Text

Forwards Update to 801030 Response to Suppl 3 of IE Bulletin 79-01B, Environ Qualification of Class IE Equipment. Master List of Electrical Equipment,Component Evaluation Worksheets & Svc Condition Profiles Encl
	ML19350B687
Person / Time
Site:	Point Beach
Issue date:	01/30/1981
From:	Fay C; WISCONSIN ELECTRIC POWER CO.
To:	James Keppler; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
	IEB-79-01B, IEB-79-1B, NUDOCS 8103230309
	Download: ML19350B687 (130)
	v • d • e

{{#Wiki_filter:-. .l',,,.= 1 Wisconsin Electnc m cwmr . 0' 0R BRIG.W'" 231 w. MICHIGAN. P.O. BOX 2046. MILWAUKEE. WI 53201 January 30, 1931 d ..r. J. G. Kappler, Regional Director w Of fica of Inst.uction anc Enforcoc ent, Region III O. S. aLCLLAR FIGLLA?,ORY COMMISSION 7H Accsevelt.4cau Glen Ullyn, Illiaoia 50137 vear dr. Koppler: LOcEET NOS. 50-266 A:40 50-301 P.ESPO;.bi; TO II.; SUPPLLME;iT NO. 3_ TO SULLETIN I40. 79-010 EdVIROSiC.TAL GUALIFICATICH OF

.LiCTRICAL *.QL;IPMu.T POIa7 BLACE i.L;CLt.AR PLA.T, CiffTU 1 A!C (

Tau attachec enclosures provide our responso to Supplo: aunt do. 3 to Ih Julietin ho. 7 3-J10 anc up. late our previous suixalttal cat.se Octor,ur 3u, 1980. Enclosuru 1 to tnia lutter provides sn upcatoo "naster list" of clactrical 6 quip-nont. This list inclucius tno additional itano raquired by cuppleauent no. 3 (T.II Action plan electrical cc::ponents and equipnout requirou to acl.iavo and maintain a cold snutcown conwition). Enciosures 2, ., and 4 f.rovice ccangos anc aduitions to tne component v,aluation worAsheeta, servico conoic. ion profilos, and equipsont qualification plan, roussetively, j Changes from our previous sutcittal are ladicated with a l vertical lino in the rigat =argin. i Laclosuru 4 lista zevaral eco;.onenta whica could not 1;u faily coc uentue to noot snu ;GR Gu1Julinas. It la Our intention ttat tasso couponents co environ:awntally tac cec, upgraced, or replacoc in ccaformanco with ;iac requirar. cats L,y J ur.a 30, 1 s.s 2. Tnia lottur and encicouros are affirceu in 8103ab D309

Mr. J. G. Keppler January 30, 1981 accoraance witn the provisions of 10 CFR 50.54(f).

le would be pleased to respond to any questions you may have related to this submittal.

Very truly yours, C. W. Fay, Director Nuclear Power Department Enclosures Subscribec and sworn to before rae This 30ta day of January, 1381. Y

t. s s.

.m. m~m t Notary Public, state of Wisconsin My Commission expiras ' i ' l 4 Copies to: NRC Resident Inspector Point Beach Nucicar Plant Mr. Norman C. Mosley, Director Division of F.accor operations Inspection } Office of Inspection and Enforcement l I l I 1 i l l t l L 1 n

I ENCLOSURE 1 I f l l t i I ( i l l l l 1 l I i

ENCLOSURE 1 FACILITY: Point Beach Nuclear Plant, Unics 1 anc 2 page 1 of 14 ASTER LIST Rev. 4 DOCKET NO.: 50-266 and 50-301 (CLASS IE ELECTRICAL EGUIPMENT REOUIRED TO FUNCTICN UNDER POSTULATED ACCIOENT CCNDITIONS) I. SYSTEM: Safety Injection COMDoNENTS LoCATICN PLANT IDENTIFICATION INSIDE PRIMARY OUTSIDE PRIMARY N W ER GENERIC NAME CCNTAINMENT CCNTAINMENT 1-P14A&B Pump Motors X 2-P14A&L l-P15A&B 2-P15A&B Pump Motors X 1-SI851A&B Valve Motor 2-SI851A&B Operators X l-SI871A&B Valve Motor 2-SI871A&B Operators X 1-51860A, B, C, & D Valve Motor 2-SI850A, B, C, & D Operators X 1-SI852A&B Valve Motor 2-SI852A&B ODerators y 1-SIB 78B7D Valve Motor 2-SIS 788&D Operators X l-SI836A&B Electro-Pneumatic 2-SI836A&B Transducers X Namco "SnaD-Lock" D2400X Limit Switches X l-PT922&923 Pressure ?-PT922&923 Transmitters X i i l-FT924&925 ?-FT924&925 Flow Transmitters X l -FT928 ?-FT928 Flow Transmitters X l-LT931 j ?-LT931 Level Transmitt. l 1-LC942A&B, 943A&B ?-LC942A&B, 943A&B Level Switches X American Oil Co. Amolith #2 Lubricant (Grease) X American Oil Co. Amolith #1EP Lubricant (Grease) X X 40011 011 Co. !28 Lubricant (Grease) X X American Oil Co. Industrial #35 Lubricant (Oil) v American Oil Co. Rykon Industrial #15 Lubricant (011) X t Okonite 5,000 Volt AC Power Cables

==== mens.

. =

M

Pace 2 of 1: Rev. : SYSTEM: Safety Injection (continued) CCMPCNPFI '^^ ~" PLANT IDENTIFICATION INSIDE PRIMARY CUTSIDE PRIMARY NUMBER GENERIC NAME CCNTAINMENT CCNTAINMENT Keri te 600 Volt AC Power Cables X X Rome 600 Volt Control Cables X X Keri te 600 Volt Control Cables X X Okonite Instrumentation Cables X Boston Insulated Instrumentation Wire & Cable Cables X X Bechtel/Raychem Electrical Cable Solices X Crouse Hinds / Electrical Penetration Westinghouse Assemblies X X Welded Canister l men e

~ b II. SYSTEH: Au~iliary Coolant Page 3 cf la Rev. 4 C MPCNENTS l -l I ..--.y PLANT IDENTIFICATION NI RIMARY CUTSIDE PRIMARY NUMBER GENERIC NAME CONTAINMENT CONTA!N*.ENT l-P10A&B ? 310A&m Pume Motors X l-Pila &B 2-P11A&S~ Pumo Motors X l-AC738 A&E Valve Motor 2-AC738 AaB Ocerators X Valve Motor 1&2-AC700 Operators X* Valve Motor 1&2-AC701 Operators X* Valve Motor 182-AC720 Operators X* l-AC624&525 Electro-Pneumatic i] X 2-AC624&525 Tranducers l-AC626 Electro-Pneumatic 2-AC626 Trancucers X NAMCO " Snap-Lock" L1mi; 5wittnes l 02:00X X l-PT628&629 ? cT6?c1*?9 Dressure Transmitters X 1-FT626 1 2-FT626 Flow Transm1tters X l 1-FT619 2-FT619 Flow Transmitters X 1-TE627&S30 Temoeratuni l 2-TE627&630 Elements X 1-TE621 Temperature 2-TE621 Elements X l American Oil Co. Amelitn 42 Lubricant (Grease) X American Oil Co. Amolith di EP Lubricant (Grease) X y, Mobil Oil Co. 42c Lubricant (Grease) X* X American Oil Co. Rykf.n i Industrial #15 Lutricant (011) X American Oil Co. Industrial d21 Lucricant (011) X Aerite 600 Volt AC Pcwer l Cables X* X l

Ecuipment is recuired for cold snutdown only and not recuired for accident mitigation.

I (Equipment is not safety-related)

i II. SYSTEM: Auxiliary Coolant (continued) Page 4 of 14 Rev. 4 COMPCNENTS i l l

~~'~"

PLANT IDENTIFICATION INSIDE PRIMARY CUTSIDE PRIMARY NUMBER GENERIC NAME CONTAINMENT CONTAINMENT Kerite 600 Volt Control Cables X* 600 Volt Control Rome l Cables X Boston Insulated Instrumentation Wire & Cable Cables X Bechtel/Raychem diect-ical Cable Splices X* Crouse Hinds Electrical Penetration Westinghouse Assembly X* Welded Canister 4 1 i l l l i

Equipment is required for cold shutdown only and not required for acticent mitigation.

(Equipment is not safety-related) I se ---g m -r

? III SYSTEM: Chemical and Volume Control R COMPONENTS .ac..,nv PLANT IDENTIFICATION INSIDE PRIMARY CUTSIDE PRIMARY NUMBER GENERIC NAME CONTAINMENT CONTAINMENT I LT-106,172,&l 90 Level Transmitters X 2LT-106,172 &l90 Level Transmitters x LT-102,171,&l89 Level Transmitters X Boston Insulated Instrumentation l Wire & Cable Cables X i t I I

Page 6 of 14 E2** # IV. SYSTEM:' Reactor Control and Protection COMPONENTS PRIM Rh bbkSIDE PRIMARY N DE N MBER GENERIC NAME CONTAINMENT CONTAINMENT l-LT426,427,428 l 8433 Level Transmitters X 2-LT426,427,428 &433 Level Transmitters X l-PT429,430,431 &c49 Pressure Transmitters X 2-PT429,430,431 &a49 Pressure Transmitters X l-PT945&946 2-PT945&946 Pressure Transmitters X l-PT947&948 2-PT947&948 Pressure Transmitters X l-PT949&950 2-PT949&950 Pressure Transmitters X Okonite Instrumentation Cables X X Boston Insulated Instrumentation Wire & Cable Cables X Bechtel/Raychem Electrical Cable Solices X Crouse Hinds / Westinghouse Electrical Penetration X Welded Canister Assemblies X l 1 -e-m- am.- w y-a --- 4 e r r e-e-r, ,---w-- --rcer w

V. SYSTEM: Reactor Cooiant Page 7 of 14 Rev. A COMPCNENTS .......u PLANT IDENTIFICATION INSIDE PRIMARY CUTSIDE PRIMARY NUMBER GENERIC NAME CCNTAINMENT CONTAINMENT Valve Motor l&2-RC515&516 Doerators X 1&2-RC430&431C Solenoid Valves X NAMCO " Snap-Lock" ga'an_1stn? Limit Switches Y 1-PT420 2-PT420 Pressure Transmitters X l-TE450A&B Resistance Temperature 2-TE450A&B Elements X l-TE451A&B Resistance Temperature 2-TE451A&B Elements X In-co re 1&2-TEl-39 Thermocouples X Thermo Electric Electrical MSP-KX Connector-X i 1-REF.JBl&2 Thermocouple Reference 2-REF.JBl&2 Junction Boxes X l - vr.191c7en: T-are s.>r. s y Westinchouse Acoustic Monitor Amphenol Twinaxial Type 32225 Connectors X Westinchouse Dwg. N6. 393A701 Iten Immersion Heaters X* Burndy "HYLUG" aype YAV-L Cable Lugs X* l American Oil Co. l Amolith al EP Lubricant (Grease) X Mobil Oil Co. l l d28 Lubricant (Grease) X Instrumentation Okonite Cable X 600 Volt Power l Kerite Cable X l 600 Volt Control Kerite Cable X 600 Volt Control Rome Cable X Boston Insulated Therroccuole Wire & Cable Co. Extencien Wire X

Ecuipment is required for cold shutdown only and not recuired for accident mitigation.

(Equipment is not safety-related)

V. SYSTEM: Reactor Coolant (continued) Page 8 of 14 Rev. 4 COMPONENTS IDE PRIMARY SIDE PRIMARY N M ER GENERIC 4AME CONTAINMENT CONTAINMENT Rockbestos Twinaxial "Firewall" Instrumentation Cable X Electrical Cable Bechtel/Raychem Splices X Crouse Hinds / Electrical Penetration i Westinghouse Assemblies X X Welded Canister wa = ,_n.,

l r l c* ja d[. Oi ow e VI. SYSTEM: Main Feedwater I i Ct.9 :NENTS 4 ' ^ ^ " ' ' ' ' PLANT IDENTIFICATICN NI I EI?'AET CUIIIUI U?AEY %'9ER GENERIC NAME [ CONTAIN*ENT CONTAIN=.ENT 1-LTa61,462, &463 2-LT461,462, &463 Level Trans=t::ers I l-LT471,472, &a73 2-LT471,472. 5473 Level Trans=itters X 1-LT460 & 470 2-tT460 & 470 Level Transmitters X Okonite Instr.t ienta:t en Cables X X 5echtel/ Ray ne: Ele :rical Cable Solices X Crouse Hines/ Westinghouse Electrical Penetration l Welded Canister Asseeclies X X l I I l l l l r 1i I E l i-. - - -

i VII. SYSTEM: Main Steam Page 10 of 14 Rev. 4 COMPONENTS i ^ INSIDE PRIMARY CU SIDE PRIMARY N E GENERIC NAME CONTAINMENT CONTAINMENT 1-MS2019, 2020 Valve Motor 2-MS2019, 2020 Operators X l-PT468, 469, &482 2-PT468, 469, &482 Pressure Transmitters X l-PT478,479,&483 2-PT478,479,&483 Pressure Transmitters X l-FT464 & 465 2-FT464 & 465 Flow Transmitters X l-FT474 & 475 2-FT474 & 475 Flow Transmitters X American Oil Co. Amolith #1EP Lubricant (Grease) X Mobil Oil Co.

28 Lubricant (Grease)

X Rome 600 Volt Control Cables X Okonite Instrumentation Cables X X Kerite 600 Volt AC Power Cables X Kerite 600 Volt Control Cables X Bechtel/Raychem Electrical Cable Solices X Crouse Hinds / Westinghouse Electrical Penetration Welded Canister Assemblies X X l ,g ,+- r -r y v- .v- ,y= --w

VIII. SYSTEM: Containment Air Recirculation Cooling Page 11 of 14 i Rev. A CCMPONENTS 1 , n.. -. n w, N DE PRIMARY OUTSIDE PRIMARY NU BER GENERIC NAME CONTAINMENT CONTAINMENT l-WlAl,B1,C1,&D1 Accident Fan Cooler 2-WlAl,B1,C1,&D1 Motors X Chevron BRB-2 Lubricant (Grease) X 600 Volt AC Power Karito ca bl es y y Electrical Cable Westinghouse Splices X Crouse Hinds / Westinghouse Electrical Penetration Welded Canister Assemblies X X i l f l t l l

Pace 12 of 14 IX. SYSTEM: Containment Isolation Rey, 4 COMPCNENTS NSID R RY SIDE PRIMRY M. GENERIC NAME CONTAINMENT CONTAINMENT l-CV1296 2-CV1296 Solenoid Valves X i 1-HV3200C 2-HV3200C Solenoid Valves X l-HV3213, 3245 2-HV3213, 3245 Solenoid Valves X Namco "Snao-Lock EA180-11302 Limit Switches X Kerite 600 Volt Control Cables X X Rome 600 Volt Control Cables X X Bechtel/Raychem Electrical Cable t-14 r e y Crouse Hinds / Westinghouse Electrical Penetration Welded Canister Assemblies X 7

X. SYSTEM: Auxiliary Feedwater Page 13 of 14 Rev. 4 f COMPONENTS ,ne.~,nu NSID RIMARY OUTSIDE PRIMRY E GENERIC NAME CONTAINMENT CONTAINMENT LT4025&4031 Level Transmitters X i Boston Insulated Instrumentation Wire & Cable Cables X i a l l i { l I l t l l 'F e

XI. SYSTEM: Sampling System Page 14 of 14 Rev. 4 COMPCNENTS .n....nu PLANT IDENTIFICATION INSIDE PRIMARY OUTSIDE PRIMARY NUMBER GENERIC NAME CONTAINMENT' CONTAINMENT 1A7-9V055 Solenoid valves X l&2-SV966C Solenoid Valves X NAMC0 " Snap-Lock" 02400X Limit Switches X X 600 Volt Control Kerite Cable X 600 Volt Control Rome Cable X Electrical Cable Bechtel/Raychem Solices X Crouse Hinds Electrical Penetration Westinghouse Assemblies X X Welded Canister l l l l I'

l 4 ~ a- ,yx y i I L L k 1 l t ENCLOSURE 2 i f i i 1 i e 1 2 k.-_,--..-,.--

Page 1 of 12 Rev. 4 GENERAL NOTES 1. This type of an adverse environment is not present during the time period the equipment is required to operate. 2. This value of the parameter is the worst case. 3. This equipment will perform its safety function before it is submerged. t. g.:

Page 2 of 12 Rev. 4 OUTSTANDING ITEM NOTES A. The Nitrile Rubber (BUNA-N) 0-rings and diaphragms in this component are susceptable to themal aging degradation after approximately ten years service at temperatures up to 1220F, The nonnai ambient temperature these components are expesed to averages less than 80oF. Therefore, little degradation is expected to have occurred up to this time. These BUNA-N parts will be replaced with a periodicity of ten years or less. Should these parts fail due to aging, the air-operated valves which this equipment controls are designed to fail in the safe direction for accident mitigation. Therefore, continued safe operation of the plant is assured until these parts are replaced. It is our intention to replace these parts as soon as practicable, but in any case, by June 30, 1982. B. Only an abstract and sununary of the test results were reviewed. This information was detailed enough to allow complete evaluation of the component for environmental qualification. Due to the large volume and the proprietary corporate classification of the reports, the vendor would not send us copies of the test reports. These reports are available for NRC audit at the vendor's offices. The reports will be maintained for the life of the plant. C. These level switches have been known to survive worse environments and therefore were not required to be qualified before the plant was built (Qualification Reference 18., p. 2-2). The construction of these float-type level switches is extremely simple and rugged. There are four channels per containment sump which are located in different quadrants of the containment. After a review of their design, the level switches were judged to be able to survive and perform their safety function in the extremely unlikely event of a LOCA. Therefore, continued safe operation of the plant is assured. Since these level sensors lack the documentation required by the " DOR Guidelines" (Enclosure 4 to IE Bulletin 79-018), they will be replaced with level sensors qualified to Category I of NUREG-0588 in accordance with our schedule for modifications to meet the intent of NUREG-0578. D. The modifications specified in Qualification Reference 9B for Foxboro transmitters have not been made to these transmitters. A review of the seal design for the Foxboro units and a review of the environmental qualification tests of the Foxboro units, lead to the conclusion that these transmitters would perform their short-term safety trip function. Therefore, the continued safe operation of the plant is assured. E. This cable splice is similar but not identical to the ones successfully tested in Reference 1B. The containment fan cooler motor splice (Westinghouse Dwg. No. 20$C391) was compared in detail to the safeguards inside-containment splice (Bechtel Dwg. No. Sk-E-165, Rev.1) used elsewhere in the containment. The Bechtel splices use General Electric Co. RTV-102 type RTV adhesive / sealant on the conductors whereas the Westinghouse fan cooler motor splice uses Dow Corning #899 RTV.

