Nuclear Regulatory Commission Information Notices involving ESF systems were reviewed, to evaluate the effectiveness of the evaluations performed by plant personnel as a result of these notices. Information Notices reviewed included: IN 96-10 Potential Blockage By Debris of Safety Injection System Piping Which is Not Used During Normal Operation or Tested During Surveillance (Reference 16) IN 96-27 Potential Clogging of High Pressure Safety injection Throttle Valves During Recirculation (Reference 17) IN 96-31 Cross-Tied Safety Injection Accumulators (Reference 18) IN 96-10 described a concern that accumulation of debris in idle ECCS suction piping and the. l Reactor Containment Building sump could lead to a condition that could cause loss or reduction of I ECCS flow during the recirculation phase of emergency core cooling. This concern is alleviated at ! PSL by a regularly scheduled surveillance of the containment building and sump at 31 day and eighteen month intervals respectively. These surveillances are required by Unit I and 2 Technical ; Specifications and are scheduled by PSL Operating Procedures OP 1 and OP 2 - 0010125, " Schedule ; of Periodic Tests, Checks and Calibrations"(References 19 and 20). IN 96-27 described a concern that High Pressure Safety Injection throttle valves could be susceptible to a common mode failure mechanism during the recirculation phase of emergency core cooling. The mechanism is the result of debris of sufficient size to cause clogging of the injection throttle valves passing through the containment building sump and ECCS suction strainers. This concern was evaluated in the response to St. Lucie Action Report 960369, "HPSI Injection Valve Clogging Issue," dated March 12,1996 (Reference 21). The response concluded that this failure mechanism is not a concern at PSL Unit 1 or Unit 2. A review of this response indicates that the conclusion contained in the response was based on sound engineering judgement and a thorough review of technical information including strainer screen mesh dimensions, valve sizes and stem travel. This concern was first identified by the plant through review ofindustry information distributed on the Nuclear Network, and the Plant's review and evaluation was completed approximately two months prior to issue ofIN-96-27. This demonstrates a proactive approach to the use ofindustry information to identify and resolve issues that may effect St. Lucie Plant operation. IN 96-31 was issued to alert addressees of a potential for operation in an unanalyzed condition by operating with Safety injection Tanks (SITS) cross-tied. This condition may reduce protection provided by the SITS durinr'some loss-of-coolant accidents (LOCA) due to bleed off of nitrogen over pressure through the fauhed loop to containment. An evaluation of the impact of cross-tied SIT operation on a Large Break LOCA (LBLOCA) was provided by Engineering Evaluation JPN-PSL-SEFJ-96-021, " Impact on Large Break and Small Break LOCAs of Cross-Connecting SITS to Common N, Header"(Reference 22). This evaluation concluded that there is no significant iinpact
i ITR 96-015 Page 5 of 9 on the LOCA analyses of record for PSL Unit 1 or 2 due to operation with the SITS cross-tied via the nitrogen header, The Independent Technical Review group questioned several aspects of the engineering evaluation, which are discussed below.
- 1. The Engineering Evaluation states that the LBLOCA analysis of record. EMF-92-176,"St. Lucie !
Unit 1 Large Break LOCA/ECCS Analysis with 25
- 7% SGTP " Siemens Power Corporation. l dated February 1993 (Reference 23), uses a nominal pressure of 230 psia SIT pressure to j determine LBLOCA results. The Engineering Evaluation uses this same initial SIT pressure, as l well as total flow volume into the faulted loop before the SITS start to inject into the intact loops, and an ideal gas approximation, to determine the initial intact loop SIT pressure (= 223 psia) at the stan of the injection phase. Based on the RCS rate of depressurization during a LBLOCA, the engineering evaluation concludes that the potential effect on calculated peak cladding temperature (PCT) will be insignificant. ITR determined that a quantitative analysis should be ,
included in the evaluation or a qualitative uncertainty value should be added to PCT to I demonstrate that 10CFR50.46 (b) limits for peak cladding temperature, cladding oxidation, hydrogen generation, coolable geometry, and long-temi cooling will be met. The ITR Engineer submitted condition report CR 96-1726 (Reference 24) recommending a re- l analysis to determine the most limiting SIT configuration, an'd to determine the quantitative effect on the LBLOCA analysis results. The preliminary evaluation of this condition report, conducted by FPL Nuclear Fuels, indicates that there is sufficient margin (i.e., > 250 F) between 1 the PCT obtained by the current LBLOCA analysis of record and 10CFR50.46 limits to I compensate for the small change in SIT pressure calculated, allowing them to conclude that the PCT resulting from cross-tied SIT effects will remain well within the limits specified in 10CFR50.46. The ITR 'Jngineer concluded that the qualitative evaluation provided by JPN- ) PSL-SEFJ-96-021 is acceptable until a quantitative evaluation is provided by the fuel vend,r. Additionally, PMAI 96-04-070 (Reference 25) has been issued by the plant to address a re-analysis of the LBLOCA, using cross-tied SITS, to determine the quantitative effects on LBLOCA core parameters. Corrective actions for this issue will be tracked through CR and PMAI processes.
- 2. The initial SIT pressure used in the engineering evaluation and the LBLOCA analysis of record is not consistent with the low nitrogen pressure limit for the SITS specified in Technical Specification 3.5.1. d). The analysis of record and Engineering Evaluation JPN-PSL-SEFJ 021 do not reflect the lowest allowable SIT pressure that may occur during normal operation and, as such, may be non-conservative with respect to initial SIT pressure used in the LBLOCA analysis. A re-analysis of the LBLOCA utilizing using initial SIT pressure at 215 psia may be
- warranted to demonstrate and document that the limits of 10CFR50.46 are being met.
The ITR Engineer submitted CR 96-1631 (Reference 26) recommending an evaluation to determine that the effects of the lower SIT pressure are bounded by the current LBLOCA analysis methodology and to determine the effect on the results during the next required re-analysis . In response to this CR, Siemens Power Corporation (SPC) letter " Safety Injection (SIT) Pressure for LOCA Analysis," dated July 9,1996 (Reference 27) SPC explains that the
ITR 96-015 Page 6 of 9 SIT pressure is not a critical parameter in the LBLOCA analysis. Since there can be offsetting effects relative to SIT pressure in the LBLOCA analysis, SPC guidelines indicate that a nominal value for initial SIT pressure should be used in the analysis and the nominal SIT pressure of 215 psig is considered to acceptably bound the minimum Technical Specification value of 200 psig. Siemens concludes that the current LBLOCA analysis supports the minimum SIT pressure allowed by Technical Specifications. In conversation with FPL Nuclear Fuels, personnel indicated that other offsetting effects such as total SIT volume and flow rates should be considered (i.e., the SITS installed are much larger than required to meet ECCS performance requirements). The ITR Engineer previously verified this during reviews of design bases documents (DBD) contained in St. Lucie Unit 1 Updated Final Safety Analysis Report, Chapter 6," Engineered Safety Features"(Reference 28) and St. Lucie Unit 1 Design Basis Document, DBD-HPSI-1,"High Pressure Safety Injection" (Reference 29). The SIT volume required to re-flood the core,2200 cubic feet, and that available from three intact SIT's,3270 cubic feet, supports the conclusion stated in the SPC letter. Based on review of this additional information ITR concurs with the SPC conclusion and considers this matter closed. During the above reviews the ITR Engineer noted that chapter fifteen of the FUSAR has been revised with the cycle eleven reload large break loss of coolant accident analysis data, but does not include the re-analysis results for cycle thirteen. This ana'ysis was completed in February 1993 and was flagged for but not included in the FUSAR Amendment No.14, dated June 1995. (Recommendation 3) CONCLUSIONS: The as-installed configuration of the Unit 1 Enginer il Safety Features Systems and the Pressurizer Code Safeties (as partially walked down via this ellort) is accurate'y reflected In Selected Record Drawings for the Reactor Coolant, Safety Injection, and Containment Spray systems. The general cleanliness and material condition of the systems and their components is satisfactory. Sufficient levels of maintenance and cleanliness are being applied to maintain system operability. With the exception of a SIT recirculation line vent and drain valve issue, PSL Unit 1 operating procedures properly implement the requirements of the St. Lucie Unit 1 Updated Final Safety Analysis Repo:t for the ESF systems examined. A question regarding the most limiting SIT configuration on the LBLOCA analysis of record remains unresolved pending a quantitative evaluation by the fuel vendor. RECOMMENDATIONS:
- 1. Submit a Design Basis Document (DBD) Change Package to incorporate the design changes and modification history into DBD-PZR-1 resulting from PC/M 040-196M.
(Expected Responsibility: PSL Site Engineering Manager)
- 2. Revise Minor Engineering Package (MEP) preparation Form 131 to include a list of probable documents that may be effected by the MEP or include a reference to Form 3 for the existing list.
(Expected Responsibility: PSL Site Engineering Manager)
ITR 96-015 Page 7 of 9 l
- 3. Include cycle 13 large break analysis data in the next revision of the PSL Unit 1 FUSAR.
(Expected Responsibility: PSL Site Engineering Manager)
REFERENCES:
1
- 1. Plant Change / Modification package PC/M 040-196M. " Pressurizer Code Safety Valve Replacement - Forged Body Design," Revision 0.
l
- 2. PSL Selected Record Drawing 8770-G-078, Sheet 110. " Flow Diagram Reactor Coolant l System," Revision 18.
- 3. PSL Selected Record Drawing 8770-G-078, SI.eet 130," Flow Diagram Safety Injection System (Sheet 1)," Revision 16.
- 4. PSL Selected Record Drawing 8770-G-078. Sheet 131," Flow Diagram Safety injection System (Sheet 2)," Revision 11. '
- 5. PSL Selected Record Drawing 8770-G-088," Flow Diagram Containment Spray and Refueling Water Systems," Revision 33.
- 6. PSL Operating Procedure OP l-0410020, "HPSI/LPSI - Normal Operation," Revision 40.
- 7. PSL Operating Procedure OP l-0410021," Safety Injection Tank Normal Operation," Revision 46.
- 8. PSL Operating Procedure OP l-0420020, " Containment Spray - Initial Valve Alignment,"
Revision 33.
- 9. PSL Operating Procedure OP l-0230020, "N, System." Revision 32.
- 10. St. Lucie Plant Unit 1 Technical Specification 3.5.3, "ECCS Subsystems - T,y <325 F,"
Amendment 143. I1. St. Lucie Plant Unit 1 Technical Specification 3.5.1, " Safety Injection Tanks," Original.
- 12. PSL Condition Report CR 96-1630,"ECCS Subsystem Valve Lineup," dated July 15,1996. j
- 13. St. Lucie Unit 1 Design Basis Document DBD-PZR-1," Pressurizer System," Revision 0. ,
l
- 14. Engineering Quality Instruction ENG-QI 1.1, " Engineering Packages," Revision 0.
- 15. Engineering Quality Instruction ENG-Q1 1.2, " Minor Engineering Package (MEP)," Revision 1.
- 16. NRC Information Notice 96-10. " Potential Blockage By Debris of Safety Injection System Piping Which is Not Used During Normal Operation or Tested During Surveillance," dated l February 13,1996. j l
ITR 96-015
. Page 8 of 9 I
- 17. NRC Information Notice 96-27 " Potential Clogging of High Pressure Safety Injection Throttle Valves During Recirculation," dated May 1,1996.
- 18. NRC Information Notice 96-31, " Cross-Tied Safety Injection Accumulators " dated May 22,1996. l
- 19. PSL Operating Procedure OP l-0010125, " Schedule of Periodic Tests. Checks and Calibra: ions "
Revision 5. I
- 20. PSL Operating Procedure OP 2-0010125, " Schedule of Periodic Tests, Checks and Calibrations,"
Revision 4. I
- 21. St. Lucie Action Report 960369 response,"HPSI Injection Valve Cloggbg issue," dated March 12,1996.
- 22. Engineering Evaluation JPN-PSL-SEFJ-96-021, " Impact on Large Break and Small Break LOCAs of Cross-Connecting SITS to Common N2 Header," Revision 0.
- 23. St. Lucie Unit 1 LBLOCA analysis of record EMF-92-176, "St. Lucie Unit 1 Large Break LOCA/ECCS Analysis with 25
- 7% SGTP," Siemens Power Corporation, dated February 1993. ;
I
- 24. PSL Condition Report CR 96-1726," Quantitative Evaluation of Cross-Tied SITS on the Large J Break Analysis," dated July 12,1996.
- 25. PSL Plant Manager's Action item PM96-04-070, " Indian Point #3," dated April 5,1996.
- 26. PSL Condition Report CR 96-1631, "Large Break LOCA Analysis SIT pressure input parameter," dated July 15,1996,
- 27. The Code of Federal Regulations,10CFR50.46," Acceptance criteria for emergency core cooling systems for light water nuclear power reactors," dated January 1,1995.
- 28. St. Lucie Unit 1 Updated Final Safety Analysis Report, Chapter 6," Engineered Safety Features,"
Amendment No.14, dated June 1995.
- 29. St. Lucie Unit 1 Design Basis Document DBD-HPSI-1, "High Pressure Safety injection,"
Revision 0.
- 30. St. Lucie Unit 1 Design i s Document DBD-SDC-1, " Shutdown Cooling System," Revision 0.
- 31. St. Lucie Nuclear Power Plant Operations Department Night Order, dated March 26,1996.
l
- 32. PSL Operating Procedure OP l-0410022, " Shutdown Cooling," Revision 27.
- 33. PSL Operating Procedure OP l-1600023," Refueling Sequencing Guidelines," Revision 62.
1 I
ITR 96-015 - Page 9 of 9 1
- 34. PSL Normal Operating Procedure NOP l-00300120," Pre-Stanup Check-Off List /' Revision 0. '
- 35. PSL Off-Normal Operating ProceJure ONOP l-00300131. " Plant Annunciatcr Summary,"
Revision 64.
- 36. PSL Off Normal Operating Procedure ONOP 1 -00300133," Local Plant Annunciator Summary,"
Revision 17
- 37. PSL Off-Normal Operating Procedure ONOP l-00410030,"High Pressure Safety Injection,"
Revision 4.
- 38. PSL Off-Normal Operating Procedure ONOP 1-0440030, " Shutdown Cooling Off-Nonnal."
Revision 26. ,
- 39. Engineering Quality Instruction. ENG-QI 1.0," Design Control." Revision 3.
- 40. Siemens Power Corporation Letter, " Safety ) .1-ction Tank (SIT) Pressure for LOCA Analysis."
dated July 9,1996.
- 41. St. Lucie Unit 1 Design Basis Document, DBD.CS-1, " Containment Spray System," Revision 0.
- 42. St. Lucie Unit 1 Updated Final Safety Analysis Report, Chapter 5, " Reactor Coolant System,"
Amendment 14.
- 43. St. Lucie Unit 1 Updated Final Safety Analysis Report, Chapter 15, " Accident Analysis,"
Amendment 14. dE Submitted: y Date: ;uiv 26.1996 C.E. Norris, ITR Engineer i
// i Approved:
Date: 7 #
/ /
R. J. De La Espriella, ITR Supervisor
o Inter-Office Correspondence FPL. ITR RECOMMENDATION RESPONSE FORM To: L.W. Bladow, Quality Manager Date: July 26,1996 From: D. J. Denver, ENG MGR/PSL Department: PSL Engineering
Subject:
ITR Recommendation Response Due By August 26,1996
Reference:
- 1. ITR Report #ITR 96-015, " Safety System Walk Down," Recommendation #1 (issued via QA letterbook # JQQ-96-101, dated July 26,1996).
- 2. CR # 96-1855 Recommendation:
(1) Submit a Design Basis Document (DBD) Change Package to incorporate the design changes and modification history into DBD-PZR-1 resulting from PC/M 040-196M. I have reviewed the concerns and recommendation (s) of the ITR report referenced above. For the specific recommendation (s) which are deemed applicable to my department, the following disposition is provided: l Agree with recommendation (s) # and will take the actions as discussed i below: ) RecommendatiOD_#_ PMAI # PMAI Due Date: l I 1 __ Do not agree with recommendation (s) # as discussed below: 1 Discussion: (Attach additional sheets if needed) 9 Signature of Department Head
l Inter-Office Correspondence FPL ITR RECOMMENDATION RESPONSE FORM j To: L.W. Bladow, Quality Manager Date: July 16,1996 ' l From: D. J. Denver, ENG MGR/PSL Department: PSL Engineering i
Subject:
ITR Recommendation Response Due By August 26,1996 i
Reference:
- 1. ITR Report #1TR 96 )l5, " Safety System Walk Down," Recommendation #2 l
~
(issued via QA letterbook # JQQ-96-101, dated July 26,1996).
- 2. CR # 96-1855 Recommendation:
(2) Revise Minor Engineering Package (MEP) preparation Form 131 to include a list of probable documents that may be effected by the MEP or include a reference to Form 3 for the existing list. _I have reviewed the concerns and recommendation (s) of the ITR report referenced above. For the specific recommendation (s) which are deemed applicable to my department, the following disposition is provided: _ rgree with recommendation (s) # and will take the actions as discussed be% w: { hmmendation # PMAI # PMAI Due Date: i i Do not ag 9e with recommendation (s) # as discussed below: I Discussion: (Attach additional sheets if needed) Signature of Department Head
Inter-Office Correspondence 5:PL ITR RECOMMENDATION RESPONSE FORM l To: L.W. Bladow, Quality Manager cate: July 26,1996 From: D. J. Denver, ENG MGR/PSL Department: PSL Engineering
Subject:
ITR Recommendation Response Due By August 26,1996
Reference:
- 1. ITR Report #ITR 96-015, " Safety System Walk Down," Recommendation #3 (issued via QA letterbook # JQQ-96-101, dated July 26,1996).
- 2. CR # 96-1855 Recommendation: ,
1 (3) Include cycle 13 Irge break analysis data from the current analysis of record, EMF-92-176, "St. Lucie Unit 1 Large Break LOCA/ECCS Analysis with 25 7% SGTP." Siemens Power Corporation, dated February 1993, in the next revision of the PSL Unit 1 FUSAR l l have reviewed the concerns and recommendation (s) of the ITR report referenced above. For the specific recommendation (s) which are deemed applicable to my department, the following disposition is provided: l _ Agree with recommendation (s) # and will trke the actions as discussed below: Recommendation # PMAI # PMAI Due Date: l _ Do not agree with recommendation (s) # as discussed below: Discussion: (Attach additional sheets if needed) i Signature of Department Head
^'y ~ h - /g - Jg 7p
/s/ - vf :,57 <ig Imer.ogg;C' Correspondence I
FPL ! I JQQ-96-114 To: W . G. W hite Date: August 16,1996 From- L. W. Bladow Department: JNA/PSL
Subject:
Gate Log Summaries Attached is a list of 18 badged personnel at St. Lucie site. For the purpose of auditing compliance with Tech Spec and Admm procedure requirements regarding overtime controls QA is requesting l a Gate Log printout of time spent on site for the two week period of 7 July 96 to 4 August 96. L. W. Bladow Quality Manager - PSL I LWB/str 1 Attachment ' I a B e
J J. A. Stall Vice President - St. Lucie Plant R.. E. Dawson Business Systems Manager C. L. Burton Sne-4afermatien-Services E. Weinkam Licensing Manager G. J. Boissy Materials Manager J. Scarola Plant General Manager R. Sipos Steam Gen. Replacement Project Manager L. C. Morgan Human Resource Manager J. Marchese Maintenance Manager H. Johnson Operations Manager C. Wood Acting Work Control Manager D. Denver Site Engineering Manager L. W. Bladow Quality Assurance Manager K. Beichel Rotating Maintenance Shift Supervisors J. Brady Rotating Maintenance Shift Supervisors E. Burgess Rotating Maintenance Shift Supervisors F. Gigele Rotating Maintenance Shift Supervisors L. Large Rotating Maintenance Shift Supervisors
]
1
~
9 4 w
Paga 5 of 5
- c. ST. LUCIE PLANT Af> /-
ADMINISTRATIVE PROCEDURE NO. 0010119, REVISION 14 A- 0 OVERTIME LIMITATIONS FOR PLANT PERSONNEL / FIGURE 1 REQUEST TO DEVIATE FROM OVERTIME GUIDELINES TO: Vice President - St. Lucie Plant / Plant General Mgr/ Services Mgr. FROM: E M A RCFtESE. oAn '7/Ld/% 4
SUBJECT:
DEVIATION FROM OVERTIME GUIDEUNES FOR (NAMES): % 7/27/W /R1
- 3. M 6.RC.A ESE /R1 i
ORIGINATOR Request the below listed individuals to exceed the following overtime guidelines Greater than 16 hours s?Jaight Greater than 16 hours in a 24 hour penod Greater than 24 hours in a 48 hour penod .
/ Greater than 72 hours in a 7 day period A break of at least 8 hours (including shift tumover time)
SCOPE OF WORK M SA PK4*ATA BASIS FOR DEVIATION O Personnel have unique C -M--Vtrainmg
. Sufficient rest will be provided
. O Turnover of personnoi would leopardize quality of work O Excoaswa lost time would occur and sufficient testing will ensure quality of activity Other DETAILED PLANATION OF BASIS FOR DB/lAT10N W . M Aier a e s c. mers y p e ,it P o w m a.a o misic. Av useec Am Fiu s tu A C ,ono m A:rio c CA.PAm6T-v. Pr.oPeR E957/ SoPER)(5)o%
. 4 TtAN6Po12 TAT o W D F ? G Q O t E E. D') % L L 5 EE 5%it.oJ t DE.D / FOILO isd ED APPROVAL APP I Preeeent . St. Lucie Plant / Plant Gen. Mgr. / Sennoes Mgr. (arcie one)
ROUTING Or,iginal to Nuclear Records Vault.
'su th- 46 8 8'
't6p<1 40**G 4, c , , gg, j,a qg, g g_ ,
Qm&o-yy q Inter Offica Carresp:nd:nco j f:PL To: Department Heads Date: June 19,1996 From: J. Scarola Department: Plant Manager l l
Subject:
OVERTIME LIMITS It has come to my attention that there have ber.n recent violations of the plant's policy on overtime. St. Lucie Plant has administrative and regulatory limitations on the use of ovenime, ! both during refueling outages and during normal operations. The plant's Technical ! Specification, FPL Nuclear Division Nuclear Policy (NP-306), and St. Lucie Plant Policy (PSL-202), state:
- 1. An individual should not be permitted to work more than 16 hours straight, excluding shift turnover time.
- 2. An individual should not be permitted to work more than 16 hours in any 24-hour period, nor more than 24 hours in any 48-hour period, nor more than 72 hours in any 7-day period, all excluding shift turnover time. l
- 3. A break'of at least,8 hours should be allowed between work periods, including:
shift turnover time. For St. Lucie Plant, variations from the overtime limits can be authorized on a case-by-can basis, in advance, by the Plant General Manager or the Services Manager.
~ ,
Viciations of the overtime limits will not be tolerated and are subject to disciplinary l action. We personally need to be aware of overtime worked, both with respect to our ; ov n working hours and those of the people who work for us, to ensure that we do not violate these limits. l' Please share this memorandum with your direct reports. Copies: L. W. Bladow C. L. Burton R. E. Dawson D. J. Denver C. A. Pell J. A. Stall E. J. Weinbm Form 1oos (stocked) Rev.2/es
i
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- Y$ ~ ',Yg Author: Jim Scarsic ct USFPL820 /,*i w # O ' f')_ '
Dato 7/25/96 9:46 AM , Priority: Normal To: Joe Marchese f, To: Chuck Wood l TO: Hugh Johnson i CC: J A Stall at USFPL830 CC: Chris Burton at USFPL810 CC: Bob Dawson at USFPL810 Subject Overtime Restrictions
...................................- Message Contents ------------------------..----.-----
1 It has come to my that there have been instances where individuals have-exceeded the overtime requirements in the past and reflected the time { l on their time sheets over a longer duration period thus falsely l documenting that they met the OT restrictions. I want to make it ! extremely clear that this practice is not acceptable. This practice will be considered falsification of company records and may lead to . discharge. Make certain your subordinates clearly understand my expectation in this area so that there are no surprises. The budget overruns that we currently have make it imperative that we closely manage any discretionary expenditures. Effective immediately following unit I return to service, all preacheduled overtime must be reviewed and authorized by you as managers for each individual not just by job. The department heads, NPS, and rotating maintenance managers continue to have the authority to approve emergency OT in direct support of unit operation. I expect you to manage OT so as not to incur any additional LCO out of service time as a result of this requirement. I i wo S e 9
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Author: Bill Bohlks at umfp1211
. Date: 7/22/96 6:27 AM Priority: Normal J TO: Dan Denver at USFPL800
, subject: Re: Revised Overtime Exceedance
---------------------------- Message Contents ----------------------------- '
DJD, Overtime exceedances are approved. Affected individuals should return to normal schedule as soon as is practicable. 4 WHB Reply Separator
Subject:
Revised Overtime Exceedance 1 Author: Dan Denver at USFPL800 i Date: 7/21/96 5:02 PM The purpose of this memo is to request your approval for a specific exception from the Nuclear Division overtime guidelines. The St.Lucie Plant Manager has requested that Nuclear Engineering continue to support the Unit 1 outage issues. In order to meet this request, the JPN personnel listed below will exceed the overtime guidelines: Gordon McKenzie, John Priolo, and Dan Denver As compensatory measures: I The amount of overtime will be minimized. St.Lucie Project supervision j will assure that the individuals are not fatigued. St.Lucie Project ! supervision will carefully review the quality of safety related , products. l Late Note: In addition, Walt Edwards exceeded 24 in 48 hours on 7/18 and 7/19 to support revised SG level calibration calculations. O
l,
- 4 Author: Bill Bohlko at unfp1211
, Date: -7/19/96 5:02 PM l Priority: Normal /
l TO: Dan Denver at USFPL800
Subject:
Re: Overtime Exceedance
---------------------------- Message Contents -----------------------------
1 DJD, You are authorized to exceed overtime. Please ensure that you obtain
- appropriate rest time before resuming your normal schedule and keep me appraised of your time worked for the next two weeks.
l WHB j Reply Separator
Subject:
Overtime Exceedance Author: Dan Denver at USFPL800 Date: 7/19/96 3:40 PM The purpose of this memo is to request your approval for a specific exception from the Nuclear Division overtime guidelines. The St.Lucie Plant Manager has requested that Nuclear Engineering continue to support the Unit 1 outage issues. In order to meet this request, the JPN personnel listed below will exceed the overtime guidelines: Dan Denver As compensatory measures: The amount of overtime will be minimized. St.Lucie Project supervision will assure that the individuals are not fatigued. St.Lucie Project .I supervision will carefully review the quality of safety related ' products. l l l O a
Authort Bill Bohlko at unfp1211 { Date: 6/22/96 8:09 AM f' Priority:-Normal /
! TO: Dan Denver at USFPL800 )
[:
Subject:
Re: Overtime Guideline Exceedance ;
---------------------------- Message Contents ----------------------------- i i
Nuclear Engineering shall accommodate the request of the St. Lucie Plant Manager. Please advise me when the exceadance period is over and regular l work schedule is resumed. WHB l l
Subject:
Overtime Guideline Exceedance Author: Dan Denver Date: 6/21/96 14:22 j - The purpose of this memo is to request your approval for a specific , -- exception from the Nuclear Division overtime guidelines. 1 The St.Lucie Plant Manager has requested that. Nuclear Engineering j continue to support the Unit 1 NI Unit 2 feedwater regulating valve efforts around the clock. In order to meet this request, the JPN j personnel listed below will exceed the overtime guidelines: Dan Denver Dave Wolf ' As compensatory measures:
.;The amount of overtime will be minimized. St.Lucie Project supervision will assure that the individuals are not fatigued. St.Lucie Project supervision will carefully review the quality of safety related i products. ;
- 1 4
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Form Ol 18 QAD 13-3 2/15/94
/ Name: Bobby J. Lowery l
FLORIDA POWER & LIGHT COMPANY Audit Number: RECORD OF TECHNICAL SPECIALIST QSL-PM-96-18 i
, AND AUDITOR-IN-TRAINING QUALIFICATIONS REASON FOR THIS ACCOMPANYING AUDITOR'S PARTICIPATION Auditor in training for principal auditor certification.
i AREA OF RESPONSIBILITY FOR THIS ACCOMPANYING AUDITOR i Per Management direction, Review and evaluate plant compliance with requirements of Technical Specification 6.2.2.f, " Overtime Guidelines." j l 1 QUALIFICATION e Adequate Technical and Communication Skills Commensurate with Responsibilities Assigned
' e Instructed in the Audit Plan and Scope e Indoctrinated in the Applicable Portions of the FPL QA Program Qualified By 7
. Lead Auditor Date Original: Audit File Copy: QA Training Coordinator
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13 4SEP1996 5SEP1996 c[s ACTMTY START FINISH lSEP1996
--. __.__ ... L _____ _ __..__ _.___. .._ . . _ f __
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ROOT CAUSE EVALUATION LEVEL 3
. A%cchmeny a g INVESTIGATE AND CORRECT CRs (R 94_ Z/G 6
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- 1. ANALYSIS OF THE PROBLEM / APPARENT CAUSE:
- h !MrL k fhY f M& auk M W 1
- 11. SPECIFIC CORRECTIVE ACTIONS
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s O p:: P L Attcchment # J-CR # _ L 2.W 7 Page. y of g AUDIT REPORT QSL-PM-96-18 Page 27 of 45
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I shall be reviewed monthly by the Plant General Manager or his designee to assure that exces ive hours have not been assigned." Nuclear Division Overtime Policy Revision 1 j'
" Variations from this policy can only be authorized by an officer of the Nuclear Division or his designee. In the event that unusual circumstances require the utilization of overtime in excess of the limits set forth herein, the officer or his designee taking action shall document, in writing, with a copy to the office of the undersigned, the circumstances which justify this extraordinary action."
AP0010119 " Overtime Limits for Plant Person 5 Paragraoh 8.2 "The nuclear plant personnel in all departments.shall be covered by these instructions." Paramoh 8.4
" Deviation from the overtime guidelines shall be approved by the Vice President St. Lucie Plant, Plant General Manager, or Services Manager."
Discussion: The sampled population consisted of 18 department managers and selected maintenance supervisors. The individuals selected for review were identified using the July 1996 PSL organiintional chart. Gate logs were requested and obtained for the period July 7 through August 4,1996. Time on-site was totaled and entered into an Excel Da: abase. Allowing 30 minutes for lunch and applying the established allowance for shift tumover to the criteria provided in administrative procedure AP0010119, the following maximum thresholds for allc,wed hours on-site were established:
- 1. No more than 17.5 hours in a 24-hour period.
- 2. No more than 27 hours in a 48-hour period.
- 3. No more than 82.5 hours in 7 days.
- 4. An 8-hour break exists between work periods (including shift tumover).
No cases were identified in which criterion number (1) above was exceeded. There were cases in which criteria number (2) and (3) were exceeded. In this
. regard, three personnel exceeded the 27 hour in 48-hour limit and two personnel exceeded the limit of 82.5 hours in 7 days. In addition, one individual re-entered the protected area prior to completing the required 8-hour break. In summary,
g Attachment 0 / o GEE
.s' CR#
Page
@ 2.y O f of [
AUDIT REPORT QsL_pg.96-18 Page 28 of 45 l 16.7% of the sampled population exceeded the criteria at least once during the period reviewed. Administrative procedure AP0010119 requires that a form entitled " Request To Deviate From Ovenime Guidelines," be completed for all individuals who exceed the ovenime guidelines. One individual above had submitted a deviation repon that covered eight identified cases in which criteria were exceeded. The President of the Nuclear Division did not receive a copy of this correspondence as required by NP-306. The same individual also exceeded the guidelines on two other occasions but had not submitted a deviation repon. His is indicative of a failure in the review and monitoring process. There were no forms relating to other violations of the guidelines on file in the plant quality records for the sampled period. l l Administrative procedure AP 0010119 provides clearly defined processes to identify, delineate and obtain approvel for deviations from the overtime limit guidelines for use by nuclear plant personnel. In contrast, the Engineering Department manages ovenime deviations through direct use of the provisions of the Nuclear Division Overtime Policy, NP-306. l One of the cases above in which the guidelines were exceeded is related to the Engineering Department. In this case three ccMail messages were provided indicating approval by the appropriate Nuclear Division Officer to exceed the ovenime guidelines. The first of the messages addressed a specific project. He latter two messages provided this permission to address " outage issues." These messages did not provide a limitation on the duration of the permission, and were not copied to the President, Nuclear Division as required by NP-306. Cc: mail correspondence does not comply with requirements for record status specified in the Quality Assurance Program This level of administrative control is considered unsatisfactory to meet Technical Specification and Nuclear Division requirements. Payroll time sheets were reviewed for individuals noted in excess of the overtime limits via the gate log review. In all cases concerning the management level time repons, no deviations in excess of the two-week,80-hour period were recorded. It is noted that the time frame covered by this audit encompassed a period during
'- which plant personnel were developing and implementing corrective actions to recent NRC Violations and a QA Finding in this area.
However, an inter-office memo generated by the Plant General Manager on June 19,1996 and distributed to 44 management and key supervisory personnel pre-dated the period of the audit sample and outlined the responsibilities of all plant
Attichment 0 /
?I 2N' EE
/
CR # Page 5 of 4 AUDIT REPORT QSL-PM-96-18 Page 29 of 45 personnel concerning overtime guidelines. Specifically, the memo reiterated the guidelines as stated in the Technical Specifications, NP-306, PSL-202, and AP0010119. Condition Report 96-2163 was written to document the identified ovenime violations and track corrective action. A follow-up evaluation of set ;rity gate log entries and exits was performed o'. a pre-selected population of twelve personnel involved in the 1 B Transfonner repair. The security gate logs for the selected time period of August 24 through September 8,1996 were reviewed. 1 Additional violations of criteria (3) and (4) were identified. One case involved an individual violating the criteria requiring an 8-hour break between work periods. ! Numeroes violations of over 27 hours worked in a 48-hour period were identified. I Sp::cifically 5 of the 12 sampled personnel, (41.7%), exceeded the criteria at least o' ice during the evaluation period. The overtime deviation file and the associated payroll time shew were evaluated. No deviation reonests were found which apply to this target population and evduadon period. The payroll time sheet review revealed that personnel were not effectively tracking on-site time. This is a repeat Finding, the same problem having previously been identified in Finding 3 of Audit QSL-PM-96-08. Recommendations: The following recommendations are offered to aid you in responding to the finding. However, additional or alternate actions may be necessary based upon your investigation of the finding and causal factors and generic implications identified. Your response must address each of the five elements in the audit cover letter.
- 1. Enforce the technical specification requirements as outlined in Administrative Procedure 0010119, Nuclear Policy 306 and St. Lucie Policy 202.
- 2. Ensure that all management personnel record and track on-site time.
. 3. Engineering should develop an overtime guideline procedure or follow the PSL site AP.
s Attachment 0 1 j CR# f(-24(7 Condition Report No.96-2417 Response __ Page / of ( Section 7. Discussion: , t This condition report was written by Quality Assurance to ensure a response to finding #2 of QA Audit QSL-PM-96-18. f There were three observations contained in the finding: l A. During the period July 7, through August 4, 1996, - 3 individuals out of 18 sampled exceeded the overtime ; guidelines and during the period of August 24, through
.. September 8,1996, 5 of 12 people sampled exceeded the overtime guidelines. '
B, Overtime deviation request were not' filled out for the above < examples. , C. The Engineering Department does not provide adequate guidance : to comply with the overtime guidelines. - As the QA findings indicate, there is some variation in the [ understanding and interpretation of the overtime guidelines.
~Thi-s variation has existed for some time and has been the target ;
of many attempts to correct or eliminate. The issue originates , with the NRC concern with operators and other key personnel, l doing safety related work, while being too tired to do an 1 effective job. The interpretation and applicability of this has changed over the ; years as we have tried to implement it under different
- circumstances. This changing interpretation exist through out the l industry and within the company as different companies have ;
implemented it differently and we have implemented it differently-at our three sites. Despite the several times that this issue has been addressed it still is not clear who it applies to, what work . it applies to or what has to be done to comply. Attempts to _ ~ improve one part of the problem has often resulted in adding to the problem elsewhere. Mixed in with the basic issue that the NRC is. concerned about are issues involving overtime distribution within the Union, budget constraints and control as well as industrial safety. The fundamental reason that caused the overtime guideline to be developed no longer exist. During the ,
. time that the guidelines were invoked, the industry routinely l worked operators for extended hours. This was at a time that the industry was growing very fast and new units were starting up ,
which required more operators. Operators were moving from one
t AM chmsnt # 2. CR# 9S ~L H 7
- Page 2. of g j
plant to another and it was very difficult to have a full staff. j Many companies were training operators as fast as they could but
- still could not keep up. It was routine for operators to work very long hours even if the unit was not in refueling. The NRC 5 became concerned about this and issued the overtime guidelines.
l This was before there was a fitness for duty program. Those 4 conditions no longer exist, the industry has stabilized and most companies have little trouble maintaining a full staff of operators. The overtime today is low compared to the amount typically worked back then. We now have the fitness for duty program ehich is aimed at ensuring that all workers are fit all the time. This is behavior and observation based and accounts for all reasons that an individual may be at risk. We have gotten increasingly detai, led in our attempt to comply with the guidelines and made it more and more difficult for more and more people to do their jobs. We have lost sight of the basic concern and instead focused on compliance with administrative details. The technical specifications state that the guidelines only apply to safety related functions. Generic Letter 82-12 clarifies that
" key maintenance personnel" is defined as:" Key maintenance personnel are those personnel who are responsible for the correct performance of maintenance, repair, modification or calibration of safety-related structures, systems or components, and who are personnel performing or immediately supervising the performance of such activities." This seems to imply that the guidelines apply to work done on plant equipment and this is further strengthened by GL 82-12 when it states that the definition of
" safety-related" is the same as applied to electrical equipment in 10 CFR 50.49 (b) (1) .
Some examples of variation of interpretation and understanding that exist are: - Technical specifications
- 1. List specific examples of who it applies to and all of them are hande en workers who do work on plant equipment that d,rectly i affects the unit. Other company documents imply that it applies to all division people.
- 2. It specifically says that it applies to safety related functions. Other company documents imply that it applics to all work, i
- - - J
. _- . . - ~ . - . _
' l l
- AM;chmsnt # E '
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- 3. It uses the term "should" for the actual hour limits but uses the term "shall" for the monthly review and authorization.
l This implies that it is more important for management to review what is happening on an ongoing basis than it is to control what is happening on a day to day basis. 1 i
- 4. It says that the objective is that " operating personnel work a l normal 8-hour day, 40 hour week while the unit is operating". l None of the implementing documents are designed to produce j that results. This was also noted by the resident in NRC inspection report 96-09.
NP-306
- 1. Does not specify who is covered and who is not.
- 2. Does not refer to or invoke any other document.
- 3. Uses the term "should" in all cases of specifics.
- 4. Does specify an exception that allows 84 hour work week for STAS.
