ML20079E034

Info Re Facility Const.Related Info Encl

ML20079E034
Person / Time
Site:	Perry
Issue date:	10/21/1983
From:	CLEVELAND ELECTRIC ILLUMINATING CO.
To:
Shared Package
ML20079E023	List: ML20079E028 ML20079E034 ML20079E040 ML20079E044 ML20079E048 ML20079E057
References
FOIA-83-583 NUDOCS 8401170042
Download: ML20079E034 (50)

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521 Nuclear Boiler (NSSS)

MCC Swgr & Miac Area MVACB Subsvetes (fro = U et M23 a Process Ins tru M24 entation Ba t te ry Ro ca Exha'ua t Dian)

PM Cotst bessej C Auto Oepressur=isatien M25 Control Roca NVAC P51 Service Air u ttleo wtr

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H Nuc St3 Supply Shutof f Sys Control Room Zeerg Rectre M16 PS2 B33 M27 Ins tr.:: ent Air Reactor Recirculation Co:puter Rous RVAC P53 Penetratico Pres surisa tion 3 Jet Pues Iestreent M28 Emerg Pep Area Cooling F54 C11 Tire Protection Control Rod Drtve K29 Con & Cocp Ra Ru=idif F54A Constr 4 Tire V r Supply WV

- Reactor Man control M31 Radvaste Bldg v P35 t

Buildtas Heating A Red control and Info ESV Pump Rouse v ttilation Plant Security M32 e nt ila tion P56 V

3 Hydraulic Control M33 e

Inter =ediate 31ds Vent Safety-Rela ted Instr Air P5 7 C34 Teedwater Control M35 Turbine 314; Cool & Vent P61 C41 Auxiliary Stests Standby Liquid Control M25 Neutron Monitoring

/ M37 of f-cas Sids Exhatat Aux Boiler Tuel 011 P62 C51 V r Treat 3?ds v P63 t

Sanitary Veste Trea toert

- Transve rse Incore Probe Auxiliary Elds Ntilation Indcatrial Vaste Disposal

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M38 ert11ation P64 A Start-Up Range (SMR. IRM)M39 ICCS P=p Rocs Cooling Aus Boiler Chez Treatment /

P65 3 Power Racge M40 Fuel Rndl 31dg Vent C Start-Up Range Det Dr(LPM. APM)

P66 Saattary Drain & Sever M41 Beater Bay Ventila tion Stom Drain and Sewer C61 P67 Renote Reactor Shutdevn Turbine Pvr Co= plex Vent M42 P71 C71 Reactor Pro Potable Vater Supply M43 3 Motor Genera;uction iC 21dg ventilation P72 Plant Underdrain M44 Steas typass tor $st Contr Service Eldg BVAC PSI C85 Preep Chemical Cleaning M45 Cire V r Pu=p House vent t

P82 C91 Co:puter M46 Misc Chemical Treatment Miscellaneous Ventilation Cool Tower Acid Addition PB3 C95 Ewer Resconse Info (ERIS)

M47 Steam Tunnel Cooling P84 kl7 Cooling Tvr Chlorination Plant Red Monitoring M48 Radvaste contr Rac

.P85 D17A Process Rad Monitoring Smoke Clearing

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Plant Discharge Lechlorin M49 Vent PS6 D19 Post Accident Rad Mon Nitrogen Supply M50 Cuard House EVAC P87 D21 Post Ace Sa ol Svs (PASS)

Area Red Monitoring Combus tible cas co(ntrolNonsaf)

R10 M51 D23 Cat =t Attesphere Mon Plant Electrical M52 Tech Sup Cat EVAC (Mensaf)

Station *ransformers

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D51 R11 Envirens Monitorine M53 Trn Cat /ECF Vnt Sv E12 R13 Main Steas Gensaf) R14 Isolated Phase Bus

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/ E15 Restdual heat Ac= oval

~ N11A Reheat S team R15 N11 Containent Spray 1107AC Vital Inverters E21 Lov Pressure Core Spray Tech Sup Cnt Uninter Pwr N21 Condensate R22 E22 3 Diesel CeperatorHigh Pressure Core Spray Meta.1 Clad Swgr 5-15 kV N22 Condensate T11trationMais. Reheat Extr & M R23 480 Volt load Centers N23 E31 Leak Detection N24 Motor Control Centers Condenaste De=in R25 E32 Dist Panels-120.240&4807 MSIV Leakage Control EP Rtr Drains & Vents N25 E51 R31 Power Cable Interrated 14ak Rate TestAx.Cere Isolation Cooling LP Ett Drains & Vents N26 and Vire E61 A32 Control Cable N27 Teedwater A33 F11 and Vire Puel Servicing Equipment N27A Injection V r & Vat sup Conduits and Trays T12 t

R34 Servicing Aids Croundir.g Crid N31 Turbine R35 T13 Rx Vessel Servicing Equip isrbine Control (ERC)

Reat Tres & Anti-Tres Pro R36 Cathodic Protection N32 F14 In-Vessel Servicing Iquip N33 Stest Seal R37 F15 Lightning hotection Refueling Equipnent N34 Lube 011 R41 F16 Instruments Storage Equipeent N35 Eydrogen Supply R42 DC Syst Batt. Chrgs. Sw. Ed F17 Under Rx vessel Serv Eq Extraction Stem:s R43 N36 T41 Start-Up Equipment Standby riesel Centrater N39 Turning Gear 144 T42 Tuel Transfer Ieutement Standby DC Starting Air N41 Centrator R45 G33 Standby DC Tuel 011 Aeactor Water Cleanup N42 Eydrogen Seal R46 C36 Staedby DC Jacket Vtr Cool RVCU Filter /Desin N43 Generator Stator Cool R47 C41 Standby DC Lube 011 Tuel Pool Cool & Cleanup N51 Excitation C42 R48 Stdby DC Exh. Intk.,Crnkes Suppe Pool Cleanup N61 Condenser & Auxiliaries C43 15 0 off-Site Coc=unications Suppr Pool Makeup Condenser Air Removal N62 R51 C50 Communi.

Liquid Radwaste Disposal N64 Off-Cas R$2 (1stra-Plant)

C51 Maintenance & Calibration Solid Radvaste Disposal N64A Off-Cas Vault Refris133 G60 Exclusion Area Paging Sys tes Miscellaneous S eps B off-cas Refrig chill tig R54 C61 Pro =pt Alerting System Lieutd Radvaste Su=os N71 Circulating Vater 61 M13 tain Contr la Annunciator Control Room Panels N71A Cond Cleaning R62 H22

'ocal Annunciator local Panels & Racks CE cond Iransfer & Storage Loose Parts Monitoring Pil (AMERTAP)

R63 E31 local Pat, y

711

& Racks Non-CE

,P12 Condensate Seal Vater R71 Lighting Fuel VP20 Makeup V r Pretreat

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R72 f

L51 SIT Power TransformersPe ne t Serv 31ds Mach SheF EquipCranes Roists & Elevators /P22 Two-3ed Desine L52 Mixed-Bed De=ineralizer541 L53 Step-Up Station Motor Op louver Operators Turbine Plant Sa=pling Tra nsmission Sta' P33

$42 L54 Rolling Steel Door opers Nuclear Sampling i

P34 T23 L55 P35 Contatnment De-Misc Kitchen Equipment Reactor Plant Sampling L56 CC Mach Shoo Ec (Contasin) /P41 P40

~

Service Vtr Screen Wash k M11 Containment vessel cool Service Vater Total lyste=s M12 Deleted (Catst Pool Air)

Nuclear closed coolingEmergency Closed Cooling P42 M13 Dryvell Cooling P43 Total Liste M14

/P44 C=tzt vessel & D/V Purge Turbine Eld l

MIS P45 t Closed Cool Annulue Exhaust cas Treat Emergency Service Vater N

M16 Dryvell Vacuum Relief P46 Turbine Eld

' y t Chilled V M17 P47 Controlled Access EVACCotta19 ment Vacuun Relief Control Complex Chill V r tr Mn P48 ESV Screen VashS & ESV Chlorination t

P49 l

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e NUCLE AR TEST SECTION TEST ' PROGRESS SUM M ARIES MONTH OF NOVEM11ER 1982 Total Comple.t. ion - Weighted Percqnt 37 3 Total Test Activities Completion - Weighted Percent UNIT 1 & COMMON Total Software Support Completion - Weighted Percent 13.6 23.7 TOTAL

' DEV.

THIS PERIOD TO DATE ITEMS ACTIVITIES M

SCHEDULED ACTU4L SCHEDULED ACTUAL p

y IWTD.VALUE I MONT14 START COMP. START COMP. START COMP START COMP COMP. COM y

x FEST ACTIVITIES

'URNO VER-NCS/NTS

,333)2.5)

+3 57 53 7

7 242 232 122 114 34.2%

.8; C & R TESTING 672 (35.0)

+9 71 46 26 6

422 223 280 131 19.5%

6.8:

7 STEM FLUS!!/ hut! IN 321 (15.0)

+11 28 21 11 19 141 112 88 93 29.0%

4.3:

RE-OP ACCEPTANCE TESTINCI.b '. ' ' ' 48'5 (15.0).

+4 4

3 2

2 48 35 41 35 7.2%

1.1; JRNOVER-NTS / PPD.

181 ( 2.5)

+3 3

3 0

0 31 31 16 16 8.8%

.2; ITAL TEST ACTIVITIES 1992 (70.0)

+30 163 126 46 34 884 633 547 389 19.5%

13.67 FTWA RE SUPPO RT MINISTRATIVE PROCEDURES 57 ( 2.5)

N/A N/A 0

0 N/A N/A 57 57 100.0%

2.52 ITEM SCOPING PKCS.

314 ( 5.0)

N/A N/A 0

64 N/A N/A 314 314 100.0%

5.02

f. PROCEDURES (ECP, GEN,ICP) 436 ( 9.0)

N/A N/A N/A N/A 323 314 73.0%.

6.62 T SPECIFICATIONS 169 ( 4.0)

N/A N/A 15 3

N/A N/A 167 154 96.1%

3.8%

GBil INSTRUCTIONS 75 ( 3.0)

N/A N/A 5

N/A' N/A 56 50.

71.7%

2.1%

T PROCEDURES 226 ( 5.5)

N/A N/A 33 10 N/A '

N/A 151 9 7'-

56.9%

3.1%

• a 41 ( 1.0)

N/A N/A SL SOFTWARE SUPPORT 1318 (30.0)

N/A N/A N/A{

N/A 23 22 54.7%

.5%

N/A N/A 1091 1008 80.5%

23.7%

sare Figure adjustments are cesult of upelated Irojecti>n t.

i t

N/A means llot Applicable to this category.

I

t PSPP UNIT 1 NTS TEST PROCEDURE ISDEX AND STATUS PROC. S0./

E CURRENT ID REV.

TITLE PRELIM.

APPRVL COMMENTS 1 TP 1 B13 P 001 RPV Flow Induced Vibr. w/o Fuel (GE-17A) 2 TP 1 B21A P 001 Nuclear Boiler:

820719 Proc. Instr.

(GE-4) l 3 TP 1 B21C P 001 Nuclear Boiler:

ADS (GE-4) 4 TP 1 B21H P 001 Nuclear Boiler:

NSSSS (GE-4) 5 TP 1 B33 P 001 Reactor Recire.

System (GE-8) 6 TP 1 B33 P 002 Reactor Recire.

820907 Flow Contr. Valve l

(GE-8) l i

7 TP 1 C11A P 001 Rod Control &

Information (GE-9) 8 TP 1 C11B P 001 Control Rod Drive 82-0726 Hydraulic System (GE-10) 9 TP 1 C34 P 001 Feedwater Control (GE-1) 10 TP 1 C41 P 001 SLCS (includes R36 portion)

(GE-3)

L-

c PSPP UNIT 1 NTS TEST PROCEDURE INDEX AND STATUS

~

PROC. NO./

.E CURRENT ID REV.

TITLE PRELIM.

APPRVL COMMENTS 11 TP 1 C51A P 001 Neutron Monitor 811012 Sys: SUR (A,B,C)

(GE-22A) 1 12 TP 1 C51A P CO2 Neutron Monitor 811115 Sys: IR (A,B,C)

(GE-223) 13 TP 1 C51B P d01 Neutron Monitor 820818 Sys: APRM (A,B,C)

(GE-22C) 14 TP 1 C51C P 001 Neutron Monitor 820601 Sys: Recire Flow Bias (GE-22D) 15 TP 1 C51D P 001 NMS: Traversing 820922 Incore Probe Sys.

(GE-23) 16 TP 1 C61 P 001 Reoote Reactor 820201 Shutdown (GE-14) 17 TP 1 C71 P 001 Reactor Protection System (GE-21) 18 TP 1 C71' P 002 Reactor Protection Sys. (MG Sets)

(GE-21) 19 TP 1 C85 A 001 Steam Bypass and S20520 Pressure Control (GE-30, 313) 20 TP 1 C85 A 002 Steam Bypass end 820902 Press Regult HPU (GE-30, 31B) i e

i P

en e

r PSPP L31T 1.

NTS TEST PROCEDURE INDEX AND STATUS PROC. NO./

'E CURRENT 1D REV.

TITLE PRELIM.

APPRVL COMMENTS 21 TP 1 C91 A 001 Process Computer 821011 (GE-28) 22 TP 1 D17 P 001 PRMS: Non-GE 820917 Channels (TS-D17) 23 TP 1 D17A P 001 PRMS: Off-Gas Post 820208 Treatment RMS (GE-25F) 1 24 TP 1 D17B P 001 PRMS: Off-Gas 811111 Pretreatment RMS (GE-25B) 25 TP 1 D17D P 001 PRMS: Containment 810f30 Vent. Exh. RMS (GE-25E) 26 TP 1 D17E P 001 PRMS: Main Steam 810529 Line RMS (GE-25C) 27 TP 1 D17F P 001 'RMS: ESW Liq.

820331 Loops A/B RMS (GE-25D) 28 TP 1 D17G P 001 PRMS: Liq. Rad-820201 waste Effl. RMS (GE-25D) l t

29 TP 1 D17H P 001 PRMS: NCCWS Liq.

820201 RMS (GE-25D) 30 TP 1 D21 P 001 Area Radiation 811028 i

Monitoring i

(TS-D21) 1

PNPP UNIT 1 NTS TEST PROCEDURE INDEX AND STATUS PROC. NO./

E CURRENT ID REV.

TITLE PRELIM.

APPRVL COMMENTS 31 TP 1 D51 A 001 Seismic Instrument 821108 System (TS-D51) 32 TP 1 E12 P 001 Residual Heat 801007 Removal System (GE-5) 33 TP 2 E15 P 001 Containment Spray 820614 System 34 TP 1 E21 P 001 Low Pressure Core 820604 Spray System (GE-12) 35 TP 1 E22 P 001 High Pressure Core Spray System (GE-13) 36 TP 1 E22 P 002 HPCS Diesel Generator (GE-13) 37 TP 1 E31 P 001 Leak 820331 Detection (GE-19) 38 TP 1 E32 P 001 MSIV Leakage 820727 Control. System (GE-7)

I 39 TP 1 E51 P 001 Reactor Core Isol.

Cooling System.

1 (GE-6) l 40 TP 1 E53 P 001 Containment Isol.

820319 l

System (includes GE-4 valves)

(TS-E53)

.4

.n n

..v

-3..,

a-e,

a P.NPP UNIT 1 NTS TEST PROCEDURE INDEX AND STATUS PROC. NO./

E CURRENT ID REV.

TITLE PRELIM.

APPRVL COMMENTS 41 TP 1 E61 P 001 Local Leak Rate Waiting on PPD prepared Test surveillance Proc. & FSAR (TS-E61)

Table Rev.