Page 3 of 12 Rev. 4 OUTSTANDING ITEM NOTES (Continued) These materials are similar in their resistance to aging and radiation degradation. In any case, they perform no critical function after the insulation is in place. The Bechtel splice uses Raychem Type SFR (Silicon Rubber) heat shrinkable tubing for insulation. The Westinghouse splice uses Scotch #70 silicon rubber tape in three layers (with half-lapping) alternated with MICA tape and surrounded with a glass tape overall. The silicon rubber yields the insulating and tensile strength properties required for both spiices. Since the silicon rubber perfoms the critical functions on both splices, the two splices are judged to exhibit identical resistante to degradation from agt.ig and radiation. Therefore, since the Bechtel splice was qualified to 40 years and 2x108 Rads gama radiation, the Westinghouse splice is considered qualified to the same limits. Note that each splice was tested separately for the otner LOCA/HELB environmental parameters. F. These transmitters will be replaced with redundant environmentally-qualified transmitters. The replacement schedule was establisLd in our response to Three Mile Island Short-Term Lessons Learned (NUREG-0578). G. These transmitters are being replaced with new Foxboro N-E10 Series transmitters which are presently qualified to IEEE 323-1971 including 2.2x108 Rads gama radiation and IEEE 344-1975. A Utility Transmitter Qualification Group has been fomed to qualify these transmitters to IEEE 323-1974 and IEEE 344-1975. The final qualification is scheduled to be completed by October 1981. It is our intention that the replacements be completed by June 30, 1982. The transmitters which are located inside containment or outside containment in the vicinity of high energy lines are all Foxboro transmitters which have been tested for those conditions. In most cases, the transmitters are being replaced because of a lack of traceability on the materials which prevents us from analyzing the aging characteristics. The Foxboro transmitters will, in our opinion, perform their safety function in the extremely unlikely event of a LOCA or HELS accident. The other transmitters outside containment (Barton's) will have performed their safety function prior to being exposed to a severe environment from that accident. It is unlikely that the transmitters have degraded in their approximately ten years of operation since we have seen no evidence j of such degradation. Therefore, the continued safe operation of the plant is assured until the transmitters are replaced. i H. The temperature profiles for the specification and the qualification test are essentially equal. The specification temperature was computed using extremely conservative assumptions. The highest possible superheat temperature from a steam leak at the highest secondary pressure was calculated for tne peak temocrature. This also assumed no cooling by ' the sucrounding air or equipment and that a jet of steam impinges directly on the affected equipment. The test temperature was maintained for a much longer duration than the duration of peak temperature from a steam line break outside containment. Therefore, the internal temperatu m of the equipment being. tested (e.g., valve motor aperators) reache; higher levels than that which result in an accident from a short-duration i

Page 4 of 12 Rev. OUTSTANDING ITEM NOTES (Continuec) steam line break. Electrical cables are run in conduits near hign energy itnes so that direct steam impingement on cables is impossible. Therefore, the temperature profile of the test is considered adequate to qualify the equipment to the specification temoerature profile. I. The lubricant used in the test was Westinghouse 5370lRW grease. The Westinghouse Technical Manual, Reactor Containment Fan Coolar, Point Beach Nuclear Plant Unit No. I anc No. 2, hovemoer 19c9, p. T4 states that Chevron SRB-2 grease is equivalent. J. This equipment would perform its safety-related function prior to the time when it would see a severe environment from the accident. The long-tem monitoring function would most likely be performed adequately in spite of the adverse environment, although this cannot be documented. There are several backup means of perfoming this long-tem monitoring function that are available should the component fail. Therefore, the continued safe operation of the plant is assured until this equipment is replaced. It is our intention to replace tne equipment with environmentally-qualified equ pment by June 30, 1982. i K. The environment qualification tests on NAMCO EA180 limit swi-tenes were run with the conduit port sealed from the steam environmert. These switches were installed at PBNP with a sealant for which no qualification documentation exists. However, we believe the switch would perfom its safety function under accident conditions. It is our intention to install a qualified electrical conductor seal assembly on these limit switches by June 30, 1982. L. The normal ambient temperature inside containment outside the shield wall is between 85 and 1000F. This yields a qualified life on these limit switches of 7.1 years (assuming a 350'. ambient). NAMCO is presently requalifying the limit switches for a higher qualified life (Ref. 7B-NAMCO) Test Plan LP10767-3 of July 26,1979). These switches will oe replaced or refurbished on a seven-year periccic interval based on the above qualified life unless the qualified life n extended by later testing. M. This lubricant is replaced once per year during every refueling shutdown. N. The Nitrile Rubber (BUNA-N) 0-rings have been operating in an area where ambient temperatures average 700F and there is negligible radiation. Therefore, themal or radiation degradation of these 0-rings is likely to be negligible. They will, however, be replaced as soon as practicable and in any case by June 30, 1982. O. The only applications of the Rome cable which requires operation greater than 30 minutes or greater than lx10' Rads gama radiation are the limit switches on the containment purge supply _and exhaust valves inside containment and the containment stano level switches. The purge sucaly and exhaust valves are administratively " red tagged" closed except wnen the plant is in cold shutdown. The containment sumo level switches will L_

~ Page 5 of 12 Rev. 4 OUTSTANDING ITEM NOTES (Continuec) have perfomed its major function within an hour after a LOCA in confirming sufficient sump level before initiating ECCS recirculation. After four months of operation in the mode of operation, an alternate method of detemining the sump level could be implemented. Therefore, continued safe operation of the plant is assured. It is our intention to replace this cable by June 30, 1982. P. These components are not required to mitigate LOCA or High Energy Line Break (HELB) accidents, therefore, continued safe operation of the plant is assured. However, these components could be used to aid the reactor operator in reactor coolant pressure control under some postulated accident situations. It is our intention to replace these components with environmentally-qualified components by June 30, 1982. Q. These components are not required to mitigate LOCA or HELB accidents and continued safe operation of the plant is therefore assured. These compc7ents are required to be available by the TMI Action Plan to allow the reactor operators to sample and analyze reactor coolant chemistry. It is our intention to replace these components with environmentally-qualified components by June 30, 1982. 8 R. The Reactor Coolant System loop RTDs were only tested to 1X10 RADS gama and were not themally-aged during qualification testing. The above radiation dose allows over 10 years of normal operation followed by one week of post-LOCA containment radiation. This would be suffi-cient time after a postulated accident to place the plant in a stable condition such that the RTDs would not be required. In addition, backup indication such as steam generator saturation pressure or Residual Heat Removal system temperature are available depending on the mode of plant cooling. Therefore, continued safe operation of the plant is assured. It is our intention to continue evaluation of the present RTDs for thermal aging and a higher radiation dose in order to fully qualify these RTDs to the DOR Guidelines. If fully qualified new RTDs are available, replacement will be censidered. High normal ambient temperatures and high nomal radiation dose rates make the environmental qualification of these components extremely difficult. It is our inten-tion to document the qualification of the present RTDs or replace them with fully qualified RTDs by June 30, 1982, if possible. S. The In-Core (core exit) Thermocouple system is not environmentally l qualified. This system is required to be environmentally qualified by the TMI Action Plan. This system is not required to mitigate postulated design-basis accidents, therefore, continued safe operation of the plant is assured. It is our intention to environmentally qualify the connectors, cabling, and reference junction boxes by June 30, 1982. The connectors and cabling will be replaced with qualified equipment and the reference junction boxes will be moved to a controlled environment. The presently installed themocouples are judged acceptable based on many years of operation in their normally harsh environments.

Page 6 of 12 Rev. 4 OUTSTANDING ITEM N0TES (Continued) 1 T. The acoustic monitor transducers and cable connectors on the pressurizer code safety valve discharge lines have not been environmentally qualified. This system is not required, however, to mitigate any design-basis acci-dents, therefore, continued safe operation of the plant is assured. It is our intention to obtain environmental qualification data for the presently installed system from the supplier by June 30, 1982. U. The pressurizer heaters and bolted lug-type elec',rical connectors have not been environmentally qualified. The pressurizer heaters are not required for mitigation of postulated design-balis accidents and are not safety-related, therefore, continued safe operation of the plant is assured. The heaters provide, however, one metnuJ of controlling Reactor Coolant System pressure while achieving and maintaining cold shutdown conditions. Our preliminary evaluation indicates that the heaters and connectors should be able to survive postulated accident envi ronment. The cable is presently environmentally qualified. It is our intention to continue evaluation of the environmental qualification of the heaters and connectors through the vendor.

Pace 7 of 12 Rev. 4 SPECIFICATION REFERENCES 1A. Point Beach Nuclear Plant, Final Facility Description and Safety Analysis Report t..DSARJ, Amendment 24, 1 June 30, 1978. 2A. EDS Nuclear Letter 0870-001-020 From Dan Brosnan to Dave Porter with Enclosure Dated April 14, 1980, Cumulative Radiation Doses for Ecuipnent Outside Contain-ment. 3A. Report On Analyses For Six Postulated Pipe Breaks Outside Containment At Point Beach Nuclear Plant, Bechtel Power Corporation, San Francisco, CA., May 15, 1973. 4A. Point Beach Nuclear Plant Emergency Operating Procedure-1A, Large Loss of Reactor Coola.it, Revision 17, Feb. 15, 1980. SA. Point 3each Nuclear Plant Emergency Operating Procedure-1 2A, Secondary Coolant Break, Revision 10, Feb. 5, 1980. 6A. IE Bulletin 79-01B, Enclosure 4, Section 4. 3.2-1, Nuclear Regulatory Commission, Region III, Glen Ellyn, Ill., Jan. 16, 1980 1

Page 8 of 12 Rev. 4 OUALIFICATION REFERENCES

18. WCAP 7410-L (Volume I & II), Tooical Reccrt Environmental Testino of Enoineered Safety Features Related Eouioment, Westingnouse Electric Corp. Pittsburgn, PA., Dec., 1970.

2B. WCAP 7829, Fan Cooler Motor Unit Test, Westinghouse Electric Corp., Pittsburgh, PA., April,1972. 3B, WCAP 7343-L, Topical Report Irradiation Testino of Reactor Containment Fan Cooler Motor Insulat on, Westingnouse Electric Corporation, d Pittsburgn,PA., June,l!I67.

48. Qualification of NAMCO Lontrols Limit Switch Model EA-180 to IEEE Standards 344 ('75), 323 ('74), and 382 ('72), Revision 1, ACME -

Cleveland Development Co., Highland Heignts, OH., March 3, 1978. Estimation of Qualified Life of EA180 Series Nuclear Switch, Revision Dated Feb. 27, 1980, NAMCO Controls, Cleveland, OH. Test Plan For the Qualification of Series EA180 and EA740 Switches For Use In Nuclear Power Plants In Como11ance with IEEE Standards 323-74, 382-72, and 344-75, Revision 1, July 26, 1979, NAMC0 Controls, Cleveland, SH. Bechtel Letter From D. H. Clark to D. K. Porter, dated June, 1980, LAMM Position Switches 5B. Westinghouse Letter From R. L. Korner to W. F. Geisheker with the following Attachments, dated May 22, 1978, Qualification Data for the Point Beach Nuclear Power Plants Units al and #2; 1. PEN-RLK-3-16-01, Accident Environment Test Report 2. PEN-ACD-4-72-03, Accident Environment Test Report 3. ETL Report 5261 Reports of Seismic Tests on Electrical 4. ETL Report 5275 Penetrations for Westinghouse 5. Test Report on Incident Testing of Triax Penetration WEPCO letter from R. L. Cantrell to T. J. Rodgers, dated March 1,1974, Electrical Penetrations Point Beach Nuclear Plant. WMPCo letter from R. L. Cantrell to Roger Newton, dated April 15, 1968 Electrical Penetrations. WMPCo letter from R. L. Car.trell to A. A. Sinnons, Project Manager - Westinghouse, dated September 9,1968, Point Beach Nuclear Plant Electrical Penetrations. l l Westinghouse letter from A. A. Sinnons to Glenn A. Reed, dated October 8,1968, l Point Beach Nuclear Plant Electrical Penetrations. l Westinghouse Tube Division, Ch:trical Penetrations Ouality Control Production Record Sheet, and attachments. p Crouse-Hinds Company Drawing Nos. 0100349, 0100382, 0100411, 0100334, 0100044.

Page 9 of 12 OVALIFICATION REFERENCES 6B. Westinghouse Letter From R. L. Korner to W. F. Geisheker with Attachments, dated July 28, 1978, Point Beach Nuclear Plant Oualification of Containment Electrical Penetration Safecuards Solices. 1. PEN-TR-78-45, Boric Acid Effect on Medium Voltage Ceramic Seal-Bushing. 2. PEN-TR-78-11, Statement on Effect of Borated Water on Westinghouse Penetrations for the Angra Nuclear Plant. 3. Brunswick Nuclear Plant Drawing Nos. E-2457, E-2453 E-2452. 31402, *1396, 31400, 150-31393, 150-31394, 4. WEP, WIS Drawing Nos. 150-31396. 78. IE Bulletin 79-018. Enclosure 4, Appendix C, Table C-1, Nuclear Regulatory Commission, Region III, Glen Ellyn, IL., Jan. 16, 1980. 8B. Instruction Manual and Parts List, Fisher Controls Type 546 Electro-Pneumatic Transducer, Fisher Controls Co., Marshalltown, IA., Nov.,1968. Fisher Controls Letter from Bill R. Flowers of W. D. Ehrke Co., Inc., to R. K. Hanneman, dated Sept. 29, 1980, Point Beach Nuclear Plant Environmental Oualification of Fisher Components. 9B. WCAP-7354-L, Topical Report Su) plier Post Accident Testino of Process Instrumentation, Westinghouse Electric Corp., Pittsburgh, PA., July,1969. 108. Westinghouse Letter frem C. A. Lins to R. K. Hanneman, dated June 2,1980, Point Beach Nuclear Plant Bulletin 79-01B Motor Qualification. WCAP8754, Environmental Qualification of Class IE Motors For Nuclear Out-Of-Containment Use, Westinghouse Electric Corp., Pittsburgh, PA., June, 1976. 118. Westinghouse Letter WFP78-531, From R. L. Kelly to W. F. Geisheker with Attachments, dated June 28, 1978, Qualification of Containment Electrical Penetration Safecuards Solices. Westinghouse Teletype PBW-B-3070 From N. E. Bush to J. K. Leslie of Bechtel, dated February 5,1970, Splicina Information. Bechtel Letter From H. E. Morris to W. F. Geisheker with Attachments, cated April 27,1978, Point Beach Nuclear Plant Contatirment Electrical Penetration Splices: 1. Bechtel Drawing SK-E-165, Splicing Requirements for Penetration Lead Wires. 2. Bechtel Chronological List of Correspondence. 3. Bechtel Letter PBW-W 2789C From J. K. Leslie to W. B. Henderson of Westinghouse with Attachments, dated February 10, 1970, Penetration Solices. 4. Bechtel Letter From J. K. Leslie to W. B. Henderson of Westinghouse with Attachments, dated March 3, 1970, Penetration Solices.

Page 10 of 12 Rev. 4 OUALIFICATIONREFERENCE[ (Continuec) 5. Westinghouse Teletype PBW-B-3179 From N. E. Bush to J. K. Leslie of Bechtel, dcted March 5, 1970, Safeauard Cable Solices in the Containment. 6. Westingnousr. Teletype PBW-B-3211, From N. E. Bush to J. K. Leslie of Bechtel., dated March 13, 1970 Containment Safeguards Solices. 7. Bechtel 12tter PBB-W-2905 From J. K. Leslie to W. B. Hencerson of Westinghouse, dated March 17, 1970 Solices for Safeouards Cables Inside Containment 128. Deleted 13B. Deleted 14B. Boston Insulated Wire & Cable Co. Letter dated April 23, 1980, from L. S. Lisker to R. K. Hanneman. Report B901, BIW Bostrad7 and Bostrad75 - Flame and Radiation Resistant Cables for Nuclear Power Plants, Boston Insulated Wire & Cable Company, Boston, MA., Septemoer, 1969. 15B. Report IPS-348, Test Report - Steam Line Break /LOCA Exposure of Field Cables and Teminal Blocks For American Electric Power, Conax Ccrporation, Buffalo, N.Y., May, 1978. 16B. Qualification Tyoe Test Report, limitoroue Valve Actuators For Class IE Service Outsice Primary Containment, Limitorque Corporation Test Lacoratory, Lynenourg, Virginia, June 7,1976. 17B. Rober: 0. Bolt and James G. Carroll, California Research Corporation, Radiation Effects on Oroanic Materials, Richmond, California, Academic Press, New York, 1963. 188. Westinghouse Letter from C. A. Lins to R. K. Hanneman, dated June 2. l 1980, Point Beach Nuclear Plant, Bulletin 79-018. Motor Qualification. l Westinghouse Letter from C. A. Lins to R. K. Hanneman, dated August 29, l 1980, Point Beach Nuclear Power Plant Ecuioment Qualification NRC l Bulletin 79-01B Containment Soray Pump Motors Containment Fan l Cooler Motors. i' WEPCo. Letter from R. K. Hannemar. to C. A. Lins, dated September 8, 1980, Environmental Qualification of Containment Soray Pumo and Comconent Cooling Motors at Point Beacn l4uclear Plant. Westinghouse. Letter from C. A. Lins to R. - K. Hanneman, dated October 7,1980. Point Beach Nuclear Power Plant Environmental j Qualification of Containment Soray Pumo and Comoonent Cooling Pumo i Motors at Point Beacn Nuclear Power Plant _, witn attacnment: i Westingnouse Researen Report 71-lC2-RADMC-R1, Proprietary Class 2,. ' dated December 31,1970 (Revised April 10,1971), The Effect of Radiation on Insulating Materials Used in Westinghouse Medium Motors, Dy John Bartks, Westingnouse Research.Lacoratories. ~ L

Pege 11 of 12 Rev. 4 00ALIFICATION REFERENCES (Continuec) 198. Foxboro Letter from G. Tennesen to R. K. Hanneman, dated August 5,1980, Resistance Temaerature Detectors. Installation Instructions and Parts List, "Dynathenn Resistance Bulbs with Aluminum Cap-Type Head, Model 08-1 Series", The Foxboro Company, January 1964. 203. Amoco 011 Company Letter from T. M. Warne, dated Septenter 15, 1980, Radiation Resistance of Amoco Oil Lubricants; Project 4210, with attacnment: Tne Effects of Radiation or Lucricants in Nuclear Generating Stations, by James S. Ferrie, Paul Leinonen. Dr. B. Neil, anc E. Wnarton (Ontario Hydro Research Division), for presentation at ASLE 35th Annual Meeting, Anaheim, California, May 1980. 21B. Mobil Oil Letter from J. Kestly to R. K. Hannemen dated October 13, 1980, Radiation Information Wisconsin Electric Power, with attachments for radiation test cata of Mobilgrease 28. 228. Kerite Letter from R. A. Olson to R. K. Hanneman, dated October 22, 1980, with attachment: Point Beach Nuclear Plant, Wisconsin Electric Power Comoany, LOCA Oualification of Kerite 600 Volt HTK Insulated, FR Jacketen Power Cablg. 238. Rome Cable Cocporation Letter from D. D. Sand to R. K. Hanneman, dated April 9,1980. Rome Cable Corporation letter from D. D. Sand to P. R. Belhumeur dated March 19, 1971. 248. Okonite Company Letter from J. S. Lasky to R. K. Hanneman, dated May 9,1980, With Attachment. Blodgett, R. B. & Fisher, R.G., " Insulations and Jackets for Control and Power Cables in Thermal Reactor Nuclear Generatino Stations, IEEE Transactions on Power Aooaeatus and Systems, Volume PAS-88, No. 5, May 1969. 25B. "Tyoe Test Cable Qualification Procram and Data for Nuclear Plant Desicned Life Simulation Througn Simultaneous Exoosure", Franklin Institute Research LaDaratories, Final Report F-C3594, Philadelphia, Pennsylvania, January 1974. 263. Lancaster, Ron, " Qualification of Safety-Related Eauiement Used in Nuclear Power Generating Stations Including tne Effects of Acing", Reliability Conference for tne Electric Power Inoustry,1980. Carfagno, S. P. & Gibson, R. J., "A Review of Eauioment Agine Theory and Technology", Electric Power Researen Institute, Final Report NP-1558, Palo Alto, California, September 1980~.

Page 12 of 12 Rev. 4 OUALIFICATION REFERENCES (Continued) 27B. Ellis, A. E. Miller, R. B., Environmental Oualification of Safety-Relatec Class IE Process Instrumentation, WCAP 9157, Westingnouse Electric Corporation, Pittsourgn, PA., September,1977. 28B. Rockbestos Company letter from Robert J. Genm to Paul Katers of Wisconsin Electric, dated July 28, 1980 with Enclosure. Qualification of Firewall III Class IE Electric Cables (Chemically Cross-Linked Insulation), The Rockbestos Company, New Haven, CT., July 7,19/7, Revised November 26, 1979. Qualification of Firewall III Class IE Electric Cables (Irradiation Cross-Linked Insulation), Tne RockDestos Company, New Haven, CT., June 7, 1978. Proute, R. W., Qualification of Firewall III Coaxial Constructions for C1 css IE Service in Nuclear Generating Stations The RockDestos Col.;pany, New Haven, CT., January 18, 1978. 4 l-k

W DS ~ NM AE I 1 S1 e e e e e e w n n n I n n n W o o o o o o o D" N N N N N N N m W g I I l n i l a i l l rs l i v AD t ei a a e K0l n es i i I t R l e ny n t I l util n d e u! E qsga e u b H eenn ut l A qs W JTE.A ee I ? ST 2 N 0 l 6 l S A 4) L C I 1 ) E l k) f 8 1 - 3 W E )1 0 - 5 B - l s l 4 04 l t l 1 I I I[ e A 1 5 re U Ih Q p p I I p ( RS p ( Od ( De ) I h N ) 3 Tc 0 1 1 Aa l A T T t_ i E L A 4 i 1 l 0 A_ E C 2 1 6 i H l S e f Q AE 1 de S 6T A A l e O 2 I 4 K US C I R U( E l N O P b W S a' P P T N ( ( 0 l Ty i I s AU Ig r L Eg r 8 a 0 e A Ag a 0 V Ug 1 Y e 0 E ) s l Y 1 xd 0 ~ I a 4 i N 7R E T N N O E s P M r l M N r 1 1 s a 1 I O O a e I C R e e 0 e a Y e C I H_ V L Y t 0 t t L N P o 1 o 0 o S 1 N N a N 1 E S Y E S M I T E

I R

C R G U N N L N I E EY l O E A l V1 A I I t G I i E T R i l 1 T t l t M A E S l 0 A p* E n A R P S A1 D g H I a R E M E L 1 l g R ' i A l' E R Eli I S A g U l P P O T l' Rt C R g S r a y e 1 s 0 x e lc 3 t o t u n p o N 0 a E n LS t 5 l h o s ec a E r t d n o r mi le / Y _ o a n o C o at r l J f e a i t rs o d2 t y o f a t l g t 6 p r M a n /lDm% L e e V E e Pa u td 6 a i i n n2 r p d d l L V h i m Br A c i l nc L E s ia - l ~ o 0 s i u Te / ss oi L L i PI 5 e x P R e h N ep uib d D u O f s l P R m Bt u L D e u u aC E O h A N t yv V O _ t T il o YTT n D BB N i h O. e P r l r N Y N rep [ L ta &A I C g N a 0 C El O al n II E e I [ I a l NK m H AA N A n r A C a I iEi l l UC p E I 00 O T L f i R v T l P D E a I H i ) i T N P U t E / C U V o A i '9 R O V r W u S A PP M N D 5 lN C R 1 1 C x l O O e s n A q Y L O A e O 7 l C E e O u1 i L H e F E S P C M W M5 I A S R I 1 2 A R I A S 4 4

e g C i 1 g ^ Om ZZ t c $2 e o l o e o o o e-e = e m-C c = C C O O C 0 C C C C C Z Z C I =b Z Z Z Z Z Z -* Z C = } N g l C 4 1 m m i. c.e. j 6e c a

=

<c w o-w = om O v C 0M

J 0

C A -. C a.e = =w===- = 0 Ch g ,a 6 >= 3

8=== -

L y 0 7 m C3 etp

== w C' M 39 s e e 3 *8 cCC-p e c. .,J C" M m >= L A k =.J E @ @ CC 3 3 C. h @ g 6 s m>w< o c-m s.o e e 6 m LaJ W. g g i s ~ ~. E d 5 = a m w Eo se we -e a -* C' C e Z M C C 2 Z .a t.g 8 Z gm t Z= IC 0 .C Z m .- v e >< m e. w =. < w _v e N -8 5 <w a u m v ~ -w = w e 9 h i l l 5 l H 6 8 8 w lt C b. D m C k J W e-L C 9 C C suC C 9 6 e s e

v W

e M a e a. 4.J a O a X 7 I 6 O 8 9 O I N 2 e Zw E Z m C C A l ~'* -. l 6 m 90 L e = I '"" W g W M*g ". Q M x5 C g .J mz E, >WC C C O O O Z Z Z N. w,$ V Z v. Z

==J ~ m w e E w I E v E C O g Z w Z >= LJ LJ > J w C = as: C P== w E D

= = =

v>

== =

3 E

-4A m -O

=== aIC C C ea = e <= Ez Z E C 2 w w .a { wr C =

C A

m = w- =m C C = = C. C O >= r m= v = aC l A 6 e4 h 'O"" e, C x a C C D E M. i U C m C. C i = l ~ Z O 90 3 W* m M C C L .C @ Uw O

C' d

L "O c C C .C S !iii # b C N W g C c - U 4 C C.J O v 3 C 1- @** *' l x C 4 .J L eCg .3 m c: m e a 6 e m C C

n a

c C % r=** C C .J 3@ = 4 y O = l CN L 3 CW @ C 'O 6e .= 5 c: C'@- - et: O e = c e V c S C. C w w C O. m = c. eg; = g c., Z = 3 C C

== i

c. - m c

x .c w 5+ mCv w = o = m v =. w .= 2 z = p . mc.. = .. h.J.J #c > a i OqZ .5 Z L eC ow J . > > = > = C c cl: c: .E .e v Z m-C v wC O r= > Cb 6 >= = m.J =ZM E**

=== ec ee 4C aC sit W-aC y .-e. G = ct 6 w 7 0 >= = =L m- - - C O w r= J=v w o.- Q .Z O wcv O > Q eC *** W C ^!!G5 ^

=

-v = m C

c. c.