- 5. Does not specify what work it applies to.
- 6. Uses the terms " unusual circumstances" and " extraordinary action" when referring to exceeding and approving exceeding the guidelines. This implies that it is really not to be done.
And in fact the difficulty in justifying exceeding the guideline caused people to work around by using different interpretations of what it meant. PSL-202
- 1. It is written with cost control as the main theme.
- 2. Does not specify who is and is not covered.
- 3. Do'es not specify what work is covered.
.4. Uses the term "should" in all cases.
- 5. Refers to and implements NP-306 and does not refer t6 any other document.
. AMEcht unt # 1 CR # fi-LYl2
./ Page 4 of S
- AP No.0010119
- 1. Specifically states in the scope that it applies to overtime
- work on safety related functions.
- 2. Uses both terms " plant personnel" and " Nuclear Division
! personnel" when referring to steps in the procedure.
! It is clear from the above examples that the issue of overtime 4 work on safety related functions is not clearly understood, interpreted or applied.
] l In an effort to improve this situation the following corrective j actions are proposed: 1 i 1. feiuvvuadutrequirement from the technical s ications. l Other companies are~3cTng *hia and e it'does not eliminate the need to control overt' , it does r administrative b of compliance. A PMAI will be o implemen s, the responsibility is the licensing
/g ment. LIC $({ gg g,. p f q(.
- 2. Revise NP-306, PSL-202 and AP No.0010119 to clarify the IA following issues:
- 1. What work the guidelines apply to. They should apply on y
- to safety related work. ;
j 2. What classifications they apply to. They should apply only ! 1 to those persons that do safety-related activities as ! . defined in GL 82-12. ! ! 3. What the record of compliance is. It should be the time ! sheet.
- 4. How the review must be done..
- 5. How all of the departments on-site will implement the guidelines. AP No.0010119 Should be used by all departments.
j A PMAI will be opened to implement the above changes, the responsibility is the services department. I5 g g, , g _ g g g
- 3. The Fitness for Duty Program should be reviewed to ensure that worker fatigue is properly covered in the program. A PMAI will be opened to implement this, the responsibility is the i . services department. Sec QQ-Il #llL -
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2.
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,. Page S of 8 4
The following six items are in response to SOM 16.0.
- 1. A review of the information related to this issue reveals that
- there were no violations of any document. The tech spec j applies to safety related functions, NP-306 does not specify j what it applies to. PSL-202 does not specify what it applies j to. And AP No. 0010119 specifically applies to safety related j functions. There was no evidence that any of the examples in
- the finding involved safety related functions. Discussions
} with the individuals indicate that they were not performing or
. directly supervising safety-related work as defined by GL 92-l
~
- 12. Since none of the work involved safety related functions and the requirement is for compliance on safety related A' functions there'can be no violation. However the root cause and causal factors for the apparent violation must be the confusion over the application of the overtime guidelines as pointed out above.
- 2. A review of the potential weaknesses to self-identification reveal the following. Since the issue was basically one of management oversight it is the management self-assessment
-process that needs to be evaluated. The management self-assessment process basically consist of the Quality Assurance organization and the Condition Report process. Both of these processes identified the continuing problem.
- 3. The generic issue is why our repeated efforts over several years to improve'a given problem frequently result in
- attempting to manage ever increasing detail while missing the basic point. This seems to say something about the way we respond to problems. It seems like we often only respond in small detail, one at a time and the small details a'dd up over time to something other than what was originally intended. It seems that our corrective actions sometimes miss the mark and
~
do not have the intended results as our process is focused on _ ^ compliance rather than results. There may in fact be many more areas where this is a problem. Our self-assessment j process should help us with this. l
- 4. The corrective actions proposed are listed in the above discussion section. !
N
4 j Component: HCV-09-1A Associate: EYDRLC RSVR Sys: 09 Train: (50n Fac: PSL Uhsae/02 Assign Priority: A3 j MASTER
' Name: HYDRAULIC RESERVOIR FOR HCV Work Type: 1 WOR. *' ORDER TASK 1A , ! Location: TRSL/36/N-T2/W-TA LMD: 1 l 96007328 01 l i Defect / Request: RESV. TO FULL ON HCV-09-1A,1B,2A,2B I i ER/PWO: 62 / 7169 I
Chg Loc: 910 PAGE 1 of 5 : Detailed Explanations f h ( l NPRD )i Work Request: 96004156 Def Tag: Loc: ! Trbl/Brkdown: Y 5 LCO: Y Unit Cond Req: 8 NPRDS: Y Fail Date: 03/04/96 Time: 17:05 Det: H Stat: A Symp: B Originator: AJSOIYJ SCALES AJ Date: 03/04/96 Dept: OPS Approve By: AJSOIYJ SCALES l AJ Date: 03/04/96 i t Task Determination Data: ' l IST Required : Y NCR/CR : N/A Safety Class: SR PMT Required : N PCM : N/A Q Group : D , 10 CFR 50.49 Reg Guide 1.97
- N EQ Doc Pkg : N/A Assign To : VLV I
- N Seismic Cat : I Est M/H : 8.00 ASME XI(ISI) Reqd : N Scaffold Req : Y Crew Qty : 2 Security Clearance: N Fire Prot Req: N Insul Ram : N '
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Location: TRSL/36/N-T2/W-TA LMD: 1 96007328 01 Defect / Request: RESV. TO FULL ON HCV-09-1A,1B,2A,2B ER/PWO: 62 / 7169 Chg loc: 910 PAGE 2 of 5 Continuation of Task
Description:
THIS NPWO IS TO DRAIN SOME HYDRAULIC FLUID FROM THE RESERVOIR AS a OPERATIONS HAS INDICATED THAT THE LEVEL IS TOO HIGH WHEN THE VALVE IS ? ! IN THE OPEN POSITION. n..................................................................... i _-~~____________________________________--____________________________ IF NEEDED, CONTACT THE THE PROJECTS & !JUPPORT DEPT. TO INSTALL l SCAFFOLD BOARD, THIS WILL ENABLE EASIEk ACCESS TO THE RESERVOIR FOR. 3 WORK TO BE PFRFORMED. i 3 NOTE: THIS IS A SAFETY RELATED COMPONENT IN A SAFETY RELATED AREA :
- CAUTION * -
i , 3 ALL PERSONNEL SHALL BE FAMILIAR WITH THE SAFETY HAZARDS AND HANDLING ) REQUIREMENTS OF DEH FLUID (FYRQUEL EHC) WHEN WORKING NEAR OR AROUND THIS CHEMICAL. CONSULT THE MATERIAL SAFETY DATA SHEET PRIOR TO i COMMENCEMENT OF WORK. (REF. MSDS 957.000) 1 _____---__-_-__ --_ ______--______________-_-___-_____~____________--- 4
<> VERIFY THAT YOU ARE WORKING ON THE CORRECT UNIT & COMPONENT (S) . <>
<> IF THE ID TAG ISN'T PRESBNT, CONTACT THE NPS/ANPS FOR RESOLUTION.<>
- <> THIS STEP MUST OCCUR PRIOR TO PHYSICALLY STARTING WORK. <>
, <> UNIT #2 HCV-09-1A <> ~
<> JOURNEYMAN SIGNATURE: DATE: / <>
<><><><><><><><><><><><><> y>> < > <> ><><><><><><><><><><><>
1 WORK ASK - 7--3 /-- #f - l i j CONTACT OPERATIONS FOR ON THE JOB SUPPORT. DRAIN HYDRAULIC RESERVOIR, FROM DRAIN VALVE, TO JUST ABOVE THE LOW '
; LEVEL' INDICATION. (OBSERVE THE OTHER THREE MAIN FEEDWATER ISOLATION VALVE RESERVOIRS FOR LEVEL, HCV-09-1B, 2A, & 2B) ~
i HAVE OPERATIONS VERIFY LEVEL. j UPON COMPLETION ENSURE ANY SPILL IS CLEANED UP, THIS VALVE IS-TO BE MAINTAINED TO A DEGREE OF CLEANLINESS AS REQUIRED BY QI 13-PR/PSL-2, 4
" HOUSEKEEPING & CLEANLINESS CONTROL METHODS."
j NOTIFY PROJETS & SUPPORT DEPT. TO REMOVE SCAFFOLD BOARD a MORE: Y I 1
1 Componnnt: HCV-09-1A Sys: 09 Train: Fac
; Associate PSL Units 02 HYDRLC RSVR Assign Priority: A3 MASTER j Name: HYDRAULIC RESERVOIR.FOR HCV Work Type: 1 WORK ORDER TASK 1A , Location: TRSL/36/N-T2/W-TA LMD: 1 96007328 01 i
Defect / Request: RESV. TO FULL ON HCV-09-1A,1B,2A,2B ER/PWO: 62 / 7169 Chg loct 910 PAGE 3 of 5 4 Continuation of Task
Description:
DISPOSAL OF WASTE HYDRAULIC FLUID IN ACCORDANCE WITH A.P. #0010501,
! " HAZARDOUS MATERIAL ta WASTE PROGAM."
======================================================================
NO POST TESTING IS REQUIRED AS NO PHYSICAL WORK WAS PERFORMED ON THE VALVE OR ACTUATOR
======================================================================
a 1 1 J 4 J i 4 5 W
i B Component: HCV-09-1A Sys: 09 Train: Fac: PSL Unit: 02 )
) Associate HYDRLC RSVR MASTER
{Name:HYDRAULICRESERVOIRFORHCV-09 Work
, Assign Priority:
Type: 1 A3 j l ' WORK ORDER TASK 1A i Location: TRSL/36/N-T2/W-TA LMD: 1 96007328 01 Defect / Request: RESV. TO FULL ON HCV-09-1A,1B,2A,2B ER/PWO: 62 / 7169 I Chg loc: 910 . PAGE 4 of 5 ) l JOURNEYMANS WORK REPORT I l Actual Start Date: Time: Actual Completion Dates Times ! i 7-3/-94 7'*f 7- 3/- fd 3: 30 &
- Note
- Journeyman shall sign and date text after their entries.
Trouble Found: This Section is NOT Applicable for PMs or other planned jobs l I 1 Wahof w,/4 DAr. n yhe / awl was M sku, skede'm (4M . x,
/ / ' '
k I Je
. SQkt i /t3 HUN 7- gr-fd Continued on Additional Sheets:
Suggestions For Future Planning / Variance Reason: Y h r
/, / ,
"7927*;;;; ""7"" pp;; tfc'mouitD
/ I, I hEl
- p. 6
Pcg31 of 25
/ FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT ADMINISTRATIVE PROCEDURE NO. 0010501 1 REVISION 8 l 7 c:.. _
\
1.0 TITLE
1N! I ., l
'5i l4 HAZARDOUS MATERIAL AND WASTE PROGRAM bI. !'/R8 2.0 REVIEW AND APPROVAL: PROCEDURh PloDUCTION Reviewed by Facility Review Group 9/26 1985 Approved by J. H. Barrow (for) Plant General Manager 10/2 1985 Revision _8_ Reviewed by FRG 4/18 1996 Approved by J. Scarola Plant General Mr. nager 4/18 1996 l I
3.0 SCOPE
i 3.1 Purpose l , This procedure provides guidance in the hancling, storage, disposal, and ! transportation of hazardous materials / wastes. ! 3.2 Discussion ! It is the intent of this procedure to fulfill the requirements of federal regulations 4 pertaining to: i
- 1. Hazardous waste with the exception of the following:
Reactor fuel and radioactive materials which are received, stored, processed, transported or otherw!ss handled in accordance with title
- 10 CFR and in accordance with plant license conditions as specified in the Technical Specifications.
1
- 2. Transportation of hazardous materia W (s/ jtfd3 MENT REnUIRES VERIFICAT!
AND ROJdG M E F 3.3 Authority .jg, .iues N l
~ S--OPS
- 1. 40 CFR 260-266,279 (EPA)
DATE
- 2. (poCT PROCEDURE 49 CFR 100-180 (DOT) DOCN 0010501 p -
SYS CQMP COMPLETED
;\ ihgw ,;}i ;.3h, q. . ; s /R8
'\ ( Y a a , o's/l T* * '
\/
Ol 13-PR/PSL-2 Revision 27
~ ~ ~ , - Apni,1996 g,,, ; Page 1 of 24 "I'M' T gj N U
- I M.e> :A CO.9$'s
# _ M !. _ l FLORIDA POWER & LIGHT COMPANY 5 i f1 '
j NUCLEAR ENERGY DEPARTMENT @l1 9 2l ST. LUCIE PLANT [j ' , PROCEDUTE P[ODU TION l HOUSEKEEPING AND CLEANLINESS CONTROL METHODS --
1.0 APPROVAL
l Reviewed by Plant Nuclear Safety Committee 8/14 1975 Approved by K. N. Harris Plant General Manager 8/15 1975 : Revision 27 Reviewed by Facility Review Group 3/29 & 4/17 1996 , Approved by J. Scarola Plant General Manager 4/17 1996
2.0 PURPOSE
This instruction provides acceptance criteria and controls for housekeeping and i cleanliness during operation, maintenance and modification of systems and components. i
3.0 SCOPE
l 3.1 This instruction is applicable to personnel performing operations, maintenance j and/or modifications on systems, cor ponents and spaces to ensure that they ! are adequately clean to support safe and reliable operation of the plant. m eep"\ il S OPS
; .sts p ,.
. DATE 7p. 03'8 p31 Ab DOCT PROCEDURE {
DOCN Q1-13-2 l SYS COMP COMPLETED ITM 27
n gj7omponent: 125V BATT 1A Sys: 50 Traln: A Fac: PSL Unit: 01 j t Associate: Assign Priority: A2 MASTER {
, Name: ~25V DC BATTERY 1A Work Type: 7 i WORK ORDER TASK Location: RAB/43/N-RA1/W-RAH LMD: 3 96018599 01 Defect / Request: U/1 WEEKLY PM OF 1A 125V DC BATTER: ER/PWO: 65 / 2487 ES Chg Loc: 915 PAGE 1 of 4 Detailed Explanation:
i
' PM ID: PMW1001 3.
.DUE BY DT: 07/30/96 7 EARLY DT: 07/29/96 LATE DT: 07/31/96 .s Work Request: More:
, Def Tag: Loc- - Trbl/Brkdown: NPRDS: Y Fail Date: LCO: Unit Cond Req: 1 Time: Det: Stat: Symp: Originator: Date: Dept: Approve By: Date: Task Determination Data: IST Required : N/A
- N NCR/CR Safety Class: SR PMT Required : N PCM : N/A Q Group : 1E 10 CFR 50.49 : N EQ Doc Pkg : N/A Assign To : U1EM 3 Reg Guide 1.97 : N Seismic Cat : I Est M/H : 2.00 ASME XI(ISI) Reqd : N Scaffold Req : N Crew Qty : 2 Security Clearance: N Fire Prot Req: N Insul Rem : N
- Clearance Required
- N Clearance No :
4 RWP Required: N RWP No: RCA M/H: L1: L2: L3: i QC Requirements: QC Required : Y f QL-A ... More: Work Order Task
Description:
TECH SPEC REQUIREMENT SEE PAGE 2 FOR TASK DESCRIPTION. 4 SAFETY RELATEDlQUALITY RELATED PARTS ~U5ED MU$T MEET REQUIREMENTS More: Y
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .C.F A PPEN DIX A 3 F Q1 8 1 i
Planned By : VXDOEKZ DEFRANCESCO V Date: 07/23/96 Pkg Appr By : PRE-APPR Date: 07/23/96 Time: 21:51 QC Approval : PRE-APPR Date: 07/23/96 OPERATIO S A PROVAL TO START ***********************
- NPS Start Permission: ~ .
LCO(Y/N):
- Start Date/ Time : -
3- 5ff
/ 5
- 4 *****************************g*********************************************
NPS Completion Notif: h"L Major Failure: Compl. Date/ Time: Ma]or Action :
' iN m L
, / -,
Deficiency Tag Removed (Y/N): ii
/
t
~b ~T.:omponent : 125V BATT 1A Sys: 50 Train: A Fac: PSL Unit: 01 j Associate: Assign Priority: A2 j j Name:125V.DC BATTERY 1A MASTER ,
Work Type: 7 WORK ORDER TASK Location: RAB/43/N-RA1/W-RAH LMD: 3 96018599 01 Defect / Request: U/1 WEEKLY PM OF 1A 125V DC BATTERI ER/PWO: 65 / 2487 ES Chg loc: 915 1 PAGE 2 of 4 l l Continuation of T'.sk
Description:
*************.,****************************************************** )l 1> VERIFY THAT YOU ARE WORKING ON THE CORRECT UNIT AND COMPONENT (S)
PRIOR TO STARTING ANY WORK. i UNIT 1 1A BATTERY BANK: INT:. ...DATE:.7./<..k/ ..
~
INT:........DATE:.../.../.... 2> PERFORM WEEKLY BATTERY INSPECTION IN ACCORDANCE WITH MAINTENANCE PROCEDURE 0960163.
~
3> CHECK TO ENSURE THE BATTERIES ARE CLEAN AND NO CORROSION IS PRESENT 1 ON THE INTER-CELL CONNECTIONS. 4> INSURE NO CRACKS OR DAMAGE TO BATTERY CAPS ARE PRESENT. REPLACE IF ! NEEDED USING M&S #008-46653-0. 5> CHECK CONDITION OF THE FLOOR, SINK, ETC. CLEAN IF NECESSARY. 6> DOCUMENT ALL WORK PERFORMED AND ANY TROUBLE FOUND ON THE JOURNEYMANS WORK REPORT.
~
1 7> THIS NPWO IS CLASSIFIED AS NUCLEAR SAFETY RELATED, AND AS SUCH, ALL PARTS USED MUST CONFORM TO THE PARAMETERS OUTLINED IN QI 8-PR/PSL-1 ENSURE A COPY OF THE ROS IS A'I'rACHED TO THIS NPWO FOR ALL PARTS USED. 8> CONTACT LICENSING DEPT, NOTIFY THEM THAT THE P.M. HAS BEEN
- f. sy '
SATISFACTORILY ,f COMPLETED.
# p M>. M .DATE : .k. / .M. / . M INT: .(.
^
FILE #60410 D
*************************************************************=********
NOTE * " AN ON THE JOB" TRAINING JPM IS AVAILABLE FOR THIS N.P
**************************************************************.W.O. ********
'lJEY ELATED i@AUTY 9. ELATED r.ARIS UdED VU$i MEET RECulREM!NT5 Oc J:!NOlX A OF Ct.81
e.n Component: 125V BATT 1A Sys: 50 Train: A Fac: PSL Unit: 01 i Associate: Assign Priority: A2 MASTER
; Name:125V DC BATTERY 1A Work Type: 7 WORK ORDER TASK ;
l l Location: RAB/43/N-RA1/W-RAH LMD: 3 96018599 01 I Defect / Request: U/1 WEEKLY PM OF 1A 125V DC BATTERI ER/PWO: 65 / 2487
- ES Chg loc
- 915 PAGE 3 of 4 JOURNEYMANS WORK REPORT Actual Start Date: Time: Actual Completion Date: Time: 1
~7-So-9(c, C@l 7 30-?Y 0730 \
Note: Journeyman shall sign and date text after their entries. l l Trouble Found: ! This Section is NOT Applicable for PMs or other planned jobs - l I I l l I Work Performed: SXMEP WH #f ff% /2)O M ~T)d2J2D>bbt.L . ,. I I ALIL-012. - h1A LM2un 7- 3 0 ~ 9$ ( Continued on Additional Sheets: Y N Suggestions For Future Planning / Variance Reason: Supv/ r Chief Date Su ervisor, Date QC Inspector Date
. . m _., .1 .
% )k o /bf ' ' *
< v j
,. Page 1 of 20 ) FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT
, MAINTENANCE PROCEDURE NO. 0960163 REVISION ..
A PSL
1.0 TITLE
f 125 V DC SYSTEM WEEKLY MAINTENANCE PROCEDURE PRObu 2.0 REVIEW AND APPROVAL: Reviewed by Facility Review Group 8/22 1989 Approved by G. J. Boissy Plant General Manager 9/11 1989 Revision 15 Reviewed by Facility Review Group 3/6 19_96 Approved by J. Scarola Plant General Manager 3/61996
3.0 PURPOSE
3.1 To provide instructions for the weekly maintenance checks of the St. Lucie Plant safety batteries. 3.2 To satisfy Technical Specification 4.8.2.3.2.a (Unit 1) and 4.8.2.1.a (Unit 2). 4.0 PRECAUTIONS AND LIMITS: 4.1 Steps marked with @ contain points which are commitments. Make no changes in these steps without first consulting the department head or his designee. 4.2 Do not exceed 345 amps DC output or 90 amps AC input on any battery charger. 4.3 Notify the NPS/ANPS if any cell parameter exceeds _ the specified values (Tech. Spec. Table 4.8-2., Category A Limits). 4.4 Do not allow any smoking, open flames or sparks in the battery rooms. S OPS T FOR INFORMATION ONLY oogPROCEDURE THl1 DOCUMENT IS NOT CONTROLLED. BEFORE uSE DOCN 0960163 VEtlFv INFORM ATION WITH A CONTROLLED DOCUMENT. SYS FLORIDA POWID AND UGHT CO.5T. LUCE PL/NT l COMP COMPLETED DATE VIETFifD l l INITIALS - n ATE VERiflED f f INITIALS l
. Prge 2 of 20 ST. LUCIE PLANT j MAINTENANCE PROCEDURE NO. 0960163. REVISION 15 125 V DC SYSTEM Wi!EKLY MAINTENANCE 4.0 PRECAUTIONS AND LIMITS: (continued) 4.5 Battery room ventilation fans shall be running at all times. 1 A - 1RV-2,1HVS-5A or SB 2A - 2RV-1, 2HVS-5A or 5B 1B - 1RV-1,1HVS-5A or SB 2B _2RV-2,2HVS-5A or SB 4.6 Exercise care not to spill any battery acid. Promptly wash off any spilled acid with large amounts of water. . 4.7 Determine the cause of any unintentional alarm and correct before proceeding with any step in this procedure. 4.8 Goggles, face shield and acid resistant gloves and aprons should be wom whenever handling battery acid. 4.9 Wipe electrolyte spills on cell tops and containers with bicarbonate of soda solution. Do not use hydrocarbon-type cleaning agents (oil distillates) or strong alkaline cleaners, they may cause the cell containers and covers to crack. When needed the solution should be mixed 1 lb. bicarbonate of soda to 1 gallon of water. 4.10 Use caution when wiping up acid on cell tops to not allow the bicarbonate of soda solution to get into the cell. 4.11 Request Operations assistance as necessary for breaker and equipment operations. - 5.0 RELATED SYSTEM STATUS: NPWO .2988 5.1 Gems Planner - record current pilot cell for the battery to be checked at the beginning of Section 9.0. Initials Date 1/M (0 l i
_, Page 5 of 20 ST. LUCIE PLANT 4 i / MAINTENANCE PROCEDURE NO. 0960163. REVISION 15 125 V DC SYSTEM WEEKLY MAINTENANCE 9.0 DETAILED PROCEDURE: ' NPWO $87 BATTERY .
. PILOT CELL lk _
9.1 Complete the following: 1 Fill in the general information'and record the specific gravity (SG), electrolyte level, and temperature of the pilot cell below. Correct SG readings for temperature and level using the correction factors in Table 1. l
- 2. Using DVOM record the pilot cell and battery terminal voltages below.
=
ltem TS Toleranco Actual PC Specific Gravity - - l.ny PC Corr. Spec. Gravity T 4.8-2 2 1.195 / .13 g PC Electrolyte Temp. T 4.8-2 2 50'F ' 9o PC Electrolyte Level T 4.8-2 > Min s + 1/4" 4 PC Voltage T 4.8-2 2 2.13 VDC 2.1y Battery Terminal Voltage 2129 VDC / 3 '/. (,
- Unit 1 - 4.8.2.3.2.a.2
- Unit 2 - 4.8.2.1.a.2 M&TE Nos.
Hydrometer EM-OSI- Thermometer 6' 70b initials Date 7 /.3d/95 v 9.2 Visually inspect the battery for loose material, dirt, dust, corrosion at terminal connectors, cracks and electrolyte leaks. Record any discrepancies on the NPWO.
- 1. Wipe all cell tops with damp rags to remove accumulated dust.
Pcg3 6 of 20 ST. LUCIE PLANT
/ MAINTENANCE PROCEDURE NO. 0960163, REVISION 15 125 V DC SYSTEM WEEKLY MAINTENANCE 9.0 DETAILED PROCEDURE: (continued)
NPWO N @ 9.2 (continued)
, 2.' Wipe up any spilled acid with rags moistened in bicarbonate of soda solution followed by a dam rag.
I initials Date 7/3f/97 9.3 Inform the Control Room and perform gro'und check DC bus cabinet. Both lights should be of approximately equal brilliance. A NSAT (circle one) Initials Date 7 /3 0/ 7[ 9.4 Complete the following:
- 1. Using the installed panel meters, read and record the following:
Battery Bus Volts (in DC Bus Cab) /R15 Battery amps (in DC Bus Cab) Batterv Charger DC amps Battery Charger DC volts
- 2. Using the DVOM read and record the output voltage and amps of the charger at the output shunt meter connections. Calculate output amps using the following formula:
MV X 10 = amps Installed Meter DVOM Amps SD So Volts /3Y l /3 % 7 l Battery Charger /Nb Amps L/5 l N l Volts / 3 (3 l/3Y.F l/R15 DVOM M&TE No. E- 6 9/ Initials Date 7 /3# / 74 V
__- _ _ - . . _ . . _ . _ _ _ _ . _.-- ___ _.__._._..__ __.._._.___ _ .-_...._.m
- l. Pzge 7 of 20 ST. LUCIE PLANT
- i MAINTENANCE PROCEDURE NO. 0960163, REVISION 15 125 V DC SYSTEM WEEKLY MAINTENANCE l 9.0 DETAILED PROCEDURE: (continued) t
! 9.5 If the battery bus voltage as recorded in step 9.4.1, is not between 133.5-135 l VDC (131.5 - 133 VDC for 59 cell batteries) on float or 136-137.5 on equalize
, as read with DVOM. Complete Appendix A. /R15
- Appendix A required YE circle one) 3 i
initials v Date. 7 /3Gf[
.N_.Q_TE.
' The following step is NA if one of the normal battery chargers is out of service or the AB Battery Charger is on line in place of one of the normal chargers for this battery.
/R15 9.6 Compare the current output of each of the parallel chargers. If the currents are not within 17 amps, as read on the DVOM, perform the applicable steps of Appendix B. If the battery is on equalize (136 - 137.5 V), this step is NA.
-Appendix B required YEh(circle one)
Initials - Date 7/3d/E 9.7 All data has been reviewed and any parameters not within the given specifications have been reported to the Nuclear Plant Supervisor, initials Date 7/.80/.8[
, Pcge 8 of 20 dT. cuCiE PLANT / MAINTENANCE PROCEDURE NO. 0960163, REVISION 15 l r; V DC SYSTEM WEEKLY MAINTENANCE 9.0 DETAILED PROCEDURE: (continued)
?
, 9.8 If any pilot cell parameters are not within the specified limits, complete Procedure No. 0960164, "125 VDC System Monthly Maintenance', within
. 24 hours.
- 1. Procedure 0960164 required YES circle one)
- 2. If yes, notify Electrical Supervisor. ,
Initials Date 7 /30]?/_. Completed by: ) A v/c2 ~ /71AA x fu u Date 7 /36 IR
. / '
Reviewed by: ' (C feTElectrician Date / b/b if required, NPWC written to. complete procedure 0960164 within 24 hours. NPWO No. h/ h , Data reviewed for Technical Specification compliance and test results approved. ElectricalSupervisor h k b Date 7 d /N
u Compont:nt : CHG PP 2C l Associate: PL"4P Sys: 02 Assign Pricrity: A2 I , Train: I rac: (50n
<S p . 02 MASTex Nare: 2HARGING PUMP 2C Work Type: 7 WORK ORDER TASK ,
t Location: RAB/1/N-RA2/E-RAE LMD: 1 96014720 01 Defect / Request: 021PM02-3612 PM - CHECK A "' LATO ER/PWO: 62 / 6949 Chg Loc: 910
^6 1 #
NPRD J
\ /
Detailed Explanation: U PM ID: PM02-3612 DUE BY DT: 08/08/96 EARLY DT: 08/01/96 LATE DT: 08/15/96 Work Request: More: Def Tag: Loc: Trbl/Brkdown: 3 LCO: Unit Cond Req: NPRDS: Y Fail Date: Time: Det: Stat: Symp: Originator: Date: Dept: l Approve By: Date: Task Determination Data: MCL List : PM02-3612 IST Required : Y NCR/CR : N/A Safety Class: SR PMT Required : Y PCM : N/A Q Group : B 10 CFR 50.49 Reg Guide 1.97
- A EQ Doc Pkg : N/A Assign To : ROT 1
- N Seismic Cat : I Est M/H : 8.00 ASME XI(ISI) Reqd : N Scaffold Req : N Crew Qty : 2 Security Clearance: N Fire Prot Req: N Insul Rem : N Clearance Required: Y Clearance No : 2. - 9 L CM RWP Required: Y RWP No: RCA M/H: L1: L2: L3:
QC Requirements: QC Required : Y QL-A. More: Work Order Task
Description:
SEE PAGE 2 FOR TASK DESCRIPTION.
, More: Y Planned By : WDCOBMQ CHESNEY WD Date: 06/05/96 Pkg Appr By : PRE-APPR Date: 06/05/96 Time: 12:00 QC Approval : PRE-APPR Date: 06/05/96 OPERATIONS APPROVAL TO START ***********************
NPS Start Permission: ., 7 , LCO(Y/N): 'r
- Start Date/ Time : N s' -' 'r /. / 2. 3 1 c
- NPS Completion Notif- - Major Failure:
Comp 1. Date/ Time: s < ' 91- / t9ys Major Action : Deficiency Tag Removed (Y/N): f h/
/ /
J Component: CHG PP 2C Sys: 32 Train: Fac: PSL Unit: 02 , Associate: PUMP Assign Priority: A2 { MASTER Name: CHARGING PUMP 2C Work Type: 7 WORK ORDER TASK Location: RAB/1/N-RA2/E-RAE LMD: 1 96014720 01 Defect / Request: 021PM02-3612 PM - CHECK ACCUMULATO ER/PWO: 62 / 6949 Chg loc: 910 PAGE 2 of 5 Continuation of Task
Description:
*************************** CAUTION ***********>'***************
VERIFY T OU E WORKING ON THE CO E T UNIT AND COMPONENT'S) i SIGNATURE DATE at gg
********* **************$* *4 ****************************
PERFORM PREV 4 IVE MAINTENANCE JOB #03612 PER ATTACHED INSTRUCTIONS.
. IJOTE : CALIBRATED M&TE GAUGES NEEDED TO CHECK AND CHARGE ACCUMULATORS.
kTTACHED REQUIRES VERIFICATION AND SIGNOFF: QI-11 PR/PSL-2, APPX. B GMP 2-M-0018, FILE # 03612 bOMPLETE PM ON ADDITIONAL COMPONENTS ON LIST ATTACHED!
4
> Component: CHG PP 2C
- Associate: PUMP Sys: 02 Train:
Assion Priority: A2 ll i Fac: PSL Unit: 02 MASTER i Name: CHARGING PUMP 2C ~ Work Type: 7 WORK ORDER TASK Location: RAB/1/N-RA2/E-RAE LMD: 1 96014720 01 Defect / Request: 021PM02-3612 PM - CHECK ACCUMULATO 4 ER/PWO: 62 / 6949 Chg loc: 910 PAGE 3 of 5 s JOURNEYMANS WORK REPORT Actual Start Date: Time: Actual Completion Date: Time: ! i ShkRL CC30 944L OGo { Note: Journeyman shall sign and date text after their entries. l Trouble Found: i a This Section is NOT Applicable for PMs or other planned jobs i i 4 P.M !
- l
, l Work Performed: 1 ACeeAtJ P. u . -ro s
- a s to i t ?cz t 6 . eAA . P. ;)o 2. -x cotg l
.Ta N 6LcA + ATeJ Ca' a - ses s 0 t
i / (
)
AW_% -
//
AA T e E_ Ad - l t 9 - L f4 l
/ / \
1 AA . 2 t 9 - l-t I i Continued on Additional Sheets: Y Suggestions For Future Planning / Variance Reason: l' i i' A ti .v /F eman/ hief Date Superviso D te QC Inspe{ s_ n "% QC
,7__-..-
M-
' FLORIDA POWER & LIGHT COMPANY -
M'. j 2
- ST. LUCIE UNIT 2 8 GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018 E' 8 i
REVISION 47
$ g I
1.0 TITLE
PROCEDUltEMODUCTION MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVE M PROGRAM i l 2.0 REVIEW AND APPROVAL: 3 Reviewed by Facility Review Group 10/10 1985 Approved by D. A. Saoer Plant General Manager 10/28 1985 i 1
- Revision 47 Reviewed by F R G 6/10. 6/17 1996 Approved by J. .Scarola Plant General Manager 6/17 1996
3.0 PURPOSE
1 L This procedure provides the necessary instructions to perform preventive maintenance (PMs) on safety-related and Tech. Spec. equipment as required by ! Technical Specifications 6.8.1 l 4.0 PRECAUTIONS & LIMITS: I i 1 4.1 The PM files in this procedure can only be performed under direction of an' ' l approved NPWO in accordance with Administrative Procedure AP 0010432, l
" Nuclear Plant Work Orders." 1 i
4.2 Clearances shall be established for the equipment on which the PM is to be performed prior to any work in accordance with 0010122, "In-Plant Clearance Orders." 4.3 The frequency of performance of PM files is subject to Tech. Specs., the ! i performance history and vendor recommendations. Frequencies for the l attached PMs are maintained in the PM Planners Scheduling Program and i may only be changed upon approval of Technical Support personnel (TS). 4.4 Refer to the individual PM attachments to this procedure. S 2 OPS J DATE ' DOCT PROCEDURE DOCUMENT REQUIRES VERIFICATION DOCN 2 4 0018 AND SIGNOFFS SYS
\ COMP COMPLETED l nov.DetsVened 9 d - O l nnians N ITM 47 1
. Page 107 of 454 ST. LUCIE UNIT 2 GENERAL MAINTENANCE PROCEDURE NO. 2 M-0018. REVISION '.' 4 .!
MECHANICALMAINTENANCE MAINTENANCE PHOGRAM SAFETY-RELATED PREVENT q .. 1 APPENDIX A py PM 3606, 3609, 3612 ' (Page 3 of 17)
2.0 Procedure
(continued) l 2.2 Gas Booster Pump Setup: INITIAL 1. Attach the air hose from the service air connection to the driving air inlet connection on the gas booster pump. % i / NOTE The nitrogen supply valve (V29201) is located approximately 12 inches above l ! the floor on the north wall of the charging pump hallway, near the 2A Charging Pump cubicle. 2. Attach the nitrogen supply hose from V29201 (nitrogen supply valve to the gas booster pump) to the gas booster pump suction. e4 4
/
3. Close both discharge shutoff valves on the gas booster pump discharge. cw
/
- 4. Notify OPS to open valve V29201.
2.3 Suction Accumulator Pressure Verification and Adjustment: NOTE
- 1. Contact TS to disposition any damage or wear indications.
2. The gas booster pump is not required to be running to charge the suction accumulator. 3. The suction accumu& tor vent valve is required to be open when checking or adjusting the suction accumulator pressure. Charging pump priming is not required for opening of the accumulator vent valve only. The suction ' accumulator drain valve is not required to be open. If OPS opens the suction accumulator drain valve, then charging pump priming is required.
. 1. ' If the suction accumulator vent valve is not within the clearance boundary and tagged open, then notify OPS to verify the vent valve is open. dj*
2. W Remove the valve guard from the top of the suction accumulator.
/
. P gs 108 cf 454 ST. LUCIE UNIT 2 - GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018. REVISION MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVEj ;
MAINTENANCE PROGRAM ' APPENDIX A PM 3606,3609,3612 4 (Page 4 of 17)
2.0 Procedure
(continued) - 2.3 (continued) INITIAL
- 3. l Remove the secondary plug and O-ring from the suction accumulator assembly. Inspect the 0-ring for damage and replace as necessary. A 9
- 4. Apply Snoop to the top of the valve core to determine if the j
schrader valve has a slow leak. If a leak is discovered, i then contact TS or the Mechanical Maintenance Supervisor for further direction. The schrader may require tightening or replacement. m
/ l NOTE
- 1. Use extreme caution while installing the brass adapter and the air connection valve onto the suction accumulator valve core. Over j tightening can damage the valve core. '
- 2. Ensure the T-handle on the air connection valve in fully positioned in the ;
counter clockwise direction before installing it on the brass adapter. S. Attach the M&TE gauge assembly to the suction accumulator in accordance with the following steps: i A. Retract the pin in the n!r connection valve by tuming the
- T-handle counter clockwise until it stops rotating.
B. Install the brass adapter on the suction accumulator assembly. 5<7 C. Install the air connection valve on the brass adapter. 4 / D. Connect a hose from the air connection valve on the suction accumulator to the outlet connection on the M&TE gauge 't assembly. 41
. E. Ensure the valve on the M&TE gauge assembly is in the closed position. 36 F.
Ensure the vent valve (bleeder valve) located next to the air connection valve is in the closed position. oc-,
/
4
Prgs 109 cf 454 ST. LUCIE UNIT 2
- GENERAL MAINTENANCE PROCEDURE NO. 2-M 0018. REVISION '
MECHANICALMAINTENANCEMAINTENANCE PROGRAM SAFETY-RELATED PREVENTI APPENDIX A i PM 3606,3609,3612 l (Page 5 of 17) . I
2.0 Procedure
(continued) 2.3 (continued) INITIAL NOTE 1. The target range for the As Left suction accumulator bladder pressure is 25 to 29 psig regardless of plant mode. l
- 2. Suction accumulator As-Found pressures can provide an indication of potential equipment problems. l I
A. As-Found pressures less than 20 psig may indicate that the suction accumulator valve core may be leaking or that the schrader valve may have been depressed during installation of the air connection valve. ' Contact TS or the Mechanical Maintenance Supervisor for further direction. B. As-Found Pressures greater than 35 psig may indicate that the suction l accumulator is not properly vented or a pump intemal valve is leaking ! by. Contact OPS to verify that the pump fluid block vent valve and the suction accumulator vent valve are open.
- 6. Carefully turn the T-handle clockwise on the air connection valve to engage the suction accumulator schrader valve. C~f
/
A. Acceptance Criteria: Suction accumulator pressure target range is 25 to 29 psig. B. Inspection Guidelines: Read the As-Found suction accumulator pressure on the M&TE gauge. Record the required data below. Pump (Circle One) 2A 28 @ Hour Meter Reading 3LM8d hrs. The Unit 2 Charging Pump hour meters are located in the charging pump hallway. M&TE Equipment Number E19 L As-Found Suction Accumulator Pressure C psig Initial & Date M / T / %
/
Page 110 of 454 ST. LUCIE UNIT 2 MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIV .. , MAINTENANCE PROGRAM APPENDIX A 2.0 GENERAL Procedure: (continued) 2.3 (continued) 6. PM 3606,3609,3612 (Page 6 of 17) l l (continued) ' C. Corrective Action if the acceptance criteria of Section P. 3.6.A is not met, then adjust the suction accumulator pressure to obtain an As-Left pressure between 25 and 29 psig by performing one of the following- ! NOTE
- 1. The gas booster pump is not required to be running to charge the suction accumulator.
