ML19242B638

Responds to IE Bulletin 79-01 Re Environ Qualification of Class IE Equipment.Forwards Detailed Test Documentation Package.Solenoid Valves,Limit Switches & Magnetrol Level Switches Will Be Replaced

ML19242B638
Person / Time
Site:	Turkey Point
Issue date:	07/03/1979
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 7908090238
Download: ML19242B638 (54)

Text

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• 49 July 3,.1979 L-79-182 fir. James P. O'Reilly, Director, Region II Of fice of Inspection and Enforcement U. S. tiuclear Regulatory Commission __

101 tiarietta Street, Suite 3100 c: .25 Atlanta, Georgia 30303 w

? 30 Dear Mr. O'Reilly. m j-y Re: RII:JP0 C 50-2;0, 50-251 -

IE Bulletin 79-01 .c-The attached infornation is submitted in response to the subject Bulleti:F A detailed test documentation package will be availatile at the Turkey Point plant site by early August,1979.

As discussed in the Attachment, the following equipment will be replaced:

(a) ASCO solenoid valves and ?!AMCO linit switches, including sealant naterial, on Letdown Line isolation valves, Cor.tain-mnt Purge Supply and Exhaust isolation valves , the Instru'r.ent Air Bleed isolation valve, and CVCS to RCS Cold Leg isolation valves, and (b) flagnetrol Level Switches in the containment sumps.

In addition, a design verification review will be perfonred for the instrumentation in the Emergency Containment Filter Unit.

The Attachment also discusses the justification for continued operation until the above actions can be perfonred.

Very t ruly yours ,

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Vice President c Advanced Systems & Technology g,O ",)

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REU/ MAS /cph Attachrent cc: Robert Lo.venstein , Esquire o, y .,I r' WY 79080900 hows- , _

R.ORIDA PO',;ER AND LIGli! CC.

FISPOSSE TO ILE BULLETIN 79-01 FOR TUFEIY POINT U';ITS 3 6 4 ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT July 2, 1979

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TAELE OF CONTENTS TITLE PAGE Section 1-1

1. Introduction 2-1

2. Post-Accident Environment Post-LOCA Environmental Conditions 2-1 2.1 Containment Spray Chemical Environmental 2-5 2.2 Conditions Qualification of Electrical Equipment 3-1 3.

Introducticn 3-1 3 . '.

Post-Accident Equipment Qualification 3-2 3.2 Summary 3-11 3.3 Remarks and Justification for Continued Operation 4-1

4. Conclusions 5-0 5 Qualification Data Sheets "r

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1. Introduction This report is in response to I&E Bulletin 79-01 which contained the NRC's request for written evidence of the qualification of electrical equipment required to 1 unction under post-accident conditions. The report includes a description of the licensed post-accident environmental conditions, the actual qualification data available and our conclusions.

The equipment required and environtental conditions described have been selected following a review of the Turkey Point 3 6 4 licensing docket.

Documents contained therein which were utilized to establish qualification parameters include the FSAR, the SER and various letters to the AEC/NRC outlining changes in the license and operating procedures. This search was undertaken to ensure the report contained a complete and updated compilation of electrical equipment inside containment required post-LOCA, plus the limiting environmental conditions.

The construction of Turkey Point 3 6 4 was announced on November 15, 1965, with a Construction Permit granted on April 27, 1967. Unit 3 received its Operating License on July 19, 1972, and Unit 4 on April 10, 1973.

Due to the early vintage of these units, much of the equipment purchased was state of the art at that time. In addition, the Quality Assurance' as well Quality Control programs and documentation requirements were not developed or extensively applied as they are presently. The result of this has led to difficulties in locating the documentation of the testing and qualification of some of the electrical equipment discussed in this report.

The search for the docu=entation included file searches, both at the FPL General Office and at the nlant and visits and communications with the equipment vendors to obtain records held in their files. This effort became more difficult with the passage of time as companies relocated,were purchased and absorbed by larger firms or dropped out of the nuclear supply business. Di:ficulties such as these have led to time consuminc delays in many cases when searching for documentation. Additional problems which occurred during this review, include such things as t'ne lack of an FSAR commitment for qualification to the containment chemical spray environment and the periodic changeout of original equipment due tc normal plant maintenance.