E = Z v =a vx = = c auC 0" a a e U 6 r, C3-55.s =: e .w w m c. -m v f

== m3 w aC ce v c.6 m l I

TACILITY: Point Beach Nuclear Plant II. - 3 UNIT: 1 Rev. 1 i DOCKET: 50-266 SYSTEM COMPONENT EVALUATION WORK SilEET t 00CtHiHTATIT)FRUERENCES ENVIRONMENT 1eeAttachedSheets) Equipment Description SPECIFI-7A[ITU PARAMETER SPEC!flCATION -QUALIFICAll0N 11 Call 0N Call 0N RATI M TIME SYSTEM: Auxiliary Coolant 1 Year 1 Year (Tabl Q6.4-1) 168 (p. 10)

2. Engineering Analysis PLANT ID NO.:

1-AC738A&B None TEMPElATURE Note 1 COMPONENT: Valve Motor Opera tors PRESSURE Note 1 None MANUFACTURER: Limitorque/Re1iance MODEl NO.: SMB/ Frame 18 None M46/ Class B Ins. RELATIVE 100% 100% 6A (Vol. I, p. D-1) Sequential lil#11DITY NOTE 2 168 Test FUNCTION: Remotely (p. 15) Controlled Valve Operation CllEM AL None ACCURACY: N/A Note 1 5 2 X 108 IB 2 1 X 10 9"*" RADIATION l ads Rads 2A SERVICE: Component Cooling (Vol. I. p.5-4) 7 Water Supply Line to RilR i X 10 160 (p.2) llX Valves _ Rads 18 LOCAll0N: lA Sequential None ^ I I PP' Auxiliary Building 40 Years 40 Years (pp. 4.1-11&l3) ) Test IdB(g 1 8' Elevation tower Pipeway #2 None L L EV. jfL SUBMERGENCE Note 1 AB0VE FLOOD LEVEL YES See attached sheet for notes.

i ~ G N IDS NM A[ T1 S1 e e e e e e e e l n n n n n n n n l l o o o o o o o o O N N N N N N N N g N n 0 i l rs l l i ei l a a AD es a t i C0l ny i I t l l til t r n fl sga n e e l E cnn e ut ut lM EA ut qs qs i qs ee._ ee A U ee ST _ Q 2 ST _ ST ) ) ) N 1 4 4 0 D 5 5 l i ) .) ) 5 P' p5 A B C 0 p1 1 fC I 81 B * ) B, ) F 6 B,. 2, I I fs l p 1 I I p it l p ( p .( lie A f e U l l ( l B L oB Q Mh S o6 V6 ( V1 ~N d ( 6 (1 1 We ) lh N ) 3 Tc O l 1 Aa I T Tt T i 1 [ Nt A 4 1 l CA C [ 6 2 Si M Q I 1 e F ^ AE A a I C e I C I e 6T 2 l4 M (S K l O R E O P b N P W S a P T ( N ( O I T s A r U r 7 a L a 0 e s1 s A e Y 0 d d V 'g Y 0 aXa 0 E 1 R R 1 4 T 2 N E T 5 N N O E 0 sr P M 1 M N r 1 1 1 a 1 O O a 1 Xs _ e I C R e e e 0 e d . Y e t Y t t 0 t 1 a I 0 o M V o o 1 o

2. R 4

N E N S 1 N N N T E 2 S Y EM S I T E E R C R G U N N I E Ey L 0 E E N G A R Vl A l T I I i C t R E T R U t M A E S TD A C' E M N n A R P S AI M I lf l a R E M E LM [ D I A P I R Eti l A G l l i l P P O I P Rl C R A S r a s e e lc t n g t u n o nR o i i IJ n N a l r t lP h o o a o A S r c n o t e r oo / E o a o C o m e Ct N. Y f M e a p e i B t y c r yO t s g t t 0 ip r e n F l ne n L e _ i 1 3 V I c ee A en i a v a /B s' t v / ni d E. V l n 3 r i l i l I s Mn ol N oL l i c l a l ny E l

e SI ma p

i o 0 s i V R R eV my uoa d P 25 e x D u O E / B R ol Biw L 0 e 0 h d C p t e R e A NB I yap V 0 c ps l u YlT n D A N r I q O. s

e t

T s l a u e N rvi r l s Nl Y o C r N a 0l C ES v 0 aeP t I t 1iE e I 8 I t NK m M 3 N t A o l o A C l il l I l l il Er E a LUC p E T 7 O a F t L C ir R r a I i 1 N C P r Ui E / Ct l V eV Ai e 0i V O t I C x w 0 0 e C D u S A A M e N m D 6 l o C E aXi O p A O 4 lNn C Rt LA I A1 _ O u M' L 1 e q Y L - o t A ~ i S E S P 2 C O M l M M iC A SWl F ~ lI' i. 1

FACIll1Y: Paint Be:ch Nuclear Plcnt 11.-5 .UNii: 1 Rev. 4 DOCKET: 50-266 SYSTEM COMPONENT EVALUAil0N WORK SilE_Ei DOCUHfMTATION REFERENCES ENVIRONMENT (See Attached Sheets) QUAllflCATION OUISTANDING Equipment Description PARMTER S SPEClflCAil0N QUAllFICAil0N f511100 ITEMS IB Simi taneous OPERMN TIE SYSTEM: Auxiliary Coolant i Day' 1 Day 1A (yoj,g,p,g_j) Test None (Table Q6.4-1) 168 PLAis! FD NO.: 1-AC700 (p. 10) TEMPERATURE Figure 1A Figure IB 1A IB Simultaneous i (Figure Q6.4-5) (Vol.I p.D-10) Test None COMPONENT: Valve Motor Opera tor RESSURE MANUFACTURER: 1A IB Simultaneous Limitorque/ Reliance Figure 2A Figure 2B (Fig. 14.3.4-8) (Vol. I,p.D-10) Test None MODEL NO.: SNB-?/ Frame j I 215-R1/ Class B Ins. 100% 100% Note 2 (Vol. I, p.D-1) Simultaneous 16B Test None FUNCTION: Remotel'y EI Controlled Valve ll 80 -Na0ll 1A IB Simultaneous H 80 -Na0ll Opera tion CllEMICAL 3 3 3 3 Solution Solution (p. 6.4-15) (Vol. I, pp.0-8 Test None ACCURACY:N/A SPRAY ril: 7.9-pil: 7.85 & D-10) 1 0.11 2.7X107 2X108 18 Sequential SERVICE: Residual lleat RADIAil0N RADS RADS; 1A (Vol. I, p.5-4); Test None Removal Loop Supply 2X107 RADS (Fig. Q6.4-4) ICB Isolation Valve g,y LOCAil0N: Containment IB Sequential AGINC" 46' Elevation 40 Years 40 Years (Pi> 4 1 1813) (V 1. I, pp.5-1 Test None .-u,-a h468-f e. 45) FLOOD LEVIL ELEV.,14L10= SUBMERGENCE None Note 1 AROVE It000 LEVEL Yes See atte.ched sheet for notes, em

II*-0 FACIL11Y: Point Be:ch Nuclerr Plant UNIT: 1 and 2 DOCKET: 50-266 and 50-301 SYSTEM COMPONENT EVALUAll0N WORK SilE_ET DOCINENIATION REFEREhCts Equipment Description S I - F _- (See Attached Sheets) {HV_lRONMENT QUALIrlCAil0N OUTSTANDING PARAMETER SPECiriCAil0N QUALIFICATION METH00 tiEMS "^ SYSTEM: Auxiliary Coolant l Day 1 Day (Table Q6.4-1) (Vol. I, p.D-1); Simultaneous 168 Test None PLANT ID NO.: 1-AC701 2 2-AC701 TEMPERATURE 1A IB Simultaneous Figure 1A Figure IB (Figure Q6.4-5) (Vol. I, p.0-10) Test None COMPONENT: Valve Motor Operators PRESSURE Figure 2A Figure 2B 1A 18 MANUFACTURER: (Figure 14.3.4-0)(Vol.l.p.D-10) Simultaneous Limitorque/ Peerless Test None ~ - ~ - MODEL NO.: SMB-1/ Frame P12G/ Class B Ins. RELATIVE IB 100% 100% NOTE 2 IlUNIDITY (Vol.I,p.D-1); Simultaneous = FUNC110N: Renntely 16B Test None Controlled Valve (p,- 15) r tion il 80 -Na0ll ll 80 -Na01 3 3 IB 3 3 CNEMICAL ACCURA N/A SPRAY Solution Solution lA (Vol.I,p.D-8 Simultaneous pil: 79-pil: 7.85 (p.6.4-IS) & 10) Test None 2.7X107 2X10B RADS: 1A IB SERVICE: Residual lleat RADIAil0N RADS 2X107 RADS (Figure Q6.4-4) (Vol. I,p.5-4); Sequential Removal Loop Supply 16B Test None Isolation Valve (p-2) LOCATION: Containnent 1A 10 Sequential ggggg 26' Elevation 40 Years 40 Years (pp.4.1-Il&l3) (Vol.l.pp.5-1 & Test None 5.2) FLOOD LEVEL ELEV..14 L10" SUDMERGENCE NOTE 1 None AROVE It000 LEVEL Yes See attached sheet Inr nntes.

FACILITY: Point Berch Nuclecr Plant Cli: 2 II -7 DOCKET: 50-301 SYS_ TEM COMPONENT EVALUAil0N WORK SilE_ET, Rev. 4 DOClWNTATITFli[TDENCES ENVIRONMENT (See Attached Sheets) Equipment Description 5F{Clj~i-7 A U Ti~~ pg g gp SPECIFICATION QUAllFICAil0N I i _CAil0N CAil0N 1B SYSitM: Auxiliary Coolant OPERAllNG TIME 1A (L). I,p.D-1); 1 Day 1 Day (Table Q6.4-i) 16B Simultaneous (p. 10) Test None PLANI ID NO.: 2..AC700 8 Figure 1A figure IB 1A IB Simultaneous COMPONENT: Valve Motor (Figure Q6.4-5) (Vol. I, p.D-10) Test None Operator PRESSHRE 1A IB Simultaneous MANUFACTURER: Figure 2A Figure (Figure Q6.4-5) (Vol. I, p.D-10) Test None Limitorque/ Reliance MODEL NO.: SMB-1/Frane 215-R1/ Class B Ins. RELATIVE 100% 100% NOTE 2 IB Simultaneous IIHMIDITY (Vol. I, p.D-1); Test None IUNCTION: RemoteIy 16B 1 (p--15) Controi.' "3 ve Operatf or H 0 -Na0ll 113 0 -Na0ll IA 3 Cll[MICAL 3 3 Tution oTution (p. 6.4-15) (Vol. 1, pp.0-8 Simultaneous ACCURACY: N/A SPRAY pil: 7.9-pil; 7.85 & l' 10) Test None

10. Q_.

2.7X107 2X108 1A 18 SERVICE: Residual Heat RADIAil0N RADS RADS; (Figure Q6.4-4) (Vol. I, p. 5-4) Sequential Removal Loop Supply 2X107 RADS 16B (p. 15) Test None Isolation Valve LOCATION: Containment IA IB A 46' Elevation 40 Years 40 Years (pp.4.1-11A13) (Vol. I, pp.5-1 Sequential A5-2)d611(h15L Test _. Hone - Il000 LEVEL ELEV..14'.10" SUMMEftGLNCE NOTE 1 None AROVE El000 LEVEL Yes - - - ~ ~ ~ ~ ' ~ ~ ~ ~ ~ ~ ~ ^ ' ' See attacheil sheet for notes.

r_ I 4 I v I e DS I R NM I At Ti e e e e e e e e Sl n n n n n n n n - o o o o o o o o M N N N N N N N N - M s s s s 's u u u u u o o o o o I l l l et et et et et 8 a A0 ns ns ns ns ns I t i t N.0l tl tT t T tT l ae ae ae ae ae L s t s tT H e ne l l l l l l CT e T_ E u u. M m u u u u m m m m 4 q. A e e i i i i W S S S S S S S ) L 0 ) N ) ) 1 1 ) O 0 2 4 1 1 I D. 0 ) l) 1 I I 3 A D. 5 - 0 S 55 D. p p 1 D.1 i C 0 B B B 0 ,6 r 3 8 U P6, 8 8 p6 c I N) F ,6 I p p 1 p - I I I I1 p II I 1 [ s I I ( I I Rt l Ie A l e U l l o Uh l l I l Q o o V o o O o V RS V V ( V V V ( ( ( ( ( ( Ed T e ) ) L l h 1 ) 5 8 ) rc 0 1 4 3 Aa 4 4 T l t 4 4 l kt 6 ) A E iA "C 3 I 6 4 2 5 6 J l N AQ A A1 AQ AJ I Si e r 1 l E l I I de e n i 4 e J T K 0S C l u O r 5(- R A E b g g N S. u O P a i i g W S T f f p p i N ( ( ( ( f p ( ( O B 8 ll n5 SS s I TN 2 0o8 DD r T I A I O ai AA a U lI y e e Nt7 RR e ~ L lT a r r - u Y A AA V UC D u u 0 3l 07 g g 0 0o: 00 0 7 E 1 i i 1 8Sil 11 4 f f l3 p XX T N l 22 E I l n L N N l s A A C o f. r O E 1 2 a i 9. u 7 f' M a N y Nt M N l e O Ol 0 a e e - u7l 0S Y f. i[ C R D r r 0 D 1 l Cl u u 0-0o: XA 0 0 I A M V [P C__ il

7. R 1

g g 1 4 N 3 p N i i E 5 T E f f U 2 S Y E S M I T E E R C R M. U N I E EV L E l r. I A N VI A I E R U Cy I R I l t M A E TD g A g I n A _ J P S AI Mg t g H I ~ c H I M E M Lp U in g I A _. P t R RII t A i i g EI i P P O i P g s C ~ r t e 1 s 0 n l e 3 c o t u t i N 0 n t o . n 5 a r s a 0 l o s e r t 1 h. d n o 0 ts e m e a t r s o n n o o 2 or C 7 Mo r rs O len n 4 e p l a f r e 1 Y e a i B2 t C t e f n y l u mn l. 6 e l t s no t d6 ip y A ea e /I l l e r vr P 1 ev aee i i V t e nn2 r a 1 l e / I tl uRv at l t V h ms oa d i a-c i ap e l t a t s i pa nv 1 o 0 s l VO nV A u I 1 PI5 e R q S s e / soV oe . d i D x O E r a Rd N eo Cl t D e u N R o

l e

Rl n E 0 h v 0. i t A T Ut C o

l r

YTT n D N Ti O/ Nl Y

li N

E 1 - a 0 '6 1I E e I E C m NG 0 o C E at t I t INK m M N Ai 2 t r A C va 2 l l l tI K p E I O I L L1 i t R I ol i 0 E a i I N P EP C n U V n o A 0 V l i X C u S A M iN D N o C R : . s C 0 0l e I A q Y L O A D ) C C EPI O A S L I Al - e I l I E S P C H S l I

FACILITY: Point Beach N --lear Plant UNil: 1 DOCKET: 50-266 SYSTEM COMPONENT EVALUATION t,JORK SilEET DOCL ENTA110N REFERENCES ENVIRONMENT (See Attached Sheets) Equipment Description SPEClfI- ~ 7 AUTF PARAMETER SPECiflCATION QUALIrlCATION I CATION CATION OPERAll ra TIME ^ '"9 SYSTEN: Auxiliary Coolant 1 Year 1 Year T Q6.4-1) y]3 None 178 .'LANT 10 NO.: l-AC624&625 TEMPERATURE None Note 1 COMPONENT

Electro-Pneumatic Transducers MANUFACTURER: Fisher Note 1 None Governor MODEL NO.: 546 RELATIVE loot 100%

6A BB Engineering None lit #11DITY NOTE 2 178 Analysis 4 ' FUNC110N: Current-to-Pressure Conversion for Remote Valve Operation None Cl E AL Note 1 ACCURACY: N/A 6 2A 78 Engineering SERVICE: RilR fleat Exchanger RADIATION 1.25 X 10 5.0 X None BB Analysis Outlet Line Valve Air Rads 106 Rads 17B Operators LOCAil0N: 1A 7B Engineering None A I#' Auxiliary Building 40 Years 10 Years (pp. 4.1-11&l3) 88 Analysis (Note A) 17B -5' Elevation Outside Unit'l RilR lleat Exchanger Cubicle None FLOOD LEVEL ELEV. _N/A SUBMERGENCE Note 1 ABOVE FLOOD LEVEL YES l See attached sheet for notes.

FACILITY: Point Beach Nuclerr Plant !I.-10 UNil: 2 Rev. 4 DOCKET: 50-301 SYSTEM _ COMPONENT EVALUAil0N WORK SilEET DOClHfMIATllTN RUtTtUeCES ~ Equipnent Description S ~TRI (SeeAttachedSheets) ENVIR,0NH_ENT ()UAliflCATION OtllSTANDING PARAMETER SPECirICAil0N ()UAllflCAT ION HElll00 IIEMS c SYSIEM: Auxiliary Coolant 1 Year 1 Year IA 78 Engineering OPfRATING TlHE (Table 06.4-1) 88 Analysis None l 178 PLANI 10 NO.: 2-AC624&625 IEMPERAIURE Note 1 Now --+- COMP (# LENT: Electro-Pneumatic Transducers MANilfACTURER: Fisher Note 1 None Governor H0 DEL NO.: 546 Engineering None REIATIVE toog 100% 6A 88 ^"* #5'S littilDITY NOTE 2 178 FUNCTION: Current-to-Pressure Converter for Remote Valve g gn CllEMICAL N/A SPRAY Note 1 None z --- SERVICE: RilR lleat Exchanger 1.25 X 106 S.0 X IB Engineering None R DIATION Rads 106 Rads 2A Analysis Outlet Lines LOCAll0N: 1A 78 Engineering None A IN Auxiliary Building 40 Years 10 Years (PP. 4.1-11813) BB Analysis (Note A) Outside Unit 2 RilR 178 -5' Elevat. ion lleat Exchan er Cubicle s None ILOOD l EVEL ELEV. _N/A_ SUBHERGENCE Note 1 ABOVE FLOOD 1EVEL YES See attached sheet for notes.

11.-11 FACllliY: Point Beich Nuclear Plant Rsv. 4 IINil: 1 DOC!'.E!: "4-266 SYSTEM COMPONENT EVALUATION WORK SIIEEI DOUMET ATIDii liU DThCES Equi unent Description SPE F-(See Attached Sheets) ENV_I_RONMENE QUAllflCAil0N OUTSIANDING t PARAMETER SPECIFICATION QUALIFICAil0N Hell 100 11[MS 5 % IEM: Auxiliary Coolant l Year 1 Year (Tabl Q6.4-1) y S 178 PLANI ID NO.: 1-AC626 None I Li'PERATURE Note 1 COMPONENT: Electro-Pnetsnatic Transducer ~- None Note 1 tW!HfACIURER: Fisher Governor MODEL NO.: 546 8B Engineering RELAllVE 100% 100% 6A None 17B Analysis litMIDliY NOTE 2 It'NCT ION: Current-to-Pressurr Conversion for Renote Valve Operation CI 1 AL None ACCURACY: N/A Note 1 5.0 X 7B 6 Engineering SERVICE, RilR lleat Exchanger itAulAtl(W 1.42 X 10 106 Rads 2A P's Analysis None Bype. : Line Rads 'IB lA Engineering None W ATION: AGING 40 Years 10 Years Auxiliary Building (PP. 4.1-11&l3) ^"* # I" "'^ 17B 8' Elevation Lower Pipeway #2 ValveGalleryl000 LEVEL. El EV. _G/A SilHMERGENCE Note 1 None ABOVE Ilf.X)D 1.EVEL YES See attacheel sheet for notes.

11.-12 FAClllTY: Point Beech Nuclear Plant Rev. 4 UNIT: 2 DOCKET: 50-301 SYS1EM COMPONENT EVALUATION WORK SilEET DOClhTNTKITON RETikThCES ENVIRONMENT (See Attached Sheets) ^" Equipment Description SPECIFI-QlIAUTI-PARAMETER SPEClflCAtl0N QUALIFICATION MEll100 ITEMS g,g ggg gy OPERATING TIME jA 78 Engineering None SYS1EM: Auxiliary Coolant 1 Year 1 Year (Table Q6.4-1) 88 Analysis 17B PLANT ID NO.: 2-AC626 TEMPERATURE Note 1 None COMPONENT: Electro-Pneumatic Transducer MANUFACIDRER: Fisher Note 1 None Governor MODEL NO.: 546 88 6A RELATIVE

1007, 100%

17B Engineering ilone NOTE 2 lit #11Dily Analysis FtlNCil0N: Current-to-Pressure Conversion for Remot e Valve Operation Cl AL None ACCURACY: N/A Note 1 6 I.42 X 10 5.0 X 2A 7B Engineering None SERVICE: RilR lleat Exchanger RADIATION Rads 106 Rads 88 Analysis Bypass Line 178 Engineering None 10 CATION-lA 4 Years 10 Years 88 Analysis (Note A) A Auxiliary Building (pp. 4.1-11813) j 8' Elevation Lower Pipeway #3 None FLOOD LEVEL ELEV. _N/A_ SUBMERGENCE Note 1 AB0VE FLOOD LEVEL YES l See attached sheet for notes.