42 TP 1 E61 P 002 Integrated Leak 811106 Rate Test (TS-E61) 43 TP 1 E61 P 003 ILRT Instrument 820104 Calibration (TS-E61) 44 TP 1 E61 P 004 Inter-Sys LOCA Leakage Rate Test (TS-E61D) 45 TP 1 E62 P 001 Drywell Leak 810813

. Test (TS-E62) 46 TP 1 E64 P 001 Shield Building 810708 Leak Rate Test (TS-E64) 47 TP 1 E66 P 001 Drywell Structural 820331 Integ. Test (SIT)

(TS-E66) 48 TP 1 E68 P 001 System Vibration Testing (TS-E68) 49 TP 1 Fil P C01 Fuel Servicing 820728 Equipment (GE-11) 50 TP 1 F12 P 001 Servicing Aides (GE-11)

PNPP UNIT 1 NTS TEST PROCEDURE INDEX AND STATUS PROC. NO./

E CURRENT XD REV.

TITLE PRELIM., APPRVL COMMENTS 51 TP 1 F14 P 001 In RPV Servicing 820715 I

Equipment (GE-11) 52 TP 1 F15 P 001 Refueling l

Equipment (GE-11) 195 TP 1 F16 P 501 Storage Racks (GE-11) 53 TP 1 F17 P 001 Under RPV Servicing Equip.

(GE-11) 54 TP 1 F42 P 001 Fuel Transfer Equipment (GE-11) 55 TP 1 G33 P 001 Reactor Vater 820915 Cleanup System (GE-2) 1 56 TP 1 G36 P 001 RWCU Filter /

820923 Demineralizer

(

(GE-2) l 57 TP 1 G41 P 001 Fuel Pool Cooling 820924 and Cleanup System (TS-G41) 58 TP 1 G42 P 001 Suppression Pool 810317 Cooling & Cleanup (TS-G42) 59 TP 1 G43 P 001 Suppression Pool 811109

^

Makeup l

(TS-G43)

~

PNPP U.N1T 1 NTS TEST PROCEDURE INDEX AND STATUS PROC. NO./

'E CURRENT VD REV.

TITLE PRELIM.

APPRVL COMMENTS 60 TP O G50 P 001 Liquid 820712 Radwaste (TS-G50) 61 TP O G51 P 001 ' olid Radwaste 5

Disposal (TS-G51) 62 TP 1 G60 A 001 Miscellaneous 820504 Sumps (TS-G60) 63 TP 1 G61 A 001 Liquid Radwaste 820504 Sumps (TS-G61) 64 TP O L51 A 002 ESW Pump House 791121 Crane (TS-L51) 65 TP O L51 A 003 Serv. Water Pump 791031 House Ovrh. Crane (TS-L51) 66 TP O L51 P 002 Fuel Handling Area 810514 Crane (TS-L51) i 67 TP 1 L51 A 0C1 Cire Water & Turb.

(790417) Missing Rev. 0 & 1 Rav 2 Bldg Crane (TS-L51) 68 TP 1 L51 P 001 Reactor Bldg. Pir.

810326 j

Crane (TS-131)

[

69 TP 2 L51 A 001 C. ire. Wtr. & Turb.

810119 Bldg. Crane (TS-L51) l

PSPP UNIT 1 NTS TEST PROCEDURE INDES AND STATUS PROC. NO./

E CURRENT ID REV TITLE PRELIM.

APPRVL COMMENTS 70 TP 2 L51 P 001 Reactor Bldg.

820224 Polar Crane (TS-L51) 71 TP 1 M11 P 001 Containment Vessel 820402 Rev. 1 Cooling (821011)

(TS-M11) 72 TP 1 M13 P dO1 Drywell Cooling 811119 Rev. 1 System (821011)

(TS-M13) 73 TP 1 M14 A 001 Containment Vessel M 811118 Rev. 1 ATG (821011) 74 TP 1 M15 P 001 Annulus Exhaust 820614 Grs Treatment 75 TP 1 M16 P 001 Drywell Vacuum 821014 Had released on Relief 8-24-82 by PY-GAI/CEI-5369 (TS-M16) 76 TP O M21 A 001 HVAC-Controlled 820504 Rev. 1 Access Area (820924)

(TS-M21) 77 TP 1 M23 P 001 HVAC-Batt MCC, 820623 Swgr, Misc. Equip.

Area (TS-M23) 78 TP 0 M25 P 001 HVAC-Control Room, 820614 Rev. 1 incl. CR Emerg (820924)

Recire. (TS-M25) 79 TP O M27 A 001 HVAC - Computer 810630 Re". 1 Room

~

(821011)

(TS-M27) l

PNPP UNIT 1 NTS TEST PROCEDURE INDEX AND STATUS PROC. NO./

I CURRENT ID REV.

TITLE PRELIM.

APPRVL COMMENTS 80 TP O M28 P 001 HVAC-ECCS Pump 810218 Rev. 1 Area Cooling (821108) 81 TP O M29 A 001 HVAC-Contr/ Comp.

811106 Rm. Humidification (TS-M29) 82 TP 1 M31 A 001 HVAC-Radwaste 810630 Rev. 1 Bldg. Ventil (821011)

(TS-M31) 83 TP 1 M32 P 001 HVAC-ESV Pp 810609 House Ventil (TS-M32) 84 TP O M33 A 001 HVAC-Intermediate 810821 Building (TS-M33) 85 TP 1 M35 A 001 HVAC-Turbine Bldg.

810529 Rev. 1 Cooling (821005)

(TS-M35) 86 TP 1 M36 P 001 HVAC-Off-Gas Bldg.

811118 Exhaust 87 TP O M37 A 001 HVAC-Water Treat-800610 ment Bldg.

(TS-M37) 88 TP 1 M38 A 001 HVAC-Aux. Bldg.

810708 Rev. 1 Ventilation (821011)

(TS-M38) 89 TP 1 M39 P 001 HVAC-ECCS Pump 811019 Room Cooling (TS-M39)

___m________._______________._____._mm.---

PSPP UNIT 1 NTS TEST PROCEDUKE INDEX AND STATUS PROC. NO./

.I CURRENT ID

____REV.

TITLE PRELIM.

APPRVL COMMENTS 90 TP O M40 P 001 HVAC-Fuel Handl 811113 Bldg. Ventilation (TS-M40) 196 TP 1 M41 A 001 820406 91 TP 1 M42 A 001 HVAC-Turbine Power 81052B Rsv. 1 Complex Ventil.

(821011)

(TS-M42) 92 TP 1 M43 P 001 HVAC-D/G Bldg.

810630 Ventilation (TS-M43) 93 TP O M44 A 001 HVAC - Service CEI hold Building (TS-M44) 94 TP 1 M45 A 001 HVAC-Cire Water 801029 Pump House Ventil.

(TS-M45) 95 TP 0 M46 A 001 HVAC-Miscellaneous 811215 Ventil. Systems (TS-M46) 96 TP 1 M47 A 001 HVAC-Steam Tunnel 820524 Cooling.

(TS-M47) l 97 TP O M48 A 001 HVAC-Radwaste 800730 Control Rm. Vent.

(TS-M48) t l

l l

98 TP 1 M49 A 001 HVAC-Smoke 800606 l

Venting (TS-M49) l

l PNPP UNIT 1 NTS TEST PROCEDURE INDEX AND STATUS PROC. NO./

I CURRENT ID REV.

TITLE PRELIM.

APPRVL COMMENTS 99 TP 1 M51 P 001 HVAC-Combustible 820923 Gas Control (TS-M51) 100 TP O M99 A 001 Plant Environ-

]

mental Conditions 101 TP 1 N21 A 501 Condensate '

820326 System (TS-N21) 102 TP 1 N23 A 001 Condensate Filtra-810916 tion Systam (TS-N23) 103 TP 1 N24 A 001 Condensate 820601

.Demineral System (TS-N24) 104 TP 1 N27 A 001 Feedwater 821207 System (TS-N27) 105 TP 1 N31 A 001 Main Turbine No TS Sched.

System No AT war-(TS-NONE) ranted (BOP) 1 106 TP 1 N32 A 001 Main Turbine:

821013 EHC (GE-30) 107 TP 1 N33 A 001 Steam Seal 820406 System (TS-N33) 108 TP 1 N34 A 001 Main Feedpump 820630 Lube Oil System (TS-N34)

. ~,

y

PSPP UNIT 1 NTS TEST PROCEDURE INDEX AND STATUS PROC. NO./

.1E CURRENT ID REV.

TITLE PRELIM. APPRVL COMMENTS t

109 TP 1 N35 A 001 Hydrogen Supply System 110 TP 1 N41 A 001 Main Generator 811015 (incl. Excit Sys)

(TS-N41) t 111 TP 1 N42 A 001 Generator Hydrogen No TP war-Seal Oil System ranted (BOP)

(TS-NTS) 112 TP 1 N43 A 001 Generator Stator No TP war-Cooling System ranted (BOP)

(TS-NTS) 113 TP 1 N62 A 001 Condenser Air

.820506

. Removal System (TS-N62) 114 TP 1 N64 A 001 Off-Gas Charcoal 820810 Vault Refrig. Sys.

(TS-N64) i 115 TP 1 N64 P 001 Off-Gas Process System (GE-16) 116 TP 1 N71 A 001 Cire. Water Sys.

820811 (incl. Ametrap Sys) (TS-N71) 117 TP 1 P11 A 001 Condensate Trasf &

810130 Rev. 1-Storage Sys.

(820706)

(TS-Pil) 118 TP 1 P12 A 001 Condensate Seal 820720 Water System (TS-P12) t i

PNPP UNIT 1 NTS TEST PROCEDURE INDEX AND STATUS PROC. NO./

.E CURRENT ID REV.

TITLE PRELIM.

APPRVL COMMENTS 119 TP O P20 A 001 Makeup Water 820714 Pretreatment Sys.

(TS-P20) 120 TP O P21 A 001 Two-Bed Water Dem.

801007 Rev. 1

& Distribution Sys (810224)

(TS-P21) i.

121 TP 0 P22 A dO1 Mixed-Bed Demin. &

810902 Distribution Sys (TS-P22) 122 TP 1 P33 A 001 Turbine Plant 820202 CEI Hold 9-22-80 Sampling Need addendum to (TS-P33)

FSAR.

183 TP 1 P34 A 001 Nuclear Plant

. Sampling TS-P34 in Review i

123 TP 1 P3S A 001 Reactor Plant 820601 Sampling (GE-02) 124 TP 0 P40 A 001 Service Water 800910 Rev. 1 Serben Wash (820120)

(TS-P40) i 125 TP 0 P41 A 001 Service Water 800911 System (TS-P41) i 126 TP 1 P42 P 001 Emergency Closed 82010S Cooling System (TS-P42)

{

127 TP 1 P43 A 001 Nuclear Closed 811201 1

Rsv. 1 Cooling System (820916)

(TS-P43) l I

,a

PNPP USIT 1 NTS TEST PROCEDURE INDEX AND STATUS PROC. NO./

.E CURRENT ID REV.

TITLE PRELIM.

APPRVL COMMENTS 128 TP 1 P44 A 001 Turb Bldg Closed 810804 Rev. 2 Cooling System (820714)

(TS-P44) 129 TP 1 P45 P 001 Emergency Service 810728 Water System (TS-P45) 130 TP 1 P46 A 001 Turbine Bldg 820519 Chilled Water Sys (TS-P46) 131 TP O P47 P 001 Control Complex 811014 Chilled Water Sys.

(TS-P47) 132 TP 1 P48 A 001 Serv./Emerg. Serv.

810430

, Rav. 1 Vater Chlor. Sys.

(820610)

(TS-P48) 133 TP O P49 P 001 ESW Screen Wash 810514 Rav. 1 System (820111)

(TS-P49) i 134 TP O P50 A 001 Contairment Vessel 820504 l Rev. 1 Chilled Water Sys.

(821011)

(TS-P50) 135 TP 1 P51 A 001 Service Air 810930 Ray. 1 System (821025)

(TS-P51) 136 TP 1 PS2 A 001 Instrument Air 820720 Rsv. 1 System (820922)

(TS-PS2) 137 TP 1 PS2 A 002 Loss of Instrument Air Test (TS-P52) t

a PNPP UN!T 1 i

NTS TEST PROCEDURE INDEX AND STATUS PROC. NO./

.E CURRENT XD REV.

TITLE PRELIM.

APPRVL COMMFNTS 138 TP O PS3 P 001 Penetration 800923 On hold pending Pressurization Sys design change.

l (TS-P53) 139 TP 0 P54 A 001 Fire Protec. Sys.-

801029 Aux. Boiler (TS-P54B) 140 TP O P54 A 002 Fire Protec. Sys.-

820713 GAI issued Remainder of Sys.

prelim.

(TS-P54C) 141 TP 0 P54 A 003 Fire Protec. Sys.-

821025 Cardo.x (TS-P54D) 142 TP O P54 P 001 Fire Protection 791123 Test com-Sys-Tranrormers pleted.

(TS-P54A) 143 TP 1 P54 A 001 Fire Protec. Sys.-

810807 Mn Gen Transf A (TS-P54A) 144 TP 1 P54 A 002 Fire Protec. Sys.-

810807 Mn Gen'Transf B (TS-P54A) 145 TP 1 P54 A 003 Fire Protec. Sys.-

810807 Mn Gen Transf C (TS-P54A) 146 TP 1 P54 A 004 Fire Prctec. Sys.-

810807 Unit Aux. Transf.

(TS-P54A) 186 TP 2 P54 A 001 FPS-Mn. Gen. Trans-i former A (TS-2P54A) 1 9

e h

.=. _ - - _. _ -..

j PSPP UNIT 1 NTS TEST PROCEDURE INDEX AND STATUS f

PROC. NO./

.1E CURRENT ID REV.

T'TLE PRELIM.

APPRVL COMMENTS 187 TP 2 P54 A 002 FPS-Mn. Gen. Trans-former B (TS-2P54A) i 188 TP 2 P54 A 003 FPS-Mn. Gen. Trans-former C (TS-2P54A) 189 TP 2 P54 A 004 FPS-Unit Aux. Trans-former (TS-2P54A) 190 TP 2 P54 A 005 FPS-Start-Up Trans-for=cr (TS-2P54A) 191 TP 2 P54 A 006 FPS-Interbus Trans-former A (TS-2P54A) 192 TP 2 P54 A 007 FPS-Interbus Trans-former B (TS-2P54A) l t

193 TP 2 P54 A 008 FPS-Interbus Trans-former C (TS-2P54A) 194 TP 2 P54 A C09 FPS-Mn. Gen. Trans-l former-Spare 147 TP O P55 A 001 Building 810415 Heating System (TS-PSS) 148 TP 1 P56 A 001 Plant Security System (TS-PS6)

PNPF UNIT 1 NT; TEST PROCEDURE INDEX AND STATUS PROC. NO./

E CURRENT ID REV.

TITLE PRELIM.

APPRVL COMMENTS

^

149 TP 1 P57 P 001 Safety-Related 800930 Instrument Air (TS-P57) 150 TP O P61 A 001 Auxiliary Steam 820823

)

System (TS-P61) 151 TP O P62 A 001 Auxiliary Boiler 800807 Tuel Oil System l

(TS-P62)

\\

152 TP O P64 A 001 Industrial Waste 810610 Disposal System j

(TS-P64) 1 153 TP O P65 A 001 Auxiliary Boiler 800821 Test results i

Rev. 1 Chemical Treatment (820224) approved.