A significant amount of qualification documentation was recovered for these electrical devices. In combination with the engineering extrapolation; and analyses performed where necessarv, the majority of the equipment located inside the containment was shown to be capable of performing asdesigned post-accident. In certain cases such documentation could net ce found, or the available documentation was insufficient to draw anv firm conclusions. The f ollowing sum =arites the status of these devices :

1) ASCO Solenoids (SV-200A,200B,200C; SV-2601,2603,2804,2806:

SV-2819; SV-310A,310B): These have been reordered and will be replaced during the first available outage following receipt.

2) NAMCO Limit Swit che s : These are being reordered and will be replaced during the first available outage following receipt.

3) Emergency Containment Filter Unit Thermocouple Reference Junction, Thermocouples, Thermocouple Extension k' ire and Air Flow Switches:

a post-accident design verification is underway and subsequent action will be taken to meet system qualification guidelines pending the outcome. Followup action will oe scheduled upon completion of the design review. 575 0'0

Magnetrol Limit Switch: k'e are currently investigating 4) qualified replacements. These switches will be replaced at the first available outage following receipt.

In all these cases, the function of the devices were reviewed and the determination was made that the plant could continue to operate until replacements could be tsde withrut undue risk to the health and safety of the public.

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2. Post-Accident Environment 2.1 Post-LOCA Environmental Cenditions The environmentally limiting Dest,n Eases Events for Turkey Point Units 3 & 4 are the Loss of Coolant Accident and Steam Line Break (inside containment) . The post-LOCA environment is the most limiting with respect to total mass and energy release to the containment plus maximum containment pressure (see FSAR section 14.2.5 and 14.3.4) .

The Turkey Point FSAR does not contain pressure / temperature envelopes for the time spans required. Therefore we have conservatively developed er.velopes to be used in this ef f ort.

The environment caused by the postulated double ended break LOCA (minimum safeguards operating) is described in the FSAR Section 14. 3.4.

The containment pressure envelope which bounds the FSAR curves is shown in Figure 1. In the FSAR the contain=ent pressure transient was calculated for a range of large area ruptures of the Reactor Coolunt System. ,The rupture sizes considered were (a), double ended rupture (b) 6 f t' break (c) 3ft~ break and (d) 0.5 ftbreak.

FSAR figure 14.3.4-2 presents the results of the transients. For all cases a pressure peak of less than 4;.9 psig was calculated.

In the transients one of two spray pumps and tuc of three f an coolers starting at 60 seconds were assumed.

The containment temperature envelope shown in Figure 2 was developed f rom the double ended break pressure transient of Figure 1. The temperatures associated with the respective pressures were obtained from outputs of the COC0 program runs provided by Westinghouse during the development of the FSAR accident analyses cases. This figure is not provided in the FSAR, however the maximum temperature associated with the maximum pressure (49.9 psig) is provided in the FSAR as 276*F.

The Radiation Dosc that the equipment will be exposed to is dependent on the specific period of time the equipment in required to operate following a LOCA. The FSAR states that the maximum dose rates within the containment would be approximately 4.2 x 10 6 rads per hour or 2.6 x 10' rads per week. Fur th ermor e , the LOCA radiation dose was described in Florida Power and Light Company letter to the NRC dated February 7,1969, Docket Numbers 50-250 and 50-251. The calculated intensity of the radioactivity in the containment building as a function of time after a LOCA was provided in Figure 1 of the af orementioned submittal. The amount of radioactivity postulated to be released into the containment from the core was calculated according to the assumptions given in TID-14644 reference (1).

The exposure rate to equipment inside containment is shown in Figure 3 attached " Exposure Rate of Motors and Blowers to Radioactivity."

The assumptions for the calculations are given in the figure, which was submitted to the NRC on February 7, 1969.

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2-2 *

'llei total radiation dose to each specific equipnent was obtained by us jng the curve in Figure 3 for time periods between 100 neronds and 10 seconds ('bil6 days). 1:or the first 100 seconds of tirm it was conservagivelyassuredthat at time I second the dose rate van 4.2 x 10 rada per hour (per USAR page 7.5-11 naxinun dose rate) which then linearly decreased to the value shown in Figure 3 at tite 300 secondn.