FACILITY: Point Beach Nuclear Plant gg,,j3 Cli: j SYSTEM COMPONENT EVALUATION WORK SilEET D0fkET: 50-266 DOCUHtRfAllDRTitHIDctS ENVIRONMENT (See Attached Sheets) QUAliflCA110N OUISTANDING Equipnent Description b ~ SPEClflCATION QUAllFICAil0N Hell 100 ITEMS PARAMETER OPERAH E T W SYS1EM: Auxiliary Coolant l Year N te J (Tabl Q6.4-1) l t PiANT 10 NO.: l-AC6248625 ^U None Not ' COMPONENT: Limit Switches l None MANUFAC10RER: NAMCO Note 1 M00EL NO.: D2400X 1001 6A RELATIVE Note J IluMIDITY NOTE 2 FUNCTION:. Valve Position Indication Cl CAL Note 1 None ACCURACY: N/A SERVICE: RilR lleat Exchanger 1.25 X 106 2A Note J RADIATION Rads ' Outlet Line Valves LOCATION: IA Note J A Auxiliary Building 40 Years (pp. 4.1-11&l3) -5' Elevation Outside Unit 1 RilR lleat Exchanger Cubicle None FLOOD LEVil ELEV. _N/A SullMERGENCE Note 1 i AliOVE ILOOD LEVEL YES See attached sheet for notes.

11.-14 FAClllIY: Point Ileach Nucletr Plcnt Rev. 4 g,o[y. [0-301 SYSitM COMPONENT EVALUAil0N WORK Sil[E_I, 00ClNCWATID'~litiIRINCB ~ N ENVIRONMENT (See_ Atta<. heel Sheets) QUAllIICAil0N OtllSTANDING t ~ ~ SPECIFICAil0N QUAllflCAll0N HEllK)D II[HS Equi wnent Description PARAHf.iER 1A OPERATim IIM SYSTEM: Aux 111ary Coolant 1 Year (Table 06.4-1) Note J PLANI ID NO.: 2-AC624&625 None 1[HPERATURE Note 1 COMPONENI: Limit Switches HANUIACTURER: NAMCO Note 1 None MODEL NO.: D2400X REIAllVE 1001 6A Note J lillHIDlIY NOTE 2 f ilNCil0N: Valve Position Indication Al Note 1 C'j,I None ACCllRACY: N/A c, l ) SERVICE: RilR lleat Exchanger l.25 X 106 2A Note J RADIAtl0N l Outlet Line Valves Rads lA Note J LOCAil0N: AI Auxiliary Bu11 ding 40 Years (pp. 4.1-llR13) -5' Elevation Outside Unit 2 RilR lleat Exchanger Cubicle None fl0OD lEVIL ILEV. __N/A StinMERct NCE Note 1 A!!OVE It00D IEVIL YES See att.nheil sheet for nntes.

I' FACILITY: Point Berch Nuclear Plant 11.-15 UNIT: 1 Rev. 4 DOCKET: 50-266 SYSTEM COMPONENT EVALUATION WORK SilEET DOCKNihDON REFIRENCES ENVIRONMENT (See Attached Sheets) Equi eent Description b ~ SPECIFICATION QUAllFICATION I l PAR M TER g OPERAllNG TIME 1 Year Note J SYSTEM: Auxiliary Coolant (Tabl Q6.4-1) PLANT ID NO.: 1-A 626 TEMPERATURE Note 1 None COMPONENT: Limit Switch MANUFACTURER: NAMCO Note 1 None l MODEL NO.: D2400X 100% 6A RELATIVE Note J NOTE 2 IlUMIDITY FUNCTION: Valve Position Indication CllEMICAL ACCURACY: N/A SppAy Note 1 None I.42 X 106 SERVICE. RilR lleat Exchanger 2A Note J Bypass (ine Valve RADIATION Rads LOCATION: 1A Note J~ AGING -Auxiliary Building 40 Years (pp. 4.1-11813) 8' Elevation Lower Pipeway #2 Valve Gallery FLOOD LEVEL ELEV. N/A SUBMERGENCE Note 1 None ABOVE FLOOD LEVEL YES See attached sheet for notes.

"IO I ACil.l T Y : Point Beach NucIcar Plant UNil: 2 i DOCKET: 50-301 SYSTEM COM,P_0NENI EVALUAil0N WORK SilEET ~ DDClWNTATIOiflitTIMNC15 ENVIRONMENT (See Attached Sheets) ^L"^' " ^ " Equigwnent Description SPECIFI-7 ALVI ~ PARA TER SPECIFICAil0N QUAllflCAil0N MElll00 lifMS CAil0N Call 0N ^I IA SYSTEM: Auxiliary Coolant I Year Note J (Table Q6.4-1) PLANT ID NO.: 2-AC626 None TEMPERATURE Note 1 COMPONENT: Limit Switch None MANHfACillRER: NAMC0 Note 1 MODEL NO.: D2400X t i RELATIVE 6A Note J 100% NOTE 2 IlUMID11Y IUNCil0N: Valve Position Indication CIl Al ACCURACY: N/A Note 1 None g, 4 Note J 2A SERVICE: RilR lleat Exchanger RADIAll0N s Bypass Line Valve LOCATION: IA AGING Auxiliary Building 40 Years (pp. 4.1-11&l3) 8' Elevation Lower Pipeway #3 l None FLOOD LEVEL ELEV. _N/A., SUBMERGENCE Note 1 ABOVE It000 LEVEL YES See attached sheet for notes.

C ~ G I 74 DS 1 NM D AE G .v Ti s e e e 1 e Sl e e e R n n n t n 1 I t U o o o o o o N N N O N N N g N l r a i O 9 rs i t ei l I n es a T A0 "3 i e ny t Fil ] C0 util n 1 I qsga "y eenn e ~ ut I E STEA LM qs ee A U ~ ST 1 2 Q ) A N A O p2 p I T p p 3 A A, P A l C 1 C I N) F s BI B, I I I s I e I Rt L -) .l le A lb I 4 l fe U oa o ~ O - lh Q VT V ~ V4 hS ( ( ( fd De ) lh N ) 3 lc 0 1 1 Aa 1 A E_ Tt 4 T 1 I Nt A I l EA C 6 E Si H Q 1 2 I e F A A Ge 6E I 2 K DS C T i R U( E O b N O P p a W S T p ( ( N O 7 I T 0 A 1 U r L a x s A e 0

0. d V

Y 0 a E 1 1R I I N E T 6 N N 0 O E s 1 P M r M N r 1 1 I a 1 X s O O a e d C R e e e 0 6a Y e Y t t l t I 0

2. R 0

o M V o o E N P 1 1 N N 4 N S 5 T E S YS E E R C R U N N E T E EY O [ G T A R VT I I I T R E R U t M E S TD A g E n M n A P S AI I H a R M E LM D i A I R E0 A g U l P P T P RI R A S l r a e s 1 e 0 g e l 3 r t c t a o u 0 n e h n N 5 a r c l o u s A S r h / E o c n o r s d i a n o o e o s D N_ Y f e a C r b e i B2 t u x r p g t 6 p y s o M P m n L e td6 r s F G u i V E e i ~ r a e 1 e P d E V h n n2 ~ i r 1 g l n l E s ia-c 6 a A R io i l o 0 s l P ui d D x O99 r E t N R BtRb 0 e s R G / PI5 e i ail 0 h n yvRN. u N22 e R 0 c t A 66 T t U e e N re t a O Nm Y YTT n D8& N t I 88 E i C N 0e C E r 0 al e I t TI E e I t iEd r A C u i b") I NI n M 22 N m A l l C w E a E T 66 O s F L iu R I s l l LUC l V A i '9 tsb I i I N TT P n U E Cs U V s )X u S APP M a N D Na C R e C x O e C I H e A q Y L - - O r A O Ue C E r O u1 u l A S F ~ E S P 12 C T M M IM A S P L A O ~

FACll W: Point Beach Nuclear Plant II -18 -n: 1 Rev. 4 Di)t.KE T : 50-266 SYSTEM COMPONENT EVALUATION WORK SilEET ~ ~ ~~ IWKlMENTAllW RTIREB -~~ ENVIRONMENT _ (See _ Attached Sheets) QUAliflCAil0N (MlISTANDING Equl anent Description S SPEClflCATION QUAllFICAil0N HElll00 11LMS i PARAMETER g PERATIN TlHE " ring None (Tabi Q6.4-1) (VOI-

APP ^
yNs SYSTEH: Auxiliary Coolant 1 Year 1 Year Tables 1, 2 PLANT ID NO.: fT626 IEHPERATURE Note 1 None COMPONENT : flow Transnit tter HANUFACTURER: Foxboro Note 1 None MODEL W.

613DH REl.ATIVE 100% 100% 6A 9B IU UI Y NOTE 2 (Sheet A) Sequential Notes D & G IllNCilot. f hei flow Measuric. Cl8I Al Note 1 None ACCURhcy: N/A 3,, a lB Sequential None SERVICE: RilR lleat Exchanger 5.98 X 10 1.0 x 107 2A p3g g gg g g, ' I,

Test Outlet Line Rads Rads 4,4) 10 CATION:

40 Years IA Note G AGINr' Auxiliary Building (pp. 4.1 11&l3) 8' Elevation Outside Lower Pipeway #2 1100D tEVI1. ElEV. _N/li_ SUI 1Mr1(GENCE Note 1 None A110VE ILOOD LEVEL ytS See attached sheet for notes

~ E G ~ ~ 4 D5 NM 0 AE G TT s e b e SI e e e e e n t I n n n t n o W o o o o o o N N N N N N l l NO g I n l M l T i a A0 rs i C0 ei t I i es n { FT ny e I E ut il M ga qs nn ~ U ee Q EA .ST ) N A 4, O 4 I p2 T S A p ) A p E C A, ,1 FC I ) F B 8t 1I s 9e E s I Rt L e e E e A .l h F e U lb S 1 o El Q oa ( RS VT y ( ( Nd Ee I h N ) 3 ) Tc O 1 1 Aa I T it T 8 1 i t A 4 E l 0A C 2 1 E l 6 i N 1 S I e f Q AE A A A C e i 6T 2 I4 K OS C l e O R D( E l N O P b p W S a p T N ( ( O I 7 T IN 0 A IO 1 U OT r I L a 0 x A AA e 0 s I V lC

0. d Y

1 E Q a 1 1R T N 5 E T N N 5 0 O E s 1 P H r N s l M N O O fO r 1 1 1 a 1 Xd e iI a 0 a Y e C R CT e e e e 8R 0 t t I EA Y t t M V o o o 9 0 o 1 E N PC S 1 N N N 4 N T E 5 S I Y. E S M I T E E R C R G U N N E N T EY L O EG A VT A I T I C T R E T R I I t M A E TD A E H n A R P Al I l E D I i a R E M L R l A P E E l A ul H i P P O T Rl C R ^ S ~ r a s e l r r e c t e e t u n t g o N a t n 3 n f_ S l i a h o m o h / E r Y o N_ c n o s r w c y f a o C n o o x a i a b l E w e B t y r x M F g e t L e p r T o D t n p 1 t 0 i a F 3 d a i i V E e w 1 i e d P E V h n 3 r i o 0 s .i l 6 u A l l L E s c l o i l l / i r E L une d P 25 e x F R F N Rl e Bow L D e D u O E t i n io E O h R A N n R V O c t T U e i

ytL YTT n

D N T O N m Y

L Nra L

L a 6 I E C N O C E Oave L I t TI E e 2 e t NK m M N A r A C t i ed I I I 6 LUC p E T O F L T R I T D E a T u e lli O V i T N P U E C U V A iEs O I F s l O O e C D u S A M N D N C R C a t x t L B e A q Y L O A O U C E O u u u e F E S P 2 A '8 O F A S C H M A S L I M D 4

FACILITY: Point Beach Nuclear Plant I.- 0 IINil: 1&2 Rev. 4 DOCKET: 50-266 & 50-301 SYSTEH COMPONENT EVALUATION WORK SilEET ~ D00HihTAUDh RtItii[WCES ENVIRONMENT (See Attached Sheets) QUAliflCATION OUISTANDING Equi ment Description S ~ SPECirICATION QUALIFICATION HCill0D litHS l PARAMETEft 1A 1B

1. Simultanco as Ol'ERATING ilHE SYSTEM: Auxiliary Coolant 1 Year 1 Year (Table Q6.4-1)

(Vol. I, App. A Test None Tables 1, 2, & 4 2. Engineerin i PLANT ID NO.: TEMPERAIURE Figure 4A Figure 128 3A 1A 9B (Sheet A) Simultaneous COMPONENT: Flow Transmitter 3A PRESSURE Figure SA figure 13B 1A HANUTAC10REll: Foxboro Section 14.2.5) 98 (Sheet A) Siniltaneous Test Notes D & G H0 DEL FO.: 613 DH RELATIVE 98 (Sheet A) Simultaneous IlUHipliy 100% 100% 6A Test Notes D & G NOTE 2 98 (Sheet A) FUNCTION: Fluid Flow Measurement CllDilCAL ACCtlRACY: N/A SPRAY Note 1 None SERVICE: Component Cooling RADIATION Note 1 None lleat Exchanger Outlet Line 1A W,ATION: AGING 40 Years (pp. 4.1-11 & 13 ) Note G Auxiliary Building 46' Elevation Component Cooling TLOOD LLNL^UlV. N/A-- Note 1 None SUBMERGENCE ABOVE ILOOD LEVEL Yes See attached sheet for notes.

FACILITY: Point Ileach Nuclear Plant II'~2I UNIT: -j IOCKEI: 50-266-SYS1EM COMPONENT EVALUATION WORK SilE Q '~ DOCIENTATIDii RUTHDictS ENVIRONMENI (See Attached Sheets) Equipment Description SPECIFI-T}llAGIT-PARAMETER SPECIFICAil0N QUALIFICAll0N 11 i 5 CA110N Call 0N PERATIF,TIHE ' 9 None SYSTEH: Auxiliary Coolant 1 Year 1 Year 390 (Tabl Q6.4-1) s PLANT ID NO.: 1-TE627&630 None TEMPERATURE Note 1 COMPONENT: Resistance Temperature Elements ~ None HANllf ACTURER: foxboro Note 1 H0 DEL NO.: DB130-226W Engineering RELAllVE 100% 100% 6A 19B None Analysis lillHIDI TY NOTE 2 filNCTION: Temperature to Resistance Conversion CIhlMC^l None Note 1 ACCllRACY: N/A 5 6

1. Engineerin.;

SERVICE: RilR Suction & l.08 X 10 1.0X10 2A RADIAT M B Analysis None Olscharge Lines Rads Rads

2. Se sarate

-E ifec t s-Test - -- l0 CATION: 40 Years 40 Years IA 19B Engineering None AGINP' Auxiliary Building (PP. 4.1-11&13) Analysis (Note A) 14' Elevation Lower Pipeway #2 None ILOOD LEVEL ELEV. N/L SilllHERGENCL Note 1 AB0VE FLOOD LEVEL YES See attached sheet for notes.

GN 24 I 2 DS NM ) . v. AE N 1 e lT 1 R SI e e e e e e e n n n n n n I U o o o o o o o O N N N N N t N N g s ( n e N i s T_ O g g rie g n ns est s ns I T eyat ii ii A0 rs nl rc rs C0 ey l i aae ey l i e el g n pf el fT na nAef na l E i n E SE in lM A gA gA n U n n Q E E 1 2 E - NO I T S A E C C l B B B 8 N) f 9 9 9 9 Es l 1 1 1 1 Rt l E e A + F e U Eh Q RS Nd We ) Ih N 3 Tc O ) l 1 Aa I T Tt T l E Nt A 4 2 l EA C El D 6 4 l S I e f Q AE 1 i 6T A A Ce I O 2 l4 K 0S C N R 0( E l O P b p W S a p T ( N ( O I s T r A r 6 a U a e L e 0 Y A Y 0 X, V 0

0. p 1

E 4 1 T 1 N E T Ys N N s O E r P M M N r 1 1 1 a 1 Xd e O O a C R e e e 0 e a Y e Y t t 0 t 8R t I M V o o 1 o 0 0 o E N P 4 N S I N N N E T E S YS E E R C R U N N E T E EY O EG A R VT I T I l T R E R U t M ^ E S T0 A G E N M n A P S A1 I B a R M E D 1 I 8 l A E R Et A G U P P T P Rl R A S i r a s e e l t c t o u n N a o n t h o e W A S r l c n o cs o 6 en / E o Y f N_ a o C nt r 2 ro n an o 2 ui o e i t e, b t s i g t B t y L e p r si x 0 ar t n r t 0 a ie o 3 re c i 3 V E e 1 i n 3 r sl F 1 ev us d E V h i i c eE B pn A S e l ' L E s l s R D mo / n iny E L o 0 e x e R eC N Ri uoa d i P25 D u O 0 r E T li L Biw L D e e R t e E O h. A N 3 u R c e yap V O 6 Tt U t t g N rvi E L a Na T o Nn Y YTT n 0 1 E r C N Oa C E r 0 aeP L F t TI E e 7 t A C a il

l. NK m

M 2 Ne A t l I l E r D E a i 6 Op F L T R I UC p E T s h 'Ai e O V l i T N P m U E C U V c O l C D u S A Me N D N C R C x w O O e E i T s s A q Y L O T A O U C E O u '4 o L B e e i F A S L A1 L F E S P C M M F A S D 2 R I'

i e Z t 1 l OY m Zr = = = o Z I <w C = c = OT C C O O Q l N O Z 0 0 Cw CJ ( Z Z =* C C = c C e. I e 5 oZ - aJ l Z Z Z~ Z i. .-. g _h Ch Ce e, Cn C m C 1 i et C Lm "=" " I I i I Lm y QJ h 1 B L M 8, 8, C aJ - e s a> a- = UN 8 6 s-CC 8 8 CJ - I i

== w

- = C D

t C m e a Oh 5 I 8 I "O" "C JZ CD elC i i e C 8 8 aC C C1 aC = w C B C C i O w I W< l 1 5 1 W I M WC 6,sd G m

==6"=

m I I tlC 4 I llC 8 = g g gn g a m g W m I I 4 8 1 E *# "J W CJ

== I e I I I 8C 1 8 8 I I Im. 3 aJg Cr MM l 2e c i l>=.C , Z I v C e m es:: m wl }*= **

=

I ac ) ,Z =* eC g M, N 8 I "8 f I e e ~ I s 9 9 9 "U aC C g g aC W g g elC e-g M U

==

g g @ P= 3 g g S-I l O t i T f w O L m 3 a m >= C. { b E' 3-m 16 e --. C L M L

p J

e-m I e o 4 e C I e-e aC a e i C e e ce s-

s.

"s v

>s I

e I e e W C 6 I I B I e e a e C s >= v Zl w Z Z l, C m e L c;,, C ~6 g I"" L 4 E H W G CJ CJ C m c .c O

a oa
e

~ Ga sa a u z o o C C C C l U '"E

== E >AV g Z Z C Z W* w Z w >= wid f M >= la J I, M E w aJ 2 U 2 C O Z Z w 2 a-W W >= J C w C EC C ll> >= aC >=

== =.=- e E =- U >- w >= 2 = =J Z ell' W M k-O = at at C w Z Z C eC z M aC - Ez C, C 2 w Z w J{ a=J L O

=

C W = w-lllll M EC C O

== A L C >= C E= v 2 e M l 6 k1 l e

3 "y

CD C C C a C= = 1 as t x Z m C e s c w J L r i C et f - C Q 4.n C C C C QJ C C +J e:C e O Ve L "E LQ U QJ N CJ C 'y c. U C *J C 3* = 2: c; oc glc .a @ C .O N se m

J *J 7

a y t c c

gll, h

+3 Q x N CL C2 C CM 'I c wN @ 6 mE C e L CJ CJ C C ll> 6, = N 6 m - CJ 6 3 CJ > C "3 w .= I -ec y w m-M AC CL ,,g w e EC

a. o

== C O s a CJ W c C m .m 2 x CC CJ U N

== C 3 OO a:l' c c== kn cJ

=

==..C

>= Z OC C:

U J

C c C.. O X C w C UC

J a

.= 3 Z L g 6, D. h m +J lls. .C y ed ag' N N >- 3 lll: .. U e C e e Z.J w C Z = >. .. v Z L >C w e >==== k.J fm> WWh U Z C C O LJ X C C CJ QJ w 6 e -ZM g E-

== ==

d elC U LJ

===*-C ed P- >= Z L et

== >= - LJ O ~ W c -JGV w

== t C QJ 6 -J >= m Cc 1 C ll>

== P-= Z -NC C. O W V* O p

J aC C
=

U C 2 A eC Z i:. Z O Z m V E C y X= E C C CJ 3C O .J CO C; C" >= a C CJ ef 3 CJ U w Q w

=

w M A V >= Z E 6 cc et M *:=, et g y 6 eC M i e 9 wm-

FACILITY: Point Beach Nuclear Plant UNIT: 1&2 11.-24 Rev. 4 DOCKET: 50-266 & 50-301 SYSTEM COMPONENT EVALUATION WORK SilEET 4 DOClhENTAil0N REFERENCES ENVIRONMENT (See Attached Sheets) Equipment Description S 0 PARAMETER-SPEClflCATION QUAliflCATION ll T S 3 OPERATING TlHE SYSTEM: Auxiliary Coolant 1 Year 1 Year 1A Analysis None (Table Q6.4-1) (pp. 383, 398, & 401) PLANT ID NO.: 1-P11A & B None 2-P11A & B TEMPERATURE Note 1 COMPONENT: Oil PRESSURE Note 1 None l MANUFACTURER: American Oil MODEL NO.: Industrial #21 100% 6A Engineering 100% i Analysis None NOTE 2 (pp. 383, 398, & FUNCTION: Pump Bearing 4014 - Lubricant CllEMICAL Note 1 None ACCURACY: N/A SPRAY 7 2.32 X 105 1.0X10 2A 20B

1. Engineerint SERVICE: Component Cooling RADIATION Rads Rads 168 Analysis None Water Pumps (pp. 383, 398, & ?. Separate 401}

-Effects-Tes ts LOCATION: 3F Engineering AGING Auxiliary Building (Table Q6.4-1) Analysis None (pp. 383, 398, & 8' Elevation 901) Component Cooling Pump Area FLOOD LEVEL ELEV. N/A_ SullHERGENCE Note 1 None AB0VE ILOOD LEVEL Yes See attached sheet for notes.