- 2. Nitrogen may be added to the suction accumulator by controlling the gas booster pump discharge valve OR the M&TE gauge assembly valve.
- 3. Nitrogen may be vented from the suction accumulator through the vent valve next to the air connection valve OR the M&TE gauge assembly '
valve (provided that a hose is not connected to the inlet connection on the M&TE gauge assembly).
- 1. To increase the suction accumulator bladder pressure, connect a hose from the gas booster pump discharge to the M&TE gauge assembly inlet and add nitrogen as necessary. M
- 2. To decrease the suction accumulator bladder pressure, slowly vent nitrogen as necessary. A Record the As-Left suction accumulator pressure as read from the M&TE gauge assembly.
As-Left Suction Accumulator Pressure 77 psig initial eu Date_B_/ f/% l
Pcge 111 of 454 ST. LUClE UNIT 2 - GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018, REVISION 4 MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVE- ~N I-MAINTENANCE PROGRAM > APPENDlX A 2 f . PM 3606,3609,3612 - (Page 7 of 17)
2.0 Procedure
(continued) . _ 2 2.4 Suction Accumulator Reassembly: 1. Tum the air connection valve T handle in a counter clockwise direction untilit stops rotating. C4 4 l 2.
/ !
Close the gas booster pump discharge valve and the M&TE gauge assembly valve. 69
/
- 3. Open the vent valve (bleeder valve) next to the air connection valve to bleed pressure from the hose. Ce l
, 4. If applicable, remove the hose from the gas booster pump 1 discharge to the M&TE gauge assembly inlet connection. Ceu 5.
Remove the hose from the air connection valve on the suction
/
accumulator to the outlet connection on the M&TE gauge I assembly. o,
/
- 6. Remove the air connection valve from the brass adapter. C,
/
- 7. Remove the brass adapter from the suction accumulator valve core. C6
/
- 8. Apply snoop to the top cf the suction accumulator valve core to ensure that the schrada valve was not damaged. If a leak is detected, contact TS or the Mechanical Maintenance Supervisor for further direction. C'r
/
- 9. Remove all snoop and mo.isture from % suction accumulator valve core. 69 f
- 10. Lubricate the secondary plug O-ring with Dow Coming 55.
Q
- 11. Install the O-ring in the secondary plug and thread the secondary plug into the suction accumulator assembly. %
/
s, Pege 112 of 454 ST. LUCIE UNIT 2
- GENERAL MAINTENANCE PROCEDURE NO. 2 M-0018. REVISION 48 -
. MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVEG ~
MAINTENANCE PROGRAM APPENDIX A PM 3606,3609,3612 '
; (Page 8 of 17) ..
2.0 Procedure
(continued) 2.4 (continued) 4
- 12. Apply snoop to the top of the secondary plug to ensure the suction accumulator or bladder is not leaking. If a leak is detected, contact TS or the Mechanical Maintenance Supervisor for further direction. @
/
- 13. Reinstall the suction accumulator valve guard.
- 14. Remove the remaining gas hoses.
1 64, 2.5 Troubleshooting i 1. If leakage was detected during pressure adjustment or reassembly, contact TS and the Mechanical Maintenance Supervisor for additional troubleshooting direction. If charging problems were identified, or As-Found suction accumulator pressures were different than anticipated, TS may suggest a reverification of the suction accumulator pressure. N fA individual Contacted (Name) MkA Initial AA I Date 6 / i / *
.a -. A wc a a Page 113 of 454 ST. LUCIE UNIT 2 GENERAL MAINTENANCE PROCEDURE NO. 2 M-0018. REVISION 4, _3 . j
_ MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVE ,] MAINTENANCE PROGRAM
. .-}
- t l
APPENDlX A l PM 3606, 3609, 3612 (Pnge 9 of 17) - (
2.0 Procedure
(continued) .. ,, i t-2.6 Discharge Accumulator Pressure Verification and Adjustment: NOTE
- 1. Contact TS to disposition any damage or wear indications.
4 2. The gas booster pump is required to be running to charge the discharge accumulator. 4. The fluid block vent valve located on top of the fluid block discharge flange is required to be open when checking or adjusting the discharge ! ' accumulator pressure. Charging pump priming is not required for opening of the fluid block vent valve only. If OPS opens a drain valve, then charging pump priming is required. l 1. If the fluid block vent valve is not within the clearance boundary and tagged open, then notify OPS to verify the vent valve is open.
- 2. Remove the valve guard from the top of the discharge accumulator. g
/
- 3. Remove the secondary plug and 0-ring from the discharge accumulater assembly. Inspect the O-ring for damage and replace as necessary. 6 4
- 4. Apply Snoop to the top of the valve core to determine if the schrader valve has a slow leak, if a leak is discovered, contact TS or the Mechanical Maintenance Supervisor for further d;rection as the schrader valve may require tightening or replacement. 4
/
Prg3114 of 454 ST. LUCIE UNIT 2 MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVE . MAINTENANCE PROGRAM , APPENDIX A GENERAL PM 3606,3609,3612 (Page 10 of 17)
2.0 Procedure
(continued) - 2.6 (continued) l i NOTE
- 1. Use extreme caution while installing the brass adapter and the air connection valve onto the discharge accumulator valve core. Over .
1' tightening can damage the valve core.
- 2. Ensure the T handle on the air connection valve is fully positioned in the counter clockwise direction before installing it on the brass adapter.
i , S. Attach the M&TE gauge assembly to the discharge accumulator in accordance with the following steps: A. Retract the pin in the air connection valve by tuming the T-handle counter clockwise until it stops rotating. 6 ( B. Install the brass adapter on the discharge accumulator assembly. C4 i
/
C. Install the air connection valve on the brass adapter. f D. Connect a hose from the air connection valve on the discharge accumulator to the outlet connection on the M&TE gauge assembly. %
/
E. Ensure the valve on the M&TE gauge as^embly is in the closed position. 4'
/
F. Ensure the vent valve (bleeder valve) located next to the air connection valve is in the closed position. @
/
, , P ge 115 of 454 ST. LUCIE UNIT 2
- GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018. REVISION .4 MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVEj MAINTENANCE PROGRAM g
APPENDIX A PM 3606,3609,3612 (Page 11 of 17)
2.0 Procedure
(continued) - A 2.6 (continued) NOTE 1. The target range for the As-Left discharge accumulator bladder pressure is mode dependent. Modes 1,2 and 3 1625 to 1675 psig Modes 4, 5 and 6 480 to 520 psig The discharge accumulator is typically adjusted during plant mode changes. To assist OPS in expeditious mode changes, the accumulator pressures may be changed to reflect the Mode 3 to Mode 4 pressure difference at the direction of OPS. For example, during a reactor startup the discharge accumulator pressure may be increased to the Mode 3 pressure prior to the plant reaching Mode 3. Likewise, the pressures may be adjusted at the direction of OPS during a downpower.
- 2. Discharge accumulator As-Found pressures can provide en indication of potential equipment problems.
A. As-Found pressures less than 1300 psig may indicate that the discharge accumulator valve core may be leaking, or that the schrader valve may have been depressed during installation of the air connection valve. Contact TS or Mechanical Maintenance Supervision for further direction. B. As-Found pressures greater than 1750 psig may indicate that the discharge accumulator is not properly vented. Contact OPS to verify that the pump fluid block vent valve is open.
- 6. Carefully tum the T-handle clockwise on the air connection valve to engage the discharge accumulator schrader valve. #7 i
A. Acceptance Criteria Discharge accumulator pressure target range is 1625 to 1675 psig during Modes 1,2 and 3 OR 480 to 520 psig for Modes 4, 5 and 6.
Page 116 of 454 ST. LUClE UNIT 2 GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018. MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIV MAINTENANCE PROGRAM 4 APPENDIX A
. . .d.y PM 3606, 3609, 3612 (Page 12 of 17)
2.0 Procedure
(continued) 2.6 (continued) 1
- 6. (continued) i B. Inspection Guidelines Read the As-Found discharge accumulator pressure on the M&TE gauge. Record the required data below. W Pump (Circle One) 2A 2B h !
Hour Meter Reading Sm8 6 hrs. The Unit 2 Charging Pump hour meters are located in the charging pump hallway. i l M&TE Equipment Number e 'LW -^ Mode (Circle One) h2 3 4 5 6 As Found Discharge Accumulator Pressure / V70 psig initial A Date 6 / 9 / 9G C. Corrective Action if acceotence criteria 2.6.6.A is not met, then adjust the discharge .:. mulator pressure to obtain an As-Left pressure between 1625 to 1675 psig during Mode 1,2 and 3 OR 480 to 520 psig during Modes 4,5 and 6 by performing one of the following:
Psg3117 of 454 ST. LUCIE UNIT 2
. GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018. REVISION <
MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVE' " MAINTENANCE PROGRAM APPENDIX A PM 3606,3609,3612 ' (Page 13 of 17) j
2.0 Procedure
(continued) 2h 2.6 (continued)
- 6. (continued)
C. (continued) 4 NOTE 1. The gas booster pump is required to be running to charge the discharge accumulator. 2. Nitrogen may be added to the discharge accumulator by controlling the air supply valve to the gas booster pump. The gas booster pump discharge valve and the M&TE gauge assembly valve must be open while the gas booster pump is operating. 3. Nitrogen may be vented from the discharge accumulator through the vent valvo next to the air connection valve OR the M&TE gauge assembly ' valve (provided that a hose is not connected to the inlet connection on the M&TE gauge assembly).
- 1. To increase the discharge accumulator bladder pressure, connect a hose from the gas booster pump discharge to the M&TE gauge assembly inlet connection. Open the gas booster pump discharge valve and the M&TE gauge assembly valve, start the gas booster pump and add nitrogen as necessary.
Stop the gas booster pump after the appropriate pressure has been achieved. b
- 2. To decrease the discharge accumulator bladder pressure, slowly vent nitrogen as necessary.
- Record the As-Left discharge accumulator pressure as read from the M&TE gauge assembly.
As-Left Discharge Accumulator Pressure IWD psig Initial b Date 9 / 9 / % l
P:gn 118 of 454 ST. LUCIE UNIT 2 M*" ^ .. GENERAL MAINTENANCE PROCEDURE NO. 2 M-0018. REVISION 47 VECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVE' " MAINTENANCE PROGRAM ' APPENDIX A i
..h/
PM 3606,3609,3612 (Page 14 of 17) '
2.0 Procedure
(continued) # 2.7 Discharge Accumulator Reassembly l 1. Tum the air connection valve T-handle in a counter clockwise I direction until it stops rotating. 67 f 2. Close the gas booster pump discharge valve and the M&TE gauge assembly valve.
@ / l
- 3. Open the vent valve (bleeder valve) next to the air connection valve to bleed pressure from the hose.
69
/
4 If applicable, remove the hose from the gas booster pump discharge to the M&TE gauge assembly inlet connection. 4
/
4 5. Remove the hose from the air connection valve on the discharge accumulator to the outlet connection on the M&TE gauge assembly. &
/
- 6. Remove the air connection valve from the brass adapter. A
/
- 7. Remove the brass adapter from the discharge accumulator valve core.
O
- 8. Apply snoop to the top of the discharge accumulator valve core to ensure that the schrader valve was not damaged. If a leak is ,
detected, contact TS or the Mechanical Maintenance Supervisor I for further direction. C#
/
- 9. Remove all snoop and moisture from the discharge accumulator valve core. .
- 10. Lubricate the secondary plug O-ring with Dow Coming 55. 69
' 11. Install the O-ring in the secondary plug and thread the secondary plug into the discharge accumulator assembly. 6/
/ 3 i
Pcg3119 of 454 ST. l.UCIE UNIT 2 K GENERAL MAINTENANCE PROCEDURE NO. 2-M 0018. REVISION 40 _ MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVE "~ MAINTENANCE PROGRAM ., I' APPENDIX A ../ PM 3606,3609,3612 , (Page 15 of 17) '
2.0 Procedure
(continued) no 2.7 (continued)
- 12. Apply Snoop to the top of the secondary plug to ensure the discharge accumulator or bladder is not leaking. If a leak is !
detected, contact TS or Mechanical Maintenance Supervisor l for further direction. 9 '
- 13. Reinstall the discharge accumulator valve guard. k f
- 14. Remove the remaining gas hoses.
Q 2.8 Troubleshooting . 1. If leakage was detected during pressure adjustment or ieassembly, l contact TS and the Mechanical Maintenance Supervisor for additional troubleshooting direction. If charging problems were identified, or As-Found discharge accumulator pressures are different than anticipated, TS may suggest a reverification of the accumulator pressure. Individual Contacted (Name) d^ 4 Initial % Date 7 /'l /96 2.9 Reassembly / Restoration: NOTE The following step is not required only if the suction accumulator vent valve and the fluid block vent valve are within the clearance boundaries.
- 1. Notify OPS to close the suction accumulator vent valve and the
, fluid block vent valve. 9/
- 2. Notify OPS to close V29201. b
Pcg3120 of 454 ST. LUCIE UNIT 2 . GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018, REVISION 4 < J' SECHANICALJA NTENANCE SAFETY-RELATED PREVENT ", MAINTENANCE PROGRAM APPENDIX A - r PM 3606,3609,3612 (Page 16 of 17) .
2.0 Procedure
(continued) - 2.9 (continued)
- 3. Bleed the nitrogen pressure off the gas booster pump suction hose by opening the gas booster pump discharge valve. c4
/
- 4. Remove the hose from V29201 to the gas booster pump suction. so
/
- 5. Bleed the' pressure off the hose from the service air connection to the driving air inlet on the gas booster pump and remove same. 9
- 6. Close the gas booster pump discharge valve. a J
7. Return the M&TE gauge assembly and properly store the gas booster pump. M
/
2.10 Additional Maintenance Observations
- 1. Inspect the accumulators in general to assess any problems which may affect their ability to perform, record the observations below and to whom they were reported.
COMMENTS: ,Joce REPORTED TO: 4^ INITIALS: 9 DATE 8 / 7 / h 2.11 Housekeeping
- 1. Clean the area affected by this PM.
- 2. Store the M & TE charging and gauging assembly in the M&TE Room.
- 3. Store the gas booster pump assembly the -0.5 elevation.
Paga 121 of 454 ST. LUCIE UNIT 2 ~- GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018, REVISION 47 -
- [
3 MECHANICAL MAINTENANCE SAFETY RELATED PREVENTIVE : l MAINTENANCE PROGRAM *
'V APPENDIX A
/ l PM 3606, 3609, 3612 '
(Page 17 of 17) j 3.0 Post Maintenance Testing l I 3.1 l The NPS/ANPS shall be notified immediately of any deficiencies. ! 3.2 I TS shall review the as found pressure and compare them against the pressure from the last two consecutive PMs performed on the accumulator. A review of the data will be performed to determine whether trouble shooting or corrective action NPWOs are required. 3.3 Release clearance and retest as required by Ol 11-PR/PSL-2, " Mechanical Test Control." ~ 4.0 AdditionalInformation 1 4.1 PSL #2998-11569 Discharge Accumulator Greer Hydraulics Tech Manuai 4.2 PSL #2998-11570 Suction Accumulator Greer Hydraulics Tech Manual
- 4.3 Charging pump location drawing #8770-G-069.
4 . Suction Accumulator Portion of PM Completed Joumeyman's Name (print & sign) 4.a. Voom. Ia
' =-~ e Date f / 9 / 76 Discharge Accumulator Portion of PM Completed Journeyman's Name (print & sign) /4 . M . Vo c al- 6 i 9 /'? G
(
, l NOTE: U$o Att chments in this Appendix ist VALVES. Do NOT 953 this TcSt She:t.
APPENDIX B j , TEST SHEET (Page 1 of 2) I NPWO #: M 9Y9 WO #: 95 o / V7620 l' Component Tag # [Na 88 % PSL Unit _.M Plant Locatson E9$9/1/ A)- AA 2 / 8-= PAE 1 Equipment Name /Ljsde /ve, Pu M e $l C l DeScnption of Wott (Hked Act, u'm u 1 n-on_ % Es c 04 E. mner ieserig. 30 weerweces Aree seemson IST s tST esmpenene, een o&T renew ost Seennow w peseree. L_Au/ //A/ z w
}
Pisee (x) s meeoween Tesene
// Whmwn Accessence caene caos nem Tesorg Soeone Zlume w Ames nest j neewee one menues neem 1 O'S onesi Sea or 2:000eo ANPSws e epowr , ggm ,, son n ,,,,,, SATsund$AT i Dee Sness ASa4E Case Purve Head Pnour Per especeme pur's Dee eneet co,vumees 2 OST Sec XI(IST Program) AP 0010125. Asf AP 0010132 y j I Dee Sneet 3 CST " "
, Sec m (IST Progrefug ' AP 0010125. Ref AP 0010132 Sheen l
/ e ASuE Coos Purve Seal Lessage No EJeanrei Leeenge Urunne I SAT / UNSAT Sec 10 (nST Psegram) Permoed Dy Veneer er secrvunni empen l PungeCesapesseers feet Run phan eusament ene to seesmure d a 6 OPS SAT / UNSAT j oden ASAE See a IST Pegn4 pereyrve n weed h y opg PW8'oeConesseeers Seef Lestege No Ensus'es Lemiego presh Ses&
(Nor>ASME Sec Mi aST Pigng (Pecaeng twees Penssies er Veneer SATI M T to OPS LeonTest.RCS Per OP 0130MB SAT / UNSAT OSTOPSIer *No Leesepe G Nesmal oposseg Piast '!, 1Y OC L88" T*'I * """ 08 SAT / UNGAT 4 See M Casseeneres sier e VT4 ! 14 Hyee NearWeses
, ,g,g g , SAT / UNGAT 1
19 IS4MAINT Snecer Pwusenal Test er vleuel Test Mh 8veehesen f a eme can,,se veensen Test Pw Aset Tem gese, l 30 CPSoeu pesar c>eamer Paart T Ceaumme 4.r.T a 4.74
'T at uAstr.
nesi Essenger Tee (som Tesi ,"'*',',",,3,,'"P', SATstmSAT i
- Leakage is allowed when evaluated by OPS for continued Operation.
i i 1 DOCUMENT REQUIRES VERIFICATION AND SIGN 0FFS 1 Rev. Data Verified 42'Minitials O O i j i
- t'e g_s 1_2 c- f _
6 2- _ - - - _ _I !': 'comsrnent ice e 8ao #F 4C est unn .4A i i - ,, i APPENOlX B l TEST SHEET { (Page 2 of 2) j Piece messernese 3 (X)W teseng Seenes tese Cswe nem Tee.ig . Aegumes G#eie unremum Acceewwe Crione er Acted 5 Oest Asenses innea
# teny fusemie I 'est as Per ~
(C .APW6 Penemunne I" # I
- oP 0700000 er cP 0700038 j as ors aces svamm venene 4
}7,7,,pg7gfyy i< ene C at OPS Pen tes Aun o e,es.e,s e.es. ee SAtiUessAt i
f 30 W Ceresse.ese Pesearviel seuemers are naassacy Maimes Pro a PosttestAssuree P'sasAtiu'v5At e***v o8T i Pem . sat i usesAt 8' osierteam Las Sposer test 4 teasereseneinoveeni eussem Aeonewu. camasses- sAtiusesAt l - i l 5 I ~ j ! , ADDITIONAL TECHNICAL SUPPORT TEST REQUIREMENTS & ACCEPTANCE CI . i I i i i - 1 l
, /RE Work Review I Planned Sy is H&rs 1-1 * - _
Date ,fz_I22)N ) Technical support personnel Review M lb/Ir Date 7 /1 /4 NPS/ANPS Review ' f -! d 7 j Data f/ :P/ % - POST Work Review i O Teenne deterrea Mu Supvsoremen: onte:
- i- /-
List toets deferred and blanket NWPO '2 a l f Test results accepted by MM Supy or PMT Coord (if deferred) M Date: f.fzd,f.3(r._ j If any test is UNSAT, NPWO / WO / WR (Circle One) For Rework j i Equipment Retumed NPS/ANPS/NWE to Service j/ ! # ' Date / / t.c.,/ 4 Comments
. - - . - - n. -. -
_ _ _ - . _ _ _ . . . . _ _ _ . . _ _ _ - - _ _ . _ - - - . _. . _ . _ . . . _ m __ . _ _ . _ _ _ _ . _ .
\
s
^% ' Component: V2107 Sys: 02 Train: ' ' 'o ' Fac: PSL Unit: 02 Associata: Assign Priority: Al MASTER Names CHECK VALVE ON CHARGING PUMP 2C Work Type: 5 j WORK ORDER TASK DISCHARGE 4 !
Location: RAB/7/N-RA2/E-RAE LMD: 1 96018092 1A i' Defect / Request: REPLACE VALVE DISC ER/PWO: 62 / 7220 Chg'Locs 910 PAGE 1 of 4 Detailed Explanation: a -
- s n
More: Work Request: Def Tag: Loc Trbl/Brkdown: 1 LCO: Unit Cond Req: ' NPRDS: Y Fail Date: Time:
- Det Stat Symp:
- Originator
- Date: Dept:
Approve By: Dates l Task Determination Data:
; IST Required : Y NCR/CR : N/A Safety Class:
j PMT Required : N PCM : N/A Q Group : B
- 10 CFR 50.49
- N EQ Doc Pkg : N/A Assign To : SVC Reg Guide 1.97 : N Seismic Cat : l' Est M/H : 2.00 ASME XI(ISI) Reqd : Y Scaffold Req : N Crew Qty : 1 Security Clearance: N Fire Prot Req: N Insul Rem : N i
Clearance Required: N Clearance No : RWP Required:-Y RWP No: RCA M/H: L1: L2: L3: 4 QC Requirements: QC Required : Y ! d1-4 avrA 6/w More: 1 m a a m m a'a m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m i Work Order Task
Description:
1 i ,a l i t. SCOPE CHANGE: 1A ( , h,,- f I I
~
j SEE PAGE 2 POR TASK DESCRfPTION. 4 ! 4 I More Y mammmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmma Planned By : LXMOTKB MULE L Date: 07/17/96
, Pkg Appr By : .BWBOPVX BLASCHKE B Date: 07/17/96 Time: 14:12 3
- QC Approval
- RAHOEYZ HAWLEY RA Date: 07/17/96 i ********************** OPERATIONS APPROVAL TO START ***********************
- NPS Start Permission:
LCO(Y/N):
- Start Date/ Time :
~
/
i e
- i 1
o************************************************************************** NPS Completion Notift Major Failure
! Compl. Date/ Time / Major A'ction :
j Deficiency Tag Removed (Y/N): 7
6 l Component: V2167 Sys: 02 Train: Associate: Fac PSL Unit: 02 Assign Priority: Al MASTER NamesCHECK VALVE ON CHARGING PUMP 2C Work Type: 5 WORK ORDER TASK DISCHARGE Location: RAB/7/N-RA2/E-RAE LMD: 1 96018092 1A Defect / Request: REPLACE VALVE DISC ER/PWOt 62 / 7220 Chg. loc: 910 PAGE 2 of 4 Continuation of Task
Description:
' INSPECTOR: DAT ~7 7/ *
************ ** ** *** **************************E: ** *
- 4 &*********
- QC HOLD POINT:QC TO REIVEW SECTION XI DOCUMENT PRIOR TO WORK *
************************ SCOPE CHANGE 1A'07/17/96 ********************
kT HAS BEEN DETERMINED THAT REPLACEMENT OF VALVE DISC IS
'k'HIS SCOPE CHANGE IS FOR DOCUMENTING THE REPLACEMENT WHICH IS A SECTION XI REPLACEMENT.
bBTAIN NEW VALVE DISC AND REPLACE AS PER ATTACHED ATTACEMENT 'B' AND *C'. AP NO. 0005760 kTTACHED: SIGNOFFS REQUIRED; AP NO. 0005760 ATTACHMENT 'B' AND 'C' hO SCOPE ADDITIONAL CHANGE. POST MAINTENANCE TESTING IS REQUIRED AS A RES 9
Comp,nent: V2167 Sys: 02 Train: Fac: PSL Unit: 02
Associate Assign Priority: Al MASTER NamesCHECK VALVE ON CHARGING PUMP 2 Work Type 5 WORK ORDER TASK DISCHARGE Location: RAB/7/N-RA2/E-RAE LMD: 1 96018092 1A l Defect / Request: REPLACE VALVE DISC ER/PWO: 62 / 7220 ,
2 Chg loc: 910 PAGE 3 of 4 JOURNEYMANS WORK REPORT
- Actual Start Date: Time: Actual Completion Date: Time
] Note: Journeyman shall sign and date text after their entries. Trouble Found ' This Section is NOT Applicable for PMs or other planned jobs i Work Performed: 1 1 1 l i ) Continued on Additional Sheets: Y N Suggestions For Future Planning / Variance Reason: 1 v s l . i Supv/ Foreman /C.hief Date Supervisor Date QC Inspector Date s
Compon:nt: V2167 Sys: 02 !
, Associate: Train: Fact PSL Unit 02 >
Assign Priority: Al MASTER Name: CHECK VALVE ON CHARGING PUMP 2C Work Typer 5 WORK ORDER TASK DISCEARGE Location RAB/7/N-RA2/E-RAE LMD: 1 96018092 1A Defect / Request: REPLACE VALVE DISC ER/PMO: 62 / 7220 Chg loc: 910 PAGE 4 of 4 Continuation of Trouble Found/ Work Performed: l l 1 l 1 1 ntinued on Additional Sheets: Y N
Componcat: V2167 Sys: 02 + Train: Fac: PSL Unit 02 i Associate: Assign Priority: Al MASTER j Names CHECK VALVE ON CHARGING PUMP 2C Work Type: 5 WORK ORDER TASK DISCHARGE Location: RAB/7/N-RA2/E-RAE LMD: 1 96018092 17 J l Defect / Requests REPLACE VALVE DISC ER/PWO: 62 / 7220 Chg Loc: Page: 1 ATTACHMENT A
- TOTAL EQUIPMENT DATA BASE SHEET Facility: PSL Unit: 02 Component: V2167 Associates Comp Types VL Comp Sub Type: CC Equipment Name CHECK VALVE ON CHARGING PUMP 2C DISCHARGE Systems CHEMICAL AND VOLUME CONTROL SY Code: 02 Location Desc Location Codes RAB/7/N-RA2/E-RAE Startup Sys Code: 036A RWP Reqd Y IST Reqd: Y NPRDS: Y EQ Reqd: N GEMS Major Code: UG50 Safety Class:
GEMS Major Mfgr RCP Q-Basis GENS ID Code: 67 Q-Group: B GEMS Minor Code: Q-Level: GEMS Minor Mfgr SCEW: N/A Account Code: 530 PCM: 009-293 Equipment Mfgra ANCHOR DARLING VALVE CO .SPEER: N/A Sury Maint Note: N/A Model No: 2"-W9223870 Doc Pac: N/A Engr Data PJ.ft Seiaaic Cat I Remarks: N/A . l EQ Comp Tag: N/A EQ Rev: N/A t Purchase Order (s) : 1 CE-15 ( 94 0212 6 ) Drawine '-*
- 299% .s 2998 . .4 CH-78 2998-G-195 8770-12709 2998-G-078 122 Tisch Manual (s) :
8770-12712 Procedure (s) : Note (s) : LMD
Comptn nt: V2167 Sys: 02 Train: i t Associate: Name Assign Priority: Al Fac: PSL Units 0F l CHECK VALVE ON CHARGING PUMP 2C Work Type: MASTER DISCHARGE 5 WORK ORDER TASK Location: RAB/7/N-RA2/E-RAE LMD: 1 , 96018092 1A Defect / Request: REPLACE VALVE DISC ER/PWO: 62 / 7220 4 Chg Loc: i Page: . ATTACHMENT A 2 Note (s) : d LMD O e i I 1 I
g - ' a
- omponent: V2167 Sys: 02 '
Train: Fac: PSL Unit: 02 Associate: Assign Priority: Al MASTER Names CHECK VALVE ON CHARGING PUMP 2C Work Type: 5 WORK OPl)ER TASK DISCHARGE Location: RAB/7/N-RA2/E-RAE LMD: 1 96018092 01 Defect / Request: CHECK VALVE STICKING / FAILED OPEN ER/PWO: 62 / 7220 Chg Locs 910 PAGE 1 of 4 l l Detailed Explanation:
" DURING TROUBLESHOOTING OF 2B CHG PP AFTER MAINT., FOUND THE I CHECK VALVE FOR THE 2C CHG PP STICKING / FAILED OPEN - REPAIR Work Request: 96012211 More:
Def Tag: Loct Trbl/Brkdown: Y LCO N Unit Cond Req: 8 NPRDS: Y Fail Date: 07/17/96 Time: 05:31, Det E Originator: JWM00PC MILTON Statt A Symp A JW Date: 07/17/96 Dept MM Approve By: MGK0XUG KOGELSCHATZ MG Date: 07/17/96 Task Determination Data: IST Required : Y NCR/CR : N/A 1 PMT Required Safety Class: SR ! 10 CPR 50.49
- Y PCM : N/A Q Group : B
- N EQ Doc Pkg : N/A Assign To : VLV Reg Guide 1.97 : N Seismic Cat ASME XI(ISI) Reqd : N
- I Est M/H : 16.00 Scaffold Req N Crew Qty : 2 Security Clearance: N Fire Prot Req: N Clearance Required: Y Insul Rem : Y RWP Required: Y RWP No:
Clearance No :
- RCA M/H
- L1: L2: L3:
i QC Requirements: QC Required : Y QL-A NO HOLD POINTS BASED ON VALVE SIZE. '
==2============================================================= ..==More: ========
Work Order Task
Description:
64V Seerd e M4; (A 7-0-fG Pk, - _ _ _ , SEE PAGE ~~........____ 2 POR TASK DESCRIPTION. Y
=====================================================================More:
Planned By : KCDOVGG DIBBLEY ======== Pkg Appr By : LXMOTKB MULE K Date: 07/17/96 QC Approval : RAHOEYZ HAWLEY L Date: 07/17/96 Time: 09:56 RA Date: 07/17/96
********************** OPE S ROVAL TO START ***********************
NPS Start Permission m .m LCO(Y/N):
- a Start Date/ Time : 9 ,, Q/ y l'fa(.o __
- ju ;- tw ~ -
oo************************************************************************** NPS Completion Notif: Major Failure: Compl. Date/ Times / Major Action : D3ficiency Tag Removed (Y/N):
r o,
" Component: V2167 Sys: 02 T r.- i n : Fac Associate: PSL Unit: 02 Assign Priority: Al MASTER Name CHECK VALVE ON CHARGING PUMP 2C Work Type: 5 WORK ORDER TASK i DISCHARGE Location: RAB/7/N-RA2/E-RAE LMD: 1 96018092 01 Defect / Request: CHECK VALVE STICKING / FAILED OPEN ER/PWO: 62 / 7220 i Chg locs 910 PAGE 2 of 4 Continuation of Task Descriptions
************************* TASK DESCRIPTION ***************************
THIS NPWO IS TO INSPECT AND REPAIR AS NBCESSARY V2167. (2"- ANCHOR / DARLING 1500# PISTON CHECK VALVE) i
- i ========================= SIGNATURE REQUIRED =========================
} VERIFY THAT SIGNATURE: JOURNEYMAN YOU ARE WORKING ON UNIT-2 AND THE CORRECT COMPONENT {S} DATE:
======================================================================
***************************** JOB TASK *******************************
DISASSEMBLE / INSPECT / REPAIR / REASSEMBLE PER ATTACHED GMP-01, APPENDIX C. FOR SAFETY CLASS A, B AND C VALVES, SECTION XI EVALUATIONS ARE REQUIRED PRIOR TO PERFORMING ANY OF THE FOLLOWING ACTIVITIES:
- 1. REPAIRS INVOLVING WELDING OR METAL REMOVAL (GRINDING TO REMOVE FLAW INDICATIONS) REGARDLESS OF NPS. j
- 2. FOR VALVES > 1" NPS, REPLACEMENT OF THE DISC, BODY, BODY OPENING COVERS AND FASTENERS (BONNET, HINGE PIN, BOTTOM, ETC...), BODY PLUGS, SAFETY RELIEF VALVE DISCS, NOZZLES, '
SPINDLES, SPRINGS, SPRING WASHERS AND SET PRESSURE ADJUSTING ' BOLTS (SCREWS), AND INLET OR OUTLET FLANGE FASTENERS. IF REPAIRS AS STATED ABOVE ARE REQUIRED, RETURN PKG TO SUPERVISION FOR SCOPE CHANGE, SECTION XI REVJEW AND ANY ADDITIONAL REQUIREMENTS. CONTACT THE S.C.E FOR INSPECTION OF THE VALVE AFTER IT HAS BEEN DISASSEMBLED. AFTER REASSEMBLY, VENT PUMP PER ATTACHED 2-M-0041, SECTION 9.7. ATTACHED: REQUIRES VERIFICATION AND SIGN OFFS. GMP-01 GMP-02 2-M-0041, SECTION 9.7 (PUMP VENTING) QI 11-PR/PSL-2 APPENDIX B, ATTACHMENT E
REFERENCE:
TECH MANUAL 8770-12712 I 1 J
, Component: V2167 Sys: 02 Train:
Associates Fac: PSL Unit: 02 Assign Priority: Al MASTER Name: CHECK VALVE ON CHARGING PUMP 2 Work Type: 5 WORK ORDER TASK DISCHARGE Location: RAB/7/N-RA2/E-RAE LMD: 1 96018092 01 Defect / Request: CHECK VALVE STICKING / FAILED OPEN 1 ER/PWO: 62 / 7220 l Chg loc: 91'O PAGE 3 of 4 { i 4 JOURNEYMANS WORK REPORT , " Actual Start Date: Time: Actual Completion Date: Times b 7//7/f4 /Yro i Note: Journeyman shall sign and date text after their entries, j Trouble Found: ' This Section is NOT Applicable for PMs or other planned jobs i l i l l l Work Performed: 1 D* M Sf b V280 / M AaDlvwY des'r. W ' M d s.h- d' n MJ tuf 2 PlJo. dlu', /2ud-a Y Y0 v Avh hY - M het a 17$o$ff
- i / v l
t 1 l 6
, Suggestions For Future Planning / Variance Continued Reason: on Additional Sheets: N 1
Supv/ Foreman / Chief Date Supervisor Date QC Inspector Date d
- h. Componcnt V2167 4
g Associate: Sys: 02 Trains !~ c: PSL Units 02 NamesCHECK VALVE ON CHARGING PUMP 2CAssign Priority: Al l MASTER DISCHARGE Work Type: 5 l -)RK ORDER TASK Location: RAB/7/N-RA2/E-RAE LMD: 1 l Defect / Request: 96018092 01
- CHECK VALVE STICKING / FAILED OPEN 1 1/PWO: 62 / 7221 2
- loc: 910 JE 4 of
- Continuation of Trouble Found/ Work Performed:
1330- /730 07/n /1'(. 7 Ell /M)f te27?ARr w n74 JC &~ FW2. . Md - lAE~JOR 8/2/d F W I TJJ //.R - i)/S4f.{&ttt3u;b Vht uG /X AGd i AffACHb A2056b. ANd l JCC })d2fCTTAI. 0Z$7440ed
/HER6wktt4uvr5 A5 )//2t:C]2b hsarED .sw aurx i3V W [/Atwa ieArk)
FEN /L J/JtEr ~T0 m1/armv - MA1>D wct ib Oc7Wteii /Msfec776x) AA/) /fdA145 VA7Al6 136sudes WEN /A/& (O27241) J/Jerr rc,2. 5EE Anit6/J5) utdT/sc77px/ /leTutrs.' i+ / W/lNp--- GMrM/EV /
/MtD&B Q. out4 sA-r /AW&fxN M f A SofeMfN77 cw 0/SL AC 7~3 vAtus /$c,Dj ANh CM P~o / ec;U 3f e t & A Ms A ilh4t_ J G /2 MA
?G/hfokS D
/MS*P EcfJOAt ANO (EfCC/D DA14 CA/d'7YAcHNt:NV
& 70/N66 M YWF 2-)J~9/ .% E TAAd 5 /woDerAo l
1 4 i Continued on Additional Sheets: Y N
1 4 f 4 Costponent: V2167 \
$ Sys:.02 Train: Fac: PSL Units 02 '
4 Associate Assign Priority: Al
- MASTER 1
' Name: CEECK VALVE ON CHARGING PUMP 2C Work Type 5 WORK ORDER TASK t
DISCRARGE-1 Location: RAB/7/N-RA2/E-RAE LMD: 1 96018092 01
- Defect / Request: CHECK VALVE STICKING / FAILED OPEN i
ER/PWO: 62 / 7220 l Chg Loc: 910 i
- 1. .