The post-LOCA done to each piece of equipment was calculated based on the dose rate values in Figure 3 (tor the specified tire period) nultiplied by the tire the equipment is required to function in the post-LOCA cavironment.

To arrive at the " total radiation dose" for which the equiprent should be qualified, the 40 year normal operaticn integrated dose (coeservatively 5

esticated as 1 rad per hr for 40 years continuous) cf 3.5 x 10 rads is added to the rent-LOCA dose.

Based on a review of the licensing conmittents, operational tire requirements were determined to be one of the f ollwing : 5 ninutes, 30 minutes, 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, eight hours, 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and 31 days. Using these Line periods, a bounding pressure envelope was developed. The envelope conservatively bounds the FSAR containment prert.ure transient (figure 14.3.4-2). For t.ine. greater than 10,000 see and less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the transient data was obt ained f rom curves provided by Westinghouse for FPL (let ter was dated :! arch 21, 1965, FPL- W-704) for the double ended cold len break with 2 c=ergency containtent coolers operating. For Lines greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and less than 31 days it was concluded that the pressure would be below 5 psig, based on the data provided in UCAP-7410-L which states that the pressure transients shown represents caxinun conditions for Westin;; house PWR designed reactors, (see WCAP 7410-L Figure 1) . A similar procedure was used in developing a bounding tecperature envelope.

The total radiation dose envelope for equipment5 is the sur. of the 40 year nornal operation integrated dose (3.5 x 10 rads) plus the radiation dose during the post-LOCA operation period.

The relative humidity was assumed as 100?. throughout the post-accident operation period required for the specific equipment.

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2-3 REFERD:Cl:S

1) J. J. DINunno, F. D. Anderson, K. 1:. Baker, and R. L. Waterfield, Calculation of liistance Factors for Power and Test Reactor Sites, USAI:C Report T I D- 14 8 '. 4 ,

Mar. 23, 1962.

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TABLE I TURKEY POINT 3 & 4 LOCA ENVIRO';? TENT QUALIFICATION CONDITIONS Temperature Prensure llumidity Radiation Qualification Time (PSl Q _ (Z) (1:)

Level (

• 1')

I O - 5 min 276 50 100 2 x 10 5 5 - 30 nin 266 42 100 6 x 10 5 II 0

22 100 2y 10 III 30 min - 2 hr 226 5

18 100 8 x 10 IV 2 - 3 hr 216 6

206 15 100 3 x 10 V 3 - 8 hr 6

13 100 4 x 10 VI 8 - 20 hr 198 13 103 8 x 10 3 VI' 20 - 24 hr 198 7

5 100 3 x 10 VIII 24 hr - 31 days 152 4.2 x 10 TOTAL LOCA DOSE:

NOTE 40 year nornal opgration integrated dose to be added to the total LOCA dose = 3.5 x 10 Eads

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FPL Docket I:o s . 50-250 50-251

2-8 2.2 con t a i.n.me n t sprav Chemical Environrental conditions Ter, tiny, of electrical equipnent required for the safe shutdown of the plant to determine the effects of the chemistry of the containr.cnt spray was not a desir,n commitment of 'lurkey Point. The cormitment to raise the pil to 7.2 in the sump recirculation water within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> arm:e f rom concerns over the prevention of chloride st re us corrosion.

The pil of the surr recirculation,up until the first br.tch of bora.,

is injected is 4.98.

The effects of this mild acidic environnent will only be seen directly by electrical equip:.cnt during the lennth of tirae the containnent spray is operat2ng. The containnient onrays are initiated at pressure over 20 psig and the operating procedure, allow for termination of spray any time after switch over from injection to recirculatien proviJed containment pressure is belot 30 pulg. 1herefore, it i.

most probable that the spray 1 will enly be operated for approy.i: ately 1/2 hour post-LUCT (see sectio. 2.1 for a description of tim po,t-LOCA eivironment).