4 IACIL11Y: Point Betch Nuclear Plant ~' UNil: I and 2 Rev. 4 DOCKET: 50-266 and 50-301 SY_SIEH COM""NENT EVALUATION WORK SilEET UUdlWtWIMlWRIllTEB ENVIRONMENT (See Attached Sheets) Equipment Descriptinn SPECirl-7 UA[ITI_- QUAllFICAll0N OUTSTANDING PARAW1ER SPEClflCAil0N QUAllflCAil0N HElll00 IT[HS CATION Call 0N OPERATING TIME lA IB SYSTEM: Reactor Coolant 1 Day 1 Day (Table Q6.4-1) (Vol.1,p.D-1); Simultaneous 16B Test None PLANI ID NO.: (p. 10) 1-RC515 & 516 2-RC515 & 516 1[HPERATURE 1A IB Figure 1 A Figure IB (Figure Q6.4-5) (Vol.I,p.0-10) Simul taneous COMPONENT: Valve Motor Test None Operator PRESSURE HANUFACTURER: F 2A F W 28 M IB SM Weon Limitorque/ Peerless (Fig.14.3.4-8) (Vol. I, p.D-10) Test None 7 MODEL NO.: SMB-000/ Frame Pil56B/ Class B ins. RELATIVE 100% 100% NOTE 2 1B IlUNIDlIY (Vol.I,p.D-1) Simultaneous FUNCTION: Remotely Controlle< 16B Test None Valve Operation (p 18 ) IS B 803-Na0ll 1A H 00 -Na0ll 3 3 3 EHEMICAL Solution Solution (p. 6.4-15) (Vol.1,p.D-B Simultaneous ACCURACY: N/A SPRAY pil: 7.9-pil: 7.85 & 10) lest None 10.R 2.7X107 2X108 RADS ; 1A IB SERVICE: Pressurizer Power 7 RADIAil0N RADS 2X10 RADS (Figure Q6.4-4) (Vol.I,p. 5-4); Sequential Operated Relief Valve 16B Test None Blocking Valves (pr2F LOCATION: Containment lA IB AGING 40 Years 40 Years (pp.4.1-11&l3) (Vol.I,pp.5-1 Sequential 80' Elevation & 5-2) Test None TLOOD LEVI L [ LEV. _14_',10" SURMERGENCE None All0VE It000 LEVEL Yes NOTE 1 See atlathed sheet for notes.

FACill1Y: Point Beich Nuclear Plant y,-2 UNil: I and 2 Rev. 4 00EKET: 50-266 and 50-301 SYSTEM _COMPONENI EVALUA110N WORK SitEET DOUMENIATID~MMittNtts Equl nent Description SPL (See A_ttached Sheets) . ENVIRONMENT QUAllFICA110N 00151ANDING i PARAMETER SPECIFICATION QUAllFICATION MEill00 IIEMS "^ SYSTEM: Reactor Coolant 1 Year IA (Table Q6.4-1) Note P PLANT ID NO.: 1-RC430 & 431C 2-RC430 & 431C I[MPERATURE Figure lA lA me P-COMPONENT: Solenoid Valves PRESSURE MANUFACillRER: ASCO Figure 2A lA (F g. 14.3.4-8) Note P MODEL NO.: LBX831614 RELATIVE lillMIDITY 100% NOTE 2 Note P FUNCil0N: Remotely Controlled Air-0perated 80 -Na0il ggperation CHEMICAL 11 33gfution lA

N/A SPRAY p);

7.9-(p.6.4-15) Note P IQA 1.45X108 SERVIEE: Pressurizer Power RADIA110N RADS 1A Operated Relief Valves (Figure Q6.4-4) Note P (PORV's) LOCATION: Containnent Acgyg 80' Elevation 40 Years Note P ILOOD LEVEL ELEV. _14'10" SUDMERGENCE AHOVE Il0001.EVEL Yes NOTE 1 - " - " - ~ ~ ~~ __,_n .. - - ~ ~ ~ ~ - ~ ~ ~ ~

~ -

i see attache <l sheet for notes.

FACIL11Y: Point De:ch Nucle:r Plant V.-3 UNIT: I and 2 Rev. 4 DOCKET: 50-266 and 50-301 SYSTEM CCHPCNEl1T EVALUATION WORK SilE_ET ~~UUrUMENTATION REFEli[hTES PARAMETER 0 (See Attached Sheets) EN_VIR,0NMENT QUALIFICATION OUTSTANDING Equipment Description SPECIFICAil0N QUALIFICAil0N HETIIOD 11 EMS N l.Simultaneou< OPERATING TlHE SYSTEM: Reactor Coolant 1A 4B Test 1 Year 1 Year (Table Q6.4-1) (App.D,pp.3-10) 2. Engineering Analysis None PLANT ID NO.: [ 1-RC430 & 431C 2-RC430 & 431C 1[HPERATURE 1A 4B Simultaneous Figure 1A Figure 68 (Figure Q6.4-5) (App.D,pp.3-8) Test None COMPONENT: Limit Switches (Note K) PRESSURE MANUFACTURER: NAHC0 Figure 2A Figure 78 1A 4B (Figure 14.3.4-8; (App.D,pp.3-8) Simultaneoe None Test (Note K) MODEL NO.: EA-180-11302 RELATIVE 4B Simultaneous None IlUMID11Y 100% 100% NOTE 2 (App.D,pp.3-8) Test (Note K) FUNCTION: Valve Position Indication ll 00 -Na0ll Il B0 -Na0ll 3 3 3 3 CilEMICAL Na2 2 3 1A 40 Simultaneous Solution S0 ACCURACY: N/A SPRAY pil: 7.9-pil: 10.0-(p. 6.4-15) (p. 8) Test None 111a ILO. 1.45X108 2.04X108 1A 4B Sequential RADIATION RADS RADS (Figure QF.4-4) (p. 8) Test None 0 ra ed o r er te i Relief Valves (PORV's) LOCATION: Containment IA 48 00ING 80' Elevation 40 Years 7 Years (pp. 4,1-11&l3) (Revision dated Sequential None Feb. 27,1980L Tgst __{ Note _L) l FLOOD LEVEL ELEV. 14'10" SilBHERGENCE ABOVE FLOOD LEVEL Yes NOTE 1 None l See attached sheet for notes.

FACILifYi Point Beach Nuclear Plant V -4 UNii: I and 2 Rev. 4 DOCKET: ~50-266 and 50-301 SYSTEM COMPONENT EVALUATION WORK S_IlEET 000FENIAllWWI ERWCES T _ See Attached Sheets) . Q@liflCAT ION OlliSTANDING ( ENVIRONMENI Equipment Description PARAMEIER ~ SPECIflCATION QllAliflCATION HEill00 11 EMS C ON 1A 1R 1.Simultaneou-, Reactor. Coolant GPi MilNG TlHE 1 Year 3 flours (Table Q6.4-1) (Vol. 1, App. A Test Notes D,F,8G SYSTEM: 4A Tables 1, 2 & 4: 2. Engineering (Sections 4.22&2 3) Analysis PLANT ID NO.: 1-PT420 IB Simultaneous 2-P1420 TEMPERATURE Figure lA Figure 48 IA (Vol. I, App. A Test Notes D*F*AG (Figure Q6.4-5) Tables 1, 2 & 4 COMPONENI: Pressure Transmitters 9"" ^ 9"" Notes D,F,8G MANtifACTURER: Foxboro (Figur 14.3.4-f fVol. . App. A i sbles 1, 2 & 4) MODEL NO.: 611Gil ~ IB Simultaneous Notes D,f,8G RELAilVE 100% 100% (Vol. I, App A) Test lillMIDITY 3 TilNCTION: Gage Pressure Measurement 1180 -Na0ll IB

1. Simultaneous None Il380 -Na0ii 3

3 Cl l AL (Vol. I, p. Test ACCURACY: N/A Solution olution (p. 6 -15) pil: 7.9-pil: 9.25 1-3)

2. Engineering 10.0 Analysis SERVICE: Reactor Coolint-1.45 x 1.0 x 107 1A 18 Sequential Notes D.F,8G RADIATION hide Range 108 Ilads Rads (figure Q6.4-4)

(Vol. I, p. 1-3: Test " Engineering 40 Yea n M Ana hs h M es D,F,8G 10CAil0N: Containment AG I NI,' 66' Elevation (pp. 4.1-11813) i ILOOD l EVEL El EV. M']Q" SUHMERGENCE Note 1 None l l AROVE fl000 LEVEL. VES t See attache <l sheet for notes.

1 IACILITY: Point Hear.h Nuclear Plant y,. r, UNil: 1 pey, 4 DOCKET: 50-266 SYSTEM _ COMPON[ fit EVAL,l}AlION WORK _ Sil[I T ~~ ~ ~~~UUUWtWIAT1DFli[IllifMCB ENVIRONMENT (See A_ttacheil Sheets) QUAllFICATION OUISTAN0 LNG Equipment Description SPEClIl- ~~T)llAElfl-pgpgggggp SPECiriCAll0N QllAllflCAll0N METil00 li[MS CAT 10N CAT 10N i

1. Sequential SYSIIM:

Reactor Coolant OPEllATING TIME 2 711 Test IA (pp.2-5 & A-3

2. Engineering Note R 1 Year 1 Week (Table Q6.4-1)

A flg. 5.3) Analysis PLANT 10 NO.: 1-TE4500 1-TE451B ItMPERAIURE 1A 278 figure lA figure 2211 (figure Q6.4-5) (figure 5.3) Simultaneous COMPONENT: Resistance Test None Temperature Element PRESSilRE MANIIIACIURER: Rosemount lA 278 figure 2A figure 2211 (fig. 14.3.4-8) (figure 5.3) Simul taneous MODEL NO. 176KS ~ -None lest RI' *iiVE 270 Simultaneous IIUHIDI TY 100% 100% NOTE 2 (figure 5.3) Test None Ill3Cil0N: Temperature to Resistance Conversion ll3l10 -Na0!! Il 003-Na0ll 3 3 Cil[HICAL ACCllRACY:N/A sppgy Solution Solution 1A 270 Simultaneous pil: 7.9-(p. 6.4-15) (pp. 2-7 & 5-1) Test None 10.D ___ 1.45X108 1.0 X 108 1A 270

1. Sequenttal SERVICE: Reactor Coolant Test RADIAll0N RADS RADS (fig. Q6.4-4)

(pp. 2-5 & A-3) llot Legs plus 27B

2. Engineering Note R 3.0X108

~ ( fi g'. 7 1 ) - Analysi r LOCATION: Con tainment RADSIA0yCs) 10 Years IA 278

1. Sequential AC. I NC' 35' Elevation (Racit a tion (pp. 4.1-11813)

(figure 2-1) Test Note R .J10_ Yea rs_ Aging _onjy1

2. Enginggrinm________

Analysis Il000 lEVIL llLV. ~ ~ ~14'10" SilllHIRGINCL None NOTE I All0VE I t000 IiVII. Yes See altarheil sheel Inr notes.

V.-6 FAr1LITY: point Bezch Nuclear Pltnt Rey, 4 ' UNIT: I and 2 DOCKET: 50-266 and 50-301 SYSTEM COMP 0NEHi EVALUATION WORK SIIEET DOCtMDifATIWM RLFtillhCES ENVIRONMENT (See Attached Sheets) QUAllFICATION OUTSTANDING Equipment Description SPICIFI-

7UAEITI'~

PARAMETER SPECIFICATION QUALIFICATION Heil 100 ITEMS __CA110N __ CATION

1. Sequential OPERATING TlHE 1A 270 Test SYSTEM: Reactor Coolant 1 Year 1 Week (Table Q6.4-5)

(pp.2-5 & A-3

2. Engineering Note R

& Figure 5.3) Analysis ptAN7 ID NO.: 1-Tl450A 1-TL151A TEMPERATURE lA 278 Simultaneous 2-TE450A Figure 1A Figure 220 (Figure Q6.4-5) (Figure 5.3) Test None COMPONENT: Resistance Temperature Element PRESSURE IA 278 Simultaneous MANUEACTURER: Rosemount Figure 2A Figure 22F (Fig.14.3.4-8) (Figure 5.3) Test None HDDEL NO.: 176KS RELATIVE HUMIDITY 100% 100% NOTE 2 278 Simultaneous FUNCil0N: Temperature to (Figure 5.3) Test None Resistance Conversion H 80 -Na0H H 80 -Na0H 3 3 Cil[HICAL 3 3 ACCURACY: N/A Solution Solution IA 278 Simultaneous 3ppgy pil: 7.9-(p. 6.4-15) (pp. 2 78 5-1) Test None LQA.

l. Sequential 0

0 SERVICE: Reactor Coolant 1.45 X 10 1.0 X 10 1A 27B Test RADIATION Cold Legs RADS RADS (Figure Q6.4-4) (pp. 2-6 & A-3) 2.EngineerM plus i _._Ana] M s__. ___ Note R 8 3.0X10

1. Sequential LOCATION: Containment AGING RADS (40yn 10 Years IA 27B Test 35' Elevation 40 Years (Radiation (pp. 4.1-11&l3)

(Figure 2-1)

2. Engineering Note R A ing on13 )-

- Analys-i r 9 FLOOD LEVEL ELEV. 14'0" SUBMERGENCE None NOTE 1 AB0VE FLOOD LEVEL Yes ^-- See attached sheel for notes.

EACILITY: Point Den.h Nucle r Plant Y -7 IINil: 2 Rev. 4 DOCKET: 50-301 SYSith COMPONENT EVALUATION WORK SilfET ~~ ~~D00M[hl AfiDh'~lilTUlfEB ENVIRONMENI (SeeAttachedSheets) QUAllflCATION OUISTANDING Equipment Description SPECirl-l)ljAI'III'_ SPfClflCAll0N QUAlifl6All0N METil00 IItHS p3p3g7,gg Call 0N dil0N I-OP[ HATING TIME 270 SYSTEM: Reactor Coolant 33 1 Year 1 Week (Table Q6.4-1) IPP e53 ?. Lngineerini Analysis Note R PLANT ID NO.: 2-TE451A 1[MPERATURE 1A 27B SimulLaneous U"" 9" COMPONENI: Resistance Temperature Element IA 27B ' PRESSURE MANUT ACTURER: Sostman

Figure 2A Figure 22ii (fig. 14.3.4-8)

(Figure 5.3) Simultaneous Test None MODft NO.: 11901B ~ RilAllVE 278 lit #1IDlIY 100% 100% NOTE 2 (figure 5.3) Simultaneous IUNCTION: Temperature to Test None Resistance Conversion il 80 -Na0il H 80 -Na0ll 3 3 3 3 CilLMICAL ACCURACY: N/A Solution Solution IA 278 Simultaneous SPRAY pil: 7.9-(p. 6.3-15) (pp. 2-7 & 5-1) Test None ____ 10. 0._ 0 0 SERVICE: Reactor Coolant 1.15X10 1.0 X 10 1A 278 I. Sequential RADIATION Cold I.eg RADS RADS (figure Q6.4-4) (pp. 2-5 & A-3) 2. J neering Note R plus 3.0X10 I

An a l y s i s---

l.0 CAT 10N: ConLainment RADS (40vrt; 10 Years 1A 27B

l. Sequentia1 AGI Np' 35' Elevation (Radiation (pp.4.1-ilA13)

(figtre 2-1) Test Note R 40 Year! . aging,oni ) 2 J ngincer,inq___._..__. Anaryils ll000 lT.VIL IlLV. --""-14'10" SilHMI RGI NCE None NOIE 1 ABOVE fl00D ILVII. Yes .---I-See atIatiu il *.heei for notes.

V.-8 FACill1Y: Point Beach Nuclear Plant . UNIT: 2 Rev. 4 DOCKET: 50-301 SYSTEM COMPONENT EVALUATION WORK SilEET RKlHiNifil0N RETIRIhCES EN_VIRONMENT (SeeAttachedSheets) QUALIFICATION OUTSTANDING Equipment Description SP C T PARAMETER SPECIFICATION QUAllFICATION METHOD liEMS g ON I" Sequential OPERATING TIME 278 T 5751EM: Peactor Coolant lA (pp. 2-5 & A-3

2. Engineerino Note R 1 Year 1 Week (Table Q6.4-1)

& Figure 5.3) Analysis PLANT ID NO.: 2-TE450B 2-TE451B TEMPERATURE 1A 27B Figure 1 A Figure 220 (Figure Q6.4-5) (Figure 5.3) Simultaneous COMPONENT: Resistance Test None Temperature Elenent PRESSURE MANUFACTURER: Sostman Figure 2A Figure 22E 1A 27B Simultaneous (Fig. 14.3.4-8) (Figure 5.3) Test None l MODEL NO.: 11901B RELATIVE 27B Simultaneous IlUMIDliy FUNCTION: Temperatur to 100% 100% NOTE 2 (Figure 5.3) Test None Resistance Conversion ll380 -Na0ll II B03-Na0ll 3 3 CifEMICAL ACCURACY: N/A Solutici Solution I 1A 278 Simultaneous SPRAY pil: 7.9-(p. 6.4-15) (pp. 2-7 & 5-1) Test None 111. 0 SERVICE-' Reactor Coolant 1.45X10 1.0X108

1. Sequential 8

RADIAil0N RADS RADS 1A 27B Test Ilot Legs 2. ng Note R ""g Figure 06.4-4)_ (pp. 2-5 & A-3) 3.0X10

1. Sequential LOCATION: Containment RADS (40 yrs 10 Years Test AGING 35' Elevation (Radiation IA 278 2.

1 Note R 40 Years _ aging oMy (pp. 4.1-ll&l3) (Figure 2-1) ej rLOOD LEVEL ELEV. _B110" SUBMERGENCE None NOTE 1 AB0VE FLOOD LEVEL Yes See altar.hed sheet for notes.

Y -9 FACILITY: Point Beach Nuclesr Plant UNIT: I and 2 Rev. 4 DOCKET: 50-266 and 50-301 SYSTEMCOMPONENTEVALUATION_y0RKSil, eel UDU WNTATIDN REFERENCES ENVIRONMENT (See Attached Sheets) W M AT M ETAN0lE Equipment Description SPECiri- ~~f)UAETIT-PARAMETER SPECIFICATION QUAllflCATION MElll00 ITE MS g yg OPERATING TIME SYSTEM: Reactor Coolant 1A 1 Year (Table Q6.4-1) Note S PLANI 10 NO.: 1-TEl-39 2-TEl-39 TEMPERATURE 1A 9 9" COMPONENT: Chronel-Alumel Thermocouples PRESSURE 1A MANUfACitHER: Control Products Corp. Figure 2A (Fig. 14.3.4-8) Note S MODEL NO.: 5649018 RELATIVE HUMIDITY 100% NOTE 2 Note S FUNCTION: Tempe ra ture-to-Voltage Conversion H B0rNa0H CilEMICAL 3 ACCURACY: N/A SPRAY SoTution lA pil: 7.9-(p. 6.4-15) Note S 10.0 SERVICE: In-Core .45X108 1A RADIATION (Core Exit Coolant) RAOS (Figure Q6.4-4) Note S t LOCATION: Containment AGING 30' Elevation 40 Years IA Inside Reactor Vessel (pp. 4.1-ll_A13)_ ___fiote S FLOOD LEVEL ELEV. N/A_ SUBMERGENCE ABOVE FLOO9 LEVLL N/A NOTE 1 None See allathed sheel for not es.

FACILITY: Point Ben h Nuclear Plant V.-10 UNIT: I and 2 Rev. 4 DOCKET: 50-266 and 50-301 S_YSTEM COMPONENT EVALUATION WORK SHE_Ei ThX1HDRATION REILR WCES ENVIRfCHENT (SeeAttachedSheets) Equi eent Description SPECirl-7 A[lff~ l PARAMETER SPECIIICATION QUALIFICATION I CA_[10N CAil0N SYSTEM: Reactor Coolant OPERATING TIME I 1A 4 1 Year (Table Q6.4-1) Note 5 PLANI 10 NO.: e l-TEl-39 2-TEl-39 TEMPERATURE Figure 1A 1A COMPONENT: Electrical (Figure Q6.4-5) Note S Connectors MANUf ACTURER:Thermo-Electric figure 2A 1A (Fig. 14.3.4-8) Note S i MODEL NO.: MSP-KX RELAT!VE FUNCTION: Electrical Connection of the Thermo-U 0 -NaOH couple Lead Wire to Ext. WirrtHEMICAL 3 ACCURACY: N/A o ution lA %I, RAY l pil: 7.9-(p. 6.4-15) Note S 10.0 1 8 l SERVICE: In-Core 1.45X10 1A itA0lATION The nnocouples RADS (Figure Q6.4-4) Note S IA LOCAil0N: Containment agggg 46' Elevation 40 Years (pp. 4.1-11813) Note S l IL000 LEVI'l ILLV. _14.*]o= SullMERGENCE A110VE 11000 LEVEL Yes NOTE I None See attache I sheet for notes.