(TS-P65) 154 TP 1 P66 A 001 Sanitary Drain &

No AT war-Sewer System ranted (BOP)

(TS-NONE) 155 T? O P67 A 001 Storm Drain and No AT war-Sewer System ranted (BOP)

(TE-NONE) 156 TP O P72 P 001 Plant Foundation 800710 Underdrcin System (TS-P72) 157 TP C P83 A 001 Cooling Tower Acid 820916 Addition System (TS-P83) 4 158 TP O P84 A 001 Cooling Tower 801121 Chlorine System (TS-P84) p r

a PNPP UNZT 1 NTS TEST PROCEDURE INDEX AND STATUS PROC. NO./

.I CURRENT ID REV.

TITLE PRELIM.

APPRVL COMMENTS 197 TP 1 PS6 A 001 Nitrogen Supply 800718 System 159 TP 1 P99 A 001 Post Fuel Load B0P System Vibr.

Testing (TS-P99) 160 TP 1 R10 A 001 Normal AC Power Distribution Sys.

(TS-RIO) 161 TP 1 R11 A 001 Station Transf 810407 In'.erbus A Transf.

(TS-Ril) 162 TP 1 R11 A 002 Station Transf -

F10803 LH1B Interbus Transformer (TS-Ril) 163 TP 1 R11 A 003 Station Transf -

801103 Interbus C Transf (TS-Ril) 166 TP 1 R13 A 001 Isolated Phase 811009 Bus (TS-R13) 165 TP 1 R14 A 001 120V AC Vital Inv.

810930 and Distribution (TS-k14) 166 TP 1 R22 P 001 1E 4kV Switchgear 810615 (Metal Clad)

(TS-R22) 167 TP 1 R23 P 001 480V AC Load 810605 S

Centers (TS-R23) l l

l

i-PSPP UNIT 1 NTS TEST PROCEDURE INDEX AND STATUS PROC. NO./

{

I CURRENT i

ID REV.

TITLE PRELIM. APPRVL COMMENTS 168 TP 1 R24 P 001 Motor Control i

Centers i

l (TS-R24) l 1

169 TP O R35 A 001 Cathodic Protec.

810615 System (TS-R35)

I 170 TP 1 R42 A501(NonIE)DC 811006 System (TS-R42A) 171 TP 1 R42 P 001 1E DC 800124 System (TS-R42) 172 TP 1 R43 P 001 Div. 1 Standby 810713 r

Diesel Generator (TS-R43) 1 I

i 173 TP 1 R43 P 002 Div. 2 Standby 810716 Diesel Generator (TS-R43) i 198 TP 1 R44 P 001 810716 i

l l

199 TP 1 R44 P 002 S10727 I

i i

200 TP 1 R45 P 001 810720 l

201 TP i Rl+5 P 002

'810617 I

i l

l

=

I

PNPP UNIT 1 NTS TEST PROCEDURE INDEX AND STATUS PROC. NO./

.I CURRENT ID 3EV.

TITLE PRELIM.

APPRVL COMMENTS 207 TP 1 R46 P 001.

810708 202 TP 1 R46 P 002 810630 203 TP 1 R47 P 001 810630 204 TP 1 R47 P 002 810630 174 TP O R50 A 001 Off-site Communi-800922

. cations System (TS-R50) 175 TP O R51 A 001 Intra-Plant Com-800128 munications Sys (TS-R51) 176 TP O RS2 A 001 Plant Maintenance /

820909 Cal. Comm.

(TS-RSI) 177 TP 0 R53 A 001 On-Site Communica-820616 GAI TP drft.

tions-Parimeter arrived Evacuation 820526 (TS-R51) 205 TP O R55 A 001 Pe:manent Plant 820819 Telephone System DC Equipment 178 TP 1 R61 A'001 Sequence of Events 801125 Recorder (TS-R61) 1

PSPP CSIT 1 NTS TEST PROCEDURE INDEX AND STATUS PROC. S0./

E CURRENT ID REV.

TITLE PRELIM.

APPRVL COMMENTS 179 TP 1 R63 A 001 Loose Parts Moni-820720 toring System (TS-R63) 206 TP 1 R75 P 001 810311 180 TP 1 R'/o P 0'01 ECCS Init. Loss 820817 of Offsite Power (TS-R76) 181 TP 1 S11 A 001 Start-Up 791204 Transformer (TS-SilA) 182 TP 1 S11 A 002 (Main and Aux) Pwr 820609 Transformers (TS-S11B) 184 TP 2 S11 A 001 Start-Up Transformer (TS-2511A) 185 TP 2 S11 A 002 Main and Aux.

Transformers (TS-2511B) 193/A/FF-1/S/jg

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~ ed REMAINING SYSTEM TURNOVERS 250 - 225-i 200-p'/ 175-150- /- 125- / ,-[ 100-i '/ 75- / / ./ i S0- / l l./ // 25-[f / O J F M A M J J A 0 N O J F,M A M 1983 1934 .~.---- SCHEDULED FORECAST 1983JAN 21 14 FEB 18 16 APR ~ 30 16 MAR 8 17 MAY 6 16 JUN 13 13 JUL 11 15 AUG 13 13 SEP 16 16 OCT 12 12 NOV. 4 4 l DEC 15 15 1984 JAM 6 6 FEB 6 6 MAR 9 9 APR'

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REACTOR L sE2:lCE staa. stos. 2 l AUIlLIAar stos. 2 COOT.u!G TO\\ER Z* TURE!!!E P0'.7E2 CG: PLEX h((f 0F AS ~ C2RC-vna 9k2 TURBl!!E ROOM 2 i 2 OBSEn%TIOM STATW4 3EATE5 8AT ( 2 The Clevelcad F.loctric Illu=inating Co. Perr/1:uclear Pc.ter Plant Unit: 3 ;.: 2 PTJUC T/sYOUP 3., 4

t ) MEETING NOTICE Document Control (50-440/441) DEC 151982 NRC POR L POR PRC System NSIC LB#1 Rdg. o M. Rushbrook Project Manager J. Stefano H. Denton/E. Case D. Eisenhut/R. Purple A. Schwencer G. Knighton E. Adensam G. Lainas F. Mirag1.ia F. Schroeder M. Ernst J. Knight W. Johnston D. Muller T. Speis L. Rubenstein W.- Houston E. Jordan, DEQA:IE a J. Taylor, DRP:IE Attomey, OELD ACRS (16) cc: Service List NRC PARTICIPANTS: W. Lovelace J. Konklin P. Pelke M. Gildner J. Stefano J. Youngblood e e f l g e 8 I

t I /. UNITED STATES l' g NUCLEAR REGULATORY COMMISSION wassimoTom.o.c. osss \\...../ DEC 151982 Docket Nos. : 50-440 and 50-441 MEMORANDUM FOR: B. J. Youngblood, Chief, Licensing Branch No.1, DL FROM: J. J. Stefano, Project Manager, Licensing Branch No.1, DL

SUBJECT:

FORTHCOMING NRC CASELOAD FORECAST PANEL VISIT TO PERRY SITE DATE & TIME: January 11, 12 & 13, 1983 9 am - 4 pm LOCATION: Perry Plant Site Lake County, Ohio PURPOSE: Assess status of construction and completion schedules for Perry Units 1 & 2 (Meeting Agenda enclosed) PARTICIPANTS: NRC Staff W. Lovelace, J. Konklin, P. Pelke, M. Gildner, J. Stefano, J. Youngblood CEI Staff W. Coleman, et. al. OTHER Meeting between CEI and the NRC staff on the first day is open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pur-suant to "Open Meeting and Statement of NRC Staff Policy,' i l 43 FR 28058, June 28,1978. l h 'K/hk )Mb~/ f John J. Stefarro', ProjeIt Manager Lice ing Branch No.L1 fi Divi ion of,f.icensing Enclosure-Meeting Agenda cc w/ encl.: Se p~> l

i i Mr. Murray R. Edelman DEC 151982 Vic'e President, Nuclear Group . The Cleveland Electric Illuminating Company P. O. Box 5000 CleveJ and, Ohio ' _44J01... cc: Jay Silberg, Esq. Shaw, Pittman, Potts & Trowbridge 1800 M Street, N. W. Washington, D.-C. 20006 Donald H. Hauser, Esq. The Cleveland Electric Illuminating Company P. O. Box 5000 Cleveland, Ohio 44101-Resident Insoector's Office U. S. Nuclea' Regulatory Comission r Pamly at Center Road Perry, Ohio 44081 U. -S. Nuclear Regulatory Commission Mr. James G. Keppler, Regional Administrator, Region III w.#.%5 x.79S Rooseva).t Road.w.www.em;..,.#,-g.._:.gv v ,>.:.#.:.- w...: c .,s 3 Glen Ellyn, Illinois 60137 Donald T. Ezzone, Esq. w-Assistant Prosecuting Attorney 105 Main Street Lake County Administration Center Painesville, Ohio 44077 Daniel D. Wilt Esq. P. O. Box 08159 Cleveland, Ohio 44108 Ms. Sue Hiatt OCRE Interim Representative 8275 Munson Mentor, Ohio 44060 Terry Lodge, Esq. 915 Spitzer Building Toledo, Ohio 43604 John G. Cardinal, Esq. Prosecuting Attorney Ashtabula County Courthouse Jefferson, Ohio 44047 l I

CASELOAD FORECAST PANEL SITE VISIT MEETING AGENDA NOTE: Emphasis will be on Unit 1 construction including facilities coninon to Units 1 and 2 which are needed for Unit I completion and operation 1. Overview of project construction schedule including progress and major milestones completed, current pmblems and any anticipated problem areas that may impact the current projected fuel load date. 2. Detailed review and current status of design and engineering effort (by major discipline) including any potential problems that may arise from necessary rework. 3. Detailed review and current status of procurement activities including valves, pipe, instruments, cable, major components, etc. 4. Actual and proposed craft work force (by major craft), craft availability, productivity, potential labor negotiations and problems. 5. Detailed review and current status of all large and small bore pipe hangers, restraints, snubbers, etc., including design, rework, proccement, fabrica-tion, delivery and installation. 6. Detailed review of project schedule identifying critical path items, near critical items, amount of float for various activities, the current critical path to fuel loading, methods of implementation of corrective action for any activities with negative float, and provisions for contingencies. The esti-mated project percent complete as of December 31, 1982. 7. Detailed _ review and current status of bulk quantities including current estimated quantities, quantities installed to date, quantities scheduled to date, current percent cc.mplete for each, actual versus forecast installation rates, in cubic yards /mo., linear feet /mo., or number /mo., and basis for figures. (a) Concrete (CY) (b) Process Pipe (LF) Large Bore Pipe (2 " and larger) - Small Bore Pipe (2" and smaller) (c) YardPipe(LF) (d) Large Bore Pipe Hangers, Restraints, Snubbers (ea) (e) Small Bore Pipe Hangers, Restraints (ea) (f) Cable Tray (LF) (g) Total Conduit (LF) (h) Total Exposed Metal Conduit (LF) (i) Cable (LF) Power Control Security. - Instrumentation Plant Lighting

4 e Agen'da (Cont'd). (j) Terminations (ea) Power Control Security Instrumentation plant Lighting (k) Electrical Circuits (ea) Power Control Security (1) Instrumentation (ea) 8. Detailed review and current status of preparation of preop and acceptance ~ test procedures, integration of preop and acceptance test activities with construction suiedule, system tumover schedule, preop and acceptance tests schedule, current and proposed preop and acceptance tests program manpower. (a) Total number of procedures required for fuel lo.ad. (D) Nurser of draft procedures not started. (c) Nuder of draft procedures being written. (d) Number of procedures approved. (e) Number of procedures in review. (f) Total number of preop and acceptance tests required for fuel load. (g) Number of preop and acceptance tests completed, (h) Number of preop and acceptance tests currently in progress. (i) Number of systems turned over to start-up. 9. Detailed discussion of potential schedular influence due to changes attributed to NUREG-0737 and other recent licensing requirements.

10. Discussion of schedular impact, if any, regarding potential deficiencies reported in accordance with 10 CFR 50.55(e).

11. Overview of current construction and startup management organization showing interfaces between the two.

i l 12. Site tour and observation of construction activities. l

i ^ GPMTE !l/3/S3 PROJECT PROGRESS

SUMMARY

89.1 % UNITN1 & COMMON 9.9.4% civil STRUCTURAL 93.3% LB PIP E 92.4% SE PIP E 77.9% LB HANGERS 87.3% CABLE TRAY 77.0% CONDUlT j 69.0 % CABLE

a s 4 4 PERRY NUCLEAR POWER PLANT.. s AREA PROGRESS I UNIT #1 & COMMON AREA % COMPLETE NUCLEARISLAND 88.6 REACTOR BUILDING 78.5 TURBINE BUILDING 96.2 CONTROL COMPLEX 94.6 YARD 95.5 O eG -e e-- --n -e e +- ~r -~~-=-, -= v-+ e w w-

t a CASELOAD FORECAST PANEL SITE VISIT NRC AGENDA ITEM NUMBER 2 Detailed review and current status of design and engineering effort (by major discipline) including any potential problems that may arise from necessary Rework. Engineering Status 1. Engineering General - Engineering Progress as of November 1 is 96.5% for the basic plant design. All new engineering tasks are identified and scheduled as New Work or Rework. New activities are added to these categories as they are defined. Presently, 52% of the identified New Work tasks are complete and 79% of the identified Rework tasks are complete. Overall engineering progress is 92%. s 2. Civil / Structural - All Unit 1 and Common structural steel erection and concrete construction drawings have been completed and issued. The current efforts are final evaluation of support attachments to the containment as a result of the final new loads and finalizing designs for pipe rupture restraints and jet shields. Penetration seal design is 90% co=plete. 3

echanical - All Unit 1 and Common piping installation drawings have been completed and is.su e d. Major New Work, including ATWS is complete.

Current efforts include minor equipment relocations, and valve changes. Agenda Item No. 5 discusses pipe supports in greater detail. 4. I&C - All Unit 1 and co= mon design instrument and control routing drawings have been issued to the site. The current effort is development of detailed Instal-lation/ Fabrication drawings by Johnson Controls Engineering for ecnstruction; this is 6h% complete. New Work is dominated by R.G.1.97 implementation at 95% ERIS (NUREG 0696) at 70% complete and ATWS at 75% complete, and Post Accident Radiation Monitoring at 60% complete. 5. Electrical - All Unit 1 and comnon base design electrical drawings and cable pull slips have been issued to the site. The current efforts are development nf detailed conduit drawings by the site conduit design team; this is 70% complete. New Work is dominated by ERIS (NUREG 0696) at 60% complete, ATWS at 95% complete, Hydrogen igniters at 95% complete and Fire Parrier design which is 75% complete. Equipment Qualification documentation is being assembled to support a March 1983 NRC audit. This effort is on schedule. NRC AGENDA ITEM NUMBER 5 Detailed review and current status of all large and small bore pipe hangers, restraints, snabbers,.etc., including design, rework, procurement, fabrication, delivery and in-sis 11ation. Tne status of piping supports for Perry Unit 1 and Common facilities as of January 1, 1963 was as follows: Large Bore Small Bore Required 13,500 22,141 Designed 13,134 3,5701S.R. only) Delivered 11,872 N/A Installed 10,514 18,865

t i:' NRC AGENDA IIEM NUMBER 5 - continued The above totals include all supports - safety and non-safety class. h'owever, they include possible new designs that may be required as a result of the IE Bulletin 79-14 evaluation and vitration problems discovered during preoperational testing. These are discussed below under Rework. Safety Class Large Bore Included in the above totals are 5304 large bore safety class supports. Only 11 of these remain to be issued. Approximately 1250 snubbers are required and these have been planned for through bulk orders. Currently 25% of the required snubbers have been received en site. Safety Class Small Bore Included in the above totals are 3886 safety class small bore supports. To date 3570 of these have been designed and issued. The remainder will be completed daring the first quarter of 1983 Rework During the past year reanalysis for New Loads, design verification and redefinition of class breaks resulted in the issue of 449 new supports and 2297 revisions. Current efforts are aimed at confirming assumptions, which is expected to result in no more than 50 new supports. We expect this effort to be completed by April 1983 Additionally, we now anticipate no more than 100 new supports to result from the I.E. Bu13 ctin 79-14 evaluation. Finally, we estimate that 100 new supports may be required to resolve vibration problems discovered during preoperational testing. I I l j

ENGINEERING STATUS NOVEMBER 1,1982 NUMBER OF SCHEDULE ACTIVITIES % COMPLETE DESIGN-28,592 96.5 l NEW WORK 2,484 52 1 l REWORK 803 79 TOTAL 31,879 92 ~ l

I I I EQUIPMENT. RECEIVED l 1 TEM RECElVED % TOTAL REQUIRED VALV ES 9,517 99% INSTRUMENTATION 4,289 93% MAJOR EQUIPMENT 105 Orders 98% CABLE 5,559,457 89% REBAR 23,100 Tons 100% STRUCTURAL 9,197 Tons 100% EMBEDMENTS 1,900 Tons 100% SPOOLS 12,708 99% 1 12 /2" LARGERl HANGERS 11,872 89% llNCLUDES RESTRAINTSI

e FINAL DELIVERY DATES ITEM REMAINING DELIVERY DATE VALVES 44 11/8 3 INSTRUMENTATION 311 5/83 MAJOR EQUIPMENT 3 Orders 8/83 14 Pie' es c CABLE 706,543 5/83 REBAR O STRUCTURAL 0 EMBEDMENTS O / F SPOOLS 50 1/83 HANGERS 1,628 4/83 llNCLUDES RESTRAINTS) v.