PAGE 1
- CumTINumiiCY PARTS Qty UI M-S NBR Stock Code Unit Cost On Hand Catd Avail Actuel- I
, 1 EA 578288763 0064200 1 113.2400
- 7 7 DESC: DISC, COBALT BASE ALLOY, ITEM 2 ,
2 1 EA 573247783 0150152 3 1.0000 ) 4 4 1 DESC: PIN, ANTI-ROTATION, AISI 302, SPRING TYPE, REFERENC
- 1 EA 573299121 0150204 1 272.8000 3 3
- DESC
- DISC, ASME SA638-660 TYPE 1, ITEM 004
.i s 4 .j - i i i i l' i n t i 4 1 I 1 I I l . i N 1 4 I i I ' l i 4 d
~ Conipuncut s V2167 Associates Sys: 02 Train
- Fac PSL Unit 02 :
NamesDISCHARGE CHECK VALVE ON CHARGING PUMP 2C Work 5 TypeAssign Priority: Al MASTER i WORK ORDER TASK ; Location: RAB/7/N-RA2/E-RAE LMD: 1 ! 96018092 01 ! Defect / Request: CHECK VALVE STICKING / FAILED OPEN > j ER/PWO 62 / 7220 l
- Chg Loct 910 i
- l. PAGE 1
)
ON ORDER Qty l UI M-S NBR Stoc.* Code Unit Cost On Band Catd 1 EA 573322645 010267'- 2 Avail Actua.I i 52.0000 1 DESC: GASKET, PRESSURE SEAL, GRAPHITE , i 1 N f e
Compon nt: V2167 Associate: Sys: 02 Trais A Names I '.c : PSL Unit: 02 CHECK VALVE DISCHARGE ON CHARGING PUMP 2C Work Type: Assign Priority: MASTER
';ORK ORDER TASK Location: RAB/7/N-RA2/E-RAE LMD:
Defect / Request: 96018092 01 J CHECK VALVE STICKING / FAILED OPEN
'R/PWO: 62 / 722' C'.7 Locs 910 3E 1 NOT PICKED Qty UI M-S NBR Stock Code Unit Cost OnL. Catd Avail Actua 1 EA 573391302 0150264 1 DESC: SPRING, INCONEL X 51.6180 1 2 I
W G 1
4 e Componnnt: V2167 Sys: 02 Train: ' 3 Associates Fac: PSL Unit: 02 Assign Priority: Al MASTER Name: CHECK VALVE ON CHARGING PUMP 2C Work Type: 5 WORK ORDER TASK DISCHARGE Locations.RAB/7/N-RA2/E-RAE LMD: 1 96018092 01 Defect / Request: CHECK VALVE STICKING / FAILED OPEN ER/PWO: 62 / 7220 Chg Loc: Page: 1 ATTACEMENT A
- TOTAL EQUIPMENT DATA BASE SHEET Facility: PSL Unit: 02 Component: V2167 Associates Comp Type VL Comp Sub Type: CC Equipment Names CHECK VALVE ON CHARGING PUMP 2C DISCHARGE System CHEMICAL AND VOLUME CONTROL SY Code: 02 Location Desc:
Location Code: RAB/7/N-RA2/E-RAE Startup Sys Code: 036A RMP Reqd Y IST Reqd: Y NPRDS: Y EQ Reqd N GENS Major Codes UG50 Safety Class: GEMS Major Mfgra RCF Q-Basis: GEMS ID Code: 67 Q-Group: B GEMS Minor Code: Q-Level: GEMS Minor Mfgr SCEW: N/A Account Code: 530 PCM: 009-293 Equipment Mfgr ANCHOR DARLING VALVE CO SPEER: N/A Model No: 2"-W9223870 Surv Maint Note: N/A Engr Data Ref: Doc Pac: N/A Remarks: N/A Seismic Cat I EQ Comp Tag: N/A EQ Rev: N/A Purchase Order (s) : CE-15 (9 402126) Drawing (s) : 2998-A-051 2998-C-124 CH-78 2998-G-195 8770-12709 2998-G-078 122 Tach Manual (s) : 8770-12712 Procedure (s) : Note (s) : LMD
_ _ _ _ _ _ _ _ _ ._ - . ..m - . _. ~ . . ~ _ _ _, i ~ Component: V2167 Sys: 02 Associates Train: Fac PSL Unit: 02 Name: CHECK VALVE ON CHARGING PUMP 2C Work Type: Al Assign Priority: MASTER 5 WORK ORDER TASK DISCHARGE Location: RAB/7/N-RA2/E-RAE LMD: 1 96018092 01 )
)
4 D3fect/ Request: CHECK VALVE STICKING / FAILED OPEN ER/PWO: 62 / 7220 Chg Loc: Page: 2 ATTACEMENT A Note (s) : LMD 1 1 l l 1 1 9
OUTAGE s "" FSLFl Tomponent: DET #10
~
Sys: 64 Train: Fac: PSL Unit: 01 Associate Assign Priority: A4 MASTER Name: SFTY LIN PWR RANGE DET #10 (J-0 Work Type 1 WORK ORDER TASK
- 10) FOR UNCOMPENSATED ION CHAMBER ,
Location: RCB/18/S-8/W-3 LMD: 2 95031787 01r Defect / Request: REPLACE DET #9,10 AND CHNL A,B FOR ER/PWO: 63 / 4546 RPS Chg Loc: 915 PAGE 1 of 5 Ji-Detailed Explanation: l l NPRD f Work Request: 95018836 Def Tag: . % ,. Locs . Trbl/Brkdown: N LCO: Y Unit Cond Req: 6 NPRDS: Y Fail Date: 11/09/95 Times 15:08 Det: D Stat: A Symp: D Originator: GEBOM06 BOUSMAN G Date: 11/09/95 Dept: IC Approve By: GEBOM06 BOUSMAN G Date: 11/09/95 Task Determination Data: IST Required : N NCR/CR : N/A Safety Class: SR PMT Required : Y PCM : N/A Q Group : 1E 10 CFR 50.49 : N EQ Doc Pkg : N/A Assign To : CC 1 Reg Guide 1.97 : N Seismic Cat : I Est M/H : 16.00 ASME XI(ISI) Reqd : N Scaffold Req : N Crew Qty : 2 Security Clearance: N Fire Prot Req: N Insul Rem : N Clearance Required: N Clearance No : i-uw-ztr 6*s) RWP Required: Y RWP No t naz RCA M/HP Y:"*" " L2: L3:
; QC Requirements: QC Required : Y S t'f( f r x 4(, WYI. 'b More:
=============================================================================
Work Order Task
Description:
SEE PAGE ': FOR TASK DESCRIPTION. More: Y
=============================================================================
Planned By : GEBOM06 BOUSMAN G Date: 05/17/96 Pkg Appr By : GEBOM06 BOUSMAN G Date: 05/17/96 Time: 19:27 QC Approval : RWB0QIC BROWN RW Date: 05/17/96
********************** OPERATIONS APPROVAL START ***********************
A,~9 *
- NPS Start Permission: LCO (Y7N) : M Start Date/ Time : c-2.5:56 // /deo L *
* * *irT%
6 s --
/ot
**. <Fe *(o*lVSha *//cc)
NPS Completion Notifs .
/_ Major Failure:
, Compl. Date/ Time: 7/(,/e/ . / / C 74 Major Action :
l Deficiency Tag Removed (Y/N)i A/kl4 s
+ w w + sq.n ~<y . , q, y b J
. . - _ . _ - .= _ _ _. . . . .
Component: DET #10 Sys: 64 Train: Fac PSL Units 01 Associate: Assign Priority: A4 MASTER Name:SFTY LIN PWR RANGE DET #10 (J-0 Work Type 1 WORK ORDER TASK
- 10) FOR UNCOMPENSATED ION CHAMBER Location: RCB/18/S-8/M-3 LMD: 2 95031787 01 Defect / Request: REPLACE DET #9,10 AND CHNL A,B FOR ER/PWO: 63 / 4546 ,
RPS .Chg loc: 915 , PAGE 2 of 5 Continuation of Task
Description:
COMPLY WITH ADM 0010432 fib.3/ FIG.4 AS REQUIRED. ! l REPLACE DETECTORS LISTkD PER 1-IMP 64.01. I BET #9 LINEAR PWR RANGE DET (J-090) FOR UNCOMPENSATED IGN CHAMBER TO
- RRS CAB 1.
DET #10 SFTY LIN PWR RANGE DET #10 (J-010) FOR UNCOMPENSATED ION
. CHAMBER FOR RRS CAB 2.
DET #5 LINEAR PWR RANGE DETECTOR FOR RPS CAB A. BET #6 LINEAR PWR RANGE DETECTOR FOR RPS CAB B. kNSURE SEISMIC INSTRUMENTS ARE RESTORED TO AS FOUND. PERFORM PMT PER QI-11-4, APPENDIX B. bOCUMENT WORK PERFORMED ON JOURNEYMANS WORK REPORT. CONNELL O s .;
i l l Component: DET #10 Sys: 64 Train: Fac: PSL Unit: 01 ! Associates Assign Priority: A4 MASTER Name SFTY LIN PWR RANGE DET #10 (J- Work Type: 1 WORK ORDER TASK t " '. 10) FOR UNCOMPENSATED ION CHAMBER Location: RCB/18/S-8/W-3 LMD: 2 95031787 01 Defect / Request: REPLACE DET #9,10 AND CHNL A,B FOR ER/PWO: 63 / 4546 RPS Chg loc: 915 PAGE 3 of 5
- JOURNEYMANS WORK REPORT Actual Start Date
- Time: Actual Completion Date: Time S'~ .3 C-y G, 2acopy ? g /go b Note: Journeyman shall sign and date text after their entries.
Trouble Found: This Section is NOT Applicable for PMs or other planned jobs EJn %, L _ y - TEST E@lP. l h0<A
$~- 2.S'- 1 C. A 0b
. A 6(3 Uk, $ b[
net l on. ' DRI l
, Work Performed:kt d de e8f 12%th ;rridA b fh4rf b W O/ M J4f/5 9 0 " 9. % OF TC l 'L o o t od D t4(ther 5" 9(,17/ 4 MAO 5" 9L n n. a < d La u w.alste pe;u wrw,aw wuc. s Irrin G4/2-
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~
2/4M / y o 7,7414t,.'
1
~
Component: DET #10 Sys: 64 Train: Fac: PSL Unit: 01 Associate Assign Priority: A4 MASTER Name:SFTY LIN PWR RANGE DET #10 (J-0 Work Type: 1 WORK ORDER TASK
- 10) FOR UNCOMPENSATED ION CHAMBER
Location: RCB/18/C-8/W-3 LMD: 2 95031787 01 Defect / Request: REPLACE DET #9,10 AND CENL A,B FOR ER/PWO: 63 / 4546 RPS Chg loc: 915 PAGE 4 of 5 Continuation of Trouble Found/ Work Performed:
Tn :-^A~ $45 .%se.x-a ibee~ kn. 9 s L%~~. Y e.s % C ' A s%41 hdashes A kl a. h u>M J r+c %ew i a n" ADsK ba,i S- ' 1 ) 5 d /fA nen T + c 3 c e l. l i
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~
Continued on Additidnal Sheets: (D N
t i i a 1 Component DGT *I* Sys: . W Train: i Associate: Fac: ELL.,_ Unre oI Assign Prienty: A4 MASTER Name: SPVf LIA N E. (W G& iXT . Work Type: 1 WORK ORDER TASK l *tG o 3 t7 F1 et Locanon: R Cd / / P / 5- ?"/t s ~J LMD: "L Detect /Recesst f.wWs 06T % i o #4ao cla,JL AB fort (Lff . (M St.tre C u M a ' ER/PWO: 4 ") /WWo i A'\ Ch9 LOC: 't R $ Pagefa. Of f Joumeyman's Work Reoort i i i Work / Repairs Perforrned (cont.): A11 fools R,*g d c4 6 W V e luk M4 % r.cA4. f/11/94 (
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conunueo on Addinonal Sheets: YN / 7] [g j k 4
REVISION NO.: PROCEDURE TITLE: PAGE:
. 2 CONTROL OF PLANT WORK ORDERS PROCEDURE NO.: 69 Of 82 ADMINISTRATIVE PROCEDURE ADM-0010432 ST. LUCIE PLANT APPENDIX G
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, 3 CONTROL OF PLANT WORK ORDERS {
! PROCEDURE NO.: 70 of 83 l ADMINISTRATIVE PROCEDURE I ADM-0010432 ST. LUCIE PLANT ! APPENDIX G NPWO SCOPE CHANGE 4 NPWO SCOPE CHANGE
- ST. LUCIE UNIT NPWO SPEC ER WORK ORDER NUMBER Pl. ANT 0l 454G 63 9503n1n 01
- DATE
- 4.g.g SCOPE CHANGE NUMBER: ORIGINATOR:
1 ME: 062.6 @Pm sc 2 SCOPE CHANGE INSTRUCTIONS: 7k # I REP 4lR DamDGGD finn (ICMAL CARLE Od D6T #4 AA R*Y t.ua A noa4 h w us t.4 r n.s . 8'4**t . l FGTJ4 4 vsc conaterot sc* 0039St*3-I W vs c fotDGE Jc' 0 0 2.11 inf - l M 5 mms A 5 FleN JdLMA MS *00751b W 1 ADDITIONAL RETEST RESULTING FROM THIS SCOPE CHANGE: tr1ccGan crurer (nun. re httu> D 1000V ? lytD"dl. AcutitlBL4 Juts to to t;rowJO 9 soV ? iv re' JL Au 8f fARLs
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. Associate Assign Priority: A4 MASTER , Name: SFTY LIN PWR RANGE DET #10 (J-0 Work Type: 1 WORK ORDER TASK I
- 10) FOR UNCOMPENSATED ION CHAMBER
-Location: RCB/18/S-8/M LMD: 3 95031787 01 i
Defect / Request: RETLACE DET #9,10 AND CHNL A,B FOR ER/PWO: 63 / 4546 RPS Chg loc: 915 PAGE 5 of 5 Component List: Comp: DET #9 Assoc: Sys: 64 i Name: SFTY LIN PWR RANGE DET #9 (J-009) FOR UNCOMPENSATED ION CHAMBER Loc: RCB/18/N-8/E-3 Sfty-Cls Q-Grp 50.49 1.97 FPR PMT IST SEIS DOC NCR PCM ASME SR 1E N N N I N/A Comm i j l Comps DET #10 . Assoc: Sys: 64 3 Names SFTY LIN PWR RANGE DET #10 (J-010) FOR UNCOMPENSATED ION CHAMBER
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REVISION NO.: PROCEDURE m PAGE: 2 CONTROL OF PLANT WORK ORDERS PROCEDURE No.: 81 Of 02 ADMINISTRATIVE PROCEDURE ADM-0010432 ST. LUCIE PLANT FIGURE 4 TROUBI *BHOOTING/ MAINTENANCE ALTERATION CONTROL SHEET NPWO No. YMS ER 6} UNIT C/ DESCRIPTION / LOCATION IMPt.EMENTATION RESTORATION BY IV* BY ly-
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{~ Page 1 of 6 FLORIDA POWER & LIGHT COMPANY ! .- ST. LUCIE PLANT - i I & C PROCEDURE NO. 1200062 PSL
- . REVISION 5 8" n
$ 9 5
1.0 TITLE
5o l4 l UNCOMPENSATED ION CHAMBER ACCEPTANCE TEST PROCEDuftE PRODUCTION 2.0 REVIEW AND APPROVAL: Reviewed by J. Cooper I & C Engineer Auaust 2,1976 Approved by A. J. Collier I & C Supervisor Auaust 2,1976
. Revision _5_ Reviewed by Facility Review Group /-J2 19 9/
Approved by G. J. Boissy Plant Manager d-/2 19 9/
3.0 PURPOSE
This procedure provides instructions for acceptance testing of the excore uncompensated ion chamber to be performed upon receipt, prior to and following installation. 4.0 PRECAUTIONS AND LIMITS: 4.1 Perform test in a clean / dry area and maintain cleanliness throughout the test. 4.2 Do not exceed 1000 VDC applied voltage between HV center conductor to case and 100 VDC between the bottom / top signal to case. 4.3 When disconnected, the connector should be protected to keep moisture, dust and other foreign matter out of the connector. 4.4 Exercise extreme care when handling detector cables and connectors. Do not allow cables to exceed a minimum bend radius of 6 inches. 4.5 When measuring extremely small currents or high resistances, care must be taken to . ensure the test equipment is electrically isolated to prevent ground loops. Isolation plugs should be utilized and insulating material should be placed under each piece of test equipment. S__,_ OPS
- DATE oOCT enoceoune_
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Page 2 of 6
. ST. LUCIE PLANT I & C PROCEDURE NO. 1200062, REVISION 5 UNCOMPENSATED ION CHAMBER ACCEPTANCE TEST 5.0 RELATED SYSTEM STATU_S:
- None
6.0 REFERENCES
- 6.1 Detector Technical Manual 8770-4873 (Unit 1) 2998-15651 (Unit 2) 7.0 RECORDS REQUIRED
- ,
l Maintain Table A and B records in accordance with Ol-17-PR/PSL-1 and Tech Spec Paragraph 6.10.1. /R5 8.0 MATERIALS AND EQUIPMENT REQUIRED: 8.1 Megohmeter HP 4329A or equivalent. /R5 i 8.2 Impedance Bridge GR 1650 or equivalent. I 8.3 Test cables with coaxial connectors. 8.4 Cleaning materials (if required to clean connectors) j Comply with requirements of AP 0010501 " Hazardous Chemicals". /R5 l i i i ., ...-. 1
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l' Page 3 of 6 )
- I
^ ST. LUCIE PLANT l & C PROCEDURE NO. 1200062, REVISION 5 M! COMPENSATED ION CHAMBER ACCEPTANCE TEST 9.0 DETAILED PilOCEDURE: (PRIOR TO INSTALL.ATION) ! NOTE i Careful handl!ng of the assembly is a must. Intemal damage could be caused a by droppirig or bumping. Cables and connectors'are also fragile and should i not be stepped on or kinked.
- /R5
! 9.1 ' Examine the detector / cable assembly for physical damage. ] 9.2 Record detector type and serial number on Table A. 1 5 9.3 Check the insulation resistance of the coaxial test lead and record in Table A. l .I l 9.4 Connect th'. megohmeter to the top signal lead, set the voltage to 100 V, j ! measure the insulation resistance of the top signal to case and record on ! Table A. I l
- 9.5 Repeat step 9.4 for the bottom signal cable.
- 9.6 Connect the megohmeter to the HV cable, set the voltage to 1000 V l l (+ HV to center conductor), measure the insulation resistance of the HV cable
! to case, and record on Table A. i i l j 9.7 Connect the megohmeter to the HV cable and top signal cable j j (center conductors), set the voltage to 1000 V, measure the insulation l resistance, and record on Table A. /R5 , l 9.8 Repeat step 9.7 for HV to bottom signal. ; l 9.9 Connect the impedance bridge to the HV cable, measure'the capacitance l between HV and case and record on Table A. Short the conductors and j , cables not in test. i
- 9.10 Repeat step 9.9 for top signal to case.
[ 9.11 Repeat ste;) 9.9 for bottom signal to case. i 9.12 Compare the data on Table A with the manufacturer's acceptance test data and review Table A to ensure all values are above specified minimums and
!l sign Table A.
9.13 If the detector is not to be installed, repack the detector assembly in the i shipping crate and store in a humidity controlled area. 4 i 1
l Pago 4 of u
. ST. LUCIE PLANT l 1 & C PROCEDURE NO. 1200062, REVISION 5 i UNCOMPENSATED ION CHAMBER ACCEPTANCE TEST 9.0 DETAILED PROCEDU.RE: (continued) l NOTE
- Perform the following steps only if this test is to be performed following installation.
(FOLLOWING INSTALLATION) /R5 j ~ 9.14 Examine the cable connectors for damage, dirt, etc. l 9.15 Record Detector Type, Serial No., and the Holder No. or Channel Letter Designator in which the Detector is installed. (i.e. Holder #1 is Wide Range , Channel A). 9.16 Check the insulation resistance of the coaxial test lead and record in Table B. 9.17 Connect the megohmeter to the top signal lead, set the voltage to 100 V, measure the insulation resistance of tne top signal to case and record on ; Table B. l 9.18 Repeat Step 9.17 for the bottom signal cable. 9.19 Connect the megohmeter to the HV cable, . set the voltage to 500 V (+ HV to center conductor), measure the insulation resistance of the HV cable to case, and record on Table B. ;
- l 9.20 Connect the megohmeter to the HV cable and top signal cable (center conductors), set the voltage 500 V, measure the insulation resistance, and record on Table B.
9.21 Repeat Step 9.20 for HV to bottom signal. . 9.22 Connect the impedance bridge to the HV cable, measure the capacitance between HV and case and record on Table B. Short the conductors and cables not in test. 9.23 Repeat Step 9.22 for top signal to case. 9.24 Repeat Step 9.22 for bottom signal to case. 9.25 Compare the data on Table B with that of Table A, any major deviations should be investigated prior to mating the detector cables with the detector junction box cables.
Pago 5 of 6 ! i ST. LUCIE PLANT
.1 & C PROCEDURE NO. 1200062, REVISION 5
'J_NCOMPENSATED ION CHAMBER ACCEPTANCE TEST
, TABLE A C/ Ms "O &ffj Detector Type tt/c-Serial No. %l 11 b Holder No. Vf L *L3739 We01-G MEASURED MINIMUM STEP VALUE VALUE 9.3 Test lead insulation resistance I n Io'I O 10'80 9.4 Insulation resistance, top signal to case 7*## n 10"O 9.5 Insulation resistance, bottom signal to case I f y to' n' 10"O 9.6 Insulation resistance, HV to case n 10"O
$$/o" 9.7 Insulation resistance, HV to top signal oo n 10"n 9.8 Insulation resistance, HV to bottom signal oo n 10"n 9.9 Capacitance HV to case 99 m pf -
9.10 Capacitance top signal to case 3 3 o 0 pf -
. 9.11 Capacitance bottom signal to case 3oo o pf -
Test Results and Comments: Test Eouioment Used
~
Megohmeter No. Impedance Bridge No. ER- 0% (SH(s1.s-1.s) (skp 'ia- 1.id Verified by A Emen bu,b Date f / 2f / 74 1 Reviewed by 4 h Date d / 2[/'7I# 3 4
. . - . . . . - . -. - =..~ - .. -- . -. .- _ _ .
f Pegs 6 of 6 ST. LUCIE PLANT 1 & C PROCEDURE NO. 1200062, REVISION 5 9
- UNCOMPENSATED ION CHAMBER ACCEPTANCE TEST
. TABLE B gg g
*B."M RPS
, Detector Type 64 T C.- j Serial No. %I'7 I fo Holder No v t. 1- 37 fr 7 (#2'f846 MEASURED MINIMUM ) STEP VALUE VALUE 9.16 Test lead insulation resistance V /D Q 10'*n i ) 9.17 Insulation resistance, top signal to case Y W * ## on 10"O 9.18 Insulation resistance, bottom signal to case f 1 tfx ~ n' 10"O 9.19 Insulation resistance, HV to case 2 W'# n 10"O f 9.20 Insulation resistance, HV to top signal Fr ( * " n 10"n i 9.21 Insulation resistance, HV to bottom signal Y. tx to" n 10"O 9.22 Capacitance HV to case VFro pf - 9.23 Capacitance top signal to case 72. So pg _ 9.24 Capacitance bottom signal to case *STO pf - Test Results and Comments: Test Eauipment Used Megohmeter No. M-I/3
- . Impedance Bridge No. E ~ 0%
Verified by 8dh Date 6 / 08 /76 Reviewed b
- V Date 8/ oV /f4 en aa s.1 '
4 5
i Pago 5 of 6 l ST. LUCIE PLANT I & C PROCEDURE NO. 1200062 REVISION 5 UNCOMPENSATED ION CHAMBER ACCEPTANCE TEST
. TABLE A l Detector Type Id i C -
Serial No. %I'l I 7 l Holder No. WL t 37 ff 7 (JE.LL*7 MEASURED MINIMUM - STEP VALUE VALUE 9.3 Test lead insulation resistance (Syle n 10 zin 9.4 Insulation resistance, top signal to case '-I T % ' D" n 10"O 9.5 Insulation resistance, bottom signal to case 'l % 10 " n' 10"O 9.6 Insulation resistance, HV to case t."LY'*" n 10"O 9.7 Insulation resistance, HV to top signal oc n 10"O ) 9.8 Insulation resistance, HV to bottom signal m n 10"n 9.9 Capacitance HV to case y 9.o o pf - l 9.10 Capacitance top signal to case .733 o pf - 9.11 Capacitance bottom signal to case Jeoo pf - Test Results and Comments: l
, Test Eouipment Used Megohmeter No. P5 L-16 Impedance Bridge No. PR- 0%
(stvs m.D (11-,.,,) Verified by /3e<wn b4 Date rf w/ n Reviewed by b vN_ , Date S /25'/A
&WM A
f Pcg3 6 of 6 ST. LUCIE PLANT l & C PROCEDURE NO. 1200062, REVISION 5 UNCOMPENSATED ION CHAMBER ACCEPTANCE TEST TABLE B l 4 Detector Type C/2.'. Serial No. 76/7/7 Holder No. WL 2 3 787 wa-## 7 Y t , ii MEASURED MINIMUM 1 STEP VALUE VALUE l 1 9.16 Test lead insulation resistance " /*o G n 10'80 l 9.17 Insulation resistcnce, top signal to case -> /o G Q 10"n 9.18 Insulation resistance, bottom signal to case /oG Q 10"O 9.19 Insulation resistance, HV to case /Z G n 10"n 9.20 Insulation resistance, HV to top signal /26 O 10"n 9.21 Insulation resistance, HV to bottom signal /2 & Q 10"O 9.22 Capacitance HV to case Seeo pf --- 9.23 Capa'citance top signal to case J 780 pf ---- 9.24 Capacitance bottom signal to case 2 /*o pf --- Test Results and Comments: . Test Eauipment Used Megohmeter No. As L - fd Impedance Bridge No. A< l - 036
/. Verified by T E .7 ebb Date 4 /_M_/ F6 -
Reviewed by - Date 7 / 7 /94 L - 1 I
a Paga 5 of 6 ST. LUCIE PLANT I & C PROCEDURE NO. 1200062. REVISION 5 UNCOMPENSATED ION CHAMBER ACCEPTANCE TEST
. TABLE A Detector Type /g 7~ (8 Serial No. 4 /o / 7 d. /
Holder No. u) 2.23777 MEASURED MINIMUM STEP VALUE VALUE 9.3 Test lead insulation resistance 1012 9 8 X/O 'O 9.4 Insulation resistarce, top signal to case ggjo'kn 10"O 9.5 Insulation resistance, bottom signal to case 7 y, /[n 10"O 11 9.6 Insulation resistance, HV_ to case 1,5 K / o n 10"O 9.7 Insulation resistance, HV to top signal @ n 10"n 9.8 insulation resistance, HV to bottom signal @n 10"O 9.9 Capacitance HV to case 4 7 g a pf -- 9.10 Capacitance top signal to case 33gg pf - 9.11 Capacitance bottom signal to case Pf ~~~ AfCO Test Results and Comments: Test Eauipment Used
. - , . . 7
~ . , . . ,
k N-. .. S iib.O. NM' ! U ,',~~i th, ,,Cl i Megohmeter No. Psf R /3
? ws nr:5.tm .w.r o- : .e ,7 t. : p . .. + / .! v:z n a m m r.o w .u . .m ../.:.
- c:r.s:..l Impedance Bridge No._[_$ L 03 4 f R.2DA PnwhR ." m uGhT ca. t 1 ST. ur.E Yu'.Xr ;
(at:nymneo 6 -/'l '9d ;NmAt.O ?D Verified by O[O Date lo / /4/ [5 Reviewed by $ Date @ /cW /b L y p AfD .L as. i
. . .-. .- .. . . - .-. - = . -_ . . . - -_- - -
- Paga 5 of 6 ST. LUCIE PLANT I & C PROCEDURE NO. 1200062, REVISION 5
~ UNCOMPENSATED ION CHAMBER ACCEPTANCE TEST
.i ,
. TABLE A e
d Detector Type o T 6. Serial No. 4 (o / 7 2. A Holder No. u ) 423777 MEASURED MINIMUM STEP VALUE VALUE 9.3 Test lead insulation resistance 3 y /p n 10 2 9 9.4 Insulation resistance, top signal to case j y fg dO 10"O 9.5 Insulation resistance, bottom signal to case p g /p'3 n' 10"O 9.6 Insulation resistance, HV to case 3y /o #n 10"O 9.7 Insulation resistance, HV to top signal g O 10"O 9.8 Insulation resistance, HV to bottom signal QO n 10"O 9.9 Capacitance HV to case Pf --- 49oo 9.10 Capacitance top signal to case ygooP f --- 9.11 Capacitance bottom signal to case y9 p g pf -- Test Results and Comments.
= _ _ . _ , Test Eouloment Used ECff INEOR[fK~;09 0. N '.' $ Megohmeter No. k 1> 4 ff / 3 w j
} em:.rucswemnrc.
i : scc.s.u:, ,;.. . :r. .. e.-- i e-W '..~.;;.- 3
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i Impedance Bridge No.k.5 l- d 3 [3 n.an::i m;n ;
)
LD:\'M.:r';ED-..--. ~ In
.. '_ ,,_- / l -96nm.a (b @ Ol
_ _a Verified by 69O 4 [ Date l, / /# / 9 [o Date 7 / 0 /M
~
Reviewed by , m i
Paga 6 of 6 i ST. LUCIE PLANT I & C PROCEDURE NO. 1200062 REVISION 5-UNCOMPENSATED ION CHAMBER ACCEPTANCE TEST I TABLE B Detector Type /J T C_ l Serial No. Q [0 /78l Holder No /J) L jl 3 7 7 7 MEASURED MINIMUM STEP VALUE VALUE 9.16 Test lead insulation resistance n 10' n l 7 9.17 Insulation resistance, top signal to case n 10"n 9.18 Insulation resistance, bottom signal to case '//Jgk n~ 10"n cd 9.19 Insulation resistance, HV to case i n 10"O ! 9.20 Insulation resistance, HV to top signal n 10"O 9.21 Insulation resistance, HV to bottom signal n 10"O ! 9.22 Capacitance HV to case pf --
)
9.23 Capacitance top signaf to case pf -- 9.24 Capacitance bottom signal to case. pf ---
.. l Test Results and Comments: '
. ~ = - - _ _ _ _ . _ _ -
Test Eouioment Used 1
}
{ pgi,{ ' ,'y {. ". F*f.;: r. -- Megohmeter No. Y* I '31( g ww.vn.w liEN'@li'O. i '. : cx: s
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- .. . ' '3 ' '1, '.C. '..; y'.,. t f: g l's,<
. . iiiT.
R.cRICA i '.' s"....?l..'. Impedance Bridge No.
- .: O. '
ET. :.eG2 Gl.? 'r D-lT 2/.$. !$UN , Verified by # A Date / / fs i Reviewed by' ' Date' / / e
Pagh 6 of 6 ST. LUCIE PLANT I & C PROCEDURE NO. 1200062, REVISION 5 UNCOMPENSATED ION CHAMBER ACCEPTANCE TEST (
. TABLE B DetectorType a T &
Serial No. @ /o / 7 d. 2 -- Holder No. a) L 2 3 7 8 7 MEASURED MINIMUM STEP VALUE VALUE 9.16 Test lead insulation resistance A/ O 10:29 O y' 9.17 Insulation resistance, top signal to case I O 10"O
. 9.18 Insulation resistance, bottom signal to case -
Q 10"O 9.19 Insulation resistance, HV to case n 10"n- l
'A' 9.20 Insulation resistance, HV to top signal '
O 10"n 9.21 Insulation resistance, HV to bottom signal eQ 10"O 9.22 Capacitance HV to case bfp --- l l 9.23 Capacitance top signal to case pf -- l 9.24 Capacitance bottom signal to case pf - l Test Results and Comments: j Test Eouioment Used i ,es n :f. g ' f - n tt.... . . . . , - m o.s mm-
. . . _ n s- t y
- b.fNr. j Megohmeter No. f
!N.h[I:$b1 '
DYn: h ': G,; ' ' . .:;. T,'f 3. i f' :st. '.e ,c ! ear j Impedance Bridge No. s hamm.r.:m.a. (p ./.y .-9 L !!;m;L@8_Ql V \
~_ .-.___._ =
Verified by ,_ Date / // l
)
Reviewed by / - Date / / 1
S 1 OPS JEesoceouse R@WA NWM & UG i *
) DOCN 1-lMP-64.01 eSt.
' SYS 3 /
coue couetereo ST. LUCIE PLANT 2 UNIT NO.1 D( eaoctouneenco PREVIOUSLYISSUED AS 1240064 1-lMP-64.01 REVISION ~ 3
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l 1 I y - -- ii / ii ii ii ii N ii l j.__ EXCORE NEUTRON DETECTORS REMOVAL AND INSTALLATION INSTRUMENT & CONTROL PROCEDURE REVISION REVIEWED BY APPROVED BY DATE FRG ON 0 9/17/91 G. J Goissy 9/24/91 Plant General Manager i 3 6/18/96 _ _ .._ _ J. Scarola 6/18/96 l .EO?[N@NMD8N ONLY 1, l This document is not controlled. Before use, Responsible Department: instrument & Control l ver:ry informaton wrth a controlled document. [n.ut vtmnto 6 20-9C mmnfF __ BMG 6/19/96
REVISION NO.: PROCEDURE TTTLE: PAGE: 3 EXCORE NEUTRON DETECTORS PROCEDURE NO.: REMOVAL AND INSTALLATION
)~ INSTRUMENT & CONTROL PROCEDURE
, 1-lMP-64.01 ST. LUCIE UNIT 1 1
1.0 TITLE
EXCORE NEUTRON DETECTORS REMOVAL AND INSTALLATION
2.0 PURPOSE
This procedure provides instructions for the removal and installation of the Wide Range, Linear Range, Control Channel and Post Accident excore neutron detectors.
3.0 REFERENCES
3.1 Drawings
- 1. 8770-G-187 Neutron Detectors Location.
- 2. 8770-G-188 Sheet 1, #1 & #4 Neutron Detector Fixtures.
- 3. 8770-G-188 Sheet 2, #11 & #3 Neutron Detector Fixtures.
) 4. 8770-G-189 Sheet 1, #10 Neutron Detector Lateral Positioner.
- 5. 8770-G-189 Sheet 2, #2 & #6 Neutron Detector Lateral Positioners.
- 6. 8770-G-189 Sheet 3, #7 Neutron Detector Lateral Positioner.
- 7. 8770-G-189 Sheet 4, #9, #8 & #12 Neutron Detector Swing ,
Positioners. l l
- 8. 8770-G-189 Sheet 5, #5 & #2 Neutron Detector Swing Positioners.
- 9. 8770-G-190 Sheet 1, #10 Neutron Detector Lateral Positioners
! Details.
- 10. 8770-G-190 Sheet 2, #6 Neutron Detector Lateral Positioner l Details. ;
- 11. 8770-G-190 Sheet 3, #7 Neutron Detector Lateral Positioner
. Details. I
- 12. 8770-G-190 Sheet 4, #5, #9 & #2 Neutron Detector Swing Positioner Details.
k.
REVISION NO.: PROCEDURE TITLE: PAGE: 3 EXCORE NEUTRON DETECTORS PROCEDURE NO.: REMOVAL AND INSTALLATION
) INSTRUMENT & CONTROL PROCEDURE 1 -IMP-64.01 ST. LUCIE UNIT 1
3.0 REFERENCES
- (continued) 3.1 (continued) 13 8770-G-190 Sheet 5, #8 & #12 Neutron Detector Swing Positioner Details.
- 14. FSB-8770-M-313, 314 Indexing Pin.
- 15. FSB-8770-M-333, 334 Indexing Pin Details.
4.0 PREREQUISITES
4.1 The reactor is shutdown with the reactor head in place. 4.2 A Radiation Work Permit has been issued to perform this procedure. Removal and installation of detectors is performed in the refueling cavity near the reactor flange, in the detector tunnel and under the reactor behind the blast dampers. Prior to start of work, a briefing between Health Physics and the l&C Department work crew must be l
) performed to coordinate efforts to limit radiation exposures.
4.3 The nuclear instrument channel to be worked has been deenergized with an equipment clearance order issued. 4.4 A clean laydown area has been prepared in the vicinity of the refueling cavity on the operating deck. 4.5 Communications has been established between personnel above the detector well and personnel in the detector tunnel. 4.6 The polar or jib crane is available and manned to pull the detector from I its support assembly and place it in the laydown area. t 4.7 Reactor Engineering Department has been notified of Special Nuclear Material movement. 4.8 I&C Procedure 1200060, ' Fission Chamber Acceptance Test" or I&C Procedure 1200062, ' Uncompensated lon Chamber Acceptance Test", whichever is applicable has been performed prior to installation. i I g l l i
REVISION NO.: PROCEDURE TITLE: PAGE: 3 EXCORE NEUTRON DETECTORS PROCEDURE NO.: REMOVAL AND INSTALLATION 3 INSTRUMENT & CONTROL PROCEDURE 1-lMP-64.01 ST. LUCIE UNIT 1 5.0 PRECAUTIONS / LIMITATIONS: 5.1 Minimize physical contact with the irradiated detector assemblies to keep radiation exposure as low as reasonably achievable. 5.2 Use caution in handling the detector assemblies. The housings are made of reactor grade aluminum which is very soft and can easily be dented or marred. The detectors utilize ceramic insulators which could I be damaged if the detector receives a severe blow. 5.3 Use caution when raising or lowering the detector assembly in order to
. detect signs of binding in the support housing or binding of the cables.
5.4 The detector cables are extremely fragile. Care must be taken to ! prevent exceeding the cable minimum bend radius of 10 inches, j 5.5 Extreme care should be exercised when recording positions of the swing and lateral positioners to prevent mispositioning of detector support assemblies. Improper positioning would cause miscalibration of the neutron instrumentation resulting in inaccurate reactor power level l
) indications. l 6.0 RECORDS REOUIRED:
6.1 Data Sheet #1 shall be maintained in the plant files in accordance with Ol 17-PR/PSL-1, " Quality Assurance Records." 6.2 Special Nuclear Materials inventory must be updated if fission chamber configuration is modified. 7.0 MATERIALS AND EQUIPMENT REOUIRED: 7.1 Isopropyl alcohol and lint free rags. 7.2 Chain fall and rigging straps. 7.3 Approximately 100 feet of nylon line.
. 7.4 Raychem heat shrink WCSF 300/1200 & 500/1500.
7.5 Heatgun, knife, slip-joint pliers, assorted wrenches and screwdrivers and a 50 foot tape measure.
REVISION NO.: i PROCEDURE TITLE: PAGE: 3 EXCORE NEUTRON DETECTORS PROceDuRa nO.: REMOVAL AND INSTALLATION i
) . INSTRUMENT & CONTROL PROCEDURE !
1-lMP-64.01 ST. LUCIE UNIT 1 ! 7.0 MATERIALS AND EQUIPMENT REQUIRED: (continued) 7e6 Two specially designed detector holder 3'6" reach-rod tools, 1 T-handled 5/16" reach-rod and 1 standard handwheel 3/4" reach-rod stored in the l&C hot shop. These tools are only necessary for detect ! assemblies in swing and lateral positioners. l 2 i k i e I d l e e
l REVISION NO.: PROCEDURE TITLE: PAGE: 3 EXCORE NEUTRON DETECTORS PROCEDURE NO.: REMOVAL AND INSTALLATION j INSTRUMENT & CONTROL PROCEDURE , 1-lMP-64.01 ST. LUCIE UNIT 1 ' l B.0 INSTRUCTIONS: 8.1 Removal of FlXED holder detectors #1 MA Wide Range Channel, #3 ' MC Wide Range Channel, #4 MD Wide Range Channel and #11 SB Post Accident Channel is as follows:
- 1. Ensure the nuclear instrumentation channel to be worked is de-energized and an equipment clearance order is completed.
- 2. At the detector junction box located in the nuclear instrumentation l detector tunnel, disconnect the detector cables.
- 4 j 3. Cap or cover the cable connector ends. !
- 4. Tape one end of the nylon line to the detector cables approximately I one foot above the connectors.
i
- 5. Secure the other end of the line to the de'tector junction box. This line'will serve as a pull and guide cord when re-installing the detector assembly.
)
- 6. Detach the hoisting cable from the storage eyebolt.
- 7. Attach the chainfall hook or rigging to the detector hoisting cable.