V.-ll FACill1Y: Point Beach Nuclear Plant Rev. 4 UNIT: I and 2 DOCKET: 50-266 and 50-301 SYSTEM _ COMPONENT EVALUAll__0N WORK SilE_E_T. l DOCliHDif ATIFli RTERNCES ENVIRONMENT (SeeAttachedSheets) AI ANO M Equipment Descriptinn SPEClfl-l A[ I T I'- PARAMETER ATI l QUA ATI H 0 m MS Call 0N CATION SYSTEM: Reactor Coolant OPERA 11NG TlHE lA 1 Year (Table Q6.4-1) Note S PLANT ID NO.: l-REF.JBl&2 2-REF.JBl&2 TEMPERAIURE 1A figure 1A (Figure Q6.4-5) Note 5 COMPONENT: Thermocouple Reference Junction Box PRESSURE HANUFACTURER: Whittaker 1A Corporation-instrument _ Figure 2A ( Fi g. 14. 3.4-8) Note S Systems Division HDDEL NO.: 22TT-7047 RELATIVE IlUMID11Y 100% NOTE 2 Note S IUNCil0N: Thennoccuple Output Compensation Using ll 80 Na0ll a Reference Junction CllEHICAL 3 3 ACCURACY: N/A SPRAY Solution lA pil: 7.9-(p.6.4-15) Note S 10.L SERVICE: { g i ouples RA0lAil0N R 1A (Figure Q6.4-4) Note S LOCAtl0N: Containment AGING 56' Elevation 40 Years lA (pp.4.1 -l l &l 3)__ Note S FLOOD LEVEL [P.t'V.14'10" SUHMERGINCE AHOVE ILLLo LEVEL Yes NOTE 1 None i .. ~.. - -...... - See attached d eet for notes. i I l

t ~ ~ G ~ N I ~ Ds ~ 4 ~ 2 NM T 1 ^ i_ I I i A[ ~ I l i e e e e e e._ e - V ~ sl t t t t t t. n O ~ ~ i o o o o o o. o VR ~ ~ N N N N._ N l N N lO ~ ~ N 0 ~ l ~ i A0 l 1 - ~ C0 l fi ~ it ~ lM A ~ 0 ~ ~ 0 W ~ ( l l ~ A ~ C ~ I ~ ~ ~ ) I s I t L ~ e A e U h Q S ~ ~ d, ~ )3 ) ~ e h N ) t f ) c O 1 4 ~ 4 ~ a I 1 J 4 t T A 4 ) f t A 3 2 ~ 5 ( I l A C 6 I 6 ~ 1 A4 L A - Q A - i l g0 g S e l 4 I1 11 I I j y e i O e e K S C N 6 r ~~ 4 l ( I b g ug p I' 3 ( ( _S a i T f p p. i ~ ( f ( N ( O ~ I M ~ I f A f l 2 l. ~ U l . i L lAA ~ A ll V C ) ~ [ l I N_ (. N r I I N N A ~ = lun-s h O I 2 0 a o 9.1 I' H r Ni 0 a I iN ~ M Wl a e - t7 1 e J e r la X Y

+

O ( l ( l m C Ri, l Y u 0 l M_ l 0 0 g 0 1 oH 4 1 IViA i a 1 p 4 N I ~ 1 1 N'fC = 1 f f [5 I S Y f S M 1 1 I a. I R C p G g N l + l N l l CY g l _g,7 l A m VI a G l g + l R 1 l l CI g R t A 5 i D A g ( I l _. p l M I l li C p A S e, M M n 3 l I' 5 AI M N, g I t a a I L M n li r. I l . 3, l' I t l H 3 N i + l' I g O I i l f ra 'e e r 1 lc 0 o 1 a u 3 t t e e 01 I s d 1 N n o 0, 0 a n u l h. 5 l os o G I Cs n l. s a. T t n o Hr h U f t t o e H ( a' d o o A e g /v k orv mi 4 Y ( e n i C / cc n 7 e an el t I u I a t N u 9R eu eza n a l l i I 2 p r td t 1 Ll gi V nv . e l e V i -

o ss s

29 t rr t 6 i i f lnd 6 r t un e 31 dc auy a l. 1 ( V - h ~ n2 c c oe W - 0 ie A hst t [ I S I. oa - cr X5 ul / cse n I 1 n. s a l' 0 e i T R Wf i 1 0 fD i ra C0 0 a d e N sef o' . e D e l m. 5 R o I i I u N m 6 D l' S 1 I 0 i m l 1 V 0 t I i i Yl i. n D N O. N Y N I l d l l NK m M: I t C N o 0 C E 0 a, ii I e 1 1 i M 'A N A C l = t l e l l C i I I I l 0 F w d l ( l I i Hl V A 1M l l ) l N I' [ C l R C ( V i I W C u S A M iN N y N C 0 - e ) I A q _ Y t ( l A I w C E O . e t l I l = S l' C M M D A S L i A S I E i ~ i~ ; i1 il j'

FAClll1Y: Point Berch Nuclear Plant V.-13 UNIT: I and 2 Rev 4 DOCKET: 50-266 and 50-301 SYSTEM COMPONENT EVALUAil0N WORK SilE.E_T. DOClHOfiAll0N REFERENCES ENVIRONMENT (5ee Attached Sheets) Equipment Description SPECiriCATION QUAllFICAil0N ll 0 PARAMETER CAil0N CATION SYSTEM: Reactor Coolant OPERATING TIME lA 1 Year (Table Q6.4-1) Note T PLANT ID NO.: N/A TEMPERATURE IA Figure 1A (Figure Q6.4-5) Note T COMP 0NFHT: Twinaxial Connectors PRESSURE MANUFACTURER: Amphenol Figure 2A lA (Fig. 14.3.4-8) Note T MODEL NO.: Type 32225 ~~ Twinax Male RELATIVE IlUMIDITY 100% NOTE 2 Note T FUNCTION: Electrical Conductor Connection Il B0 -Na01 3 3 CIIEMICAL ACCURACY: N/A SPRAY Solution lA pil: 7.9-(p. 6.4-15) Note T .10.0 SERVICE: Acoustic Monitor RADIATION R S 1A Signal Cable Connection to Transducers (F'gure Q6.4-4) Note T LOCATION. Containment ' 80' Elevation AGING 40 Years lA (pp.4.1-ll&l3) Note T FLOOD LEVEL FLEV. 14'10" SUBMERGENCE AB0VE ILOOD LEVEL Yes NOTE 1 NO"E - - - ~ ~ ~ - - See attacheil sheet for notes. l l

GN 4 DS ~ I NH U ~ At I U U - U U 4 ~ 1 Ti e e e e e e e-v Sl t t t t t t n .e I o o o o o o o VR U N N N N N N N O ~ N ~ 0 l l A0 C0 l l l fi l E lH A U Q N 0 l l 5 A L C l l h) f [ s i i t l lt e A F e U Eh Q RS Nd ) ) ) ) De Ih N 1 8 4 3 Tc 0 1 Aa l 4 4 4 Tt T i ) 1 E ht A 6 3 2 5 6 1 E tA C Q Q 1 I H I i g A g4 E A - A A1 S i e r l j e l j1 T I e 4 I 1 Ke i O r 4 l K C b R (S N 6 u R E a g g O P T i i p W S ( f p f p ( ( ( ( N0 l i AU L A V E Q T N E T

0. 0 N

N A n-s R O r 2 o9 r n 0S a 1 PM a e 7 1 1D e O O e r XA Y E a C R Y u 0 5R T g 0 o! 4 0 O _ I M V 1 i 1 p 4 N N F 1 E ~ T E S Y E S H l i E E R C g F, U N N 7 I E EY 0 I A R Vi y I G l g T R U I i Y i R t g A E TD A A G E n g R P AI R N M I a g E M E LM P D I I I l g P E R Eti S A P p O T Rl R G U A S ra e s l s 1 r a pm l e c 0 e e c uo t u 3 t s i y k r "0 o N t a u 4 rg cf n 0 n e h 5 a l o e t r a n 1 c n l l h sm ce Ddr o s '4 e or g ue en ea ti i d o o n n ot lE rre nt Y f 1_ e n o o i hI E eeg ea i D a t C i t g l zwh mv t 2 p s s n1 t a ioc ne e l r r e i0 rm rPt il V E t 6 _ e i nd6 r o e W t7 er u aE L V h i i n2 c t n sA ve ssw t E s a l oa - s c n e3

n. h A

spS n E l R W9 .T / eu o '6 _ d P 0 e a I I 5 D e O E 3 N ros C4 L 0 _ e f R N R o Prd E 0 h t T U V 0 G r

t c

YTT n 0DD N T O o N Y a N E l a TI E e 1 && E C N N 0y C Eru 0 L I t I NK m M CC N A g A C eg 1 l t LUC p E T O F L. C e U Vaf A O V II T r R I t e i D E a O i T N TT P U E g I C D u S A M N D w Nn C R ea C O 0 e A q Y L 2 O A D D U E C El e F E S P C M H F A S I S O L l S l 1 L F A

'FACilliY: Point Becch Nuclecr Plant -UNil: 1 and 2 V.-15 Rev* 4 DOCKET: 50-266 and 50-301 SYSTEM COMPONENT EVALUATION WORK SIIE_ET DOCINENTATION REFERENCES EqulPment Description SPECIFl-7 A[ITI_- (See Attached Sheets) ENVIRONMENT QUAliFICAil0N OUISTANDING PARAMETER SPECIFICATION QUAllFICATION METil00 IT[MS _ Call 0N CAT _I_0N_ SYSTEM: F.eactor Coolant OPERATING TIME 1 Year (T ble Q6.4-1) Note U PLANT 10 NO.: 1-tlc &D 2-TIC &D TEMPE2ATURE 1A Figure 1A (Figure Q6.4-5) Note U COMPONENT: Cable Lugs MANUFACTURER: Burndy 10 Figure 2A (Fig. 14.3.4-8) Note U MODEL NO.: "IlYLUG" Type VAV-L RELATIVE iluMIDITY 100% NOTE 2 Note U FUNCTI3N: Electrical Cable Connection CilEMICAL II 80 -Na0ll 3 3 ACCURACY: N/A SPRTY SoTution lA pil: 7.9-(p. 6.4-15) Note U 10.0-0 SERVICE: Pressurizer lleaters 1.4 0 RAD'Til0N l RADS lA _IF_i_qure,_Q6. 4-4 ) , N0le Il - LOCATION: Containment agggg 46' Elevation IA ._41Llears (pp. 4J-llA13)- Note.0 FLOOD LEVIL ELEV..L4 '.10" SUHMERGENCE l ABOVE il000 LtVEL yes NOTE 1

~~

h0"" See attactied slicel for notes.

V.-16 EACILITY: Point Deich Nuclerr Plant UNIT: 1 and 2 N"V-4 IX)CkET: 50-266 and 50-301 SYSTEM COMPONENT EVAL.UAil0N W0 ilk SilEET 00CIRhTATIf)N RETUiThTE5 ENVIRONMENT ~(See Attached Sheets) ^' ^ Equipment Description 5P[CIfi- ~~l)UA[ITI'~ '~SPECIEICAll0N QUAllFICAll0N MElll0D IItMS PARAMETEll _ CATION _ _ CAllott SYSTEM: Reactor Coolant OPERATING TIME i IA 1 Year (Table Q6.4-1) Note S PLANT ID NO.: i 1-TEl-39 2-TEl-39 IEMPERATURE 1A Figure 1A (Figure Q6.4-5) Note S COMPONENT: lhermocouple Fxtension Wire MANUIACTURER: Boston 1A Insulated Wire & Cable Co. Figure 2A (Fig. 14.3.4-8) Note S MODEL NO. : Dostrad7 Thermocoule Extension Wire RELATIVE - (Chronel-Alumel) lilMIDITY 100% NOTE 2 Note S FUNCTION: Electrical Connection of Chronel-Alumel r ference Junction 00) CllEMICAL ll 00 -Na0ll T/Ctuk[kCy* N/A 3 3 SI' RAY Solution lA pil: 7.9-(p. 6.4-15) Note S 10.0- $ERVICE: In-Core RADIAil0N Thermocouples RADS 1A _(Figure 3n.4-41 __ Note S LOCAll0N: Conta innent AGINC' 46' Elevation 40 Years IA _f puA1-11 A13L - Nota _1 rt000 lEVit ELEV. _14'.1_0" SUBMERGINCE None AROVE It000 ' EVEL Yes NOTE 1 See attached sheet for notes.

FACILITY: Point BeIch Nuclear Plant V.-17 UNIT:1 and 2 Rev. 4 DOCKET: 50-266 and 50-301 SYSTEM COMPONENT EVALUAil0N WORK SIkET TiDOMMATIDimilRNIES ENVIRONMENI _1)ll (See Attached Sheets) QUAliflCATION OUISTANDING Equipment Description S I-SPECirtCAil0N QUAllflCAil0N MElll00 ITEMS PARAMETER OPERATI E TIME SYSTEM: Reactor Coolant 1A 288 Sequential 1 Year lYear (Table Q6.4-1) (pp. 2,4,7,88) Test None PLANT 10 NO.: N/A T[MPERATURE 1A 288 Simultaneous Figure IA figure 238 (Figure QC 4-5) (p. 7) Test None COMPONENT: Twinaxial Instrumentation Cable MANUFACTURER: Rockbeslos 1A 28B Simultaneaus Figure 2A figure 23B (Fig.14.3.4-8)' (p. 7) Test None MODEL NO.: "Firewall" RSS-6-112 RELATIVE 280 Simultaneous HUM 10liY 100% 100% NOTE 2 (p. 7) Test None FUNCTION: Electrical Conductor ll380 -Na0H H 80 -Na0ll 3 3 3 CHEMICAL Na2 2 3 1A 28B Simultaneous Solution 50 ACCURACY: N/A SPRAY pil: 7.9-Solution (p. 6.4-15) (p. 7) Test None M 0. __pil t_.L-U 1.45X108 2.0X108 lA 288 Sequential SERVICE: Acoustic "^ "^ 9""" EP' S3',xal Transmission Transducers LOCAil0N: Containment IA 28B Sequential ^6IN6 26' Elevation 40 Years 40 Years (pp. 4.1-11813) (pp.2,3,5, & 7) Test None FLOOD LEVIL ELEV. 14'10" SilBMERGENCE None ABOVE ILOOD LEVEL Yes NOTE 1 See attached sheet for notes,

F ACIL11Y: Point Berch Nucle:r Plant XI.-l UNIT:.1 and 2 pey, 4 00CKET: 50-266 and 50-301 SYSTEM COMPONENT EVALU? MON WORK SilE,El DOClM[WTAll0N REFERENCES ENVIRONMENT (See Attached Sheets) Equiseent Description SPECifl-TADIT' PARAMETER SPECirlCATION QUAllflCATION I CATION CAil0N OPERATING TIME SYSlEM: Sampling 1 Year 1A ( able Q6.4-1) Note Q PLANT 10 NO.: 1-SV955 2-SV955 TEMPERATURE Figure 1A lA (Figure Q6.4-5) Note Q COMPONENT: Solenoid Valves PRESSURE MANUFAClUR[R: ASCO figure 2A I MeQ MODEL No.: LB83146 RELATIVE 100% N0fE 2 llVMIDITY Note Q FUNCTION: Remotely Controllet Air Operated Valve Operatior II 80 -Na0ll CllEMICAL 3 3 1A ACCURACY:N/A Solution (p. 6.4-15) Note Q SPRAY pil: 7.9-III.n t I SERVICE: Reactor Coolant RAnlA110H RADS (Figur Q6.4-4) Note Q llot Leg Sample Valves LOCATION: Containment aggyc 20' Elevation 40 Years (pp. 4. -11&l3) Note Q FLOOD LEVEL ELEV.14'10" SUBMERGENCE None ABOVE ILOOD LEVEL Yes NOTE 1 See attached sheet for notes. se

XI*-2 FACILITY: Point Desch Nucleir Plant Rev. 4 UNIT: 1 DOCKET:50-266 SYSTEM _ COMPONENT EVALUA110N WORK SHE_E_T, 00ClME~NTATION REFERENCES ENV_lR,0NMENT (SeeAttachedSheets) QUAllFICATION OUTSTANDING ' Equipment Description S ~ SPECIFICATION QUALIFICATION METHOD ITEMS PARAMETER OPERATING TIME SYSTEM: Sampling 1A 1 Year (Table Q6.4-1) Note Q PLANT 10 NO.: i 1-SV966C TEMPERATURE e None NOTE 1 , COMPONENT: Solenoid Valve i PRESSURE MANUFACTURER: ASCO NOTE 1 None MODEL NO : LB83146 RELATIVE HUMIDliY 100% 6A FIMCTION: Remotely NOTE 2 Note Q Controlled Air-0perated Valve Opera tion CHEMICAL None NOTE 1 ACCURACY: N/A SPRAY SERVICE: Reactor Coolant flot RADIATION 2.7 X1 Leg Sample Line Isolation DS (Bounde by Valve _S1866AAB) Note Q LOCATION: Auxiliary Building AGING 40 Years lA 8' Elevation (pp.4.1-ll&l3) Note Q Lower Pipeway #1 FLOOD LEEL ELEV. N/A._, SUBMERGENCE ABOVE FLN)0 LEVEL Yes NOTE 1 None J See attached sheet for notes.

GN I DS NM Q Q Q Q AE TT e e e e e e e e SI t n n t n t t n 4 o o o o o o o o I 3 U N N N N N N N N O v I e XR NO I T AD C0 I l Fll I E LH A UQ NO I T S A E C T I h) F Ts I Rt L E e A F e U Eh Q RS Nd l Oe 3 Ih N ) 1 Tc O 1 I Aa y T_ Tt T 4 2 b) 1 E ht A E iA C 6 B 1 AQ AE A - H H I S ie F I 6T eA l1 l e O d6 Ce I l N n6 4 K OS C R D( E b u8 O P a oI p W S T BS p ( ( ( N O ,Fp I TA U L A V E T N E T s N N r O E a 1 r 1 1 1 P M M N a e O O e E E E Y E C R Y T T 0 T R T O O 0 O 0 O I M V 1 N N 1 N 4 N E N S T E S Y E S M I T E E R C U N N E R T EY L 0 E E A VT A l G T I E T R I I Cy i R 3 A G E t M A E TD I N M n A R P AI Mp I a R E M LM Ep D I H l A P E EU l 3 A G U l l P P O T RI C R A S r r e g s e n e l l i e l t c v o d o u l r t l n N a t n i V n a u s r h o l B A e o c n a o d O C o f y f i C e oe y g e i n r 4 t B t o S 6 yv C,i p n A 4 ll a L e g e 1 ea rL i V E e t 1 i 3 tV o e l y E V h n 0 r n lo 8 i A t ev ina L E s i 3 c i x xow E L B ud / cl l o s l S P 0 e p R L ee N apa uie d 25 D m O E Rt n emV At p L D e ao Ra ai F O h R a N vP V O c ri: S n : t S C T U o N e E L a YTT n D6 N I O NetY I 6 E C N O pac E gi Ol r L F t 1I E e I E e t 0rA C et NK m M 9 N A I l I La T w D E a LUC p E T V O F L T - eR O i T N S P U E C r pU V l A* o O V I C D u S A - M N D NiOC R t o C 6L O O e A q Y L 2 O A O U A C E os O L B e l L I A S F E S P C M M F A S lf 4

FACILITY: Point Decch Nuclear Plant XI.-4 tlNIT: I and 2 Rev. 4 DOCKET: 50-266 and 50-301 SYSTEM COMPONENT EVALUAi!0N WORK SilEET DOCINENTATION REFEli[NCIT ENVIR,0_NME NT (SeeAttachedSheets) Equipment Description ~~T)llAEITI_- QUAllflCATION OUISTANDING PARAMU ER SPECiriCAil0N QUALIFICATION METil0D ITEMS OPERATING TIME SYSTEM: Sampling 1 Year IA (Table Q6.4-1) Note Q PLANT ID N0.: 1-SV955 2-SV955 TEMPERATURE Figure 1A 1A COMPONENI: Limit Switches (Figure Q6.4-5) Note Q MANUfAC1URER: NAMCO Figure 2A 1A (Fig. 14.3.4-8) Note Q N0 DEL NO.: " Snap-lock" D2M R ,il 1 00% NOTE 2 Note Q FUNCTION: Valve Position Indication ACCURACY: N/A St, (p. 6. 15) Note Q 4 pil: 7.9-10,0-8 1*45X10 1A SERVICE: Reactor Coolant RADIATION RADS (Figure 46.4-4) Note Q llot Leg Sample Valves L0fATION: Containment A IN i 20' Elevation 40 Years lA (pp.4.1-11813) _ Note _Q FLOOD LEVEL ELEV..14'10" Sill 1 MERGENCE ABOVE fl0001.EVEL Yes NOTE 1 None See attached sheet for notes.

FAClllIV: Point Be:ch Nuclear Plant XI.-5 C:IT: 1 Rev, 4 DOCKET: 50-266 SYSTEM COMPONENT EVALUAllOrt lNNIK SHEET DOCUM('NTATION REFERENCES ENVIRONMENI. (See Attached Sheets) QUALIFICATION OUISTANDING Equilunent Description SPECIFICATION QUALIFICATION MEll 00 liEMS PARAMETER OPERATI E ilME SYSTEM: Sampiing lA 1 Year (Table Q6.4-1) Note Q PLANT ID NO.: 1-SV966C TEMPERATURE ~~~~~~ ~~~~~' ~~~~'~ COMPONENT: Limit Switches PRESSURE MANUFACTURER: NAMC0 None NOTE 1 MODEL NO.: " Snap-Lock" D2400X RELATIVE Il0HIDITY 100% 6A FUNCTION: Valve Position NOTE 2 Note Q Indication ACCURACY: N/A None NOTE 1 6 SERVICE: Reactor Coolant 2.76X10 2A dADIATION llot Leg Sample Line RADS (Bounded by Isolation valve S186_5A&BJ Jote Q 1A LOCAil0N: Auxiliary Building AGING 8' Elevation 40 Years (pp. 4.1-11&l3) Note Q Lower Pipeway #1 FLOOD LEVIL ILEV. N/ L SUI)MERGLNCE A110VE It000 LEVrt Yes NOTE 1 None See attached sheet for notes.