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UNIT #1 & COMMON PIPING SUPPORTS STATUS AS OF JANUARY 1,1983 l l LARGE BORE SMALL BORE l REQUIRED 13,500 22,500 1 DESIGNED 13,134 3,570 (S.R.only) DELIVERED 11,872 N/A INSTALLED 10,514 19,000

UNIT #1 & COMMON. SAFETY-RELATED PIPING SUPPORTS STATUS AS OF JANUARY 1,1983 i LARGE BORE SAFETY SMALL BORE SAFETY i REQUIRED 5304 3886 i DESIGNED 5293 (99.8%) 3570 (92%) I

j. i PROJECT SCHEDULE l CRITICAL PATH UNIT #1 A. REACTOR BUILDING l

1. PIPING

- REACTOR RECIRCULATION SYSTEM (B33) - STANDBY LIQUID CONTROL SYSTEM (C41) - LOW PRESSURE CORE SPRAY SYSTEM (E21) - HIGH PRESSURE CORE SPRAY SYSTEM (E22) - RESIDUAL HEAT REMOVAL SYSTEM (E12) I

2. ELECTRICAL I

- CONDUIT INSTALLATION TO SUSTAIN BULK j ' CABLE PULLING & TERMINATIONS IN l SUPPORT OF SYSTEM TURNOVERS

3. INSTRUMENTATION & CONTROLS

- SAME AS ABOVE PIPING SYSTEMS l l B. OTHER ITEMS OF CONCERN l

1. PENETRATION SEALING

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2. EMERGENCY RESPONSE INFORMATION SYSTEM (ERIS)

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o PERRY PROJECT Used for NHC 1/12/83 Dy: William Crawford $!CNIFICANT QUANTITIES 12/28/82 Unit 1 & Common EA C Unit 1 & Cen. mon Installed CONCRETE " 310,C00 ff 308,000 CT ~' P!PINC Large Bore 160,623 LF 149,944 LF Sea 11 Bore 156,128._ LF 144,225 LF Total 310,154 LF FFT7FFT LF L8 Hargers 13,$00 EA 10.514 EA (Iniludes Restraints) SS Hangers 22,500 EA 19,000 EA (Includes Restraints) Tard 35,000 LF 38,000 LF ELECTRICAL CABLE Power 217,46C LF 184.990 LF Control 3,926,380 LF 2,774,866 LF Security 396,000 LF 323,733 LF Instrumentation 2,116,160 LF 1,341,180 LF Total 6,656,000 LF 4,624,769 LF ELECTRICAL CONDUIT Exposed Metal 525,156 LF 404,180 LF Cable fray 115,825 LF 110,000 LF ELECTRICAL TERwlNATIONS Power 6,3 20 Ea 4,633 EA Control 153,011 EA 86,482 EA Security 13,001 EA 7,722 EA Instrumentation 102.608 EA 55,595 LA Total 275,000 EA ID=,*jd EA ELECTRICAL CIRCUIIS Power 502 EA 315 EA Control 16,833 EA 10.553 EA Security __7 te8 EA 4,882 EA t Total 25,123 EA 15,750 EA INSTRUMENTATION Tubing 318,600 LF 172,106 LF Piping 38,600 LF 6,43t LF Valves 5,400 EA 1,845 EA Instruments 4,600 EA 1,352 EA Panels-Racks 800 EA 360 EA PAINTING Arch. Painting 916,700 SF 797,529 SF Nuclear Coating 1,370,100 SF 808,359 SF Valves 2,550 EA N/A F1 ping 30,000 LF - 17,700 LF Rangers 3,900 EA N/A 12/ 29/82/jes

• Includes expected future new and revised hangers coming out of final analysis and verification effort.

s

. ~ - e ~ Nuclear Test Section Detailed review and current status of preparation of preep and accepsance test procedures, integration and preop and acceptance test activities with construction schedule, system turnover schedule, preop and acceptance test schedule, current and proposed preop and acceptance tests program manpower. A. Total numb'er of procedures required for fuel load. 737 This consists of the total number of : l. Generic, Test Procedures 436 2. Flush Instructions 75 3. Test Procedures 226 (Preop & Acceptance) B. Number of draf t procedures not started. 207 Determined by: frequired

1. started 1.

Generic Test 436 - 323 = 113 2. Flush Inst. 75 - 56 = 19 3 3. Test Procedure 226 - 151 - 75 C. Number of draf t procedures being written 69 Determined by: # Started fcompleted 1. Generic Test 323 - 314 = 9 2. Flush Inst. 56 - 50 = 6 3. Test Procedure 151 - 97 = 54 l D. Number of procedures approved 461 1 Consisting of: 1. Generic Test 314 2. Flush Inst. 50 3. Test Procedures 97 E. Number of procedures in review 7 69 (same as C above) F. Total number of preop and acceptance tests required for fuel load. 485 The 485 number came from the total test activities that exist in our Premise schedule. There are a total of 226 preop and acceptance tests to be written and performed. The 485 is larger than 226 because our schedule counts all activities associated with preop and acceptance testing as preop and acceptance related activities. Th.sta related activities are primarily that of preparing for the preop or acceptance test in the form of a dry run. These dry runs are necessary to identif y problems that would otherwise disrupt the formal preop test. The dry runs are of ten done in checking out portions of the preop test off the critical path because only a portion of the system is available at the time.

Pcgs 2 G. Number of preop and acceptance tests completed. 35 This number comes right from the attached su:m::ary. H. Number of preop and acceptance test currently in progress. -6 This is the number of preop and acceptance tests started (41) minus those completed (35). I. Number of systems turned over to start-up. - 114 of 333 This number is right from the attached sununary. NOTE 1: Number of Turnovers from NCS to NTS 333 is diff erent from the number of turnovers from NTS to PPD 181 because generally entire systems will be turned over to PPD. NOTE 2: The number ot' turnovers NCS/NTS, 333, is different than the nurrber of System Scoping Packages 314. This diff erence is expected since wt have turnovers of less than full scoping packages. In these cases the turnover boundary is easily defined without creating additional formal subecoping packages. To maintain the schedule accurately, these additional. activities were addressed in the schedule.

NUCLE AR TEST SECTION TEST enoonESS SUMMAnlES MONTH OF HOVEHilER 1982 Total Complet,lon - Weighted Percent 37.3 Total Test, Act,1vit,les Complet,lon - Weight ed Percent, 13.6 UNIT 1 & COMMON Tot,a1 Sort wa; e Support, complet,lon - Weight ed Percent 23,7 TOTAL DEV. THIS PEHIOD TO DATE ITEMS ACTIVITIES SCHEDULED A C T U A t. SCH E DULE D ACTUAL y y RV IWTD.VALUEl MONT0 START COMP. START COMP. STAHT COMP. START COMP. COMP. COMP. TEST ACTIVITIES TURNOVER-NCS /NTS 333 ( 2.5) +3 57 53 7 7 242 232 122 114 34.2% .8% IC & R TESTING 672 (35.0) +9 71 46 26 6 422 223 280 131 19.5% 6.8% SYSTEH FLUSH /RUN IN 321 (15.0) +11 28 21 11 19 141 112 88 93 29.0% 4.3% PRE-OP ACCEPTANCE TESTING 485 (15.0) +4 4 3 2 2 48 35 41 35 7.2% 1.1%* TURNOVER-NIS / PPD 181 ( 2.5) +3 3 3 0 0 31 31 16 4 16 8.8% .2% 10TAL TEST ACTIVITIES 1992 (70.0) +30 163 126 46 34 884 633 547 389 19.5% 13.6% SOFTWARE SUPPORT ADMINISTRATIVE PROCEDURES 57 ( 2.5) N/A N/A 0 0 N/A N/A 57 57 100.0% 2.5% SYSTEN SCOPING PKGS. 314 ( 5.0) N/A N/A 0 64 N/A N/A 314 314 l00.0% 5.0% GE

N. PROCEDURE

S (ECP, GEN,ICP) 436 ( 9.0) N/A N/A N/A N/A 323 314 73.0% 6.6% TEST SPECIFICATIONS 169 ( 4.0) N/A N/A 15 3 N/A N/A 167 154 96.1% 3.8% FLUSil INSTRUCTIONS 75 ( 3.0) N/A N/A 5 N/A N/A 56 50. 71.7% 2.1% TEST PROCEDURES 226 ( 5.5) N/A N/A 33 10 N/A N/A 151 97 56.9% 3.1% Tur's 41 ( l.0) N/A N/A N/A N/A 23 22 54.7% .5% TOTAL. SOFTWARE SUPPORT 1318 (30.0) N/A N/A N/A N/A 1091 1008 80.5% 23.7% inf tuare Figure adjustments are result of updated projecti m. NOTE: N/A mean.s iiot Applicable to this cate gory.

Pags 1 of 3 CEI SCitFDUI.E FOR PERRY SER CONFIRMATORY INFOftMATION Target Issue Responsible Completion No. Individual Subject Status Date ( !) RAP Final piping stress analyses to determine pipe break locations, pipe whip Awaiting CEI 6/83 restraint locations, and the ef fect of jet impingement loads (3.6.2) In formation ( 3) TIT /LHN Containment ultimate capacity analysis (3.8.2) Resolved SSER #1 (Additional CEI Info. required) ( 6) RAP The applicant must reconcile the final Mark III hydrodynamic loads with Same as outstanding 1/1/83 the loads used in plant design (3.9.3.1) Issue #9 ( 7) Performance testing of BWR relief and safety valves to TH1 Action Plan Under Staf f Letter Sent item II.D.1 (3.9.3.2.1) Review 10/8/81 ( 8) IE Bulletin 79-02 with respect to pipe support baseplate flexibility and Under Staf f Letters Sent its effects on anchor bolt loads (3.9.3.3) Reviev 7/6/79, 1/11/80 12/19/80 (10) RAP /J PE Control rod drive system on llCU floor and effects of hydrodynamic loads Austting CEI 1/7/83 (3.9.4) Information Fuel and mechanical f racturing (4.2.1.2, 4.2.3.2) Under Staff Letter Sent (11) Review 9/9/82 (12) Fuel assembly structural damage from external forces (4.2.1.3, 4.2.3.3) Under Staff Letter Sent Review 9/9/82 Fuel rod bowing (4.2.3.1) Under Staff Letter Sent (13) Review 9/9/82 t (14) Overheating of gadolinia fuel pellets (4.2.3.2) Under Staf f Letter Sent Review 9/9/02 (15) Itu/NVT Preservice and inservice inspection programs (5.2.5.2 and 5.2.5.3) Awaiting CEI 4/1/83 Information (18) KA IILil/kVT llPCI and RCIC initiation. levels to THI Action Plan Item II.K.3.13 (5.4.1) Awaiting CEI 10/82 Information 8/83 Audit ~ (19) NA Isolation of HPCI and RCIC per THI Action Plan Item II.K.3.15 (5.4.1) Avaiting 8/83 Audit NRC Audit (20) RAP Subcompartment pressure analyses (6.2.1.6) Under Staff Letter Sept Review 12/2/82 RA - Resnived with Audit s 4 d e

Pags 2 of 3 - Issue RIsponalble Targtt No. _ Individual Subjrct Completion Status Date (21) KHW/ RAP Suppression pool temperature limits (6.2.1.6) Awaiting CEI 1/15/83 Information (25) ACH ADS actuation logic modification to THI Action Plan Item II.K.3.18 (6.3.2.3) Awaiting CEI Owners Group Information Submittal (25) EMB/ACH A complete design description of the ATWS recirculating pump trip (7.2.2.3) Awaiting CEI 12/15/82 Information (27) A complete description of the modified scram discharge volume level monitoring system (7.2.2.4) (FSAR documentation) Awaiting CEI 12/15/82 Information (28) HPCS system initiation circuitry final des!gn (7.3.2.2) Under Staff Letter Sent Review 10/14/87 (30) RCIC testing procedures (7.4.2.4) Under Staff Letter Sent Review 10/14/87 (11) RA Installation and calibration of pressure switches used for te lef/ safety Tentatively $/83 Audit valve position indication to THI Action Plan Item II.D.3 (7. 2.1) Resolved (32) Additional accident monitoring instrumentation to TH1 Action Plan Under Staff Letter Sent Items II. F.1.4, II.F.1.5, and II.F.1.6 (7. 5. 2.5) Review 10/14/87 (33) Failures in vessel level sensing lines common to control ano protection Under Staff Letter Sent systems and transfer of the recirculation pump to the low-frequency H/C Review 10/14/82 sets on trip and level 2 (7.7.2.3) (35) RA ACM Arrangement and physical separation and identification nf redundant safety-Awaiting Staff Audit 5/83 related electrical systems (8.4.4) Audit (36) _ RAP Test documentation of 3-hour fire-rated penetration (9.5.1.4.1) Under Staff Letter Sent Review - Additional 8/31/82 Information Required (40) RAP Provisions for watertight curbs at all entrances into switchgear and Awaiting CEI 12/82 diesel generator rooms (9.5.1.6.4, 9.5.1.6.6) Information (41) RVT Design for noble gas ef fluent monitor to THI Action Plan Item II.F.1.1 (11.5) Under Staff Letter Sent Review 12/21/82 (42) RVT Design for sampling and analysis of plant effluents to THI Action Plan Under Staff Letter sent Item II.F.1.2 (11.5) Review 12/21/82 RA - Risolved with Audit W 4

l' age J of 3 Tarr.et

• Issu2 R2sponsible Con.pletion No.