4
- CAUTION j Be especially observant to detect signs of binding while removing the l detector if the detector is binding, it may be freed by rotating the detector assembly slightly and/or Jockeying the hoisting cable until the detector assembly becomes free. This must be done gently to avoid damage to'the ceramic insulators. A man under the reactor vessel may be needed to guide the detector cable.
4
- 8. Ensure the hoisting cable is plumb and slowly lift the detector and cables from the holder.
. 9. Once the detector assembly is clear of the holder stop the removal process. Health Physics should take area surveys, check for contamination of exterior surfaces and provide authorization for continuation of detector removal.
! i
- - _ . _ . - - . -- ._ - _ . = - - . . .
REVISloN No.: PROCEDURE TrTLE: PAGE: 3 EXCORE NEUTRON DETECTORS PROCEDURE No.: REMOVAL AND INSTALLATION
] 1-lMP-64.01 INSTRUMENT & CONTROL PROCEDURE ST. LUCIE UNIT 1 8.0 _ INSTRUCTIONS: (continued) 8.1 (continued) I
- 10. Slowly raise the detector to the laydown area.
11. Tie off the nylon line if removal from the detector assembly is required. If the line is lost, reinstallation of the detector will be l extremely more difficult. '
- 12. Consun with Health Physics for handling and disposal of removed materials. Fission chambers are classified as Special Nuclear Material and must be accounted for and inventory records updated.
B.2 i Removal of LATERAL holder detectors #6 MB Linear Range Channel,
#7 MC Linear Range Channel and #10 MB' Control Channel is as follows:
1. Ensure the nuclear instrumentation channel to be worked is de-energized and an equipment clearance order is completed.
- 2. At the detector junction box located in the nuclear instrumentation I detector tunnel, disconnect the detector cables.
- 3. Cap or cover the cable connector ends.
4. Tape one end of the nylon line to the detector cables approximately one foot above the connectors.
- 5. Secure the other end of the line to the detector junction box. This line will serve as a pull and guide cord when re-installating the detector assembly.
CAUTION Unscrew locking pin slowly. Do not over torque it on it's backseat.
. 6. Place Ine T-handled reach-rod over the 5/16' locking pin.
- 7. Tum the locking pin counter-clockwise to withdraw locking pin from i
the locking disc. Locking pin should backseat when it is fully [ withdrawn.
REVISION NO.: PF'OCEDURE TITLE: PAGE: 3 EXCORE NEUTRON DETECTORS PROCEDURE NO.: REMOVAL AND INSTALLATION INSTRUMENT & CONTROL PROCEDURE i
) 1-lMP-64.01 ST. LUCIE UNIT 1 h0 INSTRUCTIONS: (continued) 8.2 (continued)
- 8. Pull the spring loaded indexing pin outward.
- 9. Rotate the indexing pin one quarter tum clockwise and allow roll-pin to seat in the recess provided. The lateral positioner is now ready to be extended out to allow removal of the detector.
- 10. Place the handwheel reach-rod over the 3/4" drive shaft.
- 11. Observe the peinter on the spur gear position i.1dicator pointing to one of the scribe marks. This scribe mark indicates the operating position.
- 12. Begin to tum the handwheel clockwise to move the lateral positioner to the detector pulling position, while counting the number of tums out. /R3
) 13. Continue until the spur gear rotates to the second scribe mark indicating that the positioner is in the fully extended position. Use drawing 8770-G-190 Sheet p of 5 to verify. Record the number o tums on Data Sheet 1. h/A h Lof-1-/f 0.,6 ;f /R3 l
T 14. Sign Data Sheet #1 Verification Sheet.
- 15. Remove reach rods and store until re-installation of detector.
- 16. Detach the hoisting cable from the storage eyebolt.
- 17. Attach the chainfall hook or rigging to the detector hoisting cable.
CAUTION Be especially observant to detect signs of binding while removing the detector. If the detector is binding, it may be freed by rotating the detector assembly slightly and/or jockeying the hoisting cable until the detector assembly becomes free This must be done gently to avoid damage to the ceramic insulators. A man under the reactor vessel may be needed to guide the detector cable.
- 18. Ensure the hoisting cable is plumb and slowly lift the detector and cables from the holder.
REVISION NO.: PROCEDURE TITLE: PAGE: 3 EXCORE NEUTRON DETECTORS PROCEDURE NO.: REMOVAL AND INSTALLATION
,) INSTRUMENT & CONTROL PROCEDURE l
{. 1-lMP-64.01 ST. LUCIE UNIT 1 '
8.0 JNSTRUCTIONS
(continued) 8.2 (continued)
- 19. Once the detector assembly is clear of the holder, stop the removt process. Health Physics should take area surveys, check for contamination of exterior surfaces and provide authorization for continuation of detector removal.
- 20. Slowly raise the detector to the laydown area.
~
- 21. Tie off the nylon line if removal from the detector assembly is -
required. If the line is lost, reinstallation of the detector will be extremely more difficult.
- 22. Consult with Health Physics for handling and disposal of removed materials. Fission chambers are classified as Special Nuclear Material and must be accounted for and inventory records updated. l 1
8.3 Removal of SWING holder detectors #2 MB Wide Range I, #5
) MA Linear Range Channel, #8 MD Linear Range Channel MA I Control Channel and #12 SA Post Accident Channel is as ws: i NOTE 4
Channels #8 and #12 share a positioner.
- 1. Ensure the nuclear instrumentation channel to be worked is de-energized and an equipment clearance order is completed.
- 2. At the detector junction box located in the nuclear instrumentation detector tunnel, disconnect the detector cables.
\
- 3. Cap or cover the cable connector ends.
4
- 4. Tape one end of the nylon line to the detector cables approximately one foct above the connectors.
. 5. Secure the other end of the line to the detector junction box. This line will serve as a pull and guide cord when re-installing the detector assembly.
(, '
REVISION NO.: PROCEDURE TrTLE: PAGE: 3 EXCORE NEUTRON DETECTORS PROCEDURE NO.: REMOVAL AND INSTALLATION
) INSTRUMENT & CONTROL PROCEDURE i 1-lMP-64.01 ST. LUCIE UNIT 1
8.0 INSTRUCTIONS
(continued) 1 8.3 (continued) l I CAUTION I Unscrew locking pin slowly. Do not over torqu ) l 4
- 6. Place the T-handled reach-rod over the 5/16" locking pin.
- 7. Tum the locking pin counter-clockwise to withdraw locking pin from locking disc. Locking pin should backseat when it is fully withdrawn.
i 8. Pull the spring loaded indexing pin upward.
- . 9. Rotate the indexing pin one quarter tum counter-clockwise and i allow roll-pin to seat in the recess provided. The swing positioner is now ready to be swung out to the extended position.
I
- 10. Place the handwheel reach-rod over the 3/4" drive shaft.
- 11. While counting the number of tums, begin to slowly tum the handwheel counter-clockwise (clockwise for #8 MD linear range and #12 SA post accident channels) to move the swing positioner to the detector pulling position. The maximum swing you will encounter is 190 degrees for detector #9 and the minimum swing will be 48 degrees for detector #2. The positioner will be in the fully extended position when it reaches the mechanical stop.
Observe the Position Indicator Notches reach the fully extended position. Verify using drawing 8770-G-190 Sheet 4 of 5. Record i the number of tums on Data Sheet 1. og /R3 9' 12. Sign Verification Data Sheet #1.
- 13. Remove reach-rods and store until re-installation of detector.
. 14. Detach the hoisting cable from the storage eyebolt,
- 15. Attach the chainfall hook or rigging to the detector hoisting cable.
O
REVISION NO.: PROCEDURE TITLE: PAGE: 3 EXCORE NEUTRON DETECTORS PROCEDURE NO.: REMOVAL AND INSTALLATION
; INSTRUMENT & CONTROL PROCEDURE i 1-lMP-64.01 ST. LUCIE UNIT 1
8.0 INSTRUCTIONS
(continued) 8.3 (continued) _ CAUTION Be especially observant to detect signs of binding while removing the i detector. If the detector is binding, it may be freed by rotating the detector assembly slightly and/or jockeying the hoisting cable until the i detector assembly becomes free. This must be done gently to avoid damage to the ceramic insulators. A man under the reactor vessel may be needed to guide the detector cable. l
- 16. Ensure the hoisting cable is plumb and slowly lift the detector and cables from the holder.
- 17. Once the detector assembly is clear of the holder, stop the removal process. Health Physics should take area surveys, check for contamination of exterior surfaces and provide authorization for
) continuation of detector removal.
- 18. Slowly raise the detector to the laydown area.
- 19. Tie off the nylon line if removal from the detector assembly is I required. If the line is lost, reinstallation of the detector will be extremely more difficult. 4
- 20. Consult with Health Physics for handling and disposal of removed materials. Fission chambers are classified as Special Nuclear Material and must be accounted for and inventory records updated.
( ~ 8.4 Installation of FIXED holder detectors #1 MA Wide Range Channel,
#3 MC Wide Range Channel, #4 MD Wide Range and #11 SB Post Accident Channel is as follows:
- 1. Prior to installation perform l&C Procedure 1200060, " Fission Chamber Acceptance Test" or I&C Procedure 1200082,
. " Uncompensated Ion Chamber Acceptance Test" whichever is applicable.
9' 2. Record the detector serial number and detector holder into which (') the detector assembly is to be installed in the procedure above, l&C Procedure 1200060 or 1200062. /R3
i REVISION NO.: PROCEDURE TITLE: PAGE: 3 EXCORE NEUTRON DETECTORS PROCEDURE NO . REMOVAL AND INSTALLATION
) INSTRUMENT & CONTROL PROCEDURE l l 1-lMP-64.01 ST. LUCIE UNIT 1 1 4
8.0 INSTRUCTIONS
(continued) 8.4 (continued) ! 1
- 3. Straighten the detector cables taking care to prevent kinking and tape the nylon pull line to the detector cables approximately one
., foot above the connectors.
- 4. Cap or cover the cable connector ends.
l 5. Attach the chainfall hook or rigging to the detector hoisting cable.
- 6. Raise the detector to the vertical position and begin lowering the detector assembly over the holder in which it is to be installed.
j CAUTION ; Health Physics will ascertain the radiological precautions to position a l man at the reactor vessel flange above the detector holder, at the holder I
- and under the reactor vessel.
l ) l l 7. Continue to lower the detector assembly toward the holder while a
- man beneath the holder under the reactor vessel takes up the slack i on the cable pull line and ensures kinking does not take place in the cable.
l CAUTION i Be especially observant to detect signs of binding while lowering the assembly into the holder. If the assembly is binding, it may be freed by rotating the detector assembly slightly and/or Jockeying the hoisting cable a until the detector becomes free. This must be done gently to avoid damage to the ceramic insulators. A man may be needed under the reactor vessel to guide the detector cable.
- 8. Ensure the assembly is plumb at the top of the holder and begin
. lowering the assembly into the holder until the holder cap is seated.
Once the cap is seated, the detector is positioned properly.
- 9. Pull the cables through the conduit and into the junction box. The i
( man under the vessel guides the cable into the conduit as the detector is lowered ensuring kinking does not take place. 6
. 1 REVISION NO.: PROCEDURE TITLE: PAGE:
3 EXCORE NEUTRON DETECTORS I PROCEDURE NO.: REMOVAL AND INSTALLATION 3 INSTRUMENT & CONTROL PROCEDURE i 1-lMP-64.01 ST. LUCIE UNIT 1
8.0 INSTRUCTIONS
(continued) 8.4 (continued)
- 10. Disconneci the chainfall hook or rigging from the permanently l installed hoisting cable.
- 11. Attach the hoisting cabl6 to the eyebolt provided beneath the seal
. ring.
- 12. At the cable junction box perform I&C Procedure 1200060, " Fission I Chamber Acceptance Test" or I&C Procedure 1200062,
" Uncompensated lon Chamber Acceptance Test' whichever is applicable.
- 13. Following completion of the acceptance test, install Raychem over !
the connectors and mate the detector cables in the detector junction box. 8.5 Installation of LATERAL holder detectors #6 MB Linear Range Channel, l
) #7 MC Linear Range Channel and #10 MB Control Channel is as follows:
- 1. Prior to installation perform I&C Procedure 1200060, " Fission Chamber Acceptance Test" or l&C Procedure 1200062,
" Uncompensated lon Chamber Acceptance Test" whichever is applicable.
9' 2. Record the detector serial number and detector holder into which the detector assembly is to be installed in the procedure above, I&C Procedure 1200060 or 1200062. /R3
- 3. Straighten the detector cables taking care to prevent kinking and j tape the nylon pull line to the detector cables approximately one foot above the connectors.
- 4. Cap or cover the cable connector ends, j l
. 5. Attach the chainfall hook or rigging to the detector hoisting cable. i
- 6. Raise the detector to the vertical position and begin lowering the detector assembly over the holder in which it is to be installed.
i 1
- _ - .. . . _ . - . .. _ - . _ - .- .. . . ~ _
j REVISION NO.: PROCEDURE TITLE: PAGE: 3 EXCORE NEUTRON DETECTORS PROCEDURE NO.: REMOVAL AND INSTALLATION
) INSTRUMENT & CONTROL PROCEDURE
- 1-lMP-64.01 ST. LUCIE UNIT 1
8.0 INSTRUCTIONS
(continued)
- 8.5 (continued) i CAUTION
] Health Physics will ascertain the radiological precautions to position a man at the reactor vessel flange above the detector holder, at the holder and under the reactor vessel. i
- 7. Continue to lower the detector assembly toward the holder while a l man beneath the holder, under the reactor vessel, takes up the
! slack on the cable pull line and ensures kinking does not take place j in the cable. i CAUTION Be especially observant to detect signs of binding while lowering the assembly into the holder. If the assembly is binding, it may be freed by I rotating the detector assembly slightly and/or jockeying the hoisting cable
; until the detector becomes free. This must be done gently to avoid damage to the ceramic insulators. A man may be needed under the reactor vessel to guide the detector cable.
i 8. Ensure the assembly is plumb at the top of the holder and begin lowering the assembly into the holder until the holder cap is seated. j Once the cap is seated, the detector is positioned properly. l 9. Disconnect the chainfall hook or rigging from the permanently installed hoisting cable. I
- 10. Attach the hoisting cable to the eyebolt provided beneath the seal ring.
4
- 11. Place the handwheel reach-rod over the 3/4" drive shaft.
. 12. Observe the pointer on the spur gear position indicator pointing to one of the scribe marks. This scribe mark indicates the maintenance position.
I
- 13. Begin to tum the handwheel counter-clockwise to move the lateral
- positioner to the operating position counting the number of tums of the handwheel. (One tum = 360 degrees).
4 R
REVISION NO.: PROCEDURE TrTLE: PAGE: 3 EXCORE NEUTRON DETECTORS (= ~ PROCEDURE NO.: REMOVAL AND INSTALLATION
) INSTRUMENT & CONTROL PROCEDURE 1-lMP-64.01 ST. LUCIE UNIT 1
8.0 INSTRUCTIONS
(continued) 8.5 (continued)
- 14. Continue until the spur gear rotates to the second scribe mark indicating that the positioner is in the full operating position. Use drawing 8770-G-190 Sheet 2 of 5 to verify in operating position.
Record number of tums in on Data Sheet 1. /R3 l ' l 9' 15. Sign Data Sheet #1 Verification Sheet. , 1
- 16. Compare the number of tums required to move the positioner to the operating position with the number of tums recorded to remove the detector. Any discrepancy should be investigated thoroughly.
- 17. Pull the spring loaded indexing pin outward.
- 18. Rotate one quarter tum counter-clockwise and allow the indexing
~
pin to spring inward and rest against the locking disc.
) 19. Rotate the locking disc with the handwheel until the indexing pin seats into the hole provided.
- 20. Place the T-handled reach-rod over the 5/16' locking pin.
- 21. Tum the locking pin clockwise to insert locking pin into locking disc.
The positioner !3 nc.v locked in the operating position.
?2. Remove reach rods and store them in the l&C hot shop.
- 23. Pull the ceb!9s through the conduit and into the junction box. The man under the reactor vessel guides the cable into the conduit as the detector is lowered ensuring kinking does not occur.
i
- 24. At the cable junction box perform l&C Procedure 1200060, " Fission Chamber Acceptance Test" or l&C Procedure 12000ti2,
" Uncompensated lon Chamber Acceptance Test" whichever is applicable.
- 25. Following completion of the acceptance test, install Raychem over the connectors and mate the detector cables in the detector junction box.
s
. -- =. - . - . . - .-
EEVISION NO.: PROCEDUR5 TITLE: PAGE: 3 EXCORE NEUTRON DETECTORS
' PROCEDURE NO.: REMOVAL AND INSTALLATION l
-I INSTRUMENT & CONTROL PROCEDURE l 1-lMP-64.01 ST. LUCIE UNIT 1 l
8.0 INSTRUCTIONS
(continued) ' 8.6 Installation of SWING holder detectors #2 MB Wide Range Channel,
#5 MA Linear Range Channel, #8 MD Linear Range Channel, #9 MA Cos; trol Channel and #12 SA Post Accident Channel is as follows:
4 l l l l NOTE i Channels #8 and #12 share e positioner. 1
- 1. Prior to hstallation perform I&C Procedure 1200060, " Fission l
~
Chamber Acceptance Test" or l&C Procedure 1200062, I
" Uncompensated lon Chamber Acceptance Test" whichever is I
, applicable. 9' 2. Record the detector serial number and detector holder into which the detector assembly is to be installed in the procedure above, l I&C Procedure 1200060 or 1200062. /R3
- 3. Straighten the detector cables taking care to prevent kinking.
1
- 4. Tape the nylon pull line to the detector cables approximately one i foot above the connectors.
i 5. Cap or cover the cable connector ends.
- 6. Attach the chainfall hook or rigging to the detector hoisting cable. I 1
i
- 7. Raise the detector to the vertical position and begin lowering the detector assembly over the holder in which it is to be installed. I
)
CAUTION Health Physics will ascertain the radiological precautions to position a man at the reactor vessel flange above the detector holder, at the holder and under the reactor vessel.
- l
- 8. Continue to lower the detector assembly toward the holder while a man beneath the holder, under the reactor vessel, takes up the slack on the cable pull line.
\'
REtflSION NO.: PROCEDURE TITLE: PAGE: 3 EXCORE NEUTRON DETECTORS
', PROCEDURE NO.: REMOVAL AND INSTALLATION
') INSMUMENT & CONTROL PROCEDURE
, , 1-lMP-64.01 ST. LUCIE UNIT 1
8.0 INSTRUCTIONS
(continued)
- 8.6 (continued)
I CAUTION Be especially observant to detect signs of binding while lowering the I assembly into the holder, if the assembly is binding, it may be freed by rotating the detector assembly slightly and/or jockeying the hoisting cable until the detector becomes free. This must be done gently to avoid damage to the ceramic insulators. A man may be needed under the reactor vessel to guide the detector cable. i 4
- 9. Ensure the assembly is plumb at the top of.the holder and begin lowering the assembly into the holder until the holder cap is seated.
Once the cap is seated, the detector is positioned properly. i i l
- 10. Disconnect the chainfall hook or rigging from the permanently i installed hoisting cable.
)
- 11. Attach the hoisting cable to the eyebolt provided beneath the seal ring.
- 12. Place the handwheel reach-rod over the 3/4" drive shaft.
- 13. Begin to tum the handwheel clockwise (counter-clockwise for i #8 MD linear range and #12 SA post accident channel) to move the j swing positioner to the operating position.
j 14. Continue until the positioner is back in the operating position. j Verify position notches are in operating position using drawing ! t 8770-G-190 Sheey o p. Record number of tums in on Data
- Sheet 1. O,e4p%
i
/R3 T 15. Sign Data Sheet #1 Verification Sheet.
- 16. Compare the number of tums required to rnrve the positioner to
, the operating position with the number of tLms recorded to remove the detector. Any discrepancy should be investigated thoroughly.
- 17. Pull the spring loaded indexing pin upward.
k' 18. Rotate one quarter tum clockwise and allow the indexing pin to spring inward and rest against the locking disc. o . mm
REVISION NO.: PROCEDURE TrrLE: PAGE: 3 EXCORE NEUTRON DETECTORS ; a REMOVAL AND INSTALLATION PROCEDURE NO.:
) INSTRUMENT & CONTROL PROCEDURE 1-lMP-64.01 ST. LUCIE UNIT 1
8.0 INSTRUCTIONS
(continued) 8.6 (continued)
- 19. Adjust the locking disc with the handwheel until the V-notch in the locking disc aligns directly with the locking pin.
- 20. ' fl"st the locking disc slightly until the indexing pin drops into the hole provided.
- 21. Place the T-handled reach-rod over the 5/16" locking pin.
- 22. Tum the locking pin clockwise to insert locking pin into locking disc.
The positioner is now locked in the operating position. I
- 23. Remove reach rods and store them in the l&C hot shop.
- 24. Pull the cables through the conduit and into the junction box. The I man under the reactor vessel guides the cable into the conduit as the detector is lowered ensuring kinking does not occur in the l i cable.
- 25. At the cable junction box perform l&C Procedure 1200060, " Fission Chamber Acceptance Test" or l&C Procedure 1200062,
" Uncompensated lon Chamber Acceptance Test" whichever is applicable.
- 26. Following completion of the acceptance test, install Raychem over the connectors and mate the detector cables in the detector junction box.
8.7 Re-energize the Nuclear Instrument Channel and fo'llowing a four hour warmup period, perform one of the following which apply to the detector system being worked:
- 1. l&C Proce&rs 1-1210050, " Wide ~ Range Nuclear Instrumentation Test" for wide range channels.
- 2. l&C Procedure 1-1220050, " Linear Power Range Safety Channel Quarterly Calibration" for Linear Safety Channels.
- 3. l&C Procedure 1-1220051, " Linear Power Range Control Channel Quarterly Calibration" for Control Channels.
(
a REVISION NO.: PROCEDURE TITLE: PAGE: 3 EXCORE NEUTRON DETECTORS PROCEDURE NO.: REMOVAL AND INSTALLATION
) INSTRUMENT & CONTROL PROCEDURE 1-lMP-64.01 ST. LUCIE UNIT 1
8.0 INSTRUCTIONS
(continued) 8.7 (continued)
- 4. I&C Procedure 1-1240065, "Excore Neutron Flux Monitor Ouarteri for the Post Accident channels.
s i i f 4 1 4
\
4 k 4 4 e 4
REVislON NO.: PROCEDURE TirLE: PAGE: 3 EXCORE NEUTRON DETECTORS PROCEDURE NO.: REMOVAL AND INSTALLATION .
] 1-lMP-64.01 INSTRUMENT & CONTROL PROCEDURE ST. LUCIE UNIT 1 DATA SHEET 1 Date C / 10 /
NPWO W LATERAL POSITIONER
#8 MB Linear Range Channel 8.2.14 8.5.15 y Verified Out ,_, ,
Verified in Operating Position l 8.2.13 number of tums out 8.5.14 number of tums in l
#7 MC Linear Range Channel 8.2.14 8.5.15 ,
Verified Out __, Verified in Operating Position 8.2.13 number of tums out 8.5.14 number of tums in l
#10 MB Control Channel 8.2.14 8.5.15 I Vearified Out Verified in Operating Position
- 8.2.13 number of tums c ut 8.5.14 number of tums in
. SWING POSITIO!JER
#2 MB Wide Range I 8.3.12 8.6.15 Verified Out Verified in Operating Position 8.3.11 number of tums cut 8.6.14 number of tums in
#5 MA Linear Range 8.3.12 8.6.15 Verified Out Verified in Operating Position 8.3.11 number of tums ut 8.6.14 number of tums out
#8 MD Linear Range ard #12 SA Post Accident Channels
- 8.3.12 8.6.15 Verified Out 1/ Verified in Operating Position 8.3.11 number of tums out R.6.14 number of tums out l
#9 MA Control Channel !
8.3.12 8.6.15 , Verified Out vf Verified in Operating Position vf 8.3.11 number of tums out t 8.6.14 number of tums out i
. I certify that all excore detector positioners that have been moved this maintpnance eriod '
have been placed back in the operating position. (' , System Supervisor - 3 - independent Verifier
/
h f w
- Shared positioner 1
/R3
.. . . . - ~ ~ . - . _ _ . - .- .- . . - . - . . -- .. .. . . . . . -
j* j S 1 OPS ! 4
^
RNOA NWR & WM oO5enOceouse DOCN 1 LOI-l&C-16 i
# l SYS COMP COMPLETED ST. LUCIE PLANT ITM 0 FORIB FORMATION ONLY 1
ThlS DOCUVE J is f 40 t C'Jinw. LEO. EGOfM USE, vmnumm.mu ccmum usan.' 1-LOI-l&C.16
- Ft.ORi )A POWER AND UGliT co. REVISION O DATEVEmREE 5 INITIA h PIRATION DATE 5/26/97
<- m l ^
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! Jhg _ = l ' n fi- __F I k 1 1 _U - ii > ii ni ii si x si ip
- REPLACEMENT OF UNCOMPENSATED lON CHAMBER NO. 6 MB LINEAR l RANGE CHANNEL i
i- INSTRUMENT & CONTROL LETTER OF INSTRUCTION
! REVISION REVIEWED BY APPROVED BY DATE l j FRG ON 0 5/26/96 __,
J.SCAROLA 5/26/96 ! Plant General Manager Plant General Manager
*P " '
INSTRUMENT & CONTROL partrn nt j BMG 5-26-96
s . REVISION NO.: PROCEDURE TITLE: PAGE: I 0 REPLACEMENT OF UNCOMPENSATED ION CHAMBER [ PROCEDURE NO.: NO. 6 MB LINEAR RANGE CHANNEL 2 of 7 :
- INSTRUMENT & CONTROL LETTER OF INSTRUCTION
( 1-LOl-l&C-16 ST. LUCIE UNIT 1 . 1.0 TITLE: i l- , j REPLACEMENT OF UNCOMPENSATED ION CHAMBER NO. 6 MB
- LINEAR RANGE CHANNEL
2.0 PURPOSE
! Excore detector No. 6 is housed in a lateral positioner at 75* azimuth and 8'-10" from the core centerline placing the detector under a portion of the 1 A1 cold leg. Removal of the detector requires the positioner to move ' laterally and outward to 92* azimuth and 9'-13/8" from core centerline. Total positioner lateral movement is specified as 2'-8" This is necessary in order ; to obtain the necessary clearance from the vessel flange and insulation to allow the 12 ft. long detector to be pulled vertically upward. Step-by-step instructions for removal and replacement from above (upper cavity) are delineated in 1-lMP-64.01. Due to failure of the positioner, removal from above is not possible. This LOl provides the detailed instructions to facilitate replacement of the detector from below. ,
3.0 DISCUSSION
3.1 REFERENCES
- 1. Technical Manual 8770-4873, "Out of Core Neutron Detectors."
- 2. l&C Procedure 1200062, ' Uncompensated lon Chamber Acceptance Test."
- 3. l&C Procedure 1-1220050, " Linear Power Range Safety Channel Quarterly Calibration."
- 4. OPS Procedure 0010122, "In-Plant Equipment Clearance Orders."
- 5. HP Procedure HPP-1," Radiation Work Pemiit."
- 6. HP Procedure HP-2, "FP&L Health Physics Manual."
- 7. Administrative Procedure'0010505, " Confined Work Space."
- 8. Drawing 8770-3190," Neutron Detector Holder-lonization Chamber."
; 9. Drawing 8770-13427, " Support Assembly-UIC Detectore Channels 4 5, 6, 7, 8, 9, 10 & 11."
c
, O REP E E T OF UNCOMPENSATED lON CHAMBER 5
PROCEDURE NO.: NO. 6 MB LINEAR RANGE CHANNEL 3 of 7 4 INSTRUMENT & CONTROL LETTER OF INSTRUCTION 4 ( 1-LOl-l&C-16 ST. LUCIE UNIT 1 , 3.0 DISCUSSION: (continued) I 3.1 (continued)
- 10. Drawing 8770-G-189, Sheet 2 of 5, "No. 2 and 6 Neutron Detector Lateral Positioner."
- 11. Drawing 8770-12961, "St. Lucie Unit No.1 Permanent Reactor Cavity Seal / Shield Ring Layout."
3.2 PRECAUTIONS / LIMITATIONS: ,
- 1. Minimize physical contact with the irradiated detector assemblies to keep radiation exposure as low as reasonably achievable.
- 2. Work is to conducted in confined spaces therefore procedure AP 0010505, " Confined Work Space", shall be invoked.
- 3. Use caution in handling the detector assemblies. The housings are made of reactor grade aluminum which is very soft and can be easily dented or marred. The detectors use ceramic insulators which could be damaged if the detector receives a severe blow.
- 4. Use caution when raising or lowering the detector assembly in order to detect signs of binding in the support housing or binding of cables.
- 5. The detector cables are extremely fragile. Care must be taken to prevent exceeding the cable minimum bend radius of 10 inches.
- 6. The detectors will be carried to the cavity keyway. To )
accommodate transport, one of the middle damper louver must be ) Jacked and cribbed open. Prior to movement through the keyway, j the detector should be protected along with the first foot of cable. j
- 7. The approximate weight of the detector assembly is 75 pounds.
i l
,a . ] REVISION NO.: PROCEDURE TITLE: PAGE: $ 0 REPLACEMENT OF UNCOMPENSATED lON CHAMBER i PROCEDURE NO.: NO. 6 MB LINEAR RANGE CHANNEL 4 of 7 INSTRUMENT & CONTROL LETTER OF INSTRUCTION 1-l 1-LOl-l&C-16 ' ST. LUCIE UNIT 1
- 3.0 DISCUSSION
- (continued) i j 3.3 PREREQUISITES:
! 1. A Radiation Work Permit has been issued to perform this task. ' Removal and installation of the detector is performed from the top of the detector housing, near the 1 A1 Cold Leg Nozzle and the ,_ bottom of the reactor vessel. Prior to start of work, a tailboard l briefing between Health Physics and all maintenance personnel involved in the work must be performed to coordinate efforts to limit j radiation exposure. 1 L 2. The nuclear instrument channel to be worked has been j de-energized with an equipment clearance order issued. 1 e 3. I&C Procedure 1200062, " Uncompensated lon Chamber 4 Acceptance Test", has been performed prior to installation. l 4. Establish communications between crews. 1 j 5. Appropriate personnel safety devices shall be employed for the work from the upper cavity.
4.0 INSTRUCTIONS
4.1 Transport and stage the new detector and tools needed just outside the east blast damper. 4.2 Coordinate entry to have simultaneous access to the top and bottom of the detector. 4.3 Detector removal: , i
- 1. Disconnect the old detector field cables. l
- 2. Attach a pull rope to cables, then pull the cables under the reactor vessel area.
- 3. At the 1 A1 cold leg access area tie a 50 ft. rope to the old detector wire rope lanyard and secure the other end of the rope.
- 4. Raise and support the detector approximately 6 to 36 inches above the top of the detector positioner, using the detector raising tool
- from below or the rope from above or both.
REVISION NO.: PROCEDURE TITLE: PAGE: 0 REPLACEMENT OF UNCOMPENSATED ION CHAMBER PROCEDURE NO.: NO. 6 MB LINEAR RANGE CHANNEL 5 of 7 ; INSTRUMENT & CONTROL LETTER OF INSTRUCTION i 1-LOI l&C-16 l ST. LUCIE UNIT 1
4.0 INSTRUCTIONS
(continued) 4.3 (continued) l
- 5. Remove the four bushing insulators on the detector support assembly.(See Drawing 8770-13427) l l
CAUTION I ~ Be especially observant to detect signs of binding while removing the detector if the detector is binding, it may be freed by rotating the detector assembly slightly and/or jockeying the detector assembly until it becomes free. This must be done gently to avoid damage to the ceramic ] insulators. ; l
- 6. Using the rope from above and the raising tool from below lower l
l the detector. I
- 7. When the detectcr clears the positioner, guide the detector through !
the blast damper louvers and out into the keyway. The detector l cables may be cut to facilitate movement through the blast damper louvers. 1
- 8. Remove the detector support assembly from the old detector. !
l 4.4 Detector Installation: l
- 1. Verify the fit of the detector support assembly on the new detector, if acceptable, proceed with step 4.4.3. l 1
- 2. If modifications to the support assembly are required, work shall l stop until Engineering resolution is obtained. '
- 3. Install the detector support assembly on the new detector and insure the pull rope is attached. Do not install bushings ht this time.
- 4. Carefully guide the new detector into the reactor vessel area.
t U
- - _ __ __ m_.._ _ . _ . . __
REVISION NO.: PROCEDURE TITLE: PAGE:
, 0 REPLACEMENT OF UNCOMPENSATED ION CHAMBER PROCEDURE NO.: NO. 6 MB LINEAR RANGE CHANNEL 6 of 7
' INSTRUMENT & CONTROL LETTER OF INSTRUCTION 1-LOI-l&C-16 ST._LUCIE UNIT 1 i
4.0 INSTRUCTIONS
(continued) 4.4 (continued) d 4 CAUTION
- Be especially observant to detect signs of binding while inserting the i
detector. If the detector is binding, it may be freed by rotating the detector assembly slightly and/or jockeying the hoisting cable until the detector assembly becomes free. This must be done gently to avoid damage to the ceramic insulators. I 1 - , l
- 5. Using the rope from above and the raising tool from below install
, the new detector into the detector positioner and raise the detector ' approximately 6 to 36 inches above the top of the detector positioner. i 3 ' CAUTION Do no over tighten bolting from bushing insulators, which are brittle and i susceptible to cracking. 1
- 6. Install the four bushing insulators on the detector support assembly.
Pull up bolts until the insulator is tight. Do not overtighten. ,
- 7. Lower detector into place, insuring the support bushing insulators are resting on top edge of the lateral positioner tube.
- 8. Remove the rope from the detector wire rope lanyard.
- 9. Secure the detector wire rope lanyard by hooking it to its clip on the side of the vessel.
- 10. Personnel in the 1 A1 cold leg access are may cleanup and exit the area.
4 O
- _ . - ._- . _ ~ _ - .
o . REVISION No.: PROCEDURE TITLE: PAGE: 0 REPLACEMENT OF UNCOMPENSATED ION CHAMBER PROCEDURE NO.: NO. 6 MB LINEAR RANGE CHANNEL 7 of 7 INSTRUMENT & CONTROL LETTER OF INSTRUCTION 1-LOl-l&C-16 ST. LUCIE UNIT 1
4.0 INSTRUCTIONS
(continued) 4.4 (continued) CAUTION l I Tiie minimum bend radius for the detector cable is 10 inches. l 1
- 11. Carefully pull the cables through the conduit and into the junction box, ensure kinking does not occur.
- 12. At the cable junction box perform l&C Procedure 1200062, ;
4 " Uncompensated lon Chamber Acceptance Test." l
- 13. Following completion of the acceptance test:
i . A. Install Raychem.
, B. Connect the detector cables in the detector junction box.
1 Performed B :[21/_ - - - Date J / 2 f/% is l 1.V. By- -
- Date S/22/ k '
C. Heat shrink raychem over the connectors. i
- 14. Cleanup the reactor vessel area.
- 15. Exit the reactor vessel area, removing all trash, toois and the old detector.
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Peg 2 5 of 6 (, ST. LUCIE PLANT l I & C PROCEDURE NO. 1200062. REVISION 5 _ UNCOMPENSATED ION CHAMBER ACCEPTANCE TEST TABLE A Detector Type _ tt/e-Serial No. 9kl-)i 4 Holder No. u1L 'L]'189 l SEif_ MEASURED MINIMUM VALUE VALUE 9.3 Test lead insula res . 4 I5 % o'I O 10'80 9.4 insulation resistance, 7 * ## Q 10"O 9.5 Insulation resistance, i f y to
- O 10"O 9.6 Insulation resistance, Y
4> y8io" Q 10"O s 9.7 Insulation resistance, HV u oo O 10"O 9.8 Insulation resistance, HV to ao n 10"O 9.9 Capacitance HV to case 99og pf - 9.10 Capacitance top signal to case Yo sec ? - 9.11 Capacitance bv6.rm signal to case 3oo e .4 - Test Results and Comments: Test Eauipment Used
~
Megohmeter No. Impedance Bridge No. 936 0% (swp t 5-18) r (sWp 11- ?.//) Verified by b ben b cA b Date I / 2f Th
/
Reviewed by / h Date_ d / 24' / 7I# (SW E'
yagaeor6 "~ ST. LUCIE PLANT I & C PROCEDURE NO. 1200062. REVISION 5 8.~- UNCOMPENSATED ION CHAMBER ACCEPTANCE TEST
. TABLE B
- Detector Type CATC _
a Serial No. 014I1Ib
- Holder No. U t, t. 37 7-)
i ** i M E. MEASURED MINIMUM VALUE VALUE 9.16 Test lead ins ## 4X /0 Q 10'80 9.17 Insulation resi n. to case # * # Q 10"O
~
i 9.18 Insulation resi ,%t{gm to case 1. 2 f * ' O'
- 10"O i 9.19 Insulation resi
[ 3 2.. >#I 8 et 1 " tg Q 10"O g 9.20 Insulation resi - e FX (* y O 10"O P5 .a % ] 9.21 Insulation EiL5- -- y. rw to" Q 10"O . i 1 9.22 Capacitance HV to E# 47to pf - 1 l 9.23 Capacitance top 72.50 pg _ ! ) 9.24 Capacitance bottom
$ Sif0 pf -
l, Test Results and Comments: Test Eautoment Used ! Megohmeter No. [JZ-I/3 Impedance Bridge No. M 0% Verified by_ NAu, - Date / / 7 Reviewed by Date / / l.
-. -. . . _ . - . - . _ = - __ _ . , , l Page 3 of 3 l
CR %1156 UIC Resistance Values ' i l Evaluation: . l 1 The subject Condition Report states that UIC detector #6 has resistance values as low as 2.25 x l
- 10 Ohms versus the plant acceptance criteria of I x 10" Ohms.
- i These values are acceptable since the vendors criteria is for the resistance to be greater than 1 x '
105' Ohms (See reference below). l COBCiusion ;
- 1. Base on the above, the detector is acceptable as is and is therfore operable. l 1
- 2. Mode 2 hold is removed by this evaluation. I l
l
Reference:
l Gamma Metrics Neutron Flux Monitodng Syr.c=:Irrtden Meual, FPL I/M 8770-13729, Revision 0, page 10 i Prepared e By:d/4 m M , ve p 2 Verified By: 5ew".lA lC. D8 Approved By: dk. (/v/94 wia*na.- Wwa l l V
1 .. . t, _ i - SEVERHY uYE. CRm Oh0NENhhF l' '
- a %* CONDITION
- "" "O a o ie m *>.
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I I & C PROCEDURE NO. 1200062, REVISIONY I UNCOMPENSATED ION CHAMBER ACCEPTANCE TEST i 4 TABLE B l l } Detector Type U/d. i Serial No. 76/7/7 l
- - Nolder No. wi 2 3787 w<f'?