GN I DS NM Q Q Q Q AE TT e e e e e e e 4 SI t n n t n t t 6 T o o o o o o o . v. U N N N N N N N_ O I e XR N O I T A0 C0 H I FT I E LM A UQ N0 l i S A E C C l N) f E s i Rt l E e A F e U Eh Q RS Nd Tt e ih N ) r c O 1 ) Aa I 3 T t T 4 T ) l E Nt A 2 yB E EA C 6 b& 1 H M AQ AE A A A1 I S U e F I 6T 2d6 I C e I e O e6 1 K OS C l N dB R D( E b nI 4 O P a uS W S T o p ( B p N ( ( O I T A U L A ^ V E T N E T N N s O E 6 r r 1 1 1 0 a P M M N a 1 S e O O e E E E XD Y C R Y T T 0 T 6A O O 0 O

7. R 0

I M V 1 N N 1 N 4 E N 2 T E S Y E S I T E E R C F. U N N R E T EY L 0 E T I VT A A l G E T R I I Cy l R t M A E TD A A g E I n A R P Al MR g M I a R E M L i# EP D B g l A P E EL HS A g U P P O T RH C R 3 S r: g e s n s l e e i c t u h d o N c n t l n C t o n i Ls t 6 i k i a u r d n 6 w c t l B o a o 9 S o i n oe / e f e i V O lX so on y 4 f Y j B t S t C - 0 oi Ci r t M p0 Pt L a 1 p g i L e n 2 m A a4 a r e i y V E e t 0 i s 3 r i i N n2 ec oev l na E V h l c l L SD vi A tl l iow L E s o 0 s p l d / cpa xie E L R an N amV ut p d P25 e m D a O E Vi ea Aai L D e S N R RS n vP E O h t T U e V O c o YTT n D N T O N Y gi Nl r E L a TI E e I E C N O C Eet OE e L F t NK m M N A I A CL a I w t I LUC p E T O F L T R I l T o D E a i T N P U E C U Vt o A '8 L O V I O C D u S A M N D N C Ros C O O e A q Y L O A O U C El O L B e F E S P C M M F A S I i L F A S

1' XII.-1 FACILITY: ' Point Be :ch Nuclear Plant Rev. 4 UNIT: I and 2 DOCKET: 56-266 and 50-301 SYSTEM COM_PONENT EVALUATION WORK SilEET DUCUM[~IATIWN REFERENCES N Equipnent Description SP ~~T)U l _ (See Attached Sheets) ENVIRONMENT QUAliflCATION OUTSTANDING PARMTER SPECIFICATION QUALIFICATION HElll00 ITEMS 08 OPERATING TIME lA 168 Engineering None SYSIEM: Generic 1 Year 1 Year (Table Q6.4-1) (pp. 383, 398, 6 Analysis 401) PLANT ID NO.* N/A TEMPERAlllRE Note 1 None COMPONENT : Grease PRESSURE None MANUFACTURER: Americar. Oil Note 1 MODEL NO.: Amo11th #2 6A 206 RIlATIVE MMIDITY 100% 100% Note 2 16B None ' ~ IllNCil0N: Motor Bearing (PP. 383, 398, & Lubricant 10lb None i CllEMICAL Note 1 ACCURACY: N/A SPRAY

1. Engineerlin; 7

2 200 SERVICE: Various Pump Motors 6.56 X 106 1.0X10 6B Analysis fione RADIATION

2. Separate Rads Rads (EE. 383 398 401i&

NCliSSli 1A 200 Engineering AGING 40 Years 1 Year (pp. 4.1-11&l3) 6B Analysis g[,g) side Containnent 401) - None SUBHERGENCE Note 1 FLOOD LEVEL ELEV..N/A_ AB0VE ft00D LEVEL Yes See attached sheet for notes.

XII.-2. EACILITY: Point fle:ch Nuclear Plant R:v. 4 UNIT: I and 2 SYSTEM COMPONENT EVALUATION WORK SilEET DOCKET: 50-266 and 50-301 ^ DOCUKfMTKIIDil REFEREllCES ENVIRONMENT (See Attached Sheets) ^ 'C^ i Equipment Description SP ~ U PARWER SPECIFICAT IM Mll'ICATim lM 5 SYSTEM: Generic 1 Year j year lA 208 OPERATING TIME ( able 06.4-1) 168 Engineering None (pp. 383, 396, 8 Analysis PLANT 10 NO.: N/A TEMPERATURE Figure 4A Figure IB (Vol. , p. D-10 i None COMPONENT: Grease (Section 14.2.5 1

2. Engineerls"lNote11)

Analysis, Simu an 5 MANilfACIURER: American Oil NN Mgum 2A Num 2 (Fig. 4.3.4-8) (Vol. , p. D-10 l None t MODEL NO.: Amolith #IEP Simultaneous RELATIVE 100% 100% 6A IB Test None IlUMIDITY N01E 2 (Vol I* P D-1 FUNCTION: Valve Motor 168 Operator Lubricant fo ut" 'i B0 -Na0H 1A B

1. Simultanemshone CllEMICAL 3 3 ACCURACY: N/A Solution (p. 6.4-15)

(Vol. I, pp. D-8 Test SPRAY gg 79 pil: 7.85 & D-10)

2. Engineeririg Ib.0 Analysis _

I SERVICE: Valve Motor 2.30 x 106 1.0X10 1A 200 Sequential None Operators and Limit Switch Rads Ra s (Fig. Q6.4-4) 16B (p. 2) Test RADI ATIM 2X10 Rads Assemblies 40 Years 1 Year lA Engineering None LOCATION: AGIN(; Analysis (Note M) i a d Outside (pp. 4.1-11&l3) (pp. 383, ILOOD 1.EVEL ELEV. 14'10" SUBMERGENCE Note 1 None. l (Containment) i ABOVE FLOOD LEVEL YES l See attached sheet for i:otes.

XII.-3 FACILITY: Point Heath Nuclear plant Rev. 4 Utd i: I and 2 DOCKET: 50-266 and 50-301 SYSTEM COMPONENT EVALUATION WORK SilEET 000tMDiIhllDiWFETtDeM ENVIRONMENT (See Attached Sheets) QtlALIrlCAll0N OlliSTANDING SPECIFI-QdA C M _- Etluilunent Description PARAMETER SPEClflCA110N QUAllFICAll0N Hell 100 11 EMS i CATION CATION ear SYSIEM: Generic OP[RAllNG TIME 1 Year Engineering .None (Tabl Q6.4-1) Analysis (pp. 383, 398, & PLANT ID No.: N/A I* IEMPIRATURE figure 4A Figure 18 3A IB T Hone 1A (Vol. I, p. D-lo t2. "9'" (Note 11) COMP 0NERi: Grease (Section 14.2.5 n1s IB Sinus an "5 PRESSURE Figure 2A Figure 2B (Fig. .3.4-8) (V 1. I, p. D-10 l None HANUfACTURER: Mobil Oil ,t MODEL NO.:

28 6A IO S I'""I 8"' "5 RELATIVE 100%

100% Note 2 None IlUMIDITY (Vol. I, p. 0-1) Test IUNCil0N: Motor Operated 16B Valve, Geared Limit Switches (p:--15) 1 80 -NaOH ll 80 -Na0H IB I. Simultanews Lubricant CllEMICAL 3 3 3 2 1A None Solution SoTution (V 1. I, pp. D-8 Test ACCllRACY: N/A 3ppgy (p 6*4-15) & 10)

2. Engineerlin)

>ll: 7.9-pH: 7.85 10A._. Analysis. 9 2.30 X 106 3.0X10 1A Separate 2IU SERVICE: Motor Operated RADIATION Rads Rads (fig. Q6.4-4) Effects Tests Valve Motors LOCAll0N: AGING 40 Years 1 Year IA Engineering Hone inside and Outside (pp. 4.1-11&I3) Anahsis (Note ".)~~ (pp. 383, 398, a Containment 401)~ ~~ None f LOOD LEVEL It EV }_4,' j oa SURMERGENCE Note 1 A110VE ILOOD IEVE See altar. heel sheet for notes.

IACilliY: Point fletch Nuclear Plant XII.-4 t) Nil: 1&2 Rev 4 00CKET: 50-266 & 50-301 SYSTEM _ COMPONENT EVALUATION WORK SilE_ET ~ ~ DOCHNTATMWrtRhTB - ~ - - ENVIRONMENT (See Attached Sheets) QUAllFICAil0N OUISTANDING Equilmient Description ~ SPECIEICAil0N QUAliflCAil0N MElll00 II[MS PARAMETER 208 OPERATING TIME Engineering SYSTEM: Generic 1 Year 1 Year IA 16B Analysis None (Table Q6.4-1) (pp. 383, 398, & 401) PLANI ID NO.: N/A TEMPERATURE Note 1 None -""~" ~~"~"" COMPON[NT: 011 MANUFACillRER: Anerican Oil Note 1 " " ~ ~ ~ ~ ~ ~ ~ ~ None MODEL NO.: Rykon Industrial 200 Engineering N ""

15 RELAi!VE 100%

100% 6A 168 Analysis HilHI0liY NOTE 2 (pp. 383, 398, & TUNCil0NPtg and Motor 401) Bearing Lubricant I - ~ ~ ~ " None ACCURACY: N/A Note 1 y,

1. Engineerin i 7

6.27 X 106 1.0 X 10 2A Analysis None SERVICE: Various Pumps RA0lAil0N And Motors Rads Rads

2. Separate (pp. 383, 398, &

fccLs.Te.ts 401) Engineering None 1 Year 1 Year IA Analysis (Note M) i iOCATION: AGING Outside Containnent

Table Q6.4-1)

None lLOOD I EVI L [l EV. H/A._, SUBMERGENCE Note 1 A110VE El000 ElVEL yes See altar.hmt sheet for notes. I

TACillTY: Point Beach Nuclear Plant XII.-5 UNil: 1 and 2 Rev. 4 (X)CKE T : 50-266 and 50-301 SYSTEM COH_PONENT EVALUATION WORK E,iEET i ~ ~ DOClMfNTATlDFkTTElifNCES ~ ~ Equipment Descriptinn E _ (SeeAttachedSheets) ENVIR0N, MENT QUALIFICATION OUISTANDING PARAMETER ~ SPECIFICATION QUALIFICATION HElll0D ITEMS g Simultanct us OPERATING TIME 1 Year lA 22B Test .None SYSTEM: Generic 1 Year (Table Q6.4-1) (Note B)

2. Engineerir g Analysis

-PLANT ID NO.: N/A ILMPERA10RE Figure 1A figure 16B 1A 228 Simultaneous None (Figure Q6.4-5) (Note B) Test COMPONENT: 600 Volt AC Power Cable PRESSURE lA Simultaneous None MANUFACIURER: Kerite figure 2A figure 178 (Figure 14.3.4-3) 22B Test (Note B) H00EL No. : 600 V. IITK-Insulated, FR-Jacketed RELATIVE 100% 100% Note 2 22B Simultaneous None . Power Cable IIUMID11Y (Note B) Test f0NC110N: Electrical Conductor B0 -Na0li 1180 -Na0ll llbolution $oltltion lA 22B Simultaneous None CUI"I Al ACCURACY: N/A SPRAY pil: 7.9-(p. 6.4-15) (Note B) Test 10.0 SERVICE: 480 V Electrical 1.45 x 2.0X108 1A 22B Sequential None RADIATION Power Distribution 108 Rads Rads (Fig. Q6.4-4) (Note B) Test IOCATION: A ING 40 Years 40 Years IA 22B Sequential None Containment Above 16' Elevation II'P _4 l-Il&l3) (Note B) Test None It 000 LEVil ELEV.14' 10" SUBHERGENCE Note 1 ~~-- ABOVE Il00ll LEVIL YES See attached sheet for notes.

XII.-6 i FACIlliY: Point Ileech Nuclear Plant Rev. 4 UNil: I and 2 l IX)CKE T: 50-266 and 50-301 SYSTEM COMPONENT EVALUATION WORK SilEET ~ DOCtMhTATI~0N MIElIEWCE3 ENVIRONMENT (SeeAttachedSheets) QUAllflCATION OllISTANDING 4 Equipment Description SPECIflCAil0N QUALIFICATION ' METHOD IIEMS PARAPITER g I

1. Simultanemis SYSTEM: Generic OPERATING TIME 1 Year 1 Year IA 228 Test None I

(Table Q6.4-1) (Note B)

2. Engineertruj Analysis PLANT ID NO.:

N/A TEMPERATURE fi ure 4A Figure 16B 3A 22B Simultaneous None g l COMPONENT: (Section 14.2.5 600 Volt AC Power Cable PRESSURE ffgdre 7A Figure 178 3A 228 Simultaneous None MANUFACTURER: Kerite (Note 2) 1A (Note B) Test (Section 14.2.5 i MODEL NO : 600 V. IliK-4 Insulated, FR-Jacketed RELATIVE 1001 100% 6A 22B Simultaneous None Power Cable litt11DliY N01E 2 (Note B) Test i IUNCTION: Electrical Conductor i None ACCURACY: N/A Note 1 1 8 6 2.0X10 2A 22B Sequential Hone 6.56 X 10 SERVICE: 489 V Flectrical RADIATION Power Distribution Rads Rads (Note 2) (Note B) Test IA 22B Sequential Nor-LOCATION. Outside" Containment AGING 40 Years 40 Years (pp. 4.1-11A13) (Note B) Test None I 4 l FLOOD LEVEL ELEV. N/A SUBHERGENCE Note 1 l ABOVE FLOOD LEVEL Yes See attachml sheet for notes.

FACilliY: Point Be:ch Nuclear Plant. XII. 7 UNIT: I and 2 Rev. 4 DOCKET: 50-266 and 50-301 SYSTEM COMPONENT EVALUATION WOf(K SilEET DUCIMRTATIDRTfRTtDittS ENVIRONMENT __(SeeAttachedSheets) ()UAliflCATION OUISTANDING Equignent Description S ~ SPECiflCATION QUAllflCATION HElll00 ITEMS PARAMETER

1. Simultaneous

" "^ SYSTEH: Generic 1 Year 1 Year (Tabl Q6.4-1) 2. neerito} (N e B) Analysis PLANT ID NO : N/A TEMPERAIURE Figure 1A Figure 180 1A 22B Simultaneous None (Figure Q6.4-5) (Note B) Test COMPONENT: 600 Volt Control Cable PRESSURE 1A HANUFACillRER: Kerite Figure 2A Figure 190 (Figure 14.3.4-1) 228 Simultaneous . Ilone (Note B) Test H0 DEL NO.: 600 V. FR- ~~~ Insulated, FR-Jacketed RELATIVE Control Cable lillHIDI TY 100% 100% Note 2 22B Simultaneous tione I EUNCTION: Electrical (Note B) Test Conductor il380 -Na0ll 11 80 -Na0li 22B Simultaneous 3 ClhEHCAL solution holdtion (Note B) Test flor > > ACCURACY: N/A (p. 6 -15) pil: 7.9-10.0 1 0 SERVICE: Electrical Control 1.45 x 1.75 x 10 1A 22B Sequential None RADIATION Distribution 108 Rads Rads (Fig. Q6.4-4) (Note B) Test t 1.0 CAT 10N: IA AGING 40 Years 40 Years 228 Sequential None Containment (PP. 4.1-11&l3) (Note B) Test Above 16' Elevation FLOOD l EVEL ELEV.13'10" SUBMERGENCE Note 1 ABOVE ILOOD LEVEL YES See attacheti sheet for notes. i I

XII.-8 FACILITY: Point Beach Nuclear Plant Rev. 4 UNIT: I and 2 DOCKEI: 50-266 and 50-301 SYSTEM COMPONENT EVALUATION WORK SHEEI DOCIMOiTATION REFERENCl3 JS_eeAttachedSheets) ENVIRONMENT e_ Equipnent Description SPECifl-7 AUlT-PARAMETER SPECirlCATION OUALIFICATION 101) CATION CATION

1. Simultanet:us SYSTEM: Generic OPERATING TIME 1 Year 1 Year lA 228 Test (TableQ6.4-1)

(Note B)

2. Engineerimj None PLANT ID NO.: N/A TEMPERATURE Figure 4A Figure 18H 3A 228 Simultaneous None (Note 2)

'lA (Note B) Test Note il COMPONENT:. 600 Volt Control (Section 14.2.5 I Cable PRESSURE Figure 7A Figure 19E 3A 228 Simultaneous MANUFACTURER: Kerite (Note 2) lA (Note B) Test fge g (Section 14.2.5 i H0 DEL NO. : 600 V. FR-6A Insulated, FR-Jacketed RELATIVE 22B Simultaneous Control Cable llHMIDITY 100% 100% Note 2 (Note B) Test Hone IUNCTION: Electrical Conductor Sgh k Note 1 ACCURACY: N/A SERVIEE: Electrical Control RADIATION Rads Rads (Note 2) (Note B) Test Distribution LOCAIION: AGING 40 Years 40 Years IA 228 Sequential None Outside Containment (pp. 4.1-11813) (Note B) Test U "E FLOOD LEVEL ELEV. N/A SUBMERGENCE Note 1 [ ABOVE. FLOOD LEVEL Yes l See attached sheet for notes. I

FACILITY: Point Be:ch Nuclear Plant XII.-9 N#V-4 UNIT: I and 2 IX)CKET : 50-266 and 50-301 SYSTEM COM_P()NENT EVALU_ Ail 0N WORK SilEET ~~ ~~lRIMCMTATIDH TMERETCE5 ~~ ~ ~ ~ ~ ~ ~ ~ ENVI_RONMENT _(See Attached Sheets) Equipment Description b ~ F QUAllIICATION OUISTANulNG PARAMCIER SPECIflCAil0N QUAliflCAll0N METil0D IIEMS

l. Simultaneous PERATING T W.

SYSIEM: Generic 1 Year 1 Year (Tabl Q6.4-1) (Tabl I)

2. E neering None

^"' DS I S (p. B B-6) PLANT ID NO.: N/A TEMPERATURE Note I flone COMPONENI: 5,000 Volt AC Power Cable None MANUIACTURER: Okonite MODEL NO. : Okonex - Insulated 100% N "" Okoprene Jacketed 5 KV Power RELATIVE 100% Note 2 246 s Cable litetiplIV (Table IX) 2. rinq FUNCTION: Electrical Conductor CI Al None ACCURACY: N/A Note 1 -- - ~ 131isiillaneous 6 6 24B 3.31 X 10 5.0X10 73 Test None SERVICE: 4160 V. Electrical RADIAIION Rads Rads (Table XI)

2. Engineerinq Power Distribution 268 Analysis

( Fi g:-0 A 5 )- j gj;;;uitaneous 24B Test i LOCAll0N: lA Outside Containment (pp. 4.1-llA13) (Table II)

2. Engineerinq None i

A ING 40 Years 40 Years - ( p-- 3: n:6) - None Note 1 FLOOD LEVil ELEV. N/A SilBMfitGENCE AHOVE FLOOD LEVEL Yes See attached sheet for notes.

FACILITY: Point Beach Nuclear Plant Xil.10 Rrv. 4 UNIT: 1 and 2 DOCKET: 50-266 and 50-301 S_YSTEM COMPONENT EVALUATION WORK SilEET ll DOCUW NTAil0N REFEREhlES EllVIRONMENT (See Attached Sheets) QUALIFICATION OUTSTANDING Equi ment Description b I - SPECIFICATION QUALIFICATION HElll0D 11 EMS l PARAMETER 25B

1. Simultaneo as

^ SYSTEM: Generic OPERATING TIME 1 Year 1 Year ^ 9"I* (Tabl Q6 4-1) 24B

2. Engineerin.:

(Table II) Analysis PLANT ID NO.: gjg IA TEMPERATUPE Figure 1A Figure 21l l 258 Simultaneous (Figure Q6.4-5) (Figure 1) Test None COMPONENT: Instrumentation Cable PRESSURE j MANUFACTURER: Okonite Figure 2A Figure 21ll (Figur 14.3.4-3)(Figu 1) t None MODEL NO. Okotherm -insulatetl Okoseal-Jacketed, Twisted, RELAllVE 25B Simultaneous Shielded Pair llUMID11Y 100% 100% Note 2 (Figure 1) Test None FUNCTION: Electrical Conductor 3 , NA0l l 25B Simultaneous ll[0-Na0HHg8 CllEMICAL jg (pp. 3-1, 3-3) Test None . ACCURACY: N/A SPRAY y(p. 6.4-15) pH pH-10.0____ 8_ 2.0 X 10

1. Simultaneo is est None SERVICE: Instrumentation RADIATION R$

Rads (Fig. Q6.4-4) 4 $bl )

2. Engineerin j Signal Distribution

-__ Analysis.__ ja 25B (p. 1-1)

1. Sequential

^' AGING 40 Years 40 Years (pp. 4.1-11&l3) 24 b ) s None C ntai nt Above 15 Elevation -Analysis-FLOOD LEVEL ELEV. 14'10" SUBMERGENCE Note 1 None AB0VE FLOOD LEVEL YES See attached sheet for notes.

XII.-Il FACILITY: Point Beach Nuclear Plant Rev. 4 UNII: I and 2 DOCKET: 50-266 and 50-301 SYSTEM COMPONENT EVALUATION WORK SilEET 00CtHiliiAIRTN REFERENCES ~- ENV!'t0NMENT (See Attached Sheets) QUAliflCATION OUISTANDING Equirment Description SP SPECirlCATION QUALIFICATION HE1H00 IIEMS PARAMETER ON 25B

1. Simultaneous SYSTEM: Generic OPERATING TIME 1 Year 1 Year (Tabl Q6.4-1)

(Figure 1) Test None l 24B

2. Engineerino (Table 11)

Analysis a PLANT ID NO.: N/A TEMPERATURE Figure 4A Figure 211 3A 25B Simultaneous ~A (Figure 1) Test None (Note 2) 1 COMPONENT: Instrumentation (Section 14.2.5 i Cable N ue 9um 3A 25B Mmuhaneous MANUFACTURER: Okonite (Note 2) 1A (Figure 1) Test Hone (Section 14.2.5 1 MODEL NO. : Okotherm-Insulated ~ ~~ 6A Okoseal-Jacketed. Twisted RELAllVE 100% MO% 25B Simultaneous NOTE 2 Shielded Pair HUMID 11Y (Figure 1) Test None i FUNCTION: Electrical Conductor A Note 1 ACCURACY: N/A g{ Hone 258

1. Simultaneous 6

8 StRVICE: Instrumentation 6.56X10 2.10X10 2A (p. 1-1) Test None RAD A ON Signal Distribution Pads Rads 24B

2. Engineerinq

__(Tahle__l) _ Analysis _ 25B (p. 1-1)

1. Sequential AGING 40 Years 40 Years IA 24B (Table II)

Test Hone LOCATION: Outside Containment (pp. 4.1-11&l3) 26B (p. B-11)

2. Engineering Analysi w FLOOD LEVEL ELEV. N/A SUBMERGENCE Note 1 flone ABOVE FLOOD LEVEL Yes See attached sheet for notes.