Therefore, due to the mild acidic nature of the spray and th< short term exposure the devices will see, no sir,nificant corrosion problen will develop causing the potential for equipment failure.

Should sprays be required durin;; the long term post-accident tine period, the pil of the spray will have been raised to a virtually neutral level, n

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3-1

3. oualification of Electrical E q u i p =_" n_t _

3.1 Introduetion to Section The purpose of this section is to present a sun.iry of the qualification data f o r el ec t r i e.il equ ipr, n t located inside the containment which i:

required to function under postulated accident conditions (set Sectien 2 fer descriptinn of the post-accident <onditions). The selcction of the summari;ed equipment corresponds to those required for the ,a t e shutdown of the plant f ollucinr, a lle ;ign llases Accident as, stated in the various licensing docunents in the docket ( FS Alt , SER, letters to the NRC, etc.).

'lhe summary sheets in section 3.2 discuss the ne t hod used in qual i f v i:'

elettrical equipment as found in the ..cailable documents. 'l h e actual documen ta ti on .:nd a su= iry o f the report results are refetcnted in the appropriate page of Section 5. In those case- where further ana vtical wort was required or unt re j us t i f i ca t i .)n l for c ont inued unit operation har been given interin to replacerent or requalitying equipnent, a reference har f.ecn provided to the appropriate page in Sub,ection 3.3. Qualification test records and analyses will be available in site.

The inves igation for data was done on a " loop" basis. That is, the er.pl.an is uas placed on ob tainin;. qualification data for the entire electrical loep from the penetration to the device. For exar.ple, the manuf act urer and model number wa:, obtained f or the penetration, cable, splices, valve position indication and valve o;erator for all containment isolation valves, and qualificatien data was pursued for each component in the loop. Thi: approach was ut ili;:ed to avoid a piete::. cal component search, assure completeness and assure post-accident operability of each individual component required to perform a function necessary for the safe shutdown of the plant.

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SECTION 3. 2 PO51 - /,<'cI]c';7 Eq"yp:. 3, ,

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TUPKEY POINT 3 & 4 3-3 POST-ACCIDENT EQUIP!'ENT QUALIFICATION StriARY AVAILABLE MANUFACTURER POST-ACCIDENT TIME QUALITICATION QUALIFICATION

& MODEL FUNCTION REQUIRED DATA METiiOD(S) REMARKS

- Pressurizer pressure input to 30 Min. Page 5-1 By Test -

1) Fischer & Porter Company S.I. initiation logic 50EP1041BCXA-NS - Needed to decide when to initiate steam dump following a scall break LOCA

- Steam generator steam flow 5 Min. Page 5-2 By Test -

2) Fischer & Porter Company input to S.I. initiation logic 10B2496TBBABBB-NS

- Post-accident stean generator 24 Hrs. Page 5-3 By Test and See section 3.3-1

3) Fischer & Porter FPL Analysis Company 1cvel indication for level 13D2495KBB ABUB-NS centrol

- Pressurizer water level input 30 Min. Page 5-4 By Test -

4) 1TT Barton 386/351 to S.I. initiation logic

- Pressurizer water icvel input to steam line isolation logic

- RCS average tenperature input 5 Min. Page 5-5 By Test -

5) Rosemount Inc. -

176KF to S.I. initiatica actuation logic

- RCS average tenperature to stean line isolation actuation 10,",1 c

- T.ierrocouples installed to 3 Hrs. None - See section 3.3-2

6) Conax Corporation 300-E-SS12-GT4 record the air and charcoal temperature in the emergency

.q q filter units GO C IUL J/ J

TURKEY POINT 3 & 4 3-4 POST-ACCIDENT EQUIPMENT QUALIFICATION S17tARY AVAILABLE i .

MANUFACTU RER POST-ACCIDENT TIME QUALIFICATION QUALIFICATION

& MODEI. TUNCTION REQUIRED DATA METil0D(S) REMARKS

7) Consolidated Ohmie - Provides reference junction for 3 IIrs. None - See section 3.3-3 Devices the emergency containment filte r EZT 213-D9 Poc temperature elements

8) Magnetrol Inc. - Level switch provides contain- 3 Hrs. None -

See section 3.3-4 A153-F-EP/VP-X-Y- ment recirculation sump level M1311-Fu 311 indication None See section 3.3-5

9) Ball Manufacturind - Air flow switches detect loss 3 lirs.