1 . MEASURED MINIMUM i STEP VALUE VALUE I t j 9.16 Test lead insulanon resistance /*o G O 10"O l 9.17 insulation resistance, top signal to case ./oG Q 10"O 4 } 9.18 Insulation resistanos, bottom signal to cace /eG Q 10"O i 9.19 insulagon resistance, HV to case /Z G Q 10"O l i 9.20 Insulagon resistance HV to top signal /N n 10"o l 9.21 Insidagon reelstance, HV to bottom signal /24 O 10"O j 9.22 C==~1s HV to case S*** pf l 9.23 C=-;Z ~ s top signal to case J788 pf - 4 l 9.24 Capangence botom sIpalto case 2/** pt - l l ! Test Results and Comments: . Test Eauloment Used i i Megohmeter No. AK L - fdt' i impedance Bridge No. #X 4 - 03& I t Verified by T E.7 ebb Daw f_f.2_k_/76,
- Reviewed by Date / /
l k l l t
j,, , Page 5 of 6 1 ST. LUCIE PLANT 6 K 96-/S~CS~ pese 4 g g 1 & C PROCEDURE NO.1200062 REVISION 5 UNCOMPENSATED lON CHAMBER ACCEPTANCE TEST l . TMW A l Detector Type 4 iC i l Serial No. Hel 'l l 'l l Holder No. W L. M 'l T 'l VE.LL* 7 ! l 1
- i MEASURED MINIMUM i STER VALUE VALUE i
i 9.3 Test lead insulation resistance 151fe O 10"O j 9.4 Ineutstion resistance, top signal to case 4 f %8 *" Q . 10"O 9.5 insulalidn resistanos, bottom signal to case 4 %f *" O' 10"O i 9.6 insulaeon resistance, HV to case -
- t. 0 8** O 10'b 1
l
) 9.7 inouiagon resistanos, HV to top signal oo O 10"O j s.s ineutomon resistanos. HV to bosom s'gnal oss a 10"O j s.s capacannoo HV to caso y o pf -
j e.10 capaeance top signalto case .ps e e pt - [ 9.11 capmanance benom signal to case Jeoopt - i - l Test Results and Comments: ! Test Eautoment Used Meen earno. P5L-16 i ImpedW1oe Bridge No. W 0% l hySIII h
#venned by. Bu,,e /Nu.I-i.ss) l d ,. Date O_2 9 e r, Reviewed by b v ., Date_f_f2f'/._9.f, i <
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- ._ . - - - . _ ._ _._ - - .. - -.- . --- ---._-.- -- ~--
QQ Eg p CR 9645gf P4Sg of g 5- <. Combustion Engineering 7/1/96
- Nuclear Operations St.RM - 051
- Resident Site Manager i Memo i.
} To: Dan Denver, Engineering Manager ! From: Al DeGrasse, ABB Resident Site Manager
Subject:
Condhion Report 96-1565 (#9 Detector Resistance Readings) in response to the subject Condition Report addressing the findings on the Unear 3 Power Range Detector #9, the following technical responses is offered:
- Readings taken from the Detector installed in #9 have been docurnented to be
! below the minimum acceptable value as referenced in the subject Condition Report. Besed on the fact that the readings were taken inside Containment on ! less than desired conditions as compared to Factory conditions, ABB CENO ! feels that the reduced values of (1) decade in some of the categories is { acceptable for plant operation.
- r if you need additionalinformation, please advise Qh.lV A.J.DeGrosse ABB Resident Site Manager CC: J.Scarola .
R.Olson R.Filipok l 1
j-, c i
- Page 6 of 6 i
j CR 96-1565 UIC #9 Resistance Values j Evaluation: j The subject Condition Report states that UIC detector #9 had resistance values after installation ! (page 3) that were lower then the un-installed manufacturer's test criteria (Reference 1). The detector passed the pre-installation testing (page 4). As stated in Reference 2, major deviations j ber;ca before and after installation values should be investig The differences between the j after resistances are approximately one decade lower than the fore installation values. These differences are not considered major (see ABB-CE evaluation, page 6). There are no ! action we==y. l Detector #9 rovides input to the Reactor Regulating Systeun (RRS). This system provides no safety related nor Tech SMW i@J functions. Therefore there are no operability nor Mode Chang 9f gwhich are applicable. Based on the above, the detector is acceptable as is and is therefore opkable and the Mode 4 hold is removed by this evaluation. i
References:
- 1. Detector Instruction Manual, 8770-4373, Revision 0
- 2. I&C Procedure 1200062, Revision 5 l t' ,amma m.,
e ! 1. Mode HoldsImposed? _X_ No Yes l 2. AnyRenamining Mode Holds? _X_ No Yes
- 3. OperabGity enacern? _X_ No Yes
- 4. Actions Nm _X_ No Yes P.wd By:
) 4 verified By: hacMe 'r-
. Approved By: /1
- v i
1 4 a i
In- ffice correspondence FPL JPN-SPSL-96-0280 ; To: S. A. Valdes Date: .N 0 .25 Prom: "ild3h*]s**"' D. J. Denver Departre snt: Nuclear Eng;..eering JPN/PSL
Subject:
ST. LUCIE PLA2C L'IT 1 IC/M #2 96097 4 TITLE: Holder ... :' ably for E:" core Detectors 3, 6, 7, 3, 9 & 10 REF.: CR 96-1075 FILE: PC/M 96097 Attached for review, approval and us-subject PCM. s the MEP for the This package provides the details necessary to fabricate an alternate for Excoresupport Detectorsbracket
# 5, to be use with the holder assembly 6, 7, 8, 9 & 10.
If you or 7496 haveAlan any questions, Pata please contact cesar Gavidia at gxt at ert 7476 acs. DJD/AAP/CG CC: H. L. D. Pottorff Fagley - DCC=CS/PSL (w/ original) 1
- OPS /PSL J. Harmon - SCE/PSL B. Haines - MM/PSL G.
Pustover - MM/PSL FINA_. r-REVIEW ; PSL INFO SVC l g ,__ g_. . n_ l
..;;.r - ~ w : ;..e : l e s n, <r m.,v, _ .,
.. }
tCJ~ ,;g,3,.y+ -~-O w r e w . ._Ti'.q;A.,tppg 00 FCWEN p * .- k"m"Nnas-mk' -
l q l MINOR ENGINEERING PACK.1GEC.IEP) PLANT ESL UNIT 1 PC/M NUMBER 96092 SUP!". O ORIGINATING DOCUMENT CR 96-107C EXPIRATION DATE 3n1/97 PC/M CLASSIFICATION _X.SR _ QR _ NNS ADMIN i TITLE - ! 1 HOT nER ARRFMRTY FOR FYCORE NFTiI HON nKirf' TORE # L & 7 A_ 0 Jt,10 ADDITIONAL REQUIREMENTS /IN54 xUCTIONS YES NO AS-BUILDING TO COMMENCE UPON ISSUANCE OF PACKAGE? X THIS PACKAGE HAS THE POTENTIAL TO SIGNIFIC NTLY X IMPACT PERSONNEL IF YES, JPN FORM 72 IS REQUIRED. RADIATION EXPOSURE (See QI 3.13). ! I 10CFR50.59 SCREENING YES NO 1) DOES THE CHANGE REPRESENT A CilANGE TO THE FACILTTY AS DESCRIBED IN THE SAR7
- 2) X DOES THE CHANGE REPRESENT A CHANGE TO 3)
PROCEDURES AS DESCRIBED IN THE SAR7 IS THE CHANGE ASSOCIATED WITH A TESTOR X
- 4) EXPERIMENT NOT DESCRIBED IN THE SAR7 COULD THE CHANGE AFFECT NUCLEAR SAFETY IN X S) A WAY NOT PREVIOUSLY EVALUATED IN THE SAR7 DOES TiiE CHANGE REQUIRE A CHANGE TO THE X TECHNICAL SPECIFICAT10NS7 X
NO17.* IF THE ANSWER TO ANY OF THE ABOVE 10CFTJ0.59 REVIEW / APPROVAL: SED SCl LNTERFACE TYPE GROUP PREPARED YERif1ED APPROVED ITL APPROVED
- INPLT REVIEW N/A MECII x
ELECT
'x liC x s A /7 8 c
crvit uc+. x x d/[ 4.@d-
- NMM -
est n N I' NUC RTEL x m [ n
, / N' p 7 -
w wquy
- For Contractor Evals As Determined By Projects
" Review Interface As A Minimum On All Non-Admin ME FPL PROJECTS APPROVAL: Nh'b DATE:
&[7[%
PC/M QM07 Revision 0 Page 2 of 4 ENGINEERING JUSTIFICATION The holder assembly for the excore neutron detectors is composed of a combination of brackets and cables designed to retrieve and replace the detectors for maintenance. One of the components of the holder assembly is the support bracket which also functions as vertical support for the detectors, transferring vertical loads generated by the weight of the detectors, to the detector support tubes. During replacement of detector #6 problems were encountered in mounting the new detector to the existing support bracket due to slight mislaigment of the mounting holes. The misaliganet was primarily due to minor configurational differences between the old and new detector. In order to prevent , similar problems in the future, a new bracket will be designed and fabricated to properly fit the old and new detectors. This MEP provides details and instructions for the fabrication of a new support bracket to be used as an alternate to the existing brackets which are part of the holder assembly for detectors # 5, 6, 7, 8, 9& 10. The new bracket has been i designed to provide equivalent seismic restraint functions as well as equivalent maintenance functions as the existing brackets. This MEP also provides the as-built configuration, including modifications performed as per reference 5, for the existing support bracket at detectors #6. The new support bracket and support bracket for detector #6 have been evaluated and were found to be j structurally adequate as documented in reference 6. l The use of the new bracket will result in a change to the elevation of the detector of less than 1". The modification to the bracket for detector #6 has resulted in a change to the elevation of the detector of less than 1/2". These changes in elevation are less than 1% of the detector length and are acceptable from engineering considerations. Additionally, a new shape annealing factor for ! l the detectors will be determined with this new configurations consequently, the function of the detectors will not be compromised. The Excore Neutron Detectors are described in the FSAR, section 7.2.1 and 7.5.5. The Excore Neutron Detectors are part of the Reactor Protective System designed to detect i described in representative core flux conditions. The Reactor Protective System is the FSAR, section 7.2, and it is classified as safety related. i Therefore, this MEP is designated as Safety Related (SR). CONCLUSION Although the Excore Neutron Detectors are described in the FCAR, sections 7.2.1 and 7.5.5, this modification is not to the level of detail provided in the SAR or Technical Specifications and results in no degradation either directly or indirectly to any safety functions required for analyzed accidents, and does not increane any radiological hazards. This modification therefore is being performed via a MEP, and a 50.59 safety evaluation is not required. t
i t
- PC/M 9fa91
' Revision 0 Page 3 of 4 l
SPECIAL TMeTRUCTIONE\TMPTEMFWTaTION REQUIREMENTS Fabrication of the new support bracket shall be in accordance with drawing JPN-96097-001. ! Drawing JPN-96097-OO2 provides support bracket as-built configuration for l detector #6. Support bracket for detector #6 has been installed under CR 96-1075 and requires no further work. POST MODIrICATION TESTING None ) RzrEnzNCEs \
- 1. St. Lucie Unit No. 1 FSAR Amendment 14 2.
- 3. St. Lucie Unit No. 1 Technical Specifications Amendment 142 4 4.
PSL Affected drawings (DCTS) reviewed 6/6/96 5. PSL Active Safety Evaluation List, access date 6/6/96 Condition Report CR 96-1075 '
- 6. FPL Calculation PSL-1FSC-96-011, Revision 0 )
- 7. Drawing No. FSB-8770-AS-252, Rev. O i
- 8. Drawing No. 8770-3190, Rev. 4 i
- 9. Drawing No. 8770-13427, Rev. 0
- 10. Drawing No. 8770-G-187, Rev. 4
- 11. Drawing No. 8770-G-189, sheets 1,2,3,4 & 5
- 12. Drawing No. 8770-G-190, sheets 1,2,3,4 & 5 1 i
s 4 ATTACEMENTS Attachment Number Number Demerietion/ Title 21 Pages None , l O f
i r PC/M 06097 Revision 0 ! Page 4 of 4 1 DRANINGS EgfM DRANING & REE DEscRYPTfow/TIPrE (1)** AIL AFFECTED (2) (3) MEP(4) EL&gT DRANINGS REE E gg JPN-96097-001 0 Alternate support [ M 8770-3190 4 N I
! Bracket for Excore M 8770-13427 0 O
Detectors #5,6,7,8,9,&10 N O JPN-96097-002 O Support Bracket for I M 8770-3190 4 Detector #6 M 8770-13427 N O l Or N 0 ( W 4 sn-st s j i VENDOR MANUALS (2) ] EL&lE DOCUMENT NUMBER ggE MEP(4) VENDOR /EOUIPMENT g REMARKS REE i None 01 C) OtSCIPUNE C = CIVIL.1
- ELECT. !* A&C. M a MECH h = hK MA l MVISION ofh : - , _ i aannual besmu Wif ens i _
The angunas a - ..u tranunia beug maand
^ fursessvug es ese i 0)
_ , _i saanual ansnhar. (4 PRIORfTY: WEP UV1330N under In&seen Ye echange wtust less dreews No ifou3RD amada.ist PSL besar I (POOL 2 (C3tDL 3 (MDL 4 (IDL ar 3 (aew) for Pm
- ~
i 4 j 1
-_ ___ .- - . . _ _ _ . . - - .-. = _ - _
J&hent: HCV-09-1B Sys: 09 Train: Fac: PSL 150mitT 02 77- i h.iate: ACT Assign Priority: A3 MASTE e: ACTUATOR FOR HCV-09-1B Work Type: 7 WORK ORDER TASK g j ~ l ation: TRSL/36/N-T2/W-TA LMD: 1 36014512 01 l ect/ Request: 021PM09-1602 PM - LEAX TES ER/PWO: 62 / 6900 900 Chg Loc: 910 4 L NPRD I
\ /
liled Explanation: U PM ID: PM09-1602 DUE BY DT: 07/11/96 EARLY DT: 06/19/96 LATE DT: 08/02/96 More: c Request: Def Tag: Loc: 1/Brkdown: LCO: Unit Cond Reg: DS: Y Fail Date: Time: Det: Stat: Symp: ginator: Date: Dept:
- rove By
- Date:
4 Determination Data: ST Required : Y NCR/CR : N/A Safety Class:
, MT Required : N PCM : N/A Q Group : B i0 CFR F0.49 : Y EQ Doc Pkg : 35.8 Assign To : VLV 1 eg Guide 1.97 : N Seismic Cat : I Est M/H : 8.00 l SME XI(ISI) Reqd : N Scaffold Req : N Crew Qty : 2 ecurity Clearance: N Fire Prot Reg: N Insul Rem : N learance Required: Y Clearance No :
WP Required: M RWP No: RCA M/H: L1: L2: L3: Requirements: QC Required : Y QL-A-T.S.10.4 .
-~
More:
.......--......------...........----------............---===== - ...--...
k Order Task
Description:
Standard: FM1602
\
i SEE PAGE 2 FOR TASK DESCRIPTION. ! I i i More: Y nned By : DRC0X24 HOWIE D Date: 06/04/96 Appr By : PRE-APPR Datq: 06/04/96 Time: 13:31 Approval : PRE-APPR /-; Date: 06/04/96
/ /
******************* OPERATIONS PROVAL TO START ***********************
,' /
- t NPS Start Permission: /.-
l'4444 ' LCO(Y/N):
- Start Date/ Time : *o- c: / 9 ?e ,'
<*eeee*******************q*****A '} ,
i
' Completion Notif : -
Major Failure: Compl. Date/ Time: '/'>f' "t / 7 -,
,, c Major Action : ,iciency Tag Removed (Y/N)t ~
1/'/ g C y I
/
J
! Component: HCV-09-1B Sys: 09 Train: . Associate: ACT l Fac: PSL Unit: 02 l Assign Priority: A3 MASTER Name: ACTUATOR FOR HCV-09-13 Work Type: 7 WORK ORDER TASK Location: 'TRSL/36/N-T2/W-TA LMD: 1 96014512 01 Defect / Request: 021PM09-1602 PM - LEAK TEST ER/PWO: 62 / 6900 ,
Chg loc: 910 : li PAGE 3 of 4
- 1 JOURNEYMANS WORK REPORT Actual Start Date: Time: Actual Completion Date: Time: '
~7 9d 7v*L - 3r- % 3 36 &-
Note: Journeyman shalld ign and date text after their entried.
Trouble Found: i This Section is NOT Applicable for PMs or other planned jobs '
l l
l Work Performed:
bW AM J Moz /u, ops / - ,
a ssc . 4) A M o/3 /2.3 W &c5SQVts totHC$S o .
4 -Sf- %S l l
Continued on Additional Sheets:
Suggestions For Future Planning / Variance Reason: Yh '
/f .
1 Date Supervisor Date
/
Supv/F/.'2&n/ChiL/ r zwu gj g
% Q QCTnUecMrOUYteED
,4 6- s o, y a
Pag 31 of 454 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 2 GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018 M 5 ,' REVISION 47 8l u 7'l
.4,
1.0 TITLE
gc, \[ _ o /C - 28 PRO ODUCTIOl MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVE mal PROGRAM
- 2.0 REVIEW AND APPROVAL
Reviewed by Facility Review Group , 10/10 1985 Approved by D. A. Sacer Plant General Manager 10/28 1985 Revision 47 Reviewed by F R G 6/10.6/17 1996 Approved by J. Scarola Plant General Manager 6/17 1996
3.0 PURPOSE
This procedure provides the necessary instnjetions to perform preventive
- maintenance (PMs) on safety-related and Tech. Spec. equipment as required by j Technical Specifications 6.8.1 2
4.0 PRECAUTIONS & LIMITS: 4.1 The PM files in this procedure can only be performed under direction of an approved NPWO in accordance with Administrative Procedure AP 0010432,
" Nuclear Plant Work Orders."
4.2 Clearances shall be established for the equipment on which the PM is to be performed prior to any work in accordance with 0010122, "In-Plant Clearance Orders." 4.3 The frequency of performance of PM files is subject to Tech. Specs., the performance history and vendor recommendations. Frequencies for the attached PMs are maintained in the PM Planners Scheduling Program and may only be changed upon approval of Technical Support personnel (TS). 4.4 Refer to the individual PM attachments to this procedure. _ S 2 OPS
-- m, M C'lll v .,....,...,,,
DATE i i~ DOCT PROCEDURE DOCN 2.M-o018 J.'$2[.hjP ~~.! d mb- D* COMP COMPLETED ITM 47
Page 45 of 454 ST. LUCIE UNIT 2 i GENERAL MAINTENANCE PROCEDURE NO. 2 M-0018. REVISION MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVFM i MAINTENANCE PROGRAM APPENDIX A PM 01601, 01602, 01603, 01604 (Page 3 of 16)
2.0 Procedure
(continued) 2.1 (continued) 2. While working around these valves EHC fluid may be encountered. Always use safe work practices, ERC fluid is an extreme irritant. Avoid contact with skin and/or eyes. Flush immediately with water if accidental contact is made. See Material Safety Data Sheet (MSDS) No. 957 for additionalinformation. Read and follow all steps in the FYRQUEL EHC E Usage Information Sheet attached to this PM wnen working with EHC. 3. Operations assistance will be required during the performance of this PM. 4. These valves must be returned to service within four (4) hours to meet Tech Spec requirements. Therefore the following actions shall be i taken to prevent possible delays: i 4 A. i The joumeyman shall obtain an ROS for an air motor / hydraulic pump ! assembly (M&S No. 629-06910-5). ! B. The joumeyman shall perform a physical hands on verification that I i the hydraulic pump assembly is available in stores to be drawn out if it is determined at ump hange-out is required. Verified by m r-
/7 M g Date 5/.ZfC/fge__
j C. Planning shall issue PM Nos. 01605 through 01608 for air motor / hydraulic pump assembly change-out if needed. 5. Performance of this PM may identify problems that could require l&C ! corrective action therefore before starting, ensure that l&C personnel are l . on site and aware that they may be needed. 6. 4 Location of the valves is on the steam trestle at the 43' elevation. J e
. - . .. - . - . ~ , . ..
Pega 46 of 454
)
i ST. LUCIE UNIT 2 i GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018, REVISION - . l MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTI - l 8 ~ MAINTENANCE PROGRAM ' APPENDIX A PM 01601,01602,01603,01604 (Page 4 of 16)
2.0 Procedure
(continued) 2.2 Acceptance Criteria / inspection Guidelines / Corrective Action:
- 1. Nitrogen Bottles Verification:
- a
, A. Acceptance Criteria: The two (2) 6000 lb. nitrogen bottles (secured outside of the steam l trestle enclosure) must have a pressure of 4,000 psi or higher. I
\
B. Inspection Guidelines:
.I Observe the pressure in each nitrogen bottle by attaching the nitrogen regulator and gage assembly to the valves on top of each nitrogen !
bottle. Tighten the chuck to prevent gas leakage from the valve- I regulator connection. Slowly open the nitrogen valve on top of the nitrogen bottle and observe the pressure reading at the gauge. When finished, bleed off pressure and disconnect the regulator. Record the pressure below: ! Bottle #1 Pressure (PSI) Initials & Date bJOO
~ ~
M 9-)R-O Bottle # 2 Pressure (PSI) fnitials & Date bE&) W ~Y-lRf6 C. Corrective Action: If the pressure in a nitrogen bottle is below 4,000 psi, obtain a replacement nitrogen bottle from Unit 2 stores.
1Page 4B of 454 ST. LUCIE UNIT 2 GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018. REVISIO _ MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIV: MAINTENANCE PROGRAM APPENDIX A PM 01601,01602,01603,01604 (Page 6 of 16)
2.0 Procedure
(continued) 2.2 (continued)
- 2. (continued)
B. (continued) '
- 2. (continued) a.
Measure accumulator pressure and surface temperature. Record below. Accumulator Pressure (PSIG) Initials & Date 3500 ,MA 7. sI A4 i Accumulator Temperature (*F) Initials & Date IOQ S & Pyrometer M & TE No. 1-3/-9d Initials & Date E- 714 % v_st -94 3. Using the attached Accumulator - Nitrogen Precharge Pressure vs. Accumulator Temperature graph, determine if the accumulator pressure is between the upper limit and the lower limit on the graph for the measured temperature. Pressure Between Limits (Yes/No) Initials & Date Ye c:, A 1 9.2 7 - SI - %
Pago 51 of 454 l ST. LUCIE UNIT 2 ! GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018. REVISIOW . MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVI:X f
~
_ MAINTENANCE PROGRAM
\ APPENDIX A PM 01601,01602,01603,01604 (Page 9 of 16)
2.0 Procedure
(continued) 2.2 onlinued)
- 2. (continued)
C. (continued)
- 2. continued)
N g.\ Measure the final accumulator pressure and temperature. Record below. N Final Accumblator Pressure (PSIG) initials & Date N Final Accumulator Th(nperature (*F) Initials & Date N Pyrometer M & TE No. Initials & Date N h h. N Verify that the final accumdator pressure is between the upper and I,ower limits on thMraph for the measured temperature. Pressure Between Limits (Yes/No) hitials & Date N
- i. Reduce the charging regulator setting an lose the nitrogen cylinder valve.
- j. Loosen the charging regulator connection to the itrogen test tee to allow nitrogen to escape, then remove the nnection.
Pags 53 of 454 1 ST. LUCIE UNIT 2 e GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018. REVISION y MECHANICAL MAINTENANCE SAFETY RELATED PREVENTIV: ]" , N MAINTENANCE PROGRAM N APPENDlX A
\ ~
\ PM 01601,01602,01603,01604 (Page 11 of 16) 2.0 Proc' ure: (continued) 2.2 (cominued)
- 2. (co tinued) ,
% C. (continued)
\! \ \ 3. ontinued) s
\\\ \\ I
\
- d. Reinstall the test tee cap.
- e. Ha erations open the nitrogen pressure switch isolation valve.
( kk f. Snoop the p for leaks and tighten if necessary.
\ g. Record final nit en pressure and accumulator surface x temperature belo .
Final Accumulator Pressure (PSIG) Initials & Date N Final Accumulator _ Temperature (*F1 Initials & Date
\
Pyrometer M & TE No. initials & Date
\
\
h.
\
Verify that the final accumulator pressure is between the upper and lower limits on the graph for e measured temperature. Pressure Between Limits (Yes/No) Initials &'Date
\
l
s Pcga 54 of 454
/
ST. LUCIE UNIT 2 GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018. REVISION .g _ MECHANICAL- MAINTENANCE SAFETY-RELATED PREVENTIVEW. , MAINTENANCE PROGRAM APPENDIX A PM 01601,01602,01603,01604 3 (Page 12 of 16)
2.0 Procedure
(continuea) 2.2 (continued)
- 3. Hydraulic pump / air motor assembly performance check:
1 A. Acceptance Criteria: The hydraulic pump must charge the accumulators to 5000 psig or greater. B. Inspection Guidelines: I
- 1. Notify Operations to hydraulically recharge the accumulators and verify the pressure increases while the hydraulic pump is ;
operating. '
- 2. While the pump is operating, snoop the air motor and all air line fittings from the root valve to the air motor and check the air lubricator for leaks.
- 3. Correct leakage that can be stopped by minor tightening and/or initiate an NPWO for more complex work if needed.
- 4. When the pump stops, record final accumulator pressure and leak check results below:
Final Accumulator Pressure (PSIG) initials & Date 5000 M 7 -5 f-9 6 Leaks Found (Yes/No) If Yes, describe initials & Date Yes- 0.k'. v)v. FNv. eP Ps 09 2&.M '7 3l-%--
- 5. Have Operations isolate the air to the hydraulic pump. Then add Regal R&O 32 oil to the air line oiler to within 1/4" of the top of the bowl.
- 6. Have Operations retum the air valve to the normal alignment.
. 1 F
Paga 55 of 454 ST. LUCIE UNIT 2 GENERAL MAINTENANCE PROCEDURE NO. 2-M-0C- F' ilON- i MECHANICAL MAINTENANCE SAFETY-RELATED?E .TIV MAINTENANCE PROGRAM l APPENDIX A PM 01601, 01602, 01603, 01604 i (Page 13 of 16)
2.0 Procedure
(continued) ! 2.2 (continued)
- 3. (continued) 1 C. Corrective Action-i 4
If the final accumulator pressure is less than 5000 psig, nave ! Operations /l & C check air regulator adjustment. T en if me problemj still exists, with the concurrence of Operations, cna s out the hydraulic pump / air motor assembly in accordance i I i through 01608 as applicable. 1 PM 01605 ! Pump Changed Out (Yes/No) 1 Initials .. Date ! AIO $ 7- Jl'/- 94 2.4 Additional Maintenance Observations 1. Inspect the valve in general to assess any problems which mav affect it's ability to perform its function. Record the observations below and to whom they were reported. COMMENTS: C , yN /ek - 8 N.W. O PS-04 -2 B 2 i REPORTED TO: L , beorg e-INITIALS: M DA TI 7 '3l / 95 - 6
d Pcg3 56 of 454 ST. LUCIE UNIT 2 ' GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018. REVISION < ^ MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVECj MAINTENANCE PROGRAM
-~
APPENDIX A PM 01601,01602,01603,01604 I (Page 14 of 16) 4
2.0 Procedure
(continued)
\
2.4 (continued)
- 2. Document any additional inspections or maintenance performed during this PM and to whom the observations or additional work was reported. '
- COMMENTS: k + 0 32 do Oiler REPORTED TO: l- . beo ra e_
INITIALS: DATE 7 /31/ N 2.5 Housekeeping
- 1. Clean the area affected by this PM.
- 2. Dispose of any waste EHC fluid in the EHC waste fluid drum at Backfit's hazardous waste drum storage area (the key to this area is in the Backfit Maintenance Shop).
3.0 Post Maintenance Testing 3.1 Release the MFIV to Operations and stand-by until Operations is satisfied that the MFIV is ready for service. 3.2 Retesting for work performed by this procedure is contained within the procedure steps, therefore, no additional Ol 11-PR/PSL-2 testing is required. CAUTION EHC Fluid is an extreme irritant. Avoid contact with skin and/or eyes. Flush immediately with water if accidental contact is made. 3.3 When the MFIV is being retumed to service, Operations will ensure that the EHC fluid is at the correct levelin the reservoir. If requested by Operations, lower the EHC Fluid level by draining fluid from the reservoir drain into a waste container.
Pags 57 of 454 ST. LUCIE UNIT 2 - w-GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018. REVISION-MECHANICAL MAINTENANCE SAFETY REl.ATED PREVENTIVECA MAINTENANCE PROGRAM I APPENDIX A . PM 01601,01602,01603,01604 (Page 15 of 16) 4.0 Additional Information 4.1 If the air motor / pump assembly is changed out, retum the used assembly to the covered work area to be rebuilt under a separate NPWO. 4.2 Anchor Darling Tech. Manual, PSL File'#2998-11467.
/'
PM COMPLETED - ALL REQUIRED DATA AND SIGN-OFFS CHECKED Foremen's Name (print & sign) 2. h e o m e.- Q /
- 7b
~
Date 7 13f I Yh l l
M
- Component' 125V BATT 1B Sys: 50 Train: B Fac: PSL Unit: 01 Associate.: Assign Priority: A2 ll
' MASTER Name: 1~.5V DC BATTERY 1B Work Type: 7 WORK ORDER TASK Location: RAB/43/N-RA1/W-RAI LMD: 3 96020748 01 Defect / Request: U/1 WEEKLY PM OF 1B 125V DC BATTERI ER/PWO: 65 / 2565 ES Chg Loc: 915 PAGE 1 of 4 l
Detailed Explanation: PM ID: PMW1002 - DUE BY DT: 08/20/96 EARLY DT: 08/19/96 LATE DT: 08/21/96 Work Request: More: Def Tag: Loc: Trbl/Brkdown: LCO: Unit Cond Reg: , NPRDS: Y Fail Date: Time: Det: Stat: Symp: Originator: Dste: Dept: Approve By: Date: Task Determination Data: IST Required : N NCR/CR : N/A Safety Class: SR PMT Required : N PCM : N/A -Q Group : 1E 10 CFR 50.49 : N EQ Doc Pk3 : N/A Assign To : U1EM 3 ; j Reg Guide 1.97 : N Seismic Cat : I Est M/H : 2.00 l ASME XI(ISI) Reqd : N Scaffold Req : N Crew Qty : 2 Security Clearance: N l Fire Prot Reg: N Insul Rem : N Clearance Required: N Clearance No : RWP Required: N RWP No: RCA M/H: L1: L2: L3:
)
QC Requirements: QC Required : Y QL-A More: Work Order Task
Description:
TECH SPEC REQUIREMENT I SEE PAGE 2 FOR TASK DESCRIPT!ON. SAFETY RELATEDlQUAllTY RELATED PARIS USED MUST MEET REQUIREMENTS OF APPENDtX A CF Q1-31 More: Y Planned By : VXDOEKZ DEFRANCESCO V Date: 08/13/96 Pkg Appr By : PRE-APPR Date: 08/13/96 Time: 21:26 QC Approval : PRE-APPR Date: 08/13/96 i
********************** OPE ONS ROVAL TO START ***********************
NPS Start Permission: 7,v r LCO(Y/N): j Start Date/ Time : N/ h J (> fc, / <O :r S /
~
"I ' L
- 1 i
NPS Completion Notif: . ; . Major Failure: Compl. Date/ Time: WLT !!J/! / 94 4 Ma3or Action : Deficiency Tag Removed (Y/NPi ~ tiV
/
1
Component: 125V BATT 1B Sys: 50 Train: B Fac: PSL Unit: 01 ? Associate: Assign Priority: A2 MASTER l Name:125V DC BATTERY 1B Work Type: 7 WORK ORDER TASK Location: RAB/43/N-RA1/W-RAI LMD: 3 96020748 01 Defect / Request: U/1 WEEKLY PM OF 1B 125V DC BATTERI ER/PWO: 65 / 2565 FS Chg loc: 915 PAGE 2 of 4 1 Continuation of Task
Description:
********************************************************************** l 1> VERIFY THAT YOU ARE WORKING ON THE CORRECT UNIT AND COMPONENT (S) i PRIOR TO STARTING ANY WORK.
UNIT 1 1B BATTERY BANK: INT:.b:' ...DATE: . / .k h/ . . INT:........DATE:.../.../.... I 2> PERFORM WEEKLY BATTERY INSPECTION IN ACCORDANCE WITH MAINTENANCE PROCEDURE 0960163. 3> CHEOK TO ENSURE THE BATTERIES ARE CLEAN AND NO CORROSION IS PRESENT ON THE INTER-CELL CONNECTIONS. i 1 4> INSURE NO CRACKS OR DAMAGE TO BATTERY CAPS ARE PRESENT. REPLACE IF ' NEEDED USING M&S #008-46653-0. l 5>. CHECK CONDITION OF THE FLOOR, SINK, ETC. CLEAN IF NECESSARY. 6> DOCUMENT ALL WORK PERFORMED AND AND TROUBLE FOUND ON THE JOURNEYMANS WORK REPORT. 7> THIS NPWO IS CLASSIFIED AS NUCLEAR SAFETY RELATED, AND AS'SUCH, ALL PARTS USED MUST CONFORM TO THE PARAMETERS OUTLINED IN QI 8-PR/PSL-1 ENSURE A COPY OF THE ROS IS ATTACHED TO THIS PACKAGE FOR ALL PARTS USED. 8> CONTACT LICENSING DEPT, NOTIFY THEM THAT E P.M. HAS BEEN SATISFACTORILY COMPLETED. INT:........DATE:b./[.k/.f.g , FILE # 09-60420
******************w***************************************************
NOTE * " AN ON THE JOB " TRAINING JPM IS AVAILABLE FOR THIS N.P
***************************************************************.W.O. *******
Component: 125V BATT 1B Sys: 50 Train: B Fac: PSL Unit: 01
, l Associate: Assign Pr:Lority: A2 MASTER I
fName:125VDC. BATTERY 1B Work Type: 7 WORK ORDER. TASK Location: RAB/43/N-RA1/W-RAI LMD: 3 96020748 01 Defect / Request: U/1 WEEKLY PM OF 1B 125V DC BATTERI ER/PWO: 65 / 2565 ES Chg loc: 915 PAGE 3 of 4 JOURNEYMANS WORK REPORT Actual Start Date: Time: Actual Completion Date: Time: [ 2 b
- Pd C;.5]O h E0 N cfp Note: Journeyman shall sign and date text after their entries.
' Trouble Found:
This Section is NOT Applicable for PMs or other planned jobs - Work Performed: fkr-fer,w
/
? N- cm he /E 28 m k=r MPS 696 CME- dea- C b*~
(* ,fD .1 [d4 M : en :ade /77 A _ l Continued on Additional Sheets: Y N Suggestions For Future Planning / Variance Reason: Supv/ Foreman / Chief Date Supervigr Date QC Inspectm* Date
~. cm,- . o. m g
- b _w ' -
1
/
Pcgs 1 of 20 FLORIDA POWER & LIGHT COMPANY ' ST. LUCIE PLANT
, MAINTENANCE PROCEDURE NO. 0960163 REVISION 15 Pst
1.0 TITLE
d ( )!-
!3 3 !4 1 o ,
125 V DC SYSTEM WEEKLY MAINTENANCE - PROCEDURE PR05i. 2.0 REVIEW AND APPROVAL: Reviewed by Facility Review Group 8/22 19 89 Approved by G. J. Boise Plant General Manager 9/11 19 89 Revision 15 Reviewed by Facility Review Group 3/61996 Approved by J. Scarola Plant General Manager 3/61996
3.0 PURPOSE
3.1 To provide instructions for the weekly maintenance checks of the St. Lucie Plant safety batteries. 3.2 To satisfy Technical Specification 4.8.2.3.2.a (Unit 1) and 4.8.2.1.a (Unit 2). 4.0 PRECAUTIONS AND LIMITS: 4.1 Steps marked with contain points which are commitments. Make no changes in these steps without first consulting the department head or his designee. 4.2 Do not exceed 345 amps DC output or 90 amps AC input on any battery charger. 4.3 Notify the NPS/ANPS if any cell parameter exceeds the specifled values (Tech. Spec. Table 4.8-2., Category A Limits). 4.4 Do not allow any smoking, open flames or sparks in the battery rooms. S OPS 4 JGri !NFORW\TK'? : ML7 . o$T CT PROCEDURE
'"i!3 DOCUMENr15 NOT CCNikc L'O r.!FOAE USE. DOCN 0960163 96FY INFCRMATION Wlin A CC? 3 .:0 00CUMENT. ; SYS I
9.cR!DA TCMR
- NO UGHT CC. " . Ali FLwL . COMP COMPLETED
; 2ATdVIK!HED lI l b :.NITImLS L l DATI'vM ' ,' ' JiT:ALS
- Pags 2 of 20 I
ST. LUCIE PLANT ,, MAINTENANCE PROCEDURE NO. 0960163, REVISION 15 125 V DC SYSTEM WEEKLY MAINTENANCE ! ) - 4.0 PRECAUTIONS AND LIMITS: (continued) a t 1 4.5 Battery room ventilation fans shall be running at all times. I 1 A - 1RV-2,1HVS-5A or 5B 2A - 2RV-1, 2HVS-5A or SB 1B - 1RV-1,1HVS-5A or SB 2B - 2RV-2, 2HVS-5A or 58 4.6 Exercise care not to spill any battery acid. Promptly wash off any spilled acid l with large amounts of water.
)
l 4.7 Determine the cause of any unintentional alarm and correct before proceeding i , with any step in this procedure. l 4.8 Goggles, face shield and acid resistant gloves ana rprons should be wom
- whenever handling battery acid, i !
j 4.9 Wipe electrolyte spills on cell tops and containers with bicarbonate of soda i solution. Do not use hydrocarbon-type cleaning agents (oil distillates) or strong alkaline cleaners, they may cause the cell containers and covers to crack. When needed the solution should be mixei 1 lb. bicarbonate of soda j to 1 gallon of water. 4 l 4.10 Use caution when wiping up acid on cell tops to not allow the bicarbonate of [ soda solution to get into the cell. } 4.11 Request Operations assistance as necessary for breake; and equipment j operations. i j 5.0 RELATED SYSTEM STATUS: NPWO 06 d
- ~
5.1 Gems Planner - record current pilot cell for the battery to be checked at the beginning of Section 9.0. Initials ( Date 15 /.hp
. Pago 5 of 20 ST. LUCIE PLANT . MAINTENANCE PROCEDURE NO. 0960163, REVISION 15 125 V DC SYSTEM WEEKLY MAINTENANCE 9.0 DETAILED PROCEDURE: NPWO M S:h )
BATTERY \~b PILOT CELL \b 9.1 Complete the following: 1 1.- Fill in the general information and record the specifir: gravity (SG), electrolyte level, and temperature of the pilot cell below. Correct SG readings for temperature and level using the correction factors in Tabie 1.