Individual Sub]tct Status D e t s* a 4 (44) SJW/ RAP Radiation and shielding design of IFIS tube (12.3.2) Under Staff Letter Sent Review 12/21/82 (51) RA NSSS Vendor Review at low power testing, ascension and emergency operating Avaiting Audit procedures per THI Item I.C.7 (13.5.2.2) NRC Audit (52) RAS / RAP Pilot monitoring of selected emergency operating procedures per INI under Staff Letter Sent Item I.C.9 (13.5.2.2) Review 11/16/82 (53) HAP /RVT Reactor Internals Vibration Prototype (BWR/6 - 238 in.) Program -- The Under Staf f Letter Sent applicant must provide analytical predictions of reactor vessel internal Review 9/9/R2 vibration levels and resolve past BWR problems (3.9.2.3) Changed from OI Proprietary 1 No. 3 per SSER 82

• Info. Sent 10/8/82 RA - Rasolved with Aucit DW19/C/3/sa e

P. ige 1 of 1 CEI SCHEDULE FOR PERRY SER LICENSE CONDITIONS (LC) INFORMATION Perry Responsible Target Set. No, Individual Completion Subject Status D.s t e ( 1)* TPK Implementation of protective measures when the L3ke Erie shoreline recedes Under Staf f Amendment 6 to 250 ft. from the emergency service water pamphouse (2.5.5). Review ( 2)* Periodic measurement of channel box deflections must be resolved before Under Staf f LRC 11 Position start-up of the second cycle of operation (4.2.3.1). Review Submitted 5/17/82 . ( 3)* HHH/ RAP Operation beyond Cycle 1 is not permitted until stability analyses are Awaiting CEI 11/83 provided for approval (4.4.4) Information ( 4) RVT A final report analyzing inadequate core cooling instrumentation requirements Awaiting CEI 12/15/82 for THI Action Plan ~1ces II.F.2 should be submitted by July 1982 for staf f Information approval (4.4.7). ( 5) EMB/CJP/ RAP Hydrogen control for degraded core accidents to THI Actica Plan Item II.B.8 Awaiting CEI 12/15/82 subject to completion of staff generic evaluations (6.2.7 and Task A-48 of Inforsatior Appendix C). ( 6) IE' Bulletin 80-06, engineered safety feature reset control (7.3.2.5). Under Staff LRC 11 Position Review Submitted.1/17/82 Audit on Test ( 7) SJW/ RAP Postaccident sampling system to THI Action Plan Iren II.B.3 (9.3.2). Avaiting CEI 3/83 Information ( 9)* DJT Test data to demonstrate that the HPCS diesel generator will not experience Avaiting CEI 11/85 undue wear at low room temperatures is to be submitted 24 months af ter fuel Information load (9.6.4). (10)* .JJW Each operating shif t shall be assigned a person with commercial BWR start-up/ ' Awaiting CEI 3/83 operating experience for a period of 1 year from fuel load, or the attainment Information of a nominal 100% power, whichever occurs later (13.1.2.3). ] (11) RJT Test and maintenance procedures associated with engineered safety features Under Staff Audit to THI Action Plan Item II.K.1.5 (13.5.2.3). Review (12) RJT Procedures for removing safety-related systems from service to THI Action Under Staff Audit Plan Item II.K.l.10 (13.5.2.4). Review (13)= TEM Complete implementation and maintenance of staf f spproveJ physical security, Under Staff Audit guard training and qualificatior, and safeguards contingency plans (13.6). Review (14) Initial test progr am per THI I.C.1 (14). Awaiting CEI 6/83 o Information (15)= HHH/RAF Prohibition of extended cycle operation with partial feedwater heating Awaiting CEI 1/84 (15.1). Information (16) RJT Leakage serveillance preventative maintenance progr.m to THI Action Changed from 6/15/83 4 Plan Item III.D.I.1 (11.5). Confirmatory Issue No. 43 per SSER #1

• Psat OL License Condition DW15/0/4/sa

P.ege 1 of 1 PNPP OUTSTANDINC ISSUES SCIIEDULE FOR CollPLETION Target Issuc Responsible Completion No. Individual,_ Subjec t St atus D.i t e ( 1) EJT/ RAP Turbine Missile Protection--Add'itional information from the applicant is Under Staff currently under review (3.5.1.3). Review ( 4) KAN/ACH Environmental and Seismic and Dynamic Qualification of Seismic category I Under Staff 3/83 Audit ikchanical and Electric Equipment--85% to 90% of this equipment needs to Review Scheduled be installed with documentation on site before an SQRT and EQ audit can be 4 scheduled and performed (3.9.3.2.1, 3.10.3.11 and Task A-46, Appendix C). ( 5) THJ/KHW/RVT Inservice Testing of Pumps and Valves--The applicant must provide a pro-Awaiting CEI 1/30/83 gram for inservice testing of pumps and valves; and a program for leak Information tests of valves that form interface between reactor coolant pressure boundary and low pressure systems (3.9.6). ( 7) ACH Control Room Design--The applicant must provide a preliminary design assess-Partially 8/82 Audit 4 ment needed to perform human engineering evaluation / audit of the Control Resolved Room design. The applicant must also adopt a conimon reference level for readout vessel instrumentation per THI Action Plant Item II.K.3.27 by June 1982 (4.47 and 18). - ( 8) RAF Containment Systems--Several new issues concerning the design of Hark III Awaiting CEI 1/15/83 containment systems (6.2). Information Action Plan Sent 9/10/82 ~ ( 9) RAP Pool Dynamic Loads--Awaiting applicant's response to generic loads definition Awaiting CEI 1/1/83 proviced by the staff (6.2.1.8). Information (10) RAP /EMB Containment Purge--The applicant must show that operation of the purge system Under Staff Letter Sent is kept to a minimum (6.2.4). Review 12/2/82 (12) WEC/ACH Hanual Initiation / Termination of ESF Systems--Information is required to Awaiting CEI 1/15/83 ensure that ESF systems can be manually initiated and terminated in the Information event that an accident proceeds in a manner different than assumed in the accident analyses for the design to conform with the intent of IEEE-279, Section 4.17 (7.3.2.7). (13) WEC/LPL IE Bulletin ?9-27. " Loss of Non-Class IE Instrumentation and Control Power Awaiting CEI 12/15/82 System Bus During Operation"--Design changes and procedures are required Information as necessary to aid the operator to cope with the potential loss of a Class IE or non-Class IE instrument bus (7.5.2.4). I (14) WEC/LPL cantrol System Failure--The applicant must provide the results of analyses Awaiting CEI 12/15/82 os procedural changes to convince the staff that harsh environments Information associated with high-energy line breaks and multiple control system failures will not cause control system malfunctions resulting in con-sequences more severe than those analysed in Section 15, or beyond the capability of operators or safety systems (7.7.2.1). 4 0 4 1

n tn o d e ti e 2 S2 l1 8 8 s t e get I u8 / r/ rl a .d/ 5 e6 a pD e5 1 t1 Tm vh1 / t/ o ec/ 2 e1 C RS1 1 L1 2 d f l e o ar 2 ni ou e iq g t e a iR I I d l' E n En fdn Co Co fAo s i i a i u d) gt gt t t t e2 na na S a a r i m im wm t rt t r t r rer S ei i o io eio f n af af dvf eU un wn nen D( AI AI URI g n g i v g v e n a i i h v e t e r a o r a r t e. r. n pd n e) g oe o d3 i r i n s yi t u3 e cu p 1 d nq e y( ee c l m gr x t t e r e nr t ew eo s me s rp y ei e re s v k ur fe a c d or t s e ei i tf t rh f nf n at i ea a. d mt c) so o pS i2 nt m o l a l p1 l t e e. p pn h v) a3 e t e2 1 ym D e( ce f 2 t h nl o e Tn ep s5 t - o gp a t i - i ru l n 3 b ) t es l e 1 u ya m a d ( S l r ea t i ne e c ) Op sn D c 2 o 't i A ( 2 l. t nd n d ti ae e n C. in cs t a nu i s s I U-l e y s ( o pr S t d w pd n n a t ad l e a n a o i i o e r s ) - f t he t n 1 f Tb n a ( a t o r 1 t f - l C T S i s l C. - h n i d f t s a w i o I f l u i n P s q s h o t i i s S yl L s e s c u d y r m 0 n s y e l u i R e e b r a d r g r d i n e e r r n u A c t u e e a q o n o m h t e e r I f E t S r R p e k l 1, bi u sd H M F ni W C C A ov J A A R pi J / / / ct C H S an B L A RI R H R as / e 6 / C o / r. ) ) ) ) 9 so 8 9 0 1 1 i st 1 1 2 2 u I ( ( ( ( D 1 1

O I 9 FERFORMANCE ANALYSIS REPORT DECEMBER. 1982 APPENDIK C DEVIATION ANAL.YSIS NFPORT STATUS Mit DATE CONTRACTOR / (DCNIZANT QUALITY 3., _ INITIATLD DESCRIPTION SYSTDt VENDOM (SP) CKM9f5NT ENGINEER /RESPONSISLE ENGINEER s. 10-6-77 CE Safety Bettef Valve B21 CE Completion committed 5/1/83. B. C. Sot t/P. A. Nichole destan weaknese 20 12-4-79 omteston of Double N/A Ctf (SP-93) Waiting for close-out of WR C. Dadesho/E. White Clase B" Watere tspo CQA 227. 21 4-28-80 Rosemount Model 510 DV Misc. CE Gr-301) Completion conattted 1/1/81. R. C. Salt /t. W111aan 1 Trty Calibretton Unite Wetting for closeout of MR Nos. Model 1152 Pressure CQC 1677. RECI 055. RECI 056.*** 29 5-I5-J0 Class IE Motor Control R24 Cu t te r-Namme r Completion commitment revised W. J. Boyd/R. M. Bonner Rev i Centers (SP-557) to 9-15-82 (irtended again). Revleton to Final Report pending.*** 30 6-4-80 Fatture of water Soluble Mi sc. FrP NR FrP 912 closed amt. QA

5. Walrath/R. Crofton/

Purge Dam to dissolve (SP-44/45/47) input for revleton of Fleet E. Parker /J. Eppich after being heated Report pending.*** Comple-tion Unit 1. by 9-15-82. Completion Unit 2. by 7-t-85. 37 10-6-80 Dette 1 6 2 Supprengton C41 NNIC (SP-660) NR CQC 2575 pending. C. Titte6y/E, Webb/ Foote* Stainte*e Steel C4 2 W. T. Mel'a Liner C43 38 10-7-80 Standby Dieset Cenerator R43

Tranean, Final Report mailed 12-10-82.

W. Boyd/A. Fusatert Model DSRV 16: Fatential DeLaval Close-out of NR CQC 1965. O Link Rod Deficiency (SP-562) a 39 10-9-80 Nilti-Rutk Bolte Misc. Hitti. Inc. Ready for NRC review. M. R. Kritser/W. T. Mette (Sr-208) 41 31-3-80 C-41 System Fuel Foot C41 NNIC (SP-53) Ready for NRC rewtew. C. 52ubbech/E. Webb Fenetrating Piping e

9 DEVIAftbei ANALYSIS REPORT STATUS DECtNeta. 1982 FACE 2 DAR DATE CONTRACTOR / NO. INITIATED DESCRlrTION SYSTth %ENDOR (SP) W ENT ENGINEEN/RFSPONSteLE ENGINLt4 COGNIZANT QUALITY 43 12-18-30 P M Flexible Condutt Ml3 CE (SP-591) Close-out of EDl's WNOJ by R. Solt/E. Willman Crounding 6-I-82 and WRKV by 12-l-82.8 44 1-2-81 Standby Diesel R47 Traneae. Completion cumaltted for W. Boyd/A. Puestert Ceneratore Lubricating DeLaval December 1982. Close-out 011 System Defect (SP-562) of NR CQC 1966. 46 2-3-81 Limit Suitches Misc. NAMCO Controle Completion committed for D. Crou/E. Thomac Rev. ! 9-30-83. MR No. ? 52 5-22-81 Concrete Cracks and N/A MECC (SF-20) Ready for NRC review. H. Fritzer/A. McCoy eye!!s in Unit il Fuel Transfer Area of Fuel Handling tutiding 56 6-I-81 Single Failure R44 al Ready for NRC review. T. Suasutger/F. A. Nichols/ Cr1terlon/ReceEver Tank Sensing W. Coleman 57 6-3-81 No Antal Cap in Cll FFF (SF527) Close-out of NR CQC 2244.888 C. Tilleky/J. Wijces Control Rod Drive Closed by NRC. Piping Socket Welde 59 6-22-83 Antal-Flow Fame, flousing M32 Suffalo Forge Ready for NRC review. C. Tilleky/H. Dt'eckmann thicLiese M43 (Sr648) 60 6-25-81 rushbutteas for Bailey Mt3 CE/NSSS Final Report due 5-I-83. R. Solt/E. Wi!! nan 720 Utility Stations / M51 Unlee t 6 2, and Common - Close-out of NR OQC 043. SOr Panels /PCCC 61 6-25-81 CR2940 Tanden Block CE (St301) Final Repou due 5-1-8 3. R. Solt/E. Willman Suttches/ Units 1 6 2 EDDR's RLt-5 72, EL2-586. PCCC i 9

e T DEVIATION ANALYSIS REPORT STA1DS DECEMBER, l982 PACE 3 DAR DATE ODNTRACTOR/ OOGNIZANT QUALITY No. t ulTI Af r9 DESCRIPTION SYSTEM VENDOR (SP) COMMENT ENCINEER/RESPONSIBl.E ENGINt.t R l 62 7-10-81 Neavy Weight Concrete / N/A NECC (Sr20) Estension let ter ma tted H. Kritter/A. McCoy Unite I and 2 Bloehteld !!-lG-82. Close-out of NR Wells CQC 2314, comeltments: Completion Unit I, 5-t-82.* 3 Compleston Unit 2, 7-1-83. 63 8-17-81 Rockbeston Coastal Rockbestos deody for NRC teview. W. J. Boyd/E. Wiltaan Cable (Sr193-01) 64 4-31-81 ripe Spool Sandblaettag Various rullman Power Ready for NRC review. C. Fennell/L Wheater (Sr44/47) 68 9-14-81 Cable Tray Spilce Bolts Various L.K. Comstock Reedy for NkC review. J. Furnese/T. Essar* I (Sr33) 78 10-12-81 Unacceptable Indicatione 2L51 NNIC (SP660) Ready for NRC rewtew. C. Tilleky/K. WeAb to Pola r Crane Ctrder. Unit 11 1 72 13-29-81 22 Schedule 40 four tech IEl2 Prr (Sr527) Ready for NRC review. C. Titisky/J. Wilcoa elbows with queettonable 2El2 material content. IE32 2rli 73 11-12-88 NNICO Unit 1 Containment NNICO (Srl?) Ready for NRC review. C. Nubboch/K. Webb floor plate welding activity 1 74 15-57-88 2 volde in Biological NECC (SP20) Extension letter melled M. Krltzer/A. McCoy Shield concrete in Reactor 12-10-82. Close-out of Nk Bld. #2 P020-0258, c ommi t men t s: Completion Unit 1, 5-4-83.* Compla tive Unit 2, 7-5-83. 78 12 80-81 Setsetc Clearance for P49 Could (Sr501) Wa ttlag for could Setsmic T. Swansiger/K. Pech Emergency Service Water tr45 Reports through CAI. rumps 2r45 e 9 %F

d btvlATION ANALYSl5 Btroef STATUS D EC EMRER, 1982 FACE 4 COMERACTOR/ CDCNIZANT QUALITY ~~ 5AR DATE No. INITIAftB DESCMirTION SYSTEN Vt NiiOR (SP) CteW4l NT FNGINEEN/ RESPONSIBLE ENCBNI G N_ i 79 12-10-81 Storties Air System IR44 Traneamerica Final Rrport nailed 12-15-82. W. Boyd/A. rusatert e. . Check valve /Delaval 2k&4 Delaval (Sr562) NR PQS 0001 Model DSkVl6 Si l-7-82 Covernor Lube Oil Cooler IR43 Traneamerice Waiting for close-out of W. Royd/A. Fumatari (West eschanger, Standby 2R43 Delaval (SP562) Nu rQS-0002, commitment en t ended to 1-I-8 3. Dieset Cenerator System) 82 1-28-82 Strees Analyste for CRD Cll CE/CA1 Final Report due I-7-83. C. T111eky/J. rppich/ l H. rutre l System Firing 84 2-22-82 Valve Identification Various Frr (SP44) Close out of DQC 108. Coe-

r. Martin /J. Eppich/

and Traceability pletion committed for 12-17-82. L. Wynn/C. Pasker 86 3-3-82 Reactor vessel Water Level 321 CE (Sr301) Final Report due 5.-83. B. Sole /E. Willman Transmitters (B21-Nosoo) Fol's tenued, WNUM and URLD. 89 3-5-82 Diesel Generator riping IR46 Traneamerica close-out of NR 7039-0477. W. Boyd/J. Cilstrap/ Welde IR47 Delaval (Sr562) Completion committed for A. Puestert 4-1-83. 90 3-9-82 Unit I Suppreselon Pool NNICO (SPIF) Final Report due 1-14-83. C. Hubbuch/K. Webb NR closed. floor Plate Walde/(Ref. NR 17-354) 98 3-18-92 Bottoming-Out of Socket 1018 FrP (Sr44) Close-out of NR NDS 006.*** C. Father /J. Wilcom Welds with fit-up gap of Closed by NRC. 1/16" in Control Rod Drive Piping System 92 3-22-82 Review of Radiographe for NNICO (SPl?) Meat repor t due 3-31-83. A. Bradshau/H. Walle/ W. T. Helle welJe in the containment veneels (Unite t & 2) 94 4-20-82 Welding / Cable Troy and Various LKC (Sr33) Final due 3-31-83. Re f e r ence J. Furness'T Stear / NR's CQC 2441 and 2444. V. stigakt Conduit Nangere l 95 4-19-82 H-Relay Contacts / Class R24 Cut le r-Hamme r Ready for NRC reviru. W. J. Boyd/R. Bonner IE Motos Control Centers (SP557) s 9