Company of air flow thru containment filter units and initiate opening of the charcoal filter '

. unit dousing valver.

0) Limitorque Corp- - Motor operator for valve in 20 Hrs. Page 5-6 By Test -

oration lo.-head safety injection path.

SMB-3 - Closure required to block cold l 1eg injection to lineup the redundant low head hot leg injection.

- Open on S.I. signal

11) Limitorque - Motor operator for valve in 2 Hrs. Page 5-7 By Test -

Corporation hot leg injection path to -

S!3-00 preclude postulated boric acid concentration i

TURKEY POINT 3 N 4 POST-ACCIDENT EOUlt::E:IT OCALIFICATION SU'EtARY 3-5 AVAILABLE MANUFACTURER POST-ACCIDENT TIME QUALIFICATION QUALIFICATION

& !!ODEL FUNCTION REQUIRED D,\TA MErrl0D( S) REMARKS

2) Limitorque - Motor operator for redundant 2 Hrs. Page 5-8 By Test -

Corporation low head hot leg injection SMB-1 valve used to prevent postulate!

boric acid concentration

- Air supply solenoid to the 5 Min. ' ene - See section 3.3-6a

3) Item 1 l Automatic Switch instrument air biced containmen Company (ASCC) isolation valve LBB31614 None - See section 3.3-6b Item 2 - Air supply solenoid to the CVCS 8 IIrs.

Automatic Switch charging line valves Conpany (ASCO) (IICV-310A 6 B) used for post-LB831654

• LOCA chenical injection to RCS to cont rol sunp ' eater pli 5 Min. None - See section 3.3-6e Item 7 - Solenoid operator for chemical Automatic Switch and volune control system Company (ASCO) letdown line containrent L3831654 isolation valve 5 Min. None - See section 3.3-6d Item 4 - Solenoid operator for containment Automatic Switch purge system isolatten valves l Company (ASCO) .

LB-831665 0

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TURKEY POINT 3 & 4 J-6 POST-ACCIDENT EQUIP:!ENT Ol'ALIFICATION StTIARY ,

AVAILABL"  ;

MANUFACTURER POST-ACCIDENT TI!tE QUALIFICATION QCALIFICATION FU!MTION REQUIRED DATA METROD(S) REMARKS

& MODEL

- Solenoid operator for valve 72 Hrs. Page 5-9 By Test and See section 3.3-7

4) Automatic Switch FPL analysis Company (ASCO) which provides water spray to X8211-B46Sb' - charcoal filter to prevent (HV-164-196) iodine re-release upon filter heat up from decay heat following loss of air flow 3 Hrs. Page 5-10 By Test

5) Reliance Electric - Energency containnent cooler j Cc=pany rotor used to renove heat from 38-26.5-1170 containnent post-accident

6) Reliance Elec,tric - Emergency containnent filter 3 Hrs. Page 5-11 By Test -

Company (Motor) notor used to remove iodine P/BC42.25-26.7 f rom post-LOCA centainnent 1170 atnosphere

- Provides decay heat renoval from charcoal beds

- Position indication only of 8 Hrs. None - See section 3.3-8a

7) Item 1 NAMCO post-LOCA chemical addition 0 2400X valves

- Position inlication only of CVCS 5 Min. None - See section 3.3-8b Item 2 NAMCO letdown isolation valves ,

D 2400X 4 n

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TURKEY POINT 3 6 4 3-7 POST-ACCIDENT EQUIPMENT OUALITICATION St"!ARY AVAILABLE i MANUFACTUPIR POST-ACCIDENT TIME QUALIFICATION QUALIFICATION 6 MODEL FtWCTION REQUIRED DATA METHOD (S) REMARKS

- Position indication only of 5 Min. None - See section 3.3-8c Item 3 NAMCO D1200G ' containment purge isolation valves

- Position indication only of 5 Min. None - See section 3.3-8d Item 4 NAMCO instrument air bleed valve D 1200G

- Cable to equipment requiring 31 Days Page 5-12 By Test -

8) The Okenite Company post-LOCA operatien X-01cne/Okoscal

~

- Cable to equipment requiring 24 Hrs. Page 5-13 By Test -

19) Gencral Electric Company post-LOCA operation Vulkene w' ire to thermocouples installed 3 Hrs. Page 5-14 By Material See section 3.3-9

20) Thermo Electric -

Test and Company Inc. to record the air and charcoal FPL Analysis temperature in the energency ,

filter units .