- 2. Using DVOM record the pilot cell and battely terminal voltages below.
l Item TS Tolerance Actual i PC Specific Gravity - -
/.o o PC Corr. Spec. Gravity T 4.8-2 2 1.195 / Z//
PC Electrolyte Temp. T 4.8-2 2 50'F ' (/O PC Electrolyte Level T 4.8-2 > Min s + 1/4" p PC Voltage T 4.8-2 2 2.13 VDC p.f4 Battery Terminal Voltage 2129 VDC f3g.7 i
- Unit 1 - 4.8.2.3.2.a.2
- Unit 2 - 4.8.2.1.a.2 '
M&TE Nos. Hydrometer EN# - C6 P- Thermometer E-9// Initials h / Date[/20/ 94 9.2 Visually inspect the battery for loose material, dirt, dust, corrosion at terminal connectors, cracks and electrolyte leaks. Record any discrepancies on the NPWO.
- 1. . Wipe all cell tops with damp rags to remove accumulated dust.
i 4
Pcg3 6 of 20 ST. LUCIE PLANT MAINTENANCE PROCEDURE NO. 0960163, REVISION 15 125 V DC SYSTEM WEEKLY MAINTENANCE 9.0 DETAILED PROCEDURE: (continued) NPWO b /r D 9.2 (continued)
- 2. Wipe up any spilled acid with rags moistened in bicarbonate of soda solution followed by a damp rag.
I Initials ( Date / /2D/ 90 9.3 Inform the Control Room and perform ground checipon DC bus cabinet. Both
- lights should be of approximately equal brilliance. gT/UNSAT (circle one)
Initials
- M Date < / 26/ 96
- 9.4 Complete the following:
- 1. Using the installed panel meters, read and record the following:
Battery Bus Volts (in DC Bus Cab) /R15 Battery amps (in DC Bus Cab) Battery Charger DC amps
- Battery Charger DC volts
- 2. Using the DVOM read and record the output voltage and amps of the charger at the output shunt meter connections. Calculate output amps using the following formula:
MV X 10 = amps Installed Meter DVOM Battery Bus Voltage
- Battery Bus Amps
' () Amps dd Battery Charger / 3 l Volts gd l (3 # l Battery Charger /23
- Volts /,3f' l f34 8 l/R15 DVOM M&TE No. E- 6 Y Initials Date cf /Ja/ 9%
l
, Prg) 7 of 20 ST. LUCIE PLANT . MAINTENANCE PROCEDURE NO. 0960163, REVISION 15 125 V DC SYSTEM WEEKLY MAINTENANCE i
9.0 . DETAILED PROCEDURE: (continued) , 9.5 If the battery bus voltage as recorded in step 9.4.1, is not between 133.5-135 VDC (131.5 - 133 VDC for 59 cell batteries) on float or 136-137.5 on equalize as read with DVOM. Complete Appendix A. /R15 Appendix A required YE (circle one) l Initials Date D2C/ 94 NOTE The following step is NA if one of the normal battery chargers is out of service i or the AB Battery Charger is on line in place of one of the normal chargers for this battery. 9.6 Compare the current output of each of the parallel chargers. if tha currents are not within 17 amps, as read on the DVOM, perform the applicable steps of Appendix B. If the battery is on equalize (136 - 137.5 V), this step is NA.
- Appendix B required YEh (circle one)
Initials Date M/20/ 94 , 9.7 All data has been reviewed and any parameters not within the given specifications have been reported to the Nuclear Plant Supervisor. Initials LN Date [ /M/ P4 4 4 1 I
Pcge 8 of 20 ST. LUCIE PLANT
. I MAINTENANCE PROCEDURE NO. 0960163, REVISION 15 125 V DC SYSTEM WEEKLY MAINTENANCE 9.0 DETAILED PROCEDURE: (continued) i s 9.8 If any pilot cell parameters are not within the spacified limits, complete 4
l Procedure No. 0960164, "125 VDC System Monthly Maintenance", within l 24 hours. '
- 1. Procedure 0960164 required YE (circle one)
- 2. If yes, notify Electrical Supervisor.
Initials Date /d# / 94 Completed by: { E' Date # /#8 / 'P / Reviewed by:
.)
/ ' '- c '
**~~
")
DateL / - "/ Chief Electrician lf required, NPWO writt complete procedure 0960164 within 24 hours. NPWO No. l l Data reviewed for Technical Specification co.upliance and test results approved. l 1 Electrical Supervisor -
! Date h /96 5
L 3 l
- t' Component
- 125V BATT 1A Sys: 50 Train: A Fac: PSL Unit: 01
- y. Associate: l {
Assign Priority: A2 MASTER
, Nam': 125V CC EATTERY 1A Work Type: 7 WORK ORDER TASK Location: RAB/43/N-RA1/W-RAH LMD: 3 96020747 01 Defect / Request: U/1 WEEKLY PM OF 1A 125V DC BATTERI ER/PWO: 65 / 2564
, ES Chg Loc: 915 PAGE 1 of 4 l
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Detailed Explanation. PM ID: PMW1001 DUE BY DT: 08/20/96 EARLY DT: 08/19/96 LATE DT: 08/21/96 l More: Work Request: Def Tag: Loc: 1 J Trbl/Brkdown: LCO: Unit Cond Req: NPRDS: Y Fail Date: Time: Det: Stat: Symp: Originator: Date: Dept: I j Approve By: Date: l
~
Task Determinatior Data:
- IST Required
- N NCR/CR : N/A Safety Class: SR PMT Required : N PCM : N/A Q Group : 1E l
10 CFR 50.49 d
- N EQ Doc Pkg : N/A Assign To : U1EM 3 Seismic Cat Reg Guide 1.97 : N : I Est M/H : 2.00 ASME XI(ISI) Equ : N Scaffold Req : N Crew Qty : 2 Security Clearance: N Fire Prot Reg: N l 4
Insul Rem : N i Clearance Required: N Clearance No : RWP Required: N RWP No: RCA M/H: L1: L2: L3: 4 QC Requirements: QC Required : Y QL-A ... 4 More:
- Work Order Task
Description:
m.. .IRgg IECH SPEL. .... ; l l l SEE PAGE 2 FOR TASK DESCRIPTION. WEii dELnTEDiOUAUD iELATED EARIS USE0 MUST MEET RECUiREMENTS Of /IPENDlX A CF ".' .1 More: Y Planned By : VXDOEKZ DEFRANCESCO V Date: 08/13/96 Pkg Appr By : PRE-APPR Date: 08/12/96 Time: 21:26 QC Approval : PRE-APPR Date: 06/13/96
********************** OP TION A PROVAL TO START ***********************
* ) /j
- NPS Start Permission: N ,
LCO(Y/N):
- Statt Date/ Time : /
/ - U/ R J dr / __ ui r 2 i
************************** *** **s*******************,;** ****************
NPS Completion Notif: Major Failure: Compl. Date/ Time: Deficiency Tag Removed (Y/N)i
% kN%/ ' '
Of(6 Ma]or Action :
/
T l Component: 125V BATT 1A Sys: 50 Train: A fac: PSL Unit: 01
,, Associate: Assign Priority: A2 MASTER Name:125V.DC BATTERY 1A Work Type: 7 WORK ORDER TASK Location: RAB/43/N-RA1/W-RAH LMD: 3 96020747 01 De f ect / Req' Jest : U/1 WEEKLY PM OF 1A 125V DC BATTERI ER/PWO: 65 / 2564 ES Chg loc: 915 l
PAGE 2 of 4 Continuation of Task
Description:
' 1> VERIFY THAT YOU ARE WORKING ON THE CORRECT UNIT AND COMPONENT (S) PRIOR TO STARTING ANY WORK. UNIT 1 1A BATTERY BANK: INT:. ...DATE:.k./2./b. INT:........DATE:.../.../.... 2> PERFORM WEEKLY BATTERY INSPECTION IN ACCORDANCE WITH MAINTENANCE PROCEDURE 0960163. 3> CHECK TO ENSURE THE BATTERIES ARE CLEAN AND NO CORROSION IS PRESENT ON THE INTER-CELL CONNECTIONS. 4> INSURE NO CRACKS OR DAMAGE TO BATTERY CAPS ARE.PRESENT. REPLACE IF 4 NEEDED USING M&S #008-46653-0. 5> CHECK CONDITION OF THE FLOOR, SINK, ETC. CLEAN IF NECESSARY. 6> DOCUMENT ALL WORK PERFORMED AND ANY TROUBLE FOUND ON THE t JOURNEYMANS WORK REPORT. 4 7> THIS NPWO IS CLASSIFIED AS NUCLEAR SAFETY RELATED, AND AS SUCH, ALL PARTS USED MUST CONFORM TO THE PARPdSTERS OUTLINED IN QI 8-PR/PSL-1 ENSURE A COPY OF THE ROS IS ATTAC:iED TO THIS NPWO FOR ALL ] PARTS USED. 8> CONTACT LICENSING DEPT, NOTIFY THEM THAT THE P.M. HAS BEEN SATISFACTORILY COMPLETED. INT: .DATE:.$./29/.b. FILE #60410 NOTE * " AN ON THE JOB" TRAINING JPM IS AVAILABLE FOR THIS N.P.W.O. l l 4 h
. - . . - . . - - . - . . . . - .~.- ~. __ --.. - . .~ . ..- _ -
k3 i lD Component: 125V BATT 1A Sys: 50 Train: A I Fac: PSL Unit: 01 l 'f Associate: Assign Priority: A2 ! MASTER ' s i Name:125V. DC BATTERY 1A Work Type: 7 WORK ORDER. TASK , ; Location: RAB/43/N-RA1/W-RAH LMD: 3 96020747 01 Defect / Request: U/1 WEEKLY PM OF 1A 125V DC BATTERI ER/PWO: 65 / 2564 ES Chg loc: 915 4 PAGE 3 of 4 i s l JOURNEYMANS WORK REPORT ! Actual Start Date: Time: Actual Completion Date: Time: d '. 26 - }t' ,-Q S. [6 Pd Cffe : 4 Note: Journeyman shall sign and date text after their entries. l Trouble Found-This Section is NOT Applicable for PMs or other planned jobs . 1 4 4 l Work Performed: <7 , rYr ?wb h. N. 22 . /d EW as ?w AV Y C W cfCE den ckn r ,( C L M*N i o cd he./vuy/ i i i i 4 5 1 Continued on Additional Sheets: Y N Suggestions For Future Planning / Variance Reason: 1 Supv/, Foreman / Chief Date Supervisor Date QC Inspector Date ($l lO S~ v ?- 0f l S _h. 'N r a
Pags 1 of 20 0
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FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT
, MAINTENANCE PROCEDURE NO. 0960163
- REVISION 15 a
PSL
$ j
)
1.0 TITLE
B o ! "A i 125 V DC SYSTEM WEEKLY MAINTENANCE PROCEDURE PR0$i.- 2.0 REVIEW AND APPROVAL: Reviewed by Facility Review Group 8/22 19 89 Approved by G. J. Boissy Plant General Manager 9/11 1989 Revision 15 Reviewed by Facility Review Group 3/61996 Approved by J. Scarola Plant General Manager 3/61996
3.0 PURPOSE
4 3.1 To provide instructions for the weekly maintenance checks of the St. Lucie Plant safety batteries. 3.2 To satisfy Technical Specification 4.8.2.3.2.a (Unit 1) and 4.8.2.1.a (Unit 2).
- 4.0 PRECAUTIONS AND LIMITS
4.1 Steps marked with 9 contain points which are commitments. Make no changes in these steps without first consulting the department head or his q designee. 4.2 Do not exceed 345 amps DC output or 90 amps AC input on any battery charger.
- 4.3 Notify the NPS/ANPS if any cell parameter exceeds the specified values (Tech. Spec. Table 4.8-2., Category A Limits).
4.4 Do not allow any smoking, open flames or sparks in the battery rooms. S OPS y FOR INFORM TIOk O LY i $5PsoCeDune 4
'rHIS DOCUMENT 15 NOT CONTROLLED. BEFORE uSE.
DOCN 0960163 VERIFYINFORMATION WITH A CCNTECLLED DOCUMENT. SYS
. FLCRIDA POWER AND LIGHT CD. 5T. LUCll: F COMP COMPLETED DAnveRirino 7 ! l6 uf ismALS O exnveunte 7 I smAt5
,, Peg 2 2 of 20 ST. LUCIE PLANT l/ MAINTENANCE PROCEDURE NO. 0960163. REVISION 15 125 V DC SYSTEM WEEKLY MAINTENANCE 4.0 PRECAUTIONS AND LIMITS: (continued) l 4.5 Battery room ventilatlon fans shall be running at all times.
~ 1N - 1RV-2,1HVS-5A or SB 2A - 2RV-1, 2HVS-5A or 5B 18 - 1RV-1,1HVS-5A or SB 2B - 2RV-2,2HVS-5A or 58 .d 1 4.6 Exercise care not to spill any battery acid. Promptly wash off any spilled acid i with large amounts of water. 4 ! 4.7 Determine the cause of any unintentional alarm and correct before proceeding with any step in this procedure. i
- . 4.8 Goggles, face shield and acid resistant gloves and aprons should be wom whenever handling battery acid.
j 4.9 Wipe electrolyte spills on cell tops and containers with bicarbonate of soda 1 i solution. Do not use hydrocarbon-type cleaning agents (oil distillates) or j strong alkaline cleaners, they may cause the cell containers and covers to ' crack. When needed the solution should be mixed 1 lb. bicarbonate of soda i to 1 gallon of water. ! 4.10 Use caution when wiping up acid on cell tops to not allow the bicarbonate of ' j soda solution to get into the cell.
-4.11 Request Operations assistance as necessary for breaker and equipment
- operations.
5.0 RELATED SYSTEM STATUS: NPWO b l 5.1 Gems Planner - record current pilot cell for the battery to be checked at the l beginning of Section 9.0. Initials k Date 9 / \b/M i 2 4
?
j: i
~
A Ptg3 5 of 20 a ST. LUCiE PLANT r o MAINTENANCE PROCEDURE NO. 0960163. REVISION 15 125 V DC SYSTEM WEEKLY MAINTENANCE 9.0 DETAILED PROCEDURE: ' NPWO O N BATTERY /k t" PILOT CELL \V 9.1 Complete the following: 1 Fill in the general information and record the specific gravity (SG), electrolyte level, and temperature of the pilot cell below. Correct SG readings for temperature and level using the correction factors in Table 1.
- 2. Using DVOM record the pilot cell and battery terminal voltages below.
Item TS Tolerance Actual PC Specific Gravity - - f 2,2 PC Corr. Spec. Gravity T 4.8-2 2 1.195 / . gf g, PC Electrolyte Temp. T 4.8-2 2 50*F gry PC Electrolyte Level T 4.8-2 > Min s + 1/4" F PC Voltage T 4.8-2 2 2.13 VDC .:2p/ Battery Terminal Voltage 2129 VDC (34/[
- Unit 1 - 4.8.2.3.2.a.2
- Unit 2 - 4.8.2.1.a.2 M&TE Nos.
Hydrometer EAM-062 Thermometer E4N Initials Date d /2o / 94 9.2 Visually inspect the battery for loose material, dirt, dust, corrosion at terminal connectors, cracks and electrolyte leaks. Record any discrepancies on the NPWO.
- 1. . Wipe all cell tops with damp rags to remove accumulated dust.
, Pags 6 of 20 ST. LUCIE PLANT v MAINTENANCE PROCEDURE NO. 0960163. REVISION 15 125 V DC SYSTEM WEEKLY MAINTENANCE 9.0 DETAILED PROCEDURE: (continued)
NPWO h(c l 9.2 (continued) ;
- 2. Wipe up any spilled acid with rags moistened in bicarbonate of soda solution followed by a damp rag.
Initials Date J /20 /93 9.3 Inform the Control Room and perform ground check n DC bus cabinet. Both a lights should be of approximately equal brilliance. /UNSAT (circle one) Initials ( Date [ /26 / ft < 9.4 Complete the following: i
- 1. Using the installed panel meters, read and record the following:
Battery Bus Volts (in DC Bus Cab) /R15 Battery amps (in DC Bus Cab) l Battery Charger DC amps Battery Charger DC votts
- 2. Using the DVOM read and record the output voltage and amps of the !
charger at the output shunt meter connections. Calculate output amps using the following formula: MV X 10 = amps Installed Meter DVOM Battery Bus Voltage l3ff Battery Bus Amps () l Battery Charger /4 Amps 40 43 i Volts lg _ l /% l Amps 4)() l g9 l Battery Charger /d# Volts g l L'/l 8 l/R15 DVOM M&TE No. E-M Initials (_ Date [_/26/ /4
. 1 g Ptgs 7 of 20 ST. LUCIE PLANT
< MAINTENANCE PROCEDURE NO. 0960163, REVISION 15 125 V DC SYSTEM WEEKLY MAINTENANCE 9.0 DETAILED PROCEDURE: (continued) 9.5 If the battery bus voltage as recorded in step 9.4.1, is not between 133.5-135 VDC (131.5 - 133 VDC for 59 cell batteries) on float or 136-137.5 on equalize as read with DVOM. Cornplete Appendix A. /R15 Appendix A required YEh(circle one) Initials Date 8/ ##/ W NOTE The following step is NA if one of the norrnal battery chargers is out of service or the AB Battery Charger is on line in place of one of the norrnal chargers for this battery.
/R15 9.6 Compare the current output of each of the parallel chargers. If the currents are not within 17 amps, as read on the DVOM, perform the applicable steps of Appendix B. If the battery is on equalize (136 - 137.5 V), this step is NA.
Appendix B required YESh (circle one) Initials (( _ Date / /M] 96 9.7 All data has been reviewed and any parameters not within the given specifications have been reported to the Nuclear Plant Supervisor. Initials b Date [_/ co/ P6 l
. i .. Pcg3 8 of 20-ST. LUCIE PLANT MAINTENANCE PROCEDURE NO. 0960163. REVISION 15 125 V DC SYSTEM WEEKLY MAINTENANCE 9.0 DETAILED PROCEDURE: (continued)
Q, 9.8 If any pilot cell parameters are not within the specified limits, complete I Procedure No. 0960164, "125 VDC System Monthly Maintenance", within l 24 hours.
- 1. Procedure 0960164 required YEhcircle one)
- 2. If yes, notify Electrical Supervisor.
Initials M Date 2_]20/ # Completed by:
. . v -, -
a Date E / 8# / P6
/ '".1- '
Reviewed by: ~ d *' *. Date - / " C/ n Chidf Electrician l l If required, NPWO w ' en to complete procedure 0960164 within 24 hours. NPWO No. / i l ; Data reviewed for Technical Specification compliance and test results j approved. ] Electrical Supervisor -
! Date b /.36_
y a
~
%>h M
& g Component: MV-08-3 Sys: 08 Train:
M Fac: PSL Unit: 02 Associate: VALVE Assign Priority: AA l MASTER Name: THROTTLE / TRIP VALVE FOR AUXILIA Work Type: 5 WORK ORDER. TASK
! RY FEEDWATER PUMP 2C ,
Location: TRSL/22/N-T3/W-TA LMD- ' C6021327 01 f Defect / Request: WILL NOT STAY LATCHED ER/PWO: 62 / 7367 1 Chg Loc: 910 PAGE 1 of 4 Detailed Explanation: *
,- j FIX IT -'
Work Request: 96014061 More: Def Tag: N/A Loc: N/A Trbl/Brkdown: Y 1 LCO: Y Unit Cond Req,: 8 i NPRDS: Y Fail Date: 08/18/96 Time: 06:35 Det A Stat: A Symp: A Originator: CAS0IMV SIMPKINS CA Date: 08/18/96 Dept: OPS Approve By: CAS0IMV SIMPKINS CA Date: 08/18/96 Task Determination Data: IST Required : Y NCR/CR : N/A Safety Class: PMT Required : Y PCM : N/A Q Group : C 10 CFR 50.49 : A EQ Doc Pkg : N/A Assign To : VLV Reg Guide 1.97 : N Seismic Cat : I Est M/H : 8.00 ASME XI(ISI)'Reqd : N Scaffold Req : N Crew Qty : 2 l Security Clearance: N Fire Prot Reg: N Insul Rem : N l Clearance Required: N Clearance No : , RWP Required: N RWP No: RCA M/H: L1: L2: L3: l l QC Re ired : Y l QCRquirembnts: kMrne Der h/ecaa khb GesceZmtut +krAt 0eOA/ p-//-96 2.M$ I' ! V v / . n() l
............................................................../,..S....More: ........
Work Order Task
Description:
Standard: CORRUNIT l t l SEE PAGE 2 FOR TASK DESCRIPTION. t l l More: Y l ! . Planned By : LKBOPWN 3EAN LK Date: 08/18/96 Pkg Appr By : LKBOPWN BEAN LK Date: /96 Time: 07:47 QC Approval : tGeoMeSMgfas1 kr khCG*1 Date: *%f v v 08/1)M [00 $ i
********************** OPERATIONS / APPROVAL TO START ***********************
e 'l *
.
- NPS Start Permission- }'M(A'I.j LCO(Y/N):
Start Date/ Time : - -
/ *
**************************************y ,***********************************
NPS Completion Notif: F m ,- # ' Major Failure: f i Compl. Date/ Time: /- / 5'f 96 / N39 Major Action : ,- Daficiency Tag Removed (Y/N): / /
l 0 f Component: MV-08-3 Associate: VALVE Sys: 08 Train: Assign Priority: AA { Fac: PSL Unit: 02 MASTER Name: THROTTLE / TRIP VALVE FOR AUXILIA Work Type: 5 WORK ORDER TASK ;
-KY FEEDWATER PUMP 2C Location: TRSL/22/N-T3/W-TA LMD: 1 96021327 01 Defect / Request: WILL NOT STAY LATCHED ER/PWO: 62 / 7367 Chg loc: 910 PAGE 2 of 4 Continuation of Task
Description:
l l VALVE WILL NOT STAY LATCHED AFTER BEING TRIPPED.. j THIS JOB IS TO CLEAN AND INSPECT MV-08-3. KEEP BODY CLEAR OF MOVING PARTS OF VALVE AND WORK SAFELY. XXXXXXXXXXXXXXXXXXXXXXXXXXXX JOB TASK XXXXXXXXXXXXXXXXXXXXXXXXXXXXXX a i
<><><><><><><><><><><><><><><><><><><><><><><><><><><><><><><><><><><> l
<> ASSURE THAT YOU ARE WORKING ON THE CORRECT UNIT & COMPONENT (S) <>
<> PRIOR TO START OF WORK. <>
IF POSSIBLE WORK JOB AT THE DIRECTION OF T.S. (BILL GREEN) htEMOVE ANY EXCESS GREASE ON OPERATOR AND TRIP LINKAGE EQUIPMENT. CLEAN. TRIP HOOK AND LATCH UP LEVER AND OTHER PARTS AS NEEDED WITH ALCOHOL. bLEANTHEMATINGSURFACESOFTRIPHOOKANDLATCHUPLEVERWITHSCOTCH BRIGHT. INSPECT PARTS AND DOCUMENT AS FOUND CONDITION ON J.W.R. LIGHT HONING / FILING MAY BE PERFORMED AT THE DIRECTION OF T.S. ENSURE LATCH UP LEVER PIVOT BOLT TO BE WRENCH TIGHT. kTTACHED: REQUIRES VERIFICATION AND SIGN OFFS QI 11-PR/PSL-2 APPENDIX B ATTACHMENT D l
c Component: MV-08-3
'f Associate: VALVE Name:THROT*LE/ TRIP VALVE FOR AUXILI Sys: 08 Train:
Assign Priority: AA Work "'ype: 5 l Fac: PSL Unit: 02 MASTER WORK ORDER TASK RY FEEDWATER PUMP 2C Location: TRSL/22/N-T3/W-TA Q4D: 1 96021327 01 Defect / Request: WILL NOT STAY LATCHED ER/PWO: 62 / 7367 Chg . loc: 910 PAGE 3 of 4 ; JOURNEYMANS WORK REPORT
~
Actual Start Date: Time: Actual Completion Date: Time: 91- Mr- P & o.53 0 P-/ 8- 7 6 O P30 Note: Journeyman shall sign and date text after their entries. Trouble Found: This Section is NOT Applicable for PMs or other planned jobs Work Performed: YAs.lth04A'Y N//// 0 fS , CAfsstl Y#in AY)fc H A m i y O.o f} V- O Er- 3 dlS ' S [ C c ' V N S f '/ *l [ W N C c //o.d . kQW? ford jAd T4//> \/0 $f $/7 Scf f W 9 AN
/3p'o 7~ / w ' pu?^3. .Ahe/ dos 7r' in r i VAd Vf MANuA/.IV duW hlS//. f0$
0 PS /nsm A 22 v ' 7Ri%/d //4.<'VE AeAvN
/k># 0 I- // k4 T ].
~
5 l P ci N Z m/ 7o @ Orserol AffA A wd SH 7~ A w y' >$cdS. 0 P3 SEfit t.s 7tW /)24d7 5 / y' f/*' h d. Suggestions For Future Planning / Variance Continued on Additional Reason: Sheets: h 1 1 Supv/ForemaE4. Chief Date Supervisor Date QC Inspector Date (( 7-/$'-f #Bd' QC ROUTED ear #
o Component: MV-08-3 .Sys: 08 Train: Fac: PSL Unit: 02 ! j Associate: VALVE } Assign Priority: AA , MASTER i Name:THRQTTLE/ TRIP VALVE FOR AUXILIA Work Type: 5 WORK ORDER. TASK RY FEEDWATER PUMP 2C Location: TRSL/22/N-T3/W-TA 4D: 1 96021327 01 Defect / Request: WILL NOT STAY LATCHED ER/PWO: 62 / 7367 Chg loc: 910 PAGE 4 of 4 Continuation of Trouble Found/ Work Performed: 0C A ct Y Frtd QA4fre Ps d . (O A' ) 7Pn OAsavs &a con o u fr br:2$- S S,o J ./ m # dwat_s
-- , Y_ - . -S*~S&
1 Continued on Additional Sheets: Y N j
m, v . NO , PROCEDURE TITLE: PAGE: ) R - gj.. CONTROL OF PLANT WORK ORDERS 2
M
- 3 g g . NOa PROCEDURE
! .c. ,c g ., ADMINISTRATIVE PROCEDURE 10432 ST. LUCIE PLANT APPENDIX B E HARD COPY WR / NPWO
#I. (Page 1 of 3)
Th@S t- Charge Loc ER/NPWO O /
%4EL. - Account i WJOLMD. * :.1. Priority Page of
' b Grimph Task LMD
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- 9 Defkiency,T3g No. AN
- DeAciency Tag Locahon N LA. LCO (Y / N) Y LMD: Iv l TrtWBrkan (Y / N) V Unit Cond Re(d P Prionty- A4 l g* [h'., ) ,r "' NPRDS Failure Detemrne P/it-Ft 6 02-05 i
- 2 Failure Detection A Status at Time of Failure A- Symp T of Failure A e, , Origriator e W M Dept. CO Date b L/h Approved by ~ DatebbE 4
- Ii. * -
s i 0 YOrder Taak Deecrtption DEAw N@ ll*/N4*)G vo$ fr-7d' &*sfa s*J YrAd j .;
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i : 5.
- ( .
Rework Job (Y / N) A/d Eaqa, desc. attacned [Y ' ' Planned By M, # - l A#* r 0 6*W Datamme MNNU Approved By // Datamme NN Of
; w.
~i ,hTak Determirb Data:
, '.; . ',. 10 CER 50.49 Applicable? IST Required? V6J CR
.f. , Reg. Guide 1.97 Apphcable? NPRDS Related? PCM
,,,, yi E i-frmdasvi Removal Reqd? u# Scaffold Reqd? 4/ O Seistruc Cat.
; ASME XI(ISI) Reqd? uo Fire Prot Reqd? W4 EQ Doc Pkg.
j j .. Control Roorn Component? RWP Required? W RWP Number i lj 'y 'SeaJrtty Clearance Reqd? - PMT Required? VE 5 'MCL List j ,, Clearance Required? g Clearenz Number ^//A l h. k i {;g,.. c App ^ 1/. DC 1* Secunty Approval AMM Date / I_ NPS Start Pemuesen (.h Li LCO (Y / N) / 4
,, g.
.g Start Date NPS Completion Notification Stan Tune Deficiency Tag Removed?
- Completion Da*e Completion Time 1.
j bd . ..
. L.? v = G..l,':,j.,'
g..' '
? . A?
4
..--- . _ - , -. -. .... . . . . . . . - . . - - . - - - - . . - ._, . . - . . . ..-.- ._.~ -.
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QI 11-PR/RTL-2 ; i __ ib-/ don 33
> ' dix;...us ht.ia;Ri3 VEngica3g Apnl.1996 i..O :. 640n 3 Page 26 of 62 ise b .. u .:..a[IInji;, -
APPENDIX B 4 m ..._______. - ATTACHMENT D ! ] MOTOR OPERATED VALVE TesTFORM ; (Page 1 of 5) , UNIT: VALVE TAG: 'd[ NPWO: 2. 3[] WON: 9/42 /M l PLANT LOCATION: - EQUIPMENT NAME. . . . DESCRIPTION OF K: ( /P M D o l Q r & r bi%<./ Of $tVbkV/Y habMO/$c Af NP W. PLA ED BY: //l[ dBa[ DATE: [/d/f[_ : ST If IST component tb OST review is required OST Supervisor or Designee-//7. M !Av[ b!M /'* #/ 'b t t PRE WORK REVIEW NPS/ANPS/NWE: '
' DATE: 1//8J_2f COMMENTS: / !
POST WORK REVIEW l 8 PMT COMMETE (NO DEFERRAL) MAINT. FOREMAN /SUPV.: / N. he DATE: '/ /_'I _ O PMT DEFERRED ; List tests DEFERRED: r i BLANKET NPWO #: ET WO #: MAINT. FOREMAN /SUPV.: [// M O> DATE: b f # ,h _ f DEFERRED TEST RESU[TS ACCEPTED BY PMT COOR.: DATE:___ f /___ IF ANY TEST IS UNSAT, NPWO #: WO# FOR REWORK ! EQUIPMENT RETURNED TO SERVICE: ; l NPS/ANPSMWE- # ' DATE:[/d/_.sd COMMENTS: / [ L___
~
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e e 01 11-PR/P 2 Revision 33 April,1996 Page 29 of 62 APPENDIX B ATTACHMENT D MOTOR OPERATED VALVE TEST FORM (Page 4 of 5) Unit , Valve Tag , Mearwenance Performed Test Podormed la to be Post Maintenance Test Acceptance Cnterte , performed 5 Seat Lesha0e Test VerWy scat leakage is acceptable or non existing. CHECK 5e,5b, Sc. OR 5d. 5a Pre and post localleak rate tests (tLRT) are required for at 5a. t L Ri 5a (OSI) conseinment teatetton volves In amordance with OP 1300051. Vetwee are asled ser bearmenon onsy in Appens c. NOTFICATIONS REQUMEO SY FORENAN: PRE TEST - NotWy OST PRIOR to starting work. PRE TEST PRE TEST Seat tuskage xceptable per OP 1300051or SATA MSAT wolved by OST _ _ _ _ . POST TEST - Notdy OST AFTER work is axrplete POST TEST POST TEST Seat leakage acceptatWe per OP 1300051. SATAmSAT _ _ _ 5b. Pressure heon valve (PlV) last Is required for as valves 5b PtV test aneptable per IST procedire 5b (OST) tsted h Jipponen F en accordance edWe AP 0010125A Data SATAJNSAT Sheet 25.
, _ _ _ _ Sc. For other IST wolves with a specIIIc test procedure, refer 5c. Seat leakage is acceptable per IST procedure Sc. (OST) to AP 0010125A and perform Wie specmed test. SATA MSAT 5d. For all volves without e epocleic test procedure, perform 5d. Seat leakage is non existing or acceptable to 5d gOPS) eest leakege functional test to the entent poestie. Operasons. SATAJNSAT NO TEST
- Observe operational parameters such as tank level changes, non operedn0 pug solednB bocimords, pressure decay, flow noise between plug and east er temperature dWorentist to ,
versy east teekege is acce -
. When east leakage tests are not par *=s o r leastte. mark No Test and mielet. !
. e
~
Of 11-PR/P 2 - Revision 33 April,1996 Page 30 Of 62 APPENDIX B ATTACHMENT D MOTOR OPERATED VALVE TEST FORM (Page 5 Of 5) Unit , Valve Tag I* I * *E * (R Test Numtww) This test le oleo required for .x- _ _^_., related velves and operatore.
- 6. Positon Indicagon Test - Verify proper operalkm of NONE local and remote poolgon intScotone When no position Indicators exist mark None and infilat _ _ _ _
CHECK ALL THAT APPLY. 6a. Valve AND valve operator LOCAL mechanical 6a. LOCAL INDICATOR (S) reRect correct valve 6a. (OPS) position Indicators must be verflied to rollect the position by cycEng valve or other posluve SATAJNSAT correct volve position by cycling or other positive means such as system Row. means such as system flow. 6b. For IST valves, refer to AP 0010125A for POSITION 6b. POSITION INDICATION correct per IST 6b. (OST) INDICATION requirements and perform Sie speci9ed procedure SATAJNSAT test.
- 7. Flow and Pressure Test - Oblein posieve Aow or 7. Obtain positive flow or pressure IndiceGon in 7. (OPS) pressure incscagon by cycling velve or ellowing me desired direction (s). SATAJNSAT changes in Row or pressure acrose valve. Flow is permitted in the proper ESrocton(s).
- 8. Omer Test - Operatons cSecrollon, List test and 8. 8. (OPS) acceptance criteria. SATAJNSAT m____ _ _ _ _ . _ _ _ _ _ _ . . _ . _ _ _ . . _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ __ .- _ _ . _ _ _ __ __ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _
. _ . .-. - . .- _ - . = .. . . -
'N !
,pComponent: BAM PP 2A Sys: 02 Train:
Q-y Fac: P 7 d- -
~
02 i Associate: PUMP Assign Priority: A2 MAS i
; Name: BOR,IC ACID MAKE-UP FUMP 2A Work Type: 1 WORK ORDER TASK l
Location: RAB/0/N-RA4/E-RAE LMD: 1 96018716 01 I Defect / Request: REPAIR OIL LEAK m ER/PWO: 62 / 7242 l 1 NPRD Chg Loc: 910 I PAGE 1 of 5 m Detailed Explanation: PUMP LEAKS A SMALL QUANTITY OF OIL THAT RUNS DOWN'" CASING ON TO BASE AND NEEDS TO BE WIPED UP DAILY. More: Work Request: 96012233 Def Tag: .72462 Loc: ON PUMP Trbl/Brkdown: Y LCO: Y Unit Cond Reg: 8 NPRDS: Y Fail Date: 07/17/96 Time: 09:30 Det: V Stat: A Symp: D Originator: RASOIUF SHERWOOD RA Date: 07/17/96 Dept: OPS Approve By: DKA00XY ALBRITTON DK Date: 07/17/96 Task Determination Data: IST Required : Y NCR/CR : N/A Safety Class: PMT Required : Y PCM : N/A Q Group : B 10 CFR 50.49 : N EQ Doc Pkg : N/A Assign To : ROT Reg Guide 1.97 : N Seismic Cat : I Est M/H : 32.00 ASME XI(ISI) Reqd : N Scaffold Req : N Crew Qty : 8 Security Clearance: N Fire Prot Reg: N Insul Rem : N Clearance Required: Y Clearance No : S,-94-oF-C W RWP Required: Y RWP No: RCA M/H: L1: L2: L3: QC Requirements: QC Required : Y QL-A 1 More: i l Work Order Task
Description:
Standard: WORKTASK l SEE PAGE 2 FOR TASK DESCRIPTION. 1 l l More: Y
.................--..............--.........--....--.......-=====........--
Planned By : PMGOBPY GRIFFIS PM Date: 07/30/96 l Pkg Appr By : RHG0ASB GLENN P Date: 07/30/96 Time: 13:27 QC Approval : RJM0HGG MILLER RJ Date: 07/30/96
********************** OPERATIONS,AP VAL TO START ***********************
[ i !
- NPS Start Permission: k_ J ' / LCO(Y/N): 7
- Start Date/ Time : [ eg . a q c. 1 ( L.45
- i NPS Completion Notif: Major Failure:
Compl. Date/ Time: 4 ,- ) . ^ > 6 '/ ewe Major Action : Deficiency Tag Removed g N): )
) Component: BAM PP 2A Sys: 02 Train: Fac: PSL Unit: 02 - ~, Associate: PUMP Assign Priority: A2 MASTER Name: BORIC ACID MAKE-UP PUMP 2A Work Type: 1 WORK CRDER' TASK Location: RAB/0/N-RA4/E-RAE LMD: 1 96018716 01 hfect/ Request: REPAIR OIL LEAK ER/PWO: 62 / 7242 Chg loc: 910 PAGE 2 of 5 Continuaticn of Task
Description:
PUMP LEAKS A SMALL QUANTITY OF OIL.THAT RUNS DOWN CASING ON TO BASE AND NEEDS TO BE WIPED UP DAILY. INVESTIGATE AND REPAIR.
<> VERIFY THAT YOU ARE WORKING ON THE CORRECT UNIT & COMPONENT (S). <>
J
<> IF THE ID TAG ISN'T PRESENT, CONTACT THE NPS/ANPS FOR RESOLUTION.<>
<> THIS STEP MUST OCCUR PRIOR TO PHYSICALLY STARTING WORK. <>
<> \ <>
<> JOURNEYMAN SIGNATURE: .k DATE: i / 12 / % <>
<> l-+- ------- ------------- <>
////////////////////////// WORK TASK \\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\
CONTACT H.P. DEPT. PRIOR TO STARTING WORK IN RAB. CHECK CLEARANCE, ENSURE THE SYSTEM IS RACKED OUT AND TAGGED. ALL WORK TO BE PERFORMED AT THE DIRECTION OF FPL SUPERVISION OR THEIR DESIGNEE. PRIOR TO DISASSEMBLY OF ANY COMPONENTS, BE CERTAIN TO MATCH MARK, BAG AND TAG OR OTHERWISE IDENITIFY ALL PARTS AND PROVIDE SEPARATE MARKED BAGS FOR ALL SMALL PARTS. CHECK TRICO OILER FOR PROPER SETTING. (19/32" DISTANCE BETWEEN THE OF THE LOWER CROSS-ARM AND THE TOP OF THE SUPPORT PLATE). REFERENCE GMP 2-M-0018P, FILE #03603. PARAGRAPH 2.33.A THROUGH 2.33.C ADJUST TRICO OILER AS REQUI TO OETAIN PROPER SETTING,o< Mr N- *b * ^4 Mff* M vn* W - @ f/st/% 1htt/9b ADD OR DRAIN OIL FROM PUMP TO OBTAIN PROPER LEVEL. REFERENCE GMP 2-M-0018P, FILE #03603 SECTION 2.2 AND SECTION 2.4. (USE R&O 68 OIL).