4 bLWB ATIOtt ANALYSIS RtPORT STATUS t D t'4't?t% L M. 3982 FACE S Dik DATE OVN t'RACTOR / CtMMl2 ANT QUALITT NO. INITIATED DESCulrTION SYSUN VI.NIN #R (SP) Ct PIHf'NT FtEINf t'N/RESPON?lRf.E t NCINt D N e 96 4-22-82 Nut /Cland Assembly for 2R42 Cutler-Ilammer Ready f or NRC review. W. J. BoyJ/R. Bonner e . 912 DC Contactor f ound (Sr$57) not to t.e seismically Qualtfled' Class IE Motor Cont rol Cent er 99 6-8-82 Potential defect in R44 Transamerica Completion committed by W. BoyJ/A. Pusatert starting air salve Delaval (SP562) 4-I-83. Na number PQS 10,. assembly / Standby Diesel Cenerators 100 6-23-82 Valve actuator C. H. Rettle Co. Completion committed for

1. Swansiger/D. Saochett yokes (SP 648) 18-29-82.

Close-out of NR OrQC 258. Entension Letter rending.** lia 2-86-82 Coverner Drive Coupling Transamerica Comple t ion c ommi t t ed f or W. Boyd/A. F*satert Delavel (SP562) 6-15-83. Close-out of NR FQS 0011. 113 2-29-82 Stauff tubing clamps Jol.nson Controle Ready for NRC review. J. Furneam/D. Lockwood found to be understaed (Sr-090) IIS 8-11-82 CE leHA relays may not be General Electric Final seport due 10-31-83. N. Solt/E. Willman fully insulated ($r-301) Related Has are closed, t l 806 8-11-82 Incorrect "vipe setting" Ceneral Electric MR Nos. PQS-0012, PQS-0014. R. Solt/E. Willman on some convert ed MFA (SP-305) heat report due 10-31-83 relaya (en t ended ). 8 109 Il-15-82 Commercial grade wire used Transamerica Interim Report na t ted 12-23-82. W. Boyd/A. Pusatert in certain engine and panel Delaval (SF562) Final Report due 3-30-83. circuits for IE Cable has NN TAS 6022. fatted IEEE 383 Flame Test. 0 0

t Y pt4*lATIDN ANALY$l$ pl*rokT STA1US ist CDthkN, 1982 PACT' 6 ' COGNIZANT QUAI.ITV ~ tilN 8'k ACTA'H f DAR liATE No. $NITIAllD IWTNi rTline !;V M IM % t Nf 4 4K (?;P) _ s1f t"' N T I NCINITk/RI:$rON$181.E INCIND.f tt 180 82-10-a2 h e Itatteriue ctor r45 overly Hfgr. neiermin. not to be M. Plena /A. Widme r/ . operators are of (SP-530) scrorsah's. C. T9ttaky commercial grade, not intended for CInse IE Nuclear Service.

• lli 12-21-82 CE encountered problems R21/

CQS/PQS HNC notif$cd 12-22-82. .l. Cilstrap/R. Solt/ with welde for main atene R33 Interim reg. ort d e I-27-83. F. Nichole whip restraints. Il2 12-23-82 Drtilco cove Imre type PPr NkC notified I-4-83. P. Matthys/J. Wilcos Site were used for (SP-44) Interim r eport due 2-3-83. drilling' httt t bolt s, which to in violation of Hiltt's spec.

• could poselbly impact schedule w

o I SN. WICE PhtSabtNT D. R. tia Vil6HN AlellEl.'INA Il VL Tk hv. NUCIIAI UNNI VICE PRt3RDtMf gj e g g.gg;;3 g4mg

3. J. FaktlNG M. R. EbetMAN I

I I I NUCLEAR t.NGINELRING 4MIALITI ASSURANLE PLhMV (UNT 8't 93 5 f ika ltif NUCt. EAR O)MSTRUCTION Dt PA RTMLNT t*FARTMENT ggyggyntgy ft:YlftS.tfak1MLNT DEPARTENT J. J. WalbRON N. L. PAbkt.li J.A. KLINL F. R. STt.4 D C. M. SHLriTER SuthtlNILNLANT 6t ANT OPLkATIOE4 l M. p. LYSTER NUCLEA R OJMSTRUCTluN NUCLE AR 143IGN & CDeGTbuCTION 3ApgAy3og p mjggygog ungaIhtN'lloM - IdstlNG SLf1IuN ENEI NI~IEIliO ANALVSIS SECTION Quat.lTT SECTION SECTION

3. F. kLILilcul G. H. Bushamb J. H LASIGIE8 J. H. IIELLACK E. RELET ILCalNit'AL SECiluN M* h* KAw

• JI*

NOCLEAR LONSTRUCTION NUCLEAR ".! CENSING N aAM OUALITT I* I" I AIM 14ISTRafl0N A FUEL tsM. SECTION SECTION gE N I' "" 8I"" A.P. JAt6 CHEW L. D. BECK S. D. WALMATH OI LRA TIOKi SLCTION

t. J. TabtCH NUCLEAR TEST 4 tetI N. & SPECIAL tm3CUkLMLNT & AIMIN-y4Clll1LM AND r.taviits stCitoN SECTION P:d)JECTS SLCTION g3gg4 TION SECTION 1.

9. HAWNIH N = L. BA RElk y L. E. HARTLINE P+ P MANIIN ttp R N f t NA Nrk SLCTION D. J. TA A A CS tt.N:iukNt l CONSTRUCTION AuplTING R. A. UWLtLi M. A. BROWN PERRY PROJECT ORGANIZATION L

NuttLAA PNOJECT T., NiNG SECT " 11 JAN 83 n.1.. VONLRAT.LK W w e m m-

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UNITED STA hS" (o, [.( ~ ~ ~ ' ~ f y g e NUCLEAR REGULATORY COMMISSION a waswiscTow. o. c. 20ses ,, g

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c 4....,* SEP 2 81981 Docket Nos. 50-440 and 50-441 MEMORANDUM FOR: A. Schwencer, Chief, Licensing Branch No. 2 FROM: fi. D. Hous' ton, Project Manager Licer. sing 3 ranch No. 2 SUBJECi: FOR,THCOMIriG FORECAST PANEL VISIT TO PERRY SITE DATE & TIME: October 7, 8 and 9, 1981 LOCATION: Perry Site, Lake County, Ohio PURPOSE: To discuss status of construction PARTICIPANTS:1 NRC ~ 'W. Lovelace. R. Gilbert and Region III _CEICO B. Col e.T.an, e t a l ".n:- 6: .-? + r., & M. D. Houston, Project Manager Licensing Branch No. 2 Division of Licensing CC: See next page i 1 Meetings between liRC technical staff and applicants for licenses are l open for interested r.1 embers of tHe public, petitioners, intervenors, or other part.ies to attend as observers pursuant to "Open Meeting and Statement of NRC Staff Policy", 43 Federal Reciste_r_ 28058, 6/28/78. l ~ c. 0 i bb. U D j

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..

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~ ..s Mr. Dalwyn R. Davidson .. r- . _4 - Vice President. Engfneering The Cleveland Electric Illuminating Company P. O. Box 5000 Clevelend, Ohio 44101 cc: Gerald Charnoff, Esq. Shaw, Pittman, Potts & Trowbridge 1800 M Street, N. W. Washington, D. C. 20006 Donald H. Hauser, Esq. Tne Cleveland Electric Illuminating Company P. O. Box 5003 Cleveland, Ohio 44101 Resident Inspector's Office U.S.N.R.C. Parmly at Center Road Perry, Ohio 44081 Donald T. Ezzone, Esq. Assistant Prosecuting Attorney 105 Main Street Lake County Aaninistration Center ~ .Painesville, Ohio 44077 Tod J. Kenney 228 South tollege, Apt. A Bowling Green, Ohio 43402

1.iel D. kilt

-3 E r., Mestier i '. ar.ce rce r; 7301 Cnippena Roac, Suite 102 Brecksville, Onio 44141 Rcbert Alexander CCRE Interim Representative 2030 Portsmouth Street Suite 2 -custen Texas 77095 Terry Lodge, Esq. 915 Spitzer Building Toledo, Ohio 43604 i ~

a p ; -- CASELOAD FORECAST P/.NEL SITE VISIT MEETING AGENDA .r Q. f.,, ti: d 1. Overview of project construction s.:hedule including progress ] gnd majcr milestones completed, current problems and any nticipated problem areas that may impact the current projected fuel load date. y [3 2. Detailed review and current status of design and enginee.-ing i effort (by major discipline) including any potential problems i., that may arise from necessary rework. 3. Detailed rcriew and current status of procurement activities including vsives, pipe, instruments, cable, major components, S ')etc. i a 4'. Actual and proposed craft work force (by major craft), craft 4.tvailability, productivity, potential labor negotiations and r y problems. ? Detailed review and current status of all large and small bore fj, J;. . :5, pipe hangers, restraints, snubbers, etc., including design, rework, procurement, fabrication, delivery and installation. .b k 'J. /6. Detailed review of project schedule identifying critical path items, near critical items, amount of float for various a3 -A activities, the current critical path to fuel loading, g.,} .l methods of implementation of corrective action for any activities with negative float, and provisions for contingencies. a ~^ The estimated project percent complete as of-Movember-301-1980. Ah V.'. to :.17

• 6,:.y n :

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. 7. Detailed _ review and current status of bulk quantities including , q " .4.- current estimated quantitjes, quantities installed to date, ,g quantities scheduled to date, current percent complete for each, actual versus forecast installation rates, and basis .k for figures. S f j(a) Concrete (CY) db) Process Pipe (LF) h. 't ' - Large Bore Pipe (21/2" and larger) Q Small Bore Pipe (2" and smaller)

.9 f(c)

Yard Pipe (LF) n. t 'h.'g' } (d) Large Bore Pipe Hangers, Restraints, Snubbers (ea)

c..

I y [ u:.g 'j :- .W.f . E$* I. g

• MG&

".T/$$ gJ/,k.i-

e (' -2 (e) Small Bore Pipe Hangers, Restraints (ea) Cable Tray (LF) ,rc ', - (g) Total Conduit (LF) I' \\ .f. --- ( h ) Total Exposed Metal Conduit (LF) (i) Cable (LF) Power Control Security Instrumentation L. i. Plant Lighting 's (j) Terminations (ea) Power Control M Security Instrumentation gt p. Plant Lignting ~ (k) Electrical Circuits (ea) J3 Power Control j Security 7 h'. (1) Instrumentation (ea) Gj@'

Detailed review and current status of preparation of preop

'ed gf and acceptance test procedures, integration of preop and M acceptance test activities with construction scheoule, system -turnover schedule, preop and acceptance tests schedule, current and proposed preop and acceptance tests program a ,m npower. e p 'a) Total nuaber of procedures required for fuel load. fb) Number of draft procedures not started. r (c) Numbf_r of draft procedures being written. ? (d) Number of procedures approved. b, l (e) Number of procedures in review. r (f) '?! O Total number cf preop and acceptance tests required for fuel load. L

• (g) Number of preop and acceptance tests completed.

J. (h) Number of preop and acceptance tests currently in progress. 1 + q (i) Number of systems turned over to start-up. I l.t!i,; i L .(

e - / 9. Detailed discussion of potential schedular influence due to . cd, d..,?requirements. i ' changes attributed to NUREG-0737 and other recent licensing

eh.e 10.

Discussion of schedular impact, if any, regarding potential .{p-deficiencies reported in accordance with 10 CFR 50.55(e). JB % A. ., t, - '(-fqi 11. Financial commitments to complete the plant. 'sh t

e. Y : ?.12. Overview of current construction management organization i

and activities. tt,u q. . t..ii,:- kw 13. Site tour and observation of construction activities. n.;; E .?.,..:v'. 'c. Q.4h - Q. eJ.,. i.,a4 ~n Wa.% w,, a,, 7 u. . a. -n m, n s .i w. - m %_...L.;) 'f 0 e. [ s ( b,[ t. 4 .f ~ ' 4 1 9 g e e

November 3,1981 PERRY UNIT 1 AND NEEDED COMMON FACILITIES A detailed review was made of the agenda material discussed during the October 7, 1981 site meeting. A site tour to observe the construction status and ongoing construction activities was made on October 8, 1981. The applicant's target construction completion date is May 1,1983, however, the i current, in house, forecasted construction completion date is November 1,1983. In view of the foregoing and based on the following: (a) The construction work remaining ir the reactor building including piping, hangers, electrical, coating, bio shield, and new loads modifications. (b) The construction work remaining on small bore piping and in particular small bore hangers. (c) The remaining cable installation and terminations. (d) The status of the pre op testing program. (e) Observations of constructicn work remaining during the site tour. (f) The construction status of this project compared with other projects in similar stages of construction. It was concluded that a realistic construction completion date would be the first quarter of 1984, with a nominal date of February 1984. ~

J e A at .g. September 29, 1981 Muy son.rtr== pfqir'rerAc gisAwffTtf3 l '@tt 1 & Common Tnstalled tmit 14 cosmon LAf us~TO 1 302,000 C.7. 310,000 C.7. t'de I eMrmFTt 131,689 L.F. Ji9,7dd -jgg ye e % 9,000 L.F. M ??? L.F. Y1h'e so tarse tore %B,0% L.F. L.F. bea u Dore U 7,5G L.F. total 8,700 EA. La mensere,taelu ss u,658 tA. (seetratets) 3,390 EA. sa mers, raeludes 20,600 EA. (postratets) 35,000 L.r. g, 30,000 L.F. Yard f tic"1TCAt. CA9f 4 60,352 L.F. If),Joo 210,260 L.F. 1,352,767 L.F. 4,ht,4co Power 3,k16,3SO L.F. J,.73c,ene 683 ffg peo Cortrol 3%,000 L.F. M.997L.F.L.F* 9,fC0,0ca Secetty 1 60 L.F. fast 1namentation L.F. Total Ettc*1icAt celeMft1 337,000 L.F. /,Ie, eco b5$,000 L.F. u posed metal 96,000 L.F. /10,(4 0 9,000 t.F. 8 Cable Tray Ffit*ttCAL TfnNT'IAffo'E_ 1,cas u. fee, b.000 p. 37,927 U. s/5,ece e:=r 91,000 YA. if,eee /eF ec, control 8.000 EA. W,393 u. Seewity 59.000 IA. EA. 3 t utr eestation W EA. Total ffFt*1ttCAL Citetm] Ik? EA. b00 EA. 5,k18 EA. yover Ib,000 IA. 1 000 u. Control 6 600 EA. 853 u. g, Security 21,=0 u.