XII*'I2 FACILITY: Point Beach Nuclear Plant UNIT: 1 and 2 DOCKET: 50-266 and 50-301 SYSTEM COMll0NENT EVALUATION WORK S_IIEET l l DOCIEMIXTl0N REFERENCE 3 l Equi mient Description SP C Qil (See Attached Sheets) ENVIRONMENT QUAliflCATION OUISTANDING l PARAMETER SPECiflCATION QUAliflCATION MElll00 ITEMS SYSTEM: Generic 1 Year 1 Year In 14B Engineering OMRATM UK (Table Q6.4-1) ISB Analysis None PLANT III NO.: N/A TEMPERATURE figure 1A figure lA 14B Simultaneous 148 (Fig. Q6.4-5) (pp. 13 & 15) Test ' COMPONENT: Instrumentation None Cable gure 2A Mgure M MANUFACTilRER: Boston (Fig. 14.3.4-8) 148 Simultaneous r insulated Wire & Cable 14B (pp. 13 & 15) Test None 7 MODEL No. : Bostrad Twisted, Shielded Pair RELATIVE 100% 100% Note 2 14B Simultaneous lillHIDl1Y (pp. 13 & 15) Test None FUNCIl0N: Electrical Conductor 1 B0 -Na0ll 11 80 -Na0H 3 3 3 S$1utio' ISB Simultaneous CHEMICAL Solution ACCURACY: N/A SPRAY pH: 7.9-pH: 9.0-(p. 1) Test None (Ii* 6* -15) 16.0 10.0 SIRVICE: Instrumentation 1.45 x 108 1.50 X 108 1A ISB Sequential RADIAM ON Signal Distribution Rads Rads (Fig. Q6.4-4) (p. 16) Test ~~

1. Sequential lA 14B Test LOCATION:

AGING 40 Years 40 Years sPP. 4.1-U &l3) (pp. 1 8 8 ) 2. Engineerint Containment h alysis___ Jone__ _ Above 15' Elevation FLOOD t EVE L ELEV. ]_41]0a SUlWiERGENCE Note 1 ABOVE FLOOD LEVll YES See attached sheet for notes.

FACILITY: Point BeIch Nuclear Plant XII.-13 R:v. 4 UNil: 1 and 2 DOCKET: 50-266 and 50-301 SYSTEM COMPONENT EVALUAil0N WORK SHEET ~ ~ ~ DOClNENTATI6N RfERRl3 ENVIRONMENT (SeeAttachedSheets) QUAliflCAil0N OUI 51rL0 LNG Equipment Description S F,_ PARAMETER SPECIflCATION QUAliflCAil0N HETH00 lith 5 148 Engineering OPERAI N I M ^ SYSTEM: Generic i Year 1 Year ^" YS'S (Tabl Q6.4-1) PLANT ID NO.: N/A TEMPERATURE figure 4A Figure 3A 148 (Note 2) 14B 1A (pp.13 & 15) Simultaneous None Test COMPONEHT: Ins trimnentation (Section 14.2.5 Cable PRESSURE Figure 7A Figure 3A 14B HANUFACTURER: Bos ton (Note 2) 148 1A (pp. 13 & 15) Simultaneous None Insulated Wire & C ble (Section 14.2.5 Test H0 DEL NO. : Bostrad 6A Twisted, Shielded RELATIVE 100% 100% Note 2 14B None Pair lHP11DITY (pp. 13 & 15) Simultaneous FUNCTION: Electrical Test Conductor CAL yote j ___~ ACCURACY: N/A None SERVICE: Ins trianentation 6.9 x 104 1.5 X 108 2A ISB Sequential RADIAll0N Signal Distribution Rads Rads (Note 2) (p. 16) Test None 5.56 X 106 1 Sequent.ial B A ING 40 Years 40 year, (pp. 1-11&l3) (p y g g) ). E g neering Outside Containment _ Analysis __ None Note 1 N/A SUBHERGENCE fl000 LEVEL El.EV. AROVE ft000 LEV [l Yes See attached sheet for notes.

FACilliY: Point Bxch Nuclear Plant XII.-14 UNII: I and 2 DOCKET: 50-266 and 50-301 SYSTEM COMPONENT EVALUATION WORK SilEET Rev. 4 RRlWNTATIDN REFEltTFCES ENVIRONMENT (See Attached Sheets) WA ATION OUIS1AND N. Equipment Description SPECift-7 1Al V l7 PARAMETER SPECiflCATION QUALIFICATION MElll00 ITLMS Call 0N CATION 23B SYSTEM: Generic l Year 4 Months jg (p. 4 of April Engineering OPERAT W TW (Table Q6.4-1) 9 letter) Analysis Note 0 248 (Table II) PLANI ID NO.: N/A 268-(p r B= 11 )- TEMPERATURE Figure 1A Finure 208 1A 23B (Fig. Q6.4-5) (p.1 of Mar.19 Simultaneous None Letter) Test COMPONENT: 600 Volt Control Cable 23B Simultaneous PRESSURE Figure 2A Figure 208 jg MANUFACTURER: Rome (Fig. 14.3.0-8) (P.1 of Mar.15 Test None letter) M0()EL NO.: 600 Volt Control 23B lit i 1001 100% Note 2 (P of Mar.19 Simu taneous None FUNCll0N: Electrical /4B (Table IX) Conductor ll 80 -Na0ll H B0 -Na0ll 3 ACCURACY: N/A olution dol $ tion 17B Engineering None CIIEMIC^l SIRAY (P* 6* -15) (Tab e 5.4) Analysis pH:7.9-pH: 7.9 - 10.0 10.0 8 24B

1. Separate E fects SERVICE: Electrical Control 1.45 x 108 1.0 X10 14 (Table IV,V, Vill Test tiote 0 RADIATION

[)istribution Rads Rads (Fig. Q6.4-4) IX,&XI)

2. Engineerin.

23R Analysis--. lA (p.20f Apr.9 letl er) 10 Call 0N: 40 Years 40 Years (pp. 4.1-11813) 248 (Table II) Engineering None AGING Contairanen t 238 Analysis Above 15' Elevation (p.4cf Apr,9 letl er) 268 (p. B-ll) Note 1 FLOUI) LEVEL EL EV.14'ly' SUllMERGENCE A110VE FLOOD LEVEL YES See attached sheet Inr notes. i

Point Beach Nuclear Plant XII.-15 FACillTY: - 1 End 2 Rev. 4 UNIT: DOCKET: 50-266 and 50-301 'S_YSTEM COMP 0t!ENT_ EVALUATION WORK SilEET ~ DOClHiHIATIWN REITRtWCtS ENVIRONMENT _ (See Attached Sheets) QllAliflCAll0N OtllSTANDING I Equipment Description b ~ )i PAR R IER SPECll'ICAll0N QUAllrICATION MElll0D ITEMS g ^ (Tabl Q6.4-1) (p.40f r.19 let ter) SYSIEM: Generic 1 Year 1 Year 24B Engineering None t (Table II) Analysis PLANT ID No.: N/A 260_(pmBdll__ mul ane os TEMPERATURE Figure 4A figure 208 3A 23B Test None (Note 2) 1A 'pi.lof Mar.19

2. Engineerini (Note 11)

COMPONENT: 600 Volt t.ontrol (Ser ton 14.2.5 letter) A N NI-Cable gure M M9We 2% 3A 23B PRESSURE MANUF Ar.iURER: Rome (Note 2) 1A (p.lof Mar.19 Simultaneous Hone (Section 14.2.5 ) letter) Test MODEL NO.: 600 Volt Control 6A Cable RELATIVE 100% 100% Note 2 238 Simultaneous None lit #ilDITY (p.lof Har.19 Test IUNCTION: Electrical letter) Conductor CIl Al Note 1 ACCURACY: N/A g 6 7 248

1. Separate SERVICE: Electrical Control 6.5 x 10 1.0 x 10 2A Effects hone Distribution Rads Rads (Note 2)

(Tables IV,V,VII I' Test RADIATION 238 2_Ingincer_inq________ Analysis IA (p.20f Apr.9 lett e )gineering n Hone AGING 40 Years 40 Years (pp,4,j.jjgg3) 24B LOCAil0N: Outside Containment (Table II) Analysis 238 (p.40f Apr.9 letter) Hone 268 (p. B-11) Note 1 l FLOOD LEVEL ELEV. N/A SUBMERGENCE l AHOVE ILOOD LEVEL yes i See attached sheet for notes. i

. FACILITY: Point Beach Nuclear Plant XII.-16 UNIT: I and 2 Rsv. 4 - --.--.M COMP.ONENT EVALUATION _ WORK SilEET SYSIE . DOCKET: 50-266 and 50-301 ~ DDUWNTATIWRUIRECB ENVIRONMENT. (See Attached Sheets) QUAllflCAil0N OUISTANDING Equienent Description SP T __ _ _SPEClflCATIONQllAllFICAll0N MElll00 ITEMS l 'ARMTER 1.Simultaneou< SYSTEM: Generic OPERATING TIME 1 Year 1 Year Test (Table .4-1) (Vol. , p. None . Engineering 6-14 & Table 14) Analysis 11B PLANT 10 NO.: N/A itMPERAIURE Figure 1A Figure 108 ""Il'"* "5 (Fig. .4-5) (Vol. None Table 10) l COMPONINT: Electrical Cable Splice 11R 1A 18 altaneous PRESSURE Figure 2A Figure 118 (Fig. 14.3.4-8) (Vol. II, None MANUFACTURER: Bechtel/Raychen g Table 10) 11R MODEL NO.: Bechtel Dwg. SK-E-165 RELATIVE 1001 1001 Note 2 IB Simultaneous None HUMluirY (Vol. II, Table Test FUNCil0N: Electrical Cable 10) Connection 'H B0 -Na0H ,13B0 -Na0H ' ~ 3 3 1A IB I.Simultaneou< ACCURACY: N/A sh (p. 6.4-15) (Vol. II, p. Test None pH 6-6)

2. Engineering 10.0 118

_ Analysis SERVICE: Various RADIATION Ra Rads (Fig. 6.4-4) (Vol. , p. None f et 6-3)ggg LOCAil0N: 40 Years 40 Years IA 1B (pp. 4.1-11&I3) (Vol. II, p. Sequential None Containment 6-3)iig5__ Test Above 15' Elevation None FLOOD LEVEL LI EV.14'10" SullMERGENCE Note 1 i AHOVE FLOOD LEVEL YES See attached sheet for notes. I

FACillTY: Point Beach Nuclear Plant ygg,,g7 UNIT: I and 2 pey* 4 (X)CKE T : 50-266 and 50-301 SYSTEM COMPONENT EVALUATION WORK SilEET DOCthENTATIWRTEMhCES ENVIRONMENT (See Attached Sheets) Equilment Description SPECIFICAll0N QUAllFICATION IN50 5 PARAMETER OPERAT Wi T M 1 Year 1 Year SYSTEM: Generic (Tabl Q6.4-1) (Atta W nt 2, s None Figure 2)

2. Engineering Analysis PLANT ID NO.: N/A itMPERATURE Fig, lA Fig. 88 1A 58 Simultaneous (Fig Q6.4-5)

(Attachment 2, Test None COMPONENT: Electrical Figure 2) Penetration Assembly l'RESSURE Fig. 2A Fig. 9B (Fig. 4.3.4-8) (Atta W nt 2, Simultaneous None MANUFACTURER: Crouse Ilinds/ Westinghouse Figure 2) Test MODEL NO.: Welded Canister Type RL I 100% 1001 Note 2 (Atta ment 2 Simultaneous None figure 2) Test FUNCTION: Containment Electrical Cable Penetration 13B0 - NaOH ll3003-Na0ll 1A 6B

1. Sequential CilEMICAL 3

ACCURACY: N/A SPRAY Solution Solution (p. 6.4-15) (Attachment 1) Test None all: 7.9-pil: 8.5

2. Engineering 10.0 -

-- Analysis-- 8 5B SERVICE: Various 1.45 x 108 2.00 X 10 1A 22B

1. Sequential None RADIATION Rads Rads (Fig. Q6.4-4)

(Note B) Analysis 25B

2. Engineerin's 5B INIlhNlai

~ LOCAll0N: IA 22B Test Hone A I N(,. Containment 40 Years 40 Years (pp. 4.1-11813) (Note B)

2. Engineerin-i Above 16' Elevation 25B

___ Analysis __ FLOOD LEVEL ELEV.14'10" SilBMERGENCE Note 1 None AB0VE FLOOD LEVEL YES ^ See attached sheet for notes.

a 4 _m..3-a-n --a _.m__. Am, _2 _,m --a_ a --a ._4 .___J -- 4sa e m_ E A A.eam-mE-- _.A _m-, I i 4 t ENCLOSURE 3 f I l g... ..m..

=. Page 1 of 3 Rev. 4 ENCLOSURE 3 SPECIFICATION FIGURES 1A. Calculated Containment Temperature Transient (PBNP FFDSAR, Figure Q6.4-5) 2A. Containment Pressure Transient (PSNP FFDSM, Figure 14.3.4-8) 3A. Integrated Ganum Dose Level Inside Containment as a Function of Time After Release (PBNP FFDSAR, Figure Q6.4-4) 4A. Maximum Temperature Transient for Boric Acid Storage Tank Level Transmitters and AFW Pump Turbine Steam Supply Motor-Operated Valves from a 3" Auxiliary Steam Line Rupture. SA. Maximum Pressure Transient For Boric Acid Storage Tank Level Transmitters and AFW Pump Turbine Steam Supply Motor-Operated Valves From a 3" Auxiliary Steam Line Rupture. 6A. Maximum Temperature Transient at the Steam Line Pressure Transmitters in the Auxiliary Building Fan Rooms From a 30" Main Steam Line Ruptu re. 7A. Maximum Pressure Transient at the Steam Line Pressure Transmitters in the Auxiliary Building Fan Rooms From a 30" Main Steam Line Rupture. 8A. Maximum Temperature Transient at the Condensate Storage Tank Level Transmitters From a 24" Main Steam Line Rupture. 9A. Maximum Pressure Transient for Condensate Storage Tank Level Transmitters From a 24" Main Steam Line Rupture.

Page 2 of 3 Rev. 4 OVALIFICATION FIGURES 1B. Temperature Test Environment - Limitorque Valve Motor Operator With Class B Insulation (WCAP 7410-L, Volume I, Appendix 0, Figure 3) 2B Schedule of Test Environments - Saturated Steam Pressure Cycle and Limitorque Operation Cycle (WCAP 7410-L Volume I. Appendix D. Figure 3) 3B. Environmental Test Curves - Containment Fan Motor Insulation (WCAP 9003, Page 14 Figure 6) 4B. Temperature Test Environment - Foxboro Transmitters Models 611GH, 611GM, 613HM (WCAP 7410-L Volume I, Appendix A, Tables 2 & 4) SB. Pressure Test Environment - Foxboro Transmitters Models 611GH, 611GM, 613HM (WCAP 7410-L, Volume I, Appendix A, Tables 2 & 4) 6B. Temperature Test Environment - NAMCO Limit Switch Model EA-180 (Qualification Reference 4B, Appendix D, pp. 3-8) 78. Pressure Test Environment - NAMCO Limit Switch Model EA-180 (Qualification Reference 4B, Appendix D, pp. 3-8) 88. Temperature Test Environment - Crouse Hinds / Westinghouse Welded Canister Electrical Penetration Assembly (PEN-ACD-4-72-03, Accident Environment Test Report) 98. Pressure Test Environment - Crouse Hinds / Westinghouse Welded Canister Electrical Penetration Assembly (PEN-ACD-4-72-03, Accident Environment Test Report) 10B. Temperature Test Environment - Bechtel Electrical Cable Splice (WCAP 7410-L, Volume II, Table 10) 118. Pressure Test Environment - Bechtel Electrical Cable Splice (WCAP 7410-L, Volume II, Table 10) 128. Temperature Test Environment - Foxboro Transmitters Models 611GM and 613HM (WCAP 7354-L Sheet A) 138. Pressure Test Environment - Foxboro Transmitters Models 611GM and 613HM (WCAP 7354-L, Sheet A) 14B. Containment Twperature Environmental Test, BIW Part No. 7244-H-002,

16-2 Inside oontainment Instrument Cable ISB.

Containment Pressure Environmental Test, BIW Part No. 7244-H-002,

16-2 Inside Containment Instrument Cable 16B.

Temperature Profile for LOCA Qualification of Kerite 600 Volt HTK-Insulated, FR-Jacketed Power Cable 178. Pressure Profile for LOCA Qualification of Kerite 600 Volt HTK-Insulated, FR-Jacketed Power Cable

Page 3 of 3 Rev. 4 OVALIFICATION FIGURES (Cont 1nueo) 2 1 88. Temperature Profile for LOCA Qualification of Kerite 600 volt FR-Insulated, FR-Jacketed Control Cable

198, Pressure Profile fort SCA Qualification of Kerite 600 Volt FR-Insulated, FR-Jacketed Control Caole 208.

Rome Cable Corporation. Temperature-Pressure Profile for LOCA Testing of Control Cable 218. Cable Qualification Test Profile for Life, LOCA, and Post-LOCA Simulation 228. Sensor Environmental Qualification Program Pressure /Tercerature Profile - RTDs 2 38. LOCA Profile for Rockbestos Firewall III Class IE Electrical Cables i l l f__

i ~ i, r I. E t m g M i E 1 o i xocw set 6 mn O l m t m -e> I n QUAllflCATION REFERENCE 27B 0 flGURE 5.3 {, g n rigure 22H Sc"50' E"'I'onmental Oualificatiot. Proe, rain Pressure Temperature l'rofile -- fliDs

LOCA Profile Spray continuously at rate of 0.15 spa 346*F/ll3 psig ( min) per square foot of spray area with WITHIN 3TO 5 MIN solution of the following composition: 0.28 molar 18 B03 (3000 ppm boron), 3 Naoll to make pil between 9-11 at 77,F. 340 ( 333 7/93 p,g, 320 3!5'F/69 psig e 2 b -*--- 265' F/2 8 psig 9 N N r Q 3 250- - N \\ F t 280'F/70 psig ( min ) WITHIN 10 SEC 212 *F/O psig ( / 200-I 14 0 I I l l I 1 4, 10 3 5 8 11 15 SEC ltR llR llR llR llR 4 DAYS 30 DAYS TIME rigure 233 LOCA Profile for rockbestos Firewall 111 Class IE Electrical Cables I

i ENCLOSURE 4

Page '. of 2 Rev. 4 IOUIPMENT OUALIFICATION PLAN POINT BEACH NUCLEAR PLANT Most componen:s which do not meet the documentation requirements of of IE Bulletin 79-OlB (" DOR Guidelines") are being replaced. The replacement components will be qualified to Category I (i.e., IEEE 323-1974) of NUREG-0588. It is oar intention to complete the component replacements during the scheduled maintenance outages presently planned for October 1981 for Point Beach Unit 1 and March 1982 for Point Beach Unit 2. This allows time for design, equipnent procurement, and planning. The following types of items are scheduled for replacement: 1. Pressure and differential pressure transmitters; 2. Solenoid valves; 3. Limit switches; 4. Electrical :enductor seal assemblies for limit switches (inside cortainment); 5. Rome electrical cable (inside containment); 6. Electro-pneumatic transducers (outside containment only) (diaphragms and seals only); 7. Resistance temperati.re detectors (outside containment) (0-rings only); 8. Water level indicators (containment); and 9. Thermocouple connectors, extension wire, and penetration assemolies. The only replacement components which are undergoing environmental qualification under our direction are the pressure and differential pressure l tran eitters. The replacement transmitters will be Foxboro N-E10 Series transantters which are being qualified 'ay the Utility Transmitter Qualification Group with Wisconsin Electric Power Company acting as the lead utility. The qualification program consists of two phases of testing. The Phase I program tested naturally-aged Foxboro transmitters with radiation, seismic, and l LOCA/HELB tests. The Phase 11 program will be identical to Phase I except that new transmitters will be artifically-aged and then tested as above. The following is the anticipated schedule of the Phase I and II qualification programs: Phase I testing Complete January 1981 Begin Phase II Testing April 1981 Complete Phase II Testing January 1982

Pago 2 of 2 RQv. 4 The other replacement equipment will be purchased already environmentally-qualified by the vendor. The remaining electrical equipment which does not meet the requirements of the DOR Guidelines will be dealt with as follows: 1. In-Core Thermocouples are considered qualified by their long history of operation in norwally harsh environments; 2. Thermocouple reference junction boxes are planned to be moved from the containment to a controlled environment; 3. Reactor Coolant System RTDs are planned to be further analyzed for thernal aging and higher radiation doses. Qualified replacement RTDs will be used if they are available and found to be necessary; 4. Pressurizer immersion heaters and cable connectors are planned to be further analyzed for environmental quali-fication; 5. The acoustic monitor transducers and electrical connectors are planned to be environmentally qualified by the vendor on a schedule yet to be determined. It is our intention to complete the above qualification and documentation by June 30, 1982. I I i l l I

DISTRIBUTION RESPONSES TO BULLETIN 79-01 B (f... ":~

==- IE FILES 1 COPY NRR (PHIL DIBENNIDETTO)

1. COPY

'F R C (C.TANZIO) 1 COPY CENTRAL FILES 1 COPY PDR 1; COPY ACCESSIONS NSIC 1 COPY TIC 1 COPY 4% /Q 7 g, kkfb mag n = l REV. 2/5/81 n =e 5l{F}}

ML19350B687

Contents

Text

. =

=

= = =

=

=

=

Navigation menu

ML19350B687

Text

. =

=

= = =

=

=

=

Navigation menu

Search