************************** CAUTION ***********************************
- DO NOT FILL BEARING HOUSING WITH OIL THROUGH THE VENT PLUG HOLE OR *
- DIRECTLY THROUGH THE OILER BASE. IMPROPER OIL LEVEL MAY RESULT. *
- THE OIL LEVEL IN THE TRICO GLASS RESERVOIR BOTTLE IS NOT THE LEVEL *
*'IN THE BEARING HOUSING. REFERENCE GMP 2-M-0018P FILE #03603
- INSPE / REPLACE BREATHER WITH STOCK CODE 0069329 I (Ad Less p.}e. hs%
. 15OIL\ G.W-WIPE b S bM% 2p+1 (/e t/%,
FROM PUMP AND PEDESTAL. HAVE OPS RUN PUMP AND CHECK FOR EXTERNAL OIL LEAK. MORE: Y
,A Component: BAM PP 2A sys: 02 Train: e Associate: PUMP Fac: PSL Unit: 02 ! Assign Priority: A2 MASTER ! Name:2ORIC ACID MAKE-UP PUMP 2A Work Type: 1 WORK ORDER TASK Location: RAB/0/N-RA4/E-RAE LMD: 1 96018716 01 ; Defect / Request: REPAIR OIL LEAK ER/PWO: 62 / 7242 Chg loc: 910 ! PAGE 3 of 5 i Continuation of Task
Description:
hTTACHED: REQUIRES VERIFICATION AND SIGNOFFS QI-11 PR/PSL-2, APPX. B hTTACHED: REQUIRES VERIFICATION AND NO SIGNOFFS GMP 2-M-0018P, FILE #03603 l l l l 1 l I l l
- -- . _ - - _ . ~
I p component: BAM PP 2A Sys: 02 Train: Fac: PSL Unit: 02 l
, Associate: PUMP Assign Priority: A2 MASTER I Mame: BORIC ACID MAKE-UP PUMP 2A Work Type: 1 WORK ORDER. TASK
~
Location: RAB/0/N+RA4/E-RAE LMD: 1 96018716 01 3 Defect / Request: REPAIR OIL LEAK ER/PWO: 62 / 7242 1 Chg loc: 910 PAGE 4 of 5
- I 1
JOURNEYMANS WORK REPORT n n i Actual Start Date: Time: Actual Completion Date: bg Time. .
.8ll2lf& 3 '3 #P' * ' , %-n-% WA J: a Note: Journeyman shall sign and c' ate text after their entries. ""
Trouble Found: This Section is NOT Applicable for PMs or other planned jobs - Pih ni?Hr Rex hw? Rewuks. Moniht Ti
- m oc eic Pun % brwc -n fu xv rc, eiL at Pub e ~, kw /R&
l t~U 6 L A % S u $ T? N t, R E' d h M l5 M Sn.0h $l'Y11%} b tW b-l Work Performed. l RGke VVb t)itrb DiL ,, Cow b o'T~ *?~o 3)/*w NDA idd- l wen n. , tc tturb oil en kb SA TAlld M-W Hl lV StTCMD R M 1 taorrrt Ns7w ce- (ign9 rzt> Nitr6 Be+A.,'ac ces/wo v s/ac ne t,&L n.r o a n~o he rrn. L c vet . demeb v? Ahu. /.E L/ bmas er fl12 }'i C. EWEtWEG s RoNN(% 90 m? - O\L SQL.S LOWNOb - Ost oa hw - M \b -\ b(1 0m w st_ f tto r
.%uts - T Q 9.xs e s EN %\ cS\ %
- @. FCRG, WAR C
Continued on Additional Sheets: Y Suggestions For Future Planning / Variance Reason: s Date Supervisor Date Date ore EChief s - w s. ~.
#Nu QdIpehtor0UTED
, . nsvision 33
- Apnl.1996 Paca 11 nf $2 NOTE:
Use AttaCnments in this Appenatx for VALVES. Do NOT use inis Test Sheet. ) APPENDIX B 1 I TEST SHEET (Page 1 of 2) NPWO n 724E won: Woo /E7m
- component Tag e 8A.*t d# El Pst unit d2 i
P1 ant Locatan Ass / d/N-w / A- /M Equspment Name '75 etic Act o ffAed d A/AV 2,4 DeScngtion oiwork CMMs17mt / A'OM M <dse (Amer tegeng, rous Aree seervoort Sist nistenamones,rienoST OST Seeneerer Despies Ptees " Messenese 00 W Teamg Seenac Tess Cm sem Teamg Reenvoo Wumum Accesence Cmene or AceJed Gaus Osm 1 I Assuns seen Oseem Start OP 2200060 l ANP&HPS to soecay 1l l QPS l ,,,, i l SAT /UNSAT
~
A E Case Pume Heen Flow Das Eneas 2 M Per ensemede eune. Det enest Census See XI OST Progern) AP 0010125. Ref AP 0010132 Sness o m 0 8 Sheen' 3 OST m one Ceneum Seem OSTPapang AP 0010131, Asf AP 0010132 snest e s oef ^** " C*** '"s"T P os wigSeePomones m a"*"" ' **" *my" " ev"ene*rer imessess SATemmen
/ UNSAT <
* " -"--- Test Run fhat numeau une a esemesene a e
# , v
/s (Nefl> ASIS See a IST Pygmp DennASt B See m 5 7 Pvges pesInsne Wannees houmerL
-.usm L e (Passe 0) Urness Panames my Veneer .A.,,NS.T
((e, it i OPS Less Test. RCS PerOP 0120tst SAT /UNSAT 17 oC Lena Test.Non MCS See m Commonare mov mouse VT.2 SAT / UNSAT 13 Hywe. New Wease " ' or QC r E" ape k SAT /UNSAT
*WB) ter i t J 10 ISIS 4Asif. Sniemer Fwusens Test er Visual Test 4, 20 N Vesenen Test Per AsmL Teen Sees.
(Nepy Chaussy Preer) { TestConusse 4.7.7 & 4.7.4 l at MAsfT. Hem EeWienger Ties Lees Test ," ,,,, SAT / UNSAT
- Laanage is allowoo when evaluated by OPS for continued Operanon.
, -- .~
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- c. 3.,,
;c; . ' :.r.:q 4
g i*':.*Mstn.g/./$f...mek/fr. _ n.. -- = = = . r: .. . _ , _
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nsvision 33 l April.1996 Paas 12 nf 62 Comconent Tag a 3A A //# 24 ' PSL Unn 1 APPENDlX B. TEST SHFE_T
- (Page 2 of 2)
Place Aesconese 00 W Tesang Soecdc Teses Cdes nem Ta g Roewee Qous unmum ar =<==rce Creene or Aca* Den Resune unies, 23 Tony Turtune OM Tem as Per (C AFVn Perlormance OP 0700080 or oP 0700028 SAT / UNSAT 28 ops ECCS System venong {*[ [ vereng e#-- . 27 ! cps Fan Test Run "" '" I pertorme eenneed Amemors SAT / uNSAT Coremmmers Pe._.. Ecupmers anc Pg & Post Test Mosereg Emergency Hessnee Pro SAT / UNSAT Negry OST Poor SAT / UNSAT t 31lAI1 onereman ce temnces sucoorn 4-nee cmene see. SAT / UNEAT-I I CM lOFA2iA WoJ4sm m kegA I J. i 1 4
)
O rw & trA(M# l 54*- v/ddckt~l M7 1 l i l i 1 l i I i 1 I i l I f ' l l ADDITIONAL TECHNICAL SUPPORT TEST REQUIREMENTS & ACCEPTANCE Cl l s PRE Work Review l Planned By ed. - Date 7 / 3/ /1 Tecnncal suoport personnel R
'#e
_M- Date '7 /_3L/1 NPS/ANPS Review _
/U k POST Work-Meview Dans c M / i 2. / 9 (,
O Testing ceterred MM Supv/ Foreman: Date:
/
List tests deferred and blanket NWPO Test results accepad by MM Supv or PMT Coore (if deferTea) # Date: F '/.J/_fd. I f any test vis UNSAT' NPWO / WO / WR (C;rcle One) For Rework 94 0/M7N, Equipment Retumed to Sennce f NPS/ANPhi/NWE w 4[ Date '4 t T /76 Comments s/ = d */ s-o/ N k U v
P::g)1 of 211 l
- Mb 1 FLORIDA POWER & LIGHT COMPANY :::-- %~
ST. LUCIE UNIT 2 56 I -
.n :
GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018 'o" C
'.j .. '$,
REVISION 22 6
1.0 TITLE
MocCouMDucT!aN MECHANICAL MAINTENANCE SAFETY-RELATED PREVENIIVE MAINTNEMCE PROGRAM (PUMPS) ; 2.0 REVIEW AND APPROVAL: Reviewed by Facility Review Group 9/91986 Approved by D. A. Sacer Plant General Manager 10/9 1986 Revision 22 Reviewed by F R G 12/12 1996 Approved by J. Scarola Plant General Manager 12/12 1996
3.0 PURPOSE
This procedure provides the necessary instructions to perform preventive maintenance (PMs) on safety-related and Tech. Spec. equipment as required by i Technical Specification 6.8.1. i 4.0 PRECAUTIONS & LIMITS: 4.1 The PM files in this procedure can only be performed under direction of an approved NPWO in accordance with Administrative Procedure AP 0010432,
' Nuclear Plant Work Orders."
4.2 Clearances shall be established for the equipment on which the PM is to be performed prior to any work in accordance with Operating Procedure No. 0010122, "In-Plant Equipment Clearance Orders.' 00CUMENT :!EGUISES '!ERIFICAT10N l s 2 Oes
.10 .0 G:G30FFS DATE
?- 2ata hritied y/9 DOCT PROCEDURE mtials f .- t DOCN 2-M-0018P SYS COMP COMPLETED ITM 22
Page 5+of 211 -
.L****~- l ST. LUC E UNIT 2 i GENERAL MAINTENANCE PROCEDURE NO. 2 M-0018P, REVISION 22
~
MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVE MAINTENANCE PROGRAM (PUMPS) APPENDIX A H PM FILE 3601,3603 2:f . . _ (Page 3 of 9) J [y ~ 3 ,,
2.0 PROCEDURE
(continued) 2.2 (continued)
- 4. Label container for the drained oil with the date, bearing location and oil type.
- 5. Remove drain plug _from the bearing housing and drain oil into the container.
2.3 Acceptance Criteria / Inspection Guidelines / Corrective Action:
- 1. Oil Condition: I l
A. Acceptance Criteria: L The drained oil must be free of trash, water, dirt, metal shavings or other debris. 1 B. Inspection: l l Inspect the condition of the drained oil for trash, water, dirt, metal shavings or other debris. Record results below. CONDITION OF Oll: . 60 l i
)
Pcge 56 of 211 ST. LUCIE UNIT 2
' GENERAL MAINTENANCE PROCEDURE NO. 2 M-0018P, REVISION 22 "
MECHANICAL MAINTENANCE SAFETY-RELATED ._, PREVENTIVE MAINTENANCE PROGRAM (PUMPS) APPENDIX A ... . PM FILE 3601,3603 __
- (Page 5 of 9)
. u L.3.. . _ _ .
2.0 PROCEDURE
(continued) 2.3 (continued)
- 2. (continued)
B. Inspection: Inspect each oiler extema!!y for cleanliness, piping looseness, oil 1 leakage and plumb. Loosen the thumbscrew and remove the glass l reservoir bottle from the oiler base. Remove the adjusting ! mechanism and check it for bent or defective parts. Ensure that the ! mechanism can be removed and installed' freely with no interference. R Record any problems found below. OILER CONDITION: Ynr Mc l}eaf , C. Corrective Action: t If glass reservoir bottle is dirty, then clean or replace. Replace bent or defective adjusting mechanism, if the remaining acceptance criteria above cannot be met, then contact your Foreman to initiate a separate NPWO to correct the problem. 4
, PGge 59 of 211
{' ST. LUCIE UNIT 2 i
, GENERAL MAINTENANCE PROCEDURE NO. 2 M 0018P, REVISION 22 '
MECHANICAL MAINTENANCE SAFETY-RELATED 1:.t : l PREVENTIVF. MAINTENANCE PROGRAM (PUMPS) !d' ' APPENDIX A .,; - 4 .. . PM FILE 3601,3603 ;j[ i
,ip.j!M,jp, l (Page 8 of 9)
2.0 PROCEDURE
(continued) 2.4 (continued)
- 7. Several fillings of glass reservoir bottle may be required before actual oil level is reached. When oil level is reached, no more oil will run out of the i bottle. !
- 8. Tighten thumbscrew to hold reservoir bottle in place.
1 2.5 Additional Maintenance Observations: l Inspect the general area for any problems which may affect the pump's ability l to perform its function. Document inspediori results or additional maintenance ; performed during this PM. 1 INSPECTIOi4 RESULTS OR ADDITIONAL MAINTENANCE PERFORMED:
~
, F v e r v. + ,. i ~ ~
L no % $ n \L , 3
2.6 Housekeeping
~
- 1. Clean the area affected by this PM.
- 2. After release by HP, dispose of the used oil in accordance with AP 0010501, " Hazardous Waste Handling and Storage.'
t e
Pag 3 60 of 211 ST. LUCIE UNIT 2 - GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018P. REVISION ~ MECHANICAL MAINTENANCE SAFETY-RELATED 3 PREVENTIVE MAINTENANCE PROGRAM (PUMPS) APPENDIX A PM FILE 3601,3603 (Page 9 of 9) _ 3.0 POST-MAINTENANCE TESTING: - 3.1 Temporarily lift clearance and witness pump run. 4 3.2 Verify no extemal oil leakage. 3.3 Verify visible oil level in the i.:ro oiler glass reservoir bottle. ; 3.4 Release clearance and retest as required by QI 11-PR/PSL-2. 4.0 ADDITIONAL INFORMATION: I 4.1 Tech. Manual 2998-5511 , l PM COMPLETED Joumeyman's Name (print & sign) Towe'3 OEmPSU \ e _.-- Dates /G/
s Facility : PSL CcMpLg73 y
- Warehouse 3 Charge Location: 910 300 000 :SSUE T:CKET ROS . 50055878 Task: 01 =================
Work Order: 96018716 Task: 01 4374433 PWO . 7242 ================= ER . 62 EAC , 676 PRINTED 08/12/96 q Planner M. RENTZ 09:28 PM Task
Title:
REPAIR OIL LEAK PAGE: 1 W/O Shift : Crew: Dept: OPS
==============================================
Deliver To:
==============================================
+ Stock Code Location Description Qty UI
========== ============== ============================== ====== ==
0030610 1 3 D 00 143 000 PIPE, CARBON STEEL, ASME SA-10 1 FT UTC Number: 0000389823 Trace: U 281442 M t i J i 1 I e
====================================
Issued By J. BRACK , ,
==================================== 1 Issue Date 08/12/96 Time: 21:27 i
====================================
Received By: T. LACAYO ,
==================================== l Badge No. -
TSLOOOO
====================================
I Facility PSL 20MPLETE Y Warehouse 1 Charge Location: 910 300 000 ISSUE TICKET ROS 50055878 Task: 01 ================= Work Order: 96018716 Task: 01 4374432 PWO - 7242 ================= ER . 62 EAC 676 PRINTED 08/12/96 Planner - M. RENTZ 09:09 PM Task
Title:
REPAIR OIL LEAK PAGE- ' W/O Shift Crew: Dept: OPS
==============================================
Deliver To:
====================,-========================
Stock Code Location Description Qty UI
========== ============== ============================== ====== ==
0021152 3 1 P 11.060 000 OILER, SIGHT, FUSE 5, 8 OZ , SI 1 EA UTC Number: Trace: 0025979 4 2 A 08 063 000 BOTTLE, PLASTIC, SAMPLE, WITH 3 EA UTC Number: Trace: i 4
====================================
Issued By J. BRACK
====================================
Issue Date 08/12/96 Time: 21:09
====================================
Received By: T. LACAYO
====================================
Badge No. TBLOOOO
====================================
Component: yl Associate: CHG PP 2C PUMP Sys: 02 Assign Priority: A2 ! Train: l (50)4 Fac: PSL LM 02
- ame : CHARGING PL"4P IC MASTER Work Type: ~ _
WORK ORDER TASK Location: RAB/1/N-RA2/E-RAE LMD: 1 96015913 01 Defect / Request: BROKEN BOLTS-COUPLING GUARD -~ ER/PWO: 62 / 7101
} Chg Loc: 910 PAGE 1 of 4
( i1PRD. l
\ /
Detailed Explanation: U, ' WHILE DOING HOLD DOWN PUMP BOLTS REPACK BROKEN FOUND (2) BROKEN COUL @
- COVER (4) NEEDED j
Work Request: 96010575 More: Def Tag: Loc: Trbl/Brkdown: Y 6 LCO: N Unit Cond Reg: 8 i NPRDS: Y Fail Date: 06/15/96 Time: 07:09 Det: H Originator: JCAOREW ASTRUP Stat: A Symp: A Approve By: MGK0XUG KOGELSCHATZ JC Date: 06/15/96 Dept: MM MG Date: 06/15/96 i Task Determination Datai . IST Required : Y NCR/CR : N/A Safety Class: SR
- PMT Required
- N PCM : N/A Q Group : B 10 CFR 50.49 : A EQ Doc Pkg : N/A Assign To : ROT Reg Guide 1.97 : N Seismic Cat ASME XI(ISI) Reqd : N
- I Est M/H : 8.00 Scaffold Req : N Crew Qty : 1 Security Clearance: N N Insul Rem Clearance Required: Y Fire Prot Req:
Clearanc~e No : 7 -*DI~ 0M
- N RWP Required: Y RWP No: RCA M/H: L1: L2: L3:
QC Requirements: QC Required : Y QL-A
--.............--...........---....--.......------.......-......-ore:
Work Order Task
Description:
M SEE PAGE 2 FOR TASK DESCRIPTION. More
......----.....--.........--....---...........................----...----:Y Planned By : RIB 0PUJ BARINGER Pkg Appr By : PJS0X19 SARNO RI Date: 07/06/96 QC Approval : RJM0HGG MILLER PJ Date: 07/06/96 Time: 10:55 RJ Date: 07/06/96
********************** OPERATIONS APPROV TO START ***********************
NPS Start Permission: g
- LCO(Y/N): y
- Start Date/ Time : v~ rn '
/ 2U; *
- m *
**************************p* *********************************************
NPS Completion Notif: Compl. Date/ Time:
#* / V Major Failure:
' ,./: </ / Si,c Major Action :
Deficiency Tag Removed (Y/N): ;
-, Component: CHG PP 2C Sys: 02 Train:
, Associate: PUMP Fac: PSL Unit: 02 lI Assign Priority: A2 MASTER Name: CHARGING PUMP 2C Work Type: 1 WORK ORDER TASK j Location: RAB/1/N-RA2/E-RAE LMD: 1 96015913 01 Defect / Request: BROKEN BOLTS-COUPLING GUARD ER/PWO: 62 / 7101 Chg loc: 910 PAGE 2 of 4 Continuation of Task
Description:
************************* TASK DESCRIPTION ***************************
THIS NPWO IS TO REPAIR TWO BROKEN COUPLING GUARD INSTALLATION BOLTS.
========================= SIGNATURE REQUIRED =========================
VERIFY THAT YOU ARE WO NG ONj UNIT-2 AND THE CORRECT COMPONENT {S} JOURNEYMAN SIGNATURE: 7 DATE:
======================= Ct Gy
==== ===== =========================$==4==L===
***************************** JOB TASK *******************************
REMOVE THE COUPLING GUARD AND REMOVE THE TWO BROKEN BOLTS IN THE PUMP / MOTOR BASE PLATE. NOTE: BACK TWO BOLTS CLOSEST TO THE MOTOR. CLEAN AND TAP OUT HOLES AS NECESSARY. INSTALL COUPLING GUARD AND REPLACE ALL HOLD DOWN BOLTING. 9 i
- - . ~ ~ _
\
r , 3 Component: CHG PP 2C Sys: 02 Train: Associate: PUMP Fac: PSL Unit: 02
, Assign Priority: A2 MASTER Name: CHARGING PUMP 2C Work Type: 1 WORK ORDER TASK Location: RAB/1/N-RA2/E-RAE LMD: 1 96015913 01 Defect / Request: BROKEN BOLTS-COUPLING GUARD l ER/PWO: 62 / 7101 :
Chg loc: 910 l PAGE 3 of 4 JOURNEYMANS WORK REPORT 1 Act a Start Date: Time: Actual Completion Date: Time:
%% LUO
& ~ (J ~ ('/ / t.f (, g Note: Journeyman shall sign and date text after their entries.
Trouble Found: This Section is NOT Applicable for PMs or other planned jobs Coo oLs a s (-oMc\ k LTs ( 2- ) hf.ACY.d l Work Performed:
% OVEd CoODbi N 3 b OV4-Od - Ok%QP d i
1 tt0 T %) \ Ld -o O Pro m A(YA- 0 A t\l - 0 OT SYoVE BOLT S To 2 5 - 3EmjsTAu rl Sua ed-(krL i 8M u s s J ci - O t - (A<cA,,/ C4~,,i- ( L i del M /es - !%,v) id,7iii,<, LT Fmxh A i,i 7' i n Ha ns '
- c L, nd s J7' Ld T- C Ac <ld ?&m A 1 e
;i, c7' /4 / n~ Lhr rt f1 ~ niel Se /< '
heuu tb.a s. ? - 9 ~ fl Continued on Additional Sheets: Suggestions For Future Planning / Variance Reason: Yh
TIBIA 66
'l Facility PSL CCMPLETE Y P
Warehcuse 1 Charge Location: 910 300 000 :SSUE TICF.ET Work Order: 96015913- Task: 01 ================= 4374371 PWO : 7101 ================= ER . 62 EAC - 676 PRINTED 08/09/96 Planner : R. BARINGER 00:35 PM Task
Title:
BROKEN BOLTS-COUPLING GUARD PAGE: 1 W/O Shift : Crew: Dept: MM
==============================================
Deliver To:
==============================================
Stock Code Location Description Qty UI
========== ============== ============================== ====== ==
0028903 1 1 C 28 087 000 SCREW, CAP, FINISHED HEX HEAD, 2 EA UTC Number: 0000373695 Trace: U 3AH 1460 1 e
====================================
Issued By C. SUMMERS
====================================
Issue Date - 08/09/96 Time: 12:35
====================================
Received By: J. BOUDREAU
====================================
Badge No. - JVB0JFR
====================================
~, Component: CHG PP 2A Sys: 02 Traln: l 15 0 s Fac: PS DN n1p/ 02 j {
; Associate: PUMP Assign Priority: A2 i MAST ] ;
Name: CHARGING FUMP CA Work Type: , WORK CRDER TASK ' Location: RAB/1/N-RA3/E-RAE LMD: 1 96014725 01 Defect / Request: 021PM02-3606 PM - CHE V CCUMULATO ER/PWO: 62 / 6950 Chg Loc: 910 I " PAGE 1 of 5 NPRD l
\ J Detailed Explanation: U PM ID: PM02-3606 DUE DY D:': 08/10/96 EARLY DT: 08/03/96 LATE DT: 08/17/96 More:
Work Request: Def Tag: Loc: Trbl/Brkdown: 9 LCO: Unit Cond Reg: NPRDS: Y Fail Date: Time: Det: Stat: Symp: I 1 Originator: Date: Dept: ' Approve By: Date: I Task Determination Data: MCL List : PM02-3606
- IST Required
- Y NCR/CR : N/A Safety Class: SR PMT Required : Y PCM : N/A Q Group : B 10 CFR 50.49 : A EQ Doc Pkg : N/A Assign To : ROT 1 Reg Guide 1.97 : N Seismic Cat : I Est M/H : 8.00 ASME XI(ISI) Reqd : N Scaffold Req : N Crew Qty : 2 Security Clearance: N Fire Prot Reg: N Insul Rem : N Clearance Required: Y Clearance No : t- %4- 02-ot o ;
RWP Required: Y RWP No: RCA M/H: L1: L2: L3: ! l QC Requirements: QC Required : Y Q.L.-A. More: Work Order Task
Description:
SEE PAGE 2 FOR TASK DESCRIPTION. More: Y Planned By : WDCOBMQ CHESNEY WD Date: 06/05/96 Pkg Appr By : PRE-APPR Date: 06/05/96 Time: 12:00 QC Approval : PRE-APPR Date: 06/05/96
********************** OPERATIONS AP ROVAL TO START ***********************
NPS Start Permission: M et7 7 LCO(Y/N): f_)_ ** Start Date/ Time : efe5L/ /
/ 3337 w/ L *
*************************************f*************************************
NPS Completion Notif: W5 Major Failure: Compl. Date/ Time: 'an</v/ / p c;/5 Major Action : Deficiency Tag Removed (Y/N) : ,g4 (, -
/
u ., Component: CHG PP 2A Sys: 02 Train: Fac: PSL Unit: 02 l
, Associate: PUMP Assign Priority: A2 , MASTER i Name: CHARGING FUMP 2A Work Type: 7 WORK ORDER TASK Location: RAB/1/N-RA3/E-RAE LMD: 1 96014725 01 Defect / Request: 021PM02-3606 PM - CHECK ACCUMULATO ER/PWO: 62 / 6950 Chg loc: 910 PAGE 2 of 5 Continuation of Task
Description:
************************** CAUTION *****************************
VERIFY THA KYOU ARE WORKING ON THE CORRECT UNIT AND COMPONENT (S) SIGNATURE Yhw %
, DATE 7 - f - 74, h)ERFORM PREVENTIVE MAINTENANCE JOB #03606 PER ATTACHED INSTRUCTIONS.
h0TE: CALIBRATED M&TE GAUGES NEEDED TO CHECK AND CHARGE ACCUMULATORS. kTTACHED REQUIRES VERIFICATION AND SIGNOFF: GMP 2-M-0018, FILE 03606 QI-11 PR/PSL-2, APPX. B SEE ADDITIONAL COMPONENTS ATTACHED! I i e
e o Component: CHG PP 2A Sys: 02 Traln: Associate: PUMP Fac: PSL Unit: 02 ! Assign Priority: A2 { MASTER Name: CHARGING PUMP 2A Work Type: 7 WORK ORDER TASK Location: RAB/1/N-RA3/E-RAE LMD: 1 96014725 01 Defect / Request: 021PM02-3606 PM - CHECK ACCUMULATO ER/PWO: 62 / 6950 Chg loc: 910 PAGE 3 of 5 JOURNEYMANS WORK REPORT Actual Start Date: Time: Actual Completion Date: Time:
~
$- T C 7, .;2 2.^ R / f' C YG ?:$C Note: Journeyman shall sign and date text after their entries.
Trouble Found: This Section is NOT Applicable for PMs or other planned jobs Work Performed: Oh 6 < kEcf c L m a u ce - c Ar d sJ w ,< 4 M f' ip s a u r Taa. Woetad Aif tvo ou sccoade a , vvl% m eek n ivc ; a u m n ,v7 E nin WcE frLocedvRE ivc. 7-m-co te Rev:c,cw s2 s 7s i's. l . 0. I. ( h eu 4 .0 %.1 Nel Elu Fc.neiwa~ we, a c c ,n a t gT E .
) I(M OuJ M2c u s ), Dh' 6 M 4~ d y ,I- [. - f(
/ '
Continued on Additional Sheets: Suggestions For Future Planning / Variance Reason: Yh l I u v/" re hief Date Supervis. La QC Inspector Date D 4 re
~
D Of vv iD svv A l 1 T"r" n s i "v
~ ' ~ ~ ' FLORIDA POWER & LIGHT COMPANY eN
- ST. LUCIE UNIT 2 d ~
GENERAL MAINTENANCE PROCEDURE NO. 2-M 0018 E' 8 REVISION 47 1 h
1.0 TITLE
PROCEDURENODUCTION MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVE mal ANCfr .j 1 PROGRAM ~~~ ~
)
2.0 REVIEW AND APPROVAL: Reviewed by Facility Review Group 10/10 1985 Approved by D. A. Saoer Plant General Manager 10/28 1985 Revision 47 Reviewed by F R G 6/10, 6/17 19 96 Approved by J. Scarola Plant General Manager 6/17 1996
3.0 PURPOSE
This procedure provides the necessary instructions to perform preventive maintenance (PMs) on safety related and Tech. Spec. equipment as required by Technical Specifications 6.8.1 4.0 PRECAUTIONS & LIMITS: 4.1 The PM files in this procedure can only be performed under direction of an approved NPWO in accordance with Administrative Procedure AP 0010432,
" Nuclear Plant Work Orders."
4.2 Clearances shall be established for the equipment on which the PM is to be performed prior to any work in accordance with 0010122, "In-Plant Clearance Orders." 4.3 The frequency of performance of PM files is subject to Tech. Specs., the performance history and vendor recommendations. Frequencies for the attached PMs are maintained in the PM Planners Scheduling Program and may only be changed upon approval of Technical Support personnel (TS). 4.4 Refer to the individual PM attachments to this procedure. S 2 OPS DATE DOCT PROCEDURE DOCUMENT REQUIRES VERIFICATION DoCN 2-u-oo18 AND SIGNOFFS SYS COMP COMPLETED ITM 47 Rev.DateVertned %-S 81L Initials , v I J
POg3107 of 454 ST. LUCIE UNIT 2 . GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018. REVISION 4,, 4n i MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVE' ~ i MAINTENANCE PROGRAM '
~ . t' APPENDIX A
.d+
PM 3606,3609,3612 l (Page 3 of 17) d-
2.0 Procedure
(continued) 2.2 Gas Booster Pump Setup: INITIAL 1. Attach the air hose from the service air connection to the driving air inlet connection on the gas booster pump. q/(d NOTE The nitrogen supply valve (V29201) is located approximately 12 inches above the floor on the north wall of the charging pump hallway, near the 2A Charging Pump cubicle. i
- 2. Attach the nitrogen supply hose from V29201 (nitrogen supply 77 valve to the gas booster pump) to the gas booster pump suction. /
- 3. Close both discharge shutoff valves on the gas booster pump discharge.
i
- 4. Notify OPS to open valve V29201. _
2.3 Suction Accumulator Pressure Verification and Adjustment: NOTE
- 1. Contact TS to disposition any damage or wear indications.
- 2. The gas booster pump is not required to be running to charge the suction accumulator.
- 3. The suction accumulator vent valve is required to be open when checking or adjusting the suction accumulator pressure. Charging pump priming is not required for opening of the accumulator vent valve only. The suction accumulator drain valve is not required to be open. If OPS opens the suction accumulator drain valve, then charging pump priming is required.
- 1. If the suction accumulator vent valve is not within the clearance boundary and tagged open, then notify OPS to verify the vent valve is open. Q
- 2. Remove the valve guard from the top of the suction accumulator.
~ ~
~
r-age ivo or 4:>4 ST. LUCIE UNIT 2 GENERAL MAINTENANCE PROCEDURE NO. 2 M 0018. REVISION MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVE ~ '
~
MAINTENANCE PROGRAM APPENDIX A PM 3606,3609,3612 (Page 4 of 17)
2.0 Procedure
(continued) I 2.3 (continued) INITIAL
- 3. Remove the secondary plug and 0-ring from the suction I accumulator assembly. Inspect the O-ring for damage and ; l replace as necessary. I l
- 4. Apply Snoop to the top of the valve core to determine if the schrader vaive has a slow leak. If a leak is discovered, ;
then contact TS or the Mechanical Maintenance Supervisor for further direction. The schrader may require tightening or - replacement. / NOTE
- 1. Use extreme caution while installing the brass adapter and the air l connection valve onto the suction accumulator valve core. Over tightening can damage the valve core.
- 2. Ensure the T-handle on the air connection valve in fully positioned in the counter clockwise direction before installing it on the brass adapter.
1
- 5. Attach the M&TE gauge assembly to the suction accumulator in accordance with the following steps:
A. Retract the pin in the air connection valve by tuming the ), T-handle counter clockwise until it stops rotating. 7A B. Install the brass adapter on the suction accumulator assembly. N C. Install the air connection valve on the brass adapter. 7k D. Connect a hose from the air connection valve on the suction accumulator to the outlet connection on the M&TE gauge assembly. l E. Ensure the valve on the M&TE gauge assembly is in the closeds position. ' F. Ensure the vent valve (bleeder valve) located next to the air connection valve is in the closed position.
reg) 109 of 454 ST. LUCIE UNIT 2 GENERAL MAINTENANCE PROCEDURE NO. 2 M-0018, REVISION' : MECHANICAL MAINTENANCE SAFETY AELATED PREVENTIVE ~ '. ~ MAINTENANCE PROGRAM APPENDIX A - PM 3606,3609,3612
)
(Page 5 of 17) '
2.0 Procedure
(continued) - 2.3 (continued) INITIAL _ NOTE 1. The target range for the As-Left suction accumulator bladder pressure is 25 to 29 psig regardless of plant mode.
- 2. Suction accumulator As-Found pressures can provide an indication of potential equipment problems.
A. As-Found pressures less than 20 psig may indicate that the suction accumulator valve core may be leaking or that the schrader valve may have been depressed during installation of the air connection valve. Contact TS or the Mechanical Maintenance Supervisor for further direction. B. As-Found Pressures greater than 35 psig may indicate that the suction accumulator is not properly vented or a pump intemal valve is leaking by. Contact OPS to verify that the pump fluid block vent valve and the suction accumulator vent valve are open.
- 6. Carefully tum the T-handle clockwise on the air connection valve to engage the suction accumulator schrader valve. y//4 A. Acceptance Criteria:
Suction accumulator pressure target range is 25 to 29 psig. B. Inspection Guidelines: Read the As-Found suction accumulator pressure on the M&TE gauge. Record the required data below. m Pump (Circle One) 2A' 28 2C Hour Meter Reading 4G f0 3 hrs. The Unit 2 Charging Pump hour meters are located in the charging pump hallway. M&TE Equipment Number M - S N / L As-Found Suction Accumulator Pressure I7 psig Initial N Date ? / 5' / 7(- I
I rega inv oi*o* ST. LUCIE UNIT 2 GENERAL MAINTENANCE PROCEDURE NO. 2 M 0018. REVISION y. MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVEU, : . MAINTENANCE PROGRAM ~
's :
APPENDIX A PM 3606, 3609, 3612 . (Page 6 of 17)
2.0 Procedure
(continued) 2.3 (continued)
- 6. (continued)
C. Corrective Action If the acceptance criteria of Section 2.3.6.A is not met, then adjust the suction accumulator pressure to obtain an As-Left pressure between 25 and 29 psig by performing one of the following: NOTE
- 1. The gas booster pump is not required to be running to charge the suction accumulator.
- 2. Nitrogen may be added to the suction accumulator by controlling the gas booster pump discharge valve OR the M&TE gauge assembly valve.
- 3. Nitrogen may be vented from the suction accumulator through the vent valve next to the air connection valve OR the M&TE gauge assembly valve (provided that a hose is not connected to the inlet connection on the M&TE gauge assembly).
~
- 1. To increase the suction accumulator bladder pressure, connect a hose from the gas booster pump discharge to the M&TE gauge assembly inlet and add nitrogen as necessary.
- 2. To decrease the suction accumulator bladder pressure, slowly vent nitrogen as necessary. k Record the As-Left suction accumulator pressure as read from the M&TE gauge assembly.
As-Left Suction Accumulator Pressure 3f psig Initial Date I / (e / 34 i j
rega 111 ci so4 ST. LUCIE UNIT 2 j
- l GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018. REVISION,,4rg .
MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVE-" ! l' MAINTENANCE PROGRAM (, i APPENDIX A f PM 3606,3609,3612 ' (Page 7 of 17)
' ~
2.0 Procedure
(continued) l 2.4 Suction Accumulator Reassembly: l 1. Tum the air connection valve T-handle in a counter clockwise direction until it stops rotating. [ !
- 2. Close the gas booster pump discharge valve and the M&TE gauge assembly valve.
- 3. Open the vent valve (bleeder valve) next to the air connection -
valve to bleed pressure from the hose. N l l
- 4. If applicable, remove the hose from the gas booster pump discharge to the M&TE gauge assembly inlet connection. , e l
- 5. Remove the hose from the air connection valve on the suction accumulator to the outlet connection on the M&TE gauge assembly.
- 6. Remove the air connection valve from the brass adapter.
- 7. Remove the brass adapter from the suction accumulator valve -
core. E
- 8. Apply snoop to the top of the suction accumulator valve core to ensure that the schrader valve was not damaged. If a leak is detected, contact TS or the Mechanical Maintenance Supervisor for further direction. g
- 9. Remove all snoop and moisture from the suction accumulator valve y core. -
- 10. Lubricate the secondary plug O-ring with Dow Coming 55.
- 11. Install the O-ring in the secondary plug and thread the secondary plug into the suction accumulator assembly.
g l l
raga liz or 4o4 ) ST. LUCIE UNIT 2 < GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018, REVISION , I _ MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVE - < ;. l
~
MAINTENANCE PROGRAM '? APPENDIX A l PM 3606,3609,3612 l (Page 8 of 17) l
2.0 Procedure
(continued) I 2.4 (continued)
- 12. Apply snoop to the top of the secondary plug to ensure the suction
)
accumulator or bladder is not leaking. If a leak is detected, I contact TS or the Mechanical Maintenance Supervisor for further direction. -
- 13. Reinstall the suction accumulator valve guard. 1
- 14. Remove the remaining gas hoses.
2.5 Troubleshooting
- 1. If leakage was detected during pressure adjustment or reassembly, !
contact TS and the Viechanical Maintenance Supervisor for l additional troubleshooting direction. If charging problems were 1 identified, or As-Found suction accumulator pressures were different i than anticipated, TS may suggest a reverification of the suction accumulator pressure. gg 1 l Individual Contacted (Name) l Initial Ik Date E/ b / b-I
erge 113 of 4:24 i ST. LUCIE UNIT 2 .. . GENERAL MAINTENANCE PROCEDURE NO. 2-M-0018. REVISION 4,4g y MECHANICAL MAINTENANCE SAFETY-RELATED PREVENTIVE :J- _ MAINTENANCE PROGRAM y APPENDIX A * , l PM 3600,3609,3612 (Page 9 of 17) . l
2.0 Procedure
(continued) ' 2.6 Discharge Accumulator Pressure Verification and Adjustment: _ NOTE
- 1. Contact TS to disposition any damage or wear indications.
- 2. The gas booster pump is required to be running to charge the discharge accumulator.
- 4. The fluid block vent valve located on top of the fluid block discharge flange is required to be open when checking or adjusting the discharge accumulator pressure. Charging pump priming is not required for opening of the fluid block vent valve only. If OPS opens a drain valve, then charging pump priming is required.
- 1. If the fluid block vent valve is not within the clearance boundary and tagged open, then notify OPS to verify the vent valve is open.
- 2. Remove the valve guard from the top of the discharge accumulator.
- 3. Remove the secondary plug and 0-ring from the discharge accumulator assembly. Inspect the O-ring for damage and replace as necessary.
- 4. Apply Snoop to the top of the valve core to determine if the schrader valve has a slow leak, if a leak is discovered, contact TS or the Mechanical Maintenance Supervisor for further direction as the schrader valve may require tightening or replacem}}