2. tai Y27D*J4E1FPAt1OJ 153,000 L.F.

326,560 L.F. 3,100 L.F. Tublag 21,200 L.F. 1,2*5 D. Piptrg 3,900 EA. 1,150 EA. velves 3,700 EA. 270 EA. Taatrsaments 700 EA. Penels.3acks 7e f fr'Y1El 701,626 s.F. 916,700 s.F. b3k,319 3.F. Arch. Pttattag 1,370,100 8.F. Ihaelear coating 2.5 % EA. 3,000 L.F. valves 30,000 L.F. Piptag 3,900 tA. Meagers ee File k ( .\\ m s

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/O - ]~ bf PERRY PROJECT ORG ANIZ ATION ENG.A CONST R. ADMINISTRAUVE St!RV. VICE PRESIDENT VICE PRESIDENT _D R DAVI) SON R1 FADLING I I I PERRY PROJECT NUCLE AR ENG. DEPT. QUALITY ASSURANCE PERRY PLANT DEPT. SERVICES DEPARTMENT M. R. EDELMAN DEPARTMENT J.J. WALDRON R. L. FARRFIL M 1 TITAS CONSTRUCTION BUYING NUCLEAR CONSTR. CONSTR. QUALITY RADIATION PROTECT. ~ 0.N. LOCKWOOD J. K LINE E. RILEY S. F. KENSICKS ~ l DATA SYSTEMS NUCLEAR TEST PROGRAM OUALITY TECNICAL SECTION R.L. N AWORTN M. J. L ASTOVK A R.L VONDRASEK W. R. K ANDA PERSONNEL NUCLEAR DESIGN TR AINING A ADMIN. OPER ATIONS ~ ~ ~ ~ B. L. DARKLEY P. M ARTIN R. J. TADYCN R. A. OWENS 1 1 OPS-O A ROGRAM M AINTEN ANCE EQUIPMENT BUYEh NUCLEAR LIC. A FUEL ~ D. ZUPAN L.O. BECK B. D. WALRATH D. J. TA K ACS ~ ADM. & SPECIAL PROJECTS J. H. BELL ACK I

cI nn 9-r- t \\ PROJECT PROGRESS

SUMMARY

N 77.3% 'pNITN1 & COMMON 98% CIVIL STRUCTURAL 88% LB PIP E 62% SB PIPE 67% LB HANGERS n,80% ELECTRICAL RACEWAY 36% CABLE I r e

l PERRY NUCLEAR POWER PLANT AREA PROGRESS UNIT +1 & COMMON AREA % COMPLETE NUCLEARISLAND 78.4 RyCT,ORJUILDING 58.0 n vLp TURBINE BUILDING 88.0 CONTROL COMPLEX 81.6 YARD 90.4 l ~

1 e l e septaber 29, 1981 M"? M - SM m *.x.7cu'r St3 tatt 1 4 Ctenoa T.A.C. thtt 1 4 P-o tsstalled ceW T 310,000 C.T. 3D2,000 c.7. ?" MT. Large Bore 149,000 L.F. 131.689 L.F. Small more ikS.000 L.F. 91 222 L.F. attal @ L y. L.F. t la Par.sers (1seludes pestratats) 12.S58 u. S.TJO EA. 57 yagers (!aeludes nestralr.ts) 20,600 D. 3,3'O p. Tarc 35,000 L.F. 35,000 L.F.e f*_Wi".At CA ? _I WP 210..N L.T. 60.?'2 L.T.

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3.Lif,?S* L.T. 1.!!2.57 L.T.

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6as,w g,y, 7:ta. 5, N..tc .r. g.w....n L.r. ? _---s!:st

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% trJoset w:a*. L!$ pA L.F. 237,7X L.T. !stle -ray %,000 L.F. c6.000 L.T. ?!I-s

• cal Prin?"*:

"ev r k.000 IA.

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  r.- 1 91,0CC D.

37.":r" U.

et etty 8,000 EA.

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  .000 p.

IL.3M p. Total .c...w D. n .g D. !*I 7?"Ji*"T5 her 3.CC U. 147 EA. !setrol ik.00C IA. 5,k13 D. Security 6 dec EA.

== 1,000 EA. *7

• gtal 21,0cc D.

deso5 EA. ! n W a?*?4 Tubia 32,560 L.F. 153,000 L.F. 8 P!PiM 21,200 L.P. 3.12 L.F. valves 3,400 EA. 1,775 EA. N tr.mant s 3,780 EA. 1,150 IA. Panels. packs 700 EA. 270 U. Pa TT"*T, Arch. Patatias 916,700 s.r. 701,626 s.r. h etear Coatias 1,374.100 S.F. b34,319 3.y. valves 2,550 EA. Piping 30,0CD L.F. 3,000 L.F. Rangers 3,900 EA.

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PERRY NUCLEAR POWER PL ANT MAJOR PROJECT MILESTONES IUNIT 1) MILESTONES SCHEDULED ACTUAL t START CONSTRUCTION ILWA1 N. A. OCT. 21,1974 CONSTRUCTION PERMIT ISSUED N. A. MAY 3,1977 SET REACTOR PRESSURE VESSEL SEPT.11,1978 IT-41 AUG.13,1978 SET GENERATOR STATOR DEC.1979-JUN.1981 IT-51 MAY 15,1980 SET CONTAINMENT DOME MAY 12,1981 IT-61 MAY 2,1981 MILESTONES SCHEDULED TURBINE ON TURNING GEAR OCTOBER 15, 1981 SUPPRESSION POOL TURNOVER M AY 31,1982 COMPLETE RPV INTEGRATED FLUSH SEPTEMBER 16,1982 COMPLETE CONTAINMENT l.L.R.T. FEBRUARY 13, 1983 OPER ATING LICENSE M AY 1,1083 START FUEL LOAD M AY 1, 1983 INITIAL CRITICALITY JUNE 5, 1983 INITIAL TURBINE ROLL AUGUST 3, 1983 SYNCHRONIZE GENERATOR OCTOBER 1,1983 100 % POWER OPER ATION MARCH 29, 1984 COMMERCIAL OPERATION DATE MAY 1, 1984 M8 5. _.,

s SCHEDULE VERIFICATION PROGRAM OBJECTIVE: ASSURE PLANS & SCHE- ~ DULES ARE REALISTIC TO FINISH REVIEWED & UPGRADED CONSTRUC-TION SPECS TO REFLECT SITE CONDITIONS & PRODUCTIVITIES REVIEWED & UPGRADED "OUANTITY" INFORMATlON CORRECTED " WEIGHTING FACTORS" FOR WORK ELEMENTS ROLLED IN KNOWN CONTINGENCY ITEMS MOVED TO DYNAMIC SCHEDULE MODE l . EAC " BASE CONTRACT" UP 22%

CRITICAL PATH REACTOR BUILDING l . P A.I N T . PIPING Qa%) .I & C P . ELECTRICAL ICRD-202) -;o2.. f. OTHER . PLANT SECURITY l-123)

SCHEDULE TARGET VS. FORECASTED TAR G E T FORECASTED INTEGRATED FLUSH 9/16/82 3/30/83 i FUEL LOAD 5/01/8 3 11/01/83 i COMMERCI AL OPE R ATIONS 5/01/8 4 5/01/84 a j i i i 8

l CRAFT. LABOR .1982 LAST " BULK" CONSTRUCTION YEAR .1982 SLOW IN SURROUNDING COUNTIES . BASIC CRAFTS HAVE HIGH UNEMPLOYMENT .LARGE NUMBER OF TRAVELERS .MOST CONTRACTS "UP" SPRING 82 . PERRY MANPOWER UP = 10% IN 1982 . HOLDING OUT OF UNIT +2 . FORCE FINISH #1 . CASH e-.-- -w -<.w- .ene- -,- - - - - ~-- -~- -

D = PERRY NUCLEAR POWER PLANT MAJOR CONTRACTORS PERFORMANCE INDICATORS SPECIFICATION DISCIPLINE TO DATE 44/45 PIPING O.73 33/34 ELECTRICAL O.99 48/90 1&C O.74 49/91 HVAC 1.1 5 38/39 EQUIPMENT O.63 20 NUC. ISLAND CONCRET E 1.0 9 24 B.O. P. CONCRETE 2.0 0 N OT E: PERFORMANCE IN DIC ATOR OF ONE OR MORE IS ACCEPTABLE PERFORM ANCE. J

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1 .c ,7 ENGINEERING STATUS SEPTENBER 1,1981 l ....... ~ ~. NUMBER OF PERCENT SCHEDULE ACTIVITIES COlVFLETE -- l DESIGN 28,615 92 % NEW WORK 1,488 52% REWORK 5 81 33% ' TOTAL ~ 30,684 90%

SUMMARY

.NO ENGINEERING ACTIVITIE'S WILL HEAVILY IMPACT OUR SCHEDULED ' FUEL LOAD DATE .NEW WORK AND REWORK ENGIN- =. EERING IS DOMINANT . ENGINEERING OF PIPE SUPPORTS IN .. CONTAINMENT IS MOST CRITICAL smu

~ NEW WORK ENGINEERING . TECHNICAL SUPPORT CENTER ~ ~ . EMERGENCY OPERATION'S FACILITY . EMERGENCY RESPONSE INFORMATION SYSTEM (ERIS-NUREG 0696) .OTHER TMI REQUIREMENTS .l.E. BULLETIN 79-14 i . ANTICIPATED TRANSIENTS WITHOUT SCRAM (ATWS) O I [\\ '#

• PIPE SUPPO.RT REWORK NEW REVISIONS DESIGNS PIPING RE-ANALYSIS WITH FINAL "NEW LOADS" 500 200 AS-BUILT VS.

AS-DESIGNED ? 400 PRE-OPERATIONAL PIPE VIBRATION TESTING 100 ~ G

UNIT #1 & COMMON PfPING SUPPORTS 6 STATUS AS OF SEPTEMBER 1,1981 i LARGE BORE SMALL BORE i r / REQUIRED 12'858 20,600 i m ns i 77 2 l DESIGNED 12,396 (96%) 4,700 (23%) DELIVERED 10,885 (85%) N/A 1 INSTALLED 8,700 (68%) 3,390.(16%) l i -a,a

UNIT #1 & COMMON SAFETY-RELATED PIPING SUPPORTS STATUS AS OF SEPTEMBER 1,1981 LARGE BORE SAFETY SMALL BORE SAFETY REQUIRED 4423 2412 l ^ ' p o 5,... d t. ~ i 2y33 3,6 f/ DESIGNED 3961 190%) 1126 147%) l [462 REMAIN] DELIVERED 2433 15 5 %) N /A 3 L i 3 700 (16%).,7 400 (14%] INSTALLED c m en e

~ L + g CASELOAD FORECAST PANEL SITE VISIT i NRC AGENDA ITEM NUMBER 2 Detailed review and current status of design and engineering effort (by =ajor discipline) including any pctential problems that =ay arise frc= necessary Revork. Engineering Status 1. Engineering General - Engineering Progress as of Septe=ber 1st is as follows: Basic plant design is 925. All new engineering tasks are identified and scheduled as New Work and Revork. Our last engineering schedule revision in late 1980 defined the basic design activities which have been static. Kev activities are added tc Hev Work and Revork as they are defined. Presently 52% of the identified New Work tasks are co=plete and 33% of the identified Revork tasks are cobplete. Total engineering progrees is.o0%. No engineering activities vill heavily i= pact our scheduled fuel load date. 2. Structural - All Unit 1 and Co==en structural steel erection and concrete construction drawings for the =ain plant have been co=pleted and issued. Re=aining structural work affecting Unit 1 is li=ited to the Service Building, Guardhouse, and Emergency Operations Facility; plus evaluation of final nev loads impact on the structures nnd acco=odation of changes arising frcm the TMI and ATWS studies. 3 Mechanical - All but about a dozen Unit 1 and Co==en piping installation drawings have been co=pleted &nd issued. Approximately 90% of the piping hanger drawings for Unit 1 and Co==on have been issued. In this discipline, re=aining work includes the finali:ation of the pipe break, whip, and jet studies, completion of the re=aining hanger designs, design of the ATWS syste=, 24 and evaluation of the affect of new loads on the nipe hanger designs. Engineering effort of pipe supports in the contain=ent due to these topics is the most critical engineering effort that we are closely monitoring so that it does not i= pact construction. Agenda Ite= No. 5 vill discuse pipe supports in greater detail. L. I&C - All Unit 1 and Cc==on design instru=ent and control d' ravings have been released for installation. Current effort is limited to cleanup items: ATWS and NUREG 0696 (ERIS) design, and the IEEE Qualification Progrs=. Johnson Engineering - Approxi=ately 50% of the Johnsen Controls Installation / Fabrication drawings for Unit 1 and Co==en are complete and approved for construction. i I 5 Electrical - Approximately 95% of Unit 1 and Co==en electrical dravings have been ec=pleted and released for installation. Current effort consists of syste= close-out activities, ATWS and ERIS design, modifications arising frc= TMI studies. C. Site Design - GAI is designing safety-related s=all bore pipe supports and Reactor Building instrument and control line supports on site. Presently, the s=all bore safety-related effort for Unit 1 arJ Co==en is L7% co=plete while the I&C support effort is just getting underway. We anticipate having both efforts co=plete by the Fall of 1982. Pullman Power Products is designing non-safety s=all bore pipe supports and is 16% ec=plete on Unit 1 and Cc==on. ---r-

• P.

2 New Work and Pevork Engineering 1. The Technical Support Center (TSC) and the Energency Cperations Facility (EOF) are two building additions to the Plant which are spin-offs of the TMI incident. The civil / structural engineering effort on these facilities is su==ari:ed belcv. a) TSC - Dravings were prepared in Nove=ber of 1980 to define excavation limits and the additional foundation pile work for the L-shaped basement addition to the Service Building. The design construction effort is complete and concrete vork for the TSC is esser:tially complete.

Plumbing, electrical and lighting drawings have been issued to the installation contractors and this verk is presently underway.

b) EOF-The Site selection has been made and the preliminary specification for this facility has been ceveloped. The procurement specification and drawings will be ready for bid by Nove=ber 1,1981. 2. ERIS (NUREG 0696) - CEI has contracted with General Electric Nuclear Power Syste s Divisien and we have started an ERIS Plant Assessment Survey en September 22, 1981. This approach was initiated to develop the infor=ation needed for ERIS early and the full engineering. It is the intent of the survey to address the guidelines provided in NUREG 0696 as well as to incorporate important consideration for diverse sources elsewhere in the nuclear industry. The implementation schedule goal is as follevs: Application Engineering Complete 11/61 Cc plete ERIS hardware and software options / 12/81 contract agreement Functional diagra=s, equipment locations, 2/82 modifications, schematie diagrams to Ferry Architect / Engineer Deliver hardware and software to Ferry 11/82 Cc=plete testing and put in service the h/83 basic syste= 3 TMI Requiremerts Program Su==arv - We have addressed the TMI Requirements in the Ferry FSAR Table 1A-1. The status of car implementation is given in the right hand side of the table and vill be discussed later by Licensing. We are actively doing evaluation and design vork with GE, Gilbert Associates, and the BWR Ovner Group on these items, and caking the necetsary procedural changes. In addition, ve are doing the modificatien vork or have completed a significant number of TMI ite=s. The TMI requirements and their status can te categorized 4.s follows: No. of Items Status L Co:pleted, no further action required 6 Modification vork in process 7 Doing evaluation or design vork 12 373 Ovners Grcup doing evaluatien j(( Progran or Procedure changes being written

F. - 3 h.

1. 'E. Bulletin 79-1h - We have identified and are proceeding with a team of ll GAI site personnel to address the requirements of I.E. Bulletin 79-lh.

3 Procedures have developed and contractor as-builts are being reviewed in 2 preparation for taking field measurements. Our assu=ption is that the survey vill necessitate 25". reanalysis and 10'. redesign. As we obtain resu?.ts from the measurement effort, we vill be reassessing this estimate and applying resources to the reanalysis and redesign as appropriate. We are scheduling the e:6 neering and construction effort for this redesign so it 1 does not i= pact our fuel load date. 5 ATa'S Progra= Sum =ary - The Perry Project position on ATWS is that we are avaiting the results of rulemaking. However, we are evaluating Alternative 3A of NUREG-Ok60. If rulemaking requires this fix ve vill be in a position l to install it before fuel load. 1 i 1 1 1 i i 4 9 f -- -~

-. _ ~. _ , P. k i NRC AGENDA ITE4 NLHSER 5 Detailed review and current status of all large and small bore pipe hangers, restraints, snubbers, etc., including design, rework, procurement, fabricatica, delivery and installation. The status of piping supports for Perry Unit 1 and Common facilities as of September 1,1981, was as follows: Large Bore Small Bore Required 12.858 20,600 Designed 12,396 (96%) k.700 (23%) Delivered 10,885 (85%) N/A I Installed 8,700 (68%) 3,390 (16%) 1 The above totals include all supports - safaty and non/ safety class restrainsts, deadveights and anchors. They do not include any new designs re- ] sulting from reanalysis required by "new loads", preoperational vibration, or differences between as-built and as-designed installations. These supports fall under the classification of rework and will be discussed later. j Large Bore Included in the totals above are kh23 large bore safety class supports. The total that remains to be designed are k62. Of the k62, h20 are safety class and h2 are non-safety deadveights. Of the L20 safety class supports, 300 are restraints, nearly 200 of which are snubbers. Cverall 75% of snubber designs aEe complete. Fifty five percent (55%) of the required safety class supports are delivered. - The vast mayority of these are other than snubbers. Only 16% of the required snubbers have been delivered. Snubber requirements, which number about 800, have been anticipated by bulk orders. Snubbers units (minus vall and pipe attachments) i have been ordered bulk for well over a year. Presently, 400 of these units have been fabricated and avait assembly with vall and pipe attachment. hardware. To date, just over 700 safety class supports have been installed or about 16%. No snubbers have been installed. It should be noted that it is the Project's intention to install snubbers at the latest practical time to minimize damage. Small Bore 2 The totals for small bore supports are only estimates because the non-safety portion is only approximately known at this time. Of the totals, just under 2hl2 are safety class. Of these,1126 have been designed and nearly kOO (1h5) have been installed. The " delivered" status is insignificant since these supports have fabricated on site from bulk supplies of standar1 component parts. Revork i As previously stated, none of the totals include rework items. It is presently i estimated that 200 new designs and about 500 revisions vill result fron reanalysis of "new loads". However, a significant portion of the revisions vill censist only of updating load criteria and vill not result in hardware changes. All.new designs and revisions vill be the restraint type with the vast majority of these being snubbers.

._.~ P. 5 An additional quantity of supports vill require design or revision for differences as-built and as-designed installation. At this point, an estimate of four hundred (400) supports affected appears conservative. In addition to "new loacs" ite=A, new or revised support designs vill be required for vibration detected during pre-operational testing. About 100 supports are estimated. 4 These activities are already going into our cost predictions and when hardened up will be factored in the engineering and e3nstruction schedules and added to the construction manhours. These pipe support efforts are a major project concern and vill be given a heavy priority and e=phasia so that the fuel load date vill not be impacted. J 9

_= Wb EQUlPMENT. RECEIVED ~ 1 TEM RECEIVED % TOTAL REQUIRED VALVES 8,543 92% INSTRUMENTATION 3,320 88% MAJOR EQUIPMENT 104 ORDERS 96% CABLE 4,315,300 90 % REBAR 23.100 TONS 1OO% STRUCTURAL 9,017 TONS 98% EMBEDMENTS 1,900 TONS 1O0% SPOOLS 11,658 99% 1 [2 /2" LARGERI HANGERS 10,885 85 % llNCLUDES I 9 'G-RESTRAINTS)

227

' ~ FINAL DELIVERY DATES ITEM REMAINING DELIVERY DATE VALVES 780 9/82 INSTRUMENTATION 460 1 O/82 MAJOR EQUIPMENT 4 ORDERS 6/82 20 PIECES ~ CABLE 1,463,500' 7/82 .REBAR O STRUCTURAL 180 TONS 2/82 1 EMBEDMENTS O SPOOLS 142 6/82 HANGERS 1,973 12/82 llNCLUDES RESTRAINTS)

9. R Q 9

PROBLEMS

1. KNOWN REQUIREMENTS 1 VENDOR PERFORMANCE l

ACTIVITIES

1. EXPEDITING l

2. CONTRACT AMENDMENTS

3. ALTERN ATE SUPPLIERS 2

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NUC1. EAR TEST SECTION Detailed review and current status of preparation of preop and acceptance test procedures, integration of preop and acceptance test activities with construction schedule, system turnover schedule, preop and acceptance test schedule, current and proposed preop and ecceptance tests program manpower. Total number of procedures required for fuel load. - 564D a. \\ b. Number of draf t procedures not started. - 29 3 c. Number of draf t procedures being written. 8 d. Number of procedures approved. - 335 42 / e. Number of procedures in review. "yy*e e Total number of preop and acceptance tests /, required for fuel load. - 191-7 g. Number of preep and acceptance tests completed. h. Number of preop and acceptance tests currently M I D g q ~~, in progress. 1 g 1. Number of systems turned over to start-up. - 59 of 262 One Hundred Eighteen (118) people to date (50 CEI/68 consultants). yA y W pq S 'g,, p l 1,, i> ' c () 3 ,G - P y;tC/s"' 3 e,"j...y. ;,, a p. _b6 c,..;.. s G y

PERFOR.'t.tNCE ANALYSIS REPORT jg, ey-9/ SEPIDiBER, 1931 APPENDIX I DEVIATION ANALYSIS REPORT STATUS DAR DATE CONTRACTOR / NO, INITIATED DESCRIPTION SYSTEM VENDOR (SP) COMMENT 6 10-6-77 CE Safety Relief Valve B21 CE Completion commi ted 5/1 'S3. design weakness 20 12-4-79 Omission of Double N/A CLC (SP-93) Waiting for close out of NR No. Class "B" Waterstops CLC 526. 27 4-28-80. Rosemount Model 510 DV Hisc. ' CE (SP-301) Completion committed 1/1.*31. Trip Calibration Units Waiting for closeout of NR Nos. Model 1152 Pressure CQC 1677 RECI 055, RECI 056 a..! Transmitters FDL Nos. 50051 Rev. 0 & 1; '.* REC, Rev. 0 & I; WNilX, Rev. 0 & I. 26 4-28-80 Radiographs for Dikkers B21 CE (SP-301) CE report draft received; DAR i. Safety Relief Valves NDS, and closeout of NR 52. CQC 1422. 29 5-15-80 Class IE Motor Centrol R24 Cutler-!!ammer Completion commitment re.-ised I: Rzv. 1 Centers (SP-557) 12-1-81 (extended). 30 6-4-30 Failure of Water Soluble Misc. FPP Final Report mailed 8-3-51. Purge Dao to dissolve (SP-44/45/47) after being heated 37 10-6-80 Units 1 5 2 Suppression C41 NNIC (SP-17) Final Report due 12-15-S'. (exte.ded Pools' Stainless Steel C42 a second time). Liner C43 38 10-7-30 Standby Diesel Generator R43 Transam. Final Report due 12-1-81. Hodel DSRV 16 DeLaval (SP-562) 39 10-9-80 tiliti-Kwik Bolts Misc. H11tt, Inc. Ready for NRC review. (SP-208) 1

SE' TEMBC3, 1981 PAGE 2 t DAR DATE CONTRACTOR / NO. INITIATED DESCRIPTION SYSTDI VENDOR (SP) COMMENT 41 11-3-30 C-41 System Fuel Pool C41 NNIC (SP-53) Closeout of NR No. CQA-173. Penetrating Piping 43 12-18-80 PCCC Flexible Conduit H13 CE (SP-591) Final Report due 10-30-S. (ext a. fed). Grounding Close-out of FDi's WH0J and WR!:. 41 1-2-31 Standby Diesel R47 ' Transam. Final Report tentatively schede *.ed Cencrators Lubricating DeLaval for October,1931. Oil System Defect (SP-562) 46 2-3-81 Limit Switches Misc. NAMCO Controls Final Report due 10-29-S2. Rev. 1 ~ 47 4-8-31 Penetration Anchor and Misc. CAI/PPP (SP-527) Repair coopletion commi :ed Bartier Plate Material August, 1981 52 5-22-81 Concrete Cracks and N/A EECC (SP-20) Final Report mailed 10-1-31. spalls in Unit #1 Ready for NRC review. Fuel Transfer Area of Fuel Handling Building 56 6-1-S1 Single Failure R44 CAI/ General VaitIng for revision of drawings Criterion / Receiver Atomics D302-351 and D352-351. Tank Sensing 57 6-3-31 No Axial Cap in Cll PPP (SPS27) Final Report due 12-7-31 Control Rod Drive (extended). Piping Socket Welds 59 6-22-81 Axial-Flow Fans, Housing M32 Buffalo Forge Final Report due 10-31-S1. thickness M43 (SP648) 60 6-25-81 Pushbuttons for Bailey H13 CE/NSSS Final Report due 5-1-83. 720 Utility Stations / 351 Units 1 & 2, and Connon - BOP Panels /PCCC

2AR DATE CONTRACTOR /

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U;ITIATED DESCRIFFION SYSTEM VENDOR (SP) COFDIENT 61 6-25-31 CR2940 Tandem Block CE (SP301) Final Report due 8-1-83. Switches / Units 1 & 2 PCCC dl 7-10-81 Heavy Velght Concrete / N/A NECC (SP20) Final Report due 12-18-81 Units 1 and 2 Bioshield Walls 63 8-17-31 ? Rockbestos Coaxial Rockbestos Interim Report mailed 9-18-81 Cable '(SP793-01) Final Report due 1-22-82. 64 8-31-81 ' Pipe Spool Sandblasting Various Pullman Power Interim Report mailed 9-30-81 (SP44/47) Final Report due 1 82 65 9-4-31 Diesel Generator R43 Transaa. Determined not to be reportable. Engines / Intake and Delaval Exhaust Valve Springs (SPS62) 66 9-10-81 Spool Pieces IC41 PPP (SPS27) NRC notified 9-24-81 Report due 10-23-81. 67 9-11-81 Linitorque Operator NRC notified 9-22-81. Report S15-3, SMR-4, or SMB-5 due 10-22-81 Motor Pinion Key 6B 9.*;-81 Cable Tray Splice Bolts Various L.K. Constock NRC notified 9-18-81 Report (SP33) due 10-16-81 69 9-17-81 RWCU Heat Exchangers 1G33 CE NRC notified 10-1-31 Report Weld Docueentation due 10-30-81. D

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~ FrenY NuCLL AH l' OWE 2 PLANT MOJECT CAGAN42ATION I up lun;.* isto toccivia n.. s i c...il. TH E C,.EVELAN D CLECTHIC ILLUMINATING COMPANY ANo utan (NclNEEAS, INC. M E M O R A N D,U M exac.. r.w nev. o.aa R.gus.. CTnran oATc Oc t. 7,. :I To it. Jadgchew acow W140 raow phone 331 acoM W140 Piping Weighting (General) sumacci Spools N N -3% 'Was in Off Loading------------------- 33% 1. Carry-In----------------------- Effect to 2. 3. Insta11ed----------------------29% July 1981 / 4. Hangers------------------------30% % ~ Hydro----------------------- ---5% B 1. Off. i.o ad i ng ---------------------3% Now in ~ 2. Carry-In-----------------------33% Effect 3. Installed----------------------59% 4. Hydro--------------------..------5% Note: Hanger's included in "A" are not included in "B" WYr& /~% 4-izl' 1(C/fb cc: H. Scull W140 D. Younkin W210 L. Wynn W210 - 3.09,e un o X, Sec-1x1 'o"P N '- G& ? "'* 5..LMICE. 09*C9 09 4'j t g

1981 1962 olJ F M A s o 14 Jl F i ta A M 3 3, A IS. o N,.o 7 F M A M J J A I I i f 'l r j ) i l i 400.- i i 3 e i l i I t 360i -t l.- l t g -j-l i I I i i I i 320 ) i I i i l ? f. - - 4 i - 'I-- l 280s I l l l < - (: .1 p f 240 /l l s C H E D U I. E'O 5 - - f U R N O V E. R O a n i s n $di y i l-j-;'/ j- - 2 I i I I 200.* t i i l/ l /. l. I /t 1 I f I } i ,i i / l 160s-l 4 i '1 l / I i

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=- .19 8 @ 1.984 . 9e5 ~ o l.T F MA MJJ A s l_o N______ N D J F M A M J 3 Aso N D MlJ 3.A.5.o s I ~ l l I I i l l fl l! I i I I i i I I 1 i i s' c 6E l i i i i t i i i i i j I l i. 1 I i I. i. e i i i l l l l l l i. I i i l 1 l l i i 4, i i l l l-s .l I t l l !l s l l A I i I I l i I l l j l 1 j i i l t i 1 l l l l l 7 - i i i i-i i i l l l I i l I .', I ll l l l l f e i i j f I g I I ) l l l tvision - oATe oATE THE CLEVELAND ELECTRIC ILLUMINATING CO. i , PERRY NUCLEAR POWER PL ANT UNITS 1a 'l l n '.' ". " l PROJECT SCHECULING n'."w"n ,., a . -. m o r She et of D w Q. N o. . ;t. Survu /0 -?- BI

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h a 4 s ENGIl m ING II.K.3.13 - AUTdRCICRESET II.K.3 28 - ADS ACCUMUIATORS II.B.3 - POST ACCIDENT SAMPLING III.D.l.1 - I2AYAGE PATHS CUTSIDE CONTAIICGITI III.K.'3.15 - RCICTIMEDEldY III.K.3.18 - ADS ACTUATION LOGIC III.K.3 21 - HPCS AUTO RESET i III.K.3 27 - COM40N REF. LEVEL III.A.l.2 & y III.I.D.2 - ERIS/SPDS/ EOF /TSC b d *- d ' [.y b 4 &.. E.s. /J/if2 f-G. E., III.E.h.2 - CONTAIICEIG ISOLATION 3 -Q., a , e A m nq G N F I

P 2. LICENSING FROBLEMS RG - 1.97 - CORE EXIT 'Icc NEUTRON FLUX MONITORING EQUIPENT QUALIFICATION NEW LOADS g COIEROL ASI.B i l

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