I

- IIcat shrink insulation used for 30 Days Page 5-15 Ey Test' -

21) Raychem Corpora-

• tion Unit 3 6 4 requiring post-LOCA operation s'.!V ~

- , s

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LL'KKt.Y l'O I N T 3& 4 POST-ACCIDENT EQUIPMENT QUALIFICATION Str4ARY 3-8 AVAI LAB L'.:

MANUFACTURER POST-ACCIDENT TIME QUALIFICATinN QUAI.IFICATION

& IODEL FUNCTION REQUIRED DATA METHOD (S) REMARKS

) General Electric - Terminal blocks on cable to 31 Days Page 5-16 ( By Test and i See section 3.3-10 FPL Analysis I Co :pany equipment requiring post-LOCA operation

) Crouse-Hinds - Contliinrent electrical 31 Days Page 5-176 18, By Test and See section 3.3-11 Corpany penetrations FPL Analysis O

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1,

3-9 Instrumentation, Va!ves and Other Equigent Various plant components have been discussed in the Turkey-Point Uni t :, 3 & 4 USAR as being required post.-LOCA. However, due.to plant changes or other reasons as specified below, this equipnent it not requi red follouing a I OCA.

The following is a discusulon of each of these components:

(1) Steam Generator Pressure (PT-494, 495, 496, 484, 485, 486, 474, 475, 476)

This pressure indication is required by FSAR Table 6.7-1 for period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> post-LOCA. In view of the fact that these transmittsrs have been relocated to the main steam line outside the containment, this equiprent will not experience the post-1K's environoent.

(2) Accumulatc r Subsys ter ':it rogen glced (liCV 036)

These valves are normally closed and are designed to fail closed.

Following a LOCA the valve is required to remain closed. lable 6.7-1 of the rSAR states that no environnental testing is required on equiprent which is norr. ally closed and f ails closed. Therefere, these valves meet the USA" comnittents.

(3) Accumula t o r !!it rogen Supply ( A0V-85 3 A, B & C)

See item 2 above.

(4) Pressurizer Pressure (PT-444, 445, 458)

These are not required for ESF initiation or containment isolation, that function is perf orr:ed by P'I-4 55, 456, 4'il (see page 5-1). Therefcre, the requirement for environmental qualificatien contained on FSAR Table 6.7-1 is inappropriate.

(5) Pressurizer Level (LT-462)

This is a cold calibration wide rance transuitter and is net used for ESF init lation or containrs ot i:.01 a t ion , that functian 11 performed by L1-459, 4 W) , and '. 01 ( .4 e c pare 5-4). Therefore, the requirement for environr.catal qualification contained on FSAR Lable 6.7-1 is inappropriate.

(6) Accumula tor Isolation Valves (!MY 865, A, li, C)

These valves are norrally open, with power racked out and receives

t. confirmatory SIS signal. In view of the fact that these valves are maintained in the correct positien and have no credible r.ade of failing closed. 'l he re f o re , the requiretent for environnental qualificat ion contained en FSAR t able 6.7-1 is inappropriate.

• a Nu qb

3-10' (7) Accunulator Tank Level (1.T-970, 922, 924, 926, 928, 930),

Accumulator Tank Prc:, ,ure (PT 921, 921, 97';, 92 7, 929, 931)

The accumulators are a passive ESF device; they are capable of discharging borated water into the KCS pos t -1.0CA wi thout any activation signals or valve rove: nt. Therefore, the level and pres ;ure indication u not required for accideo'. mitigation, and therefore the requirement f or envi ronmental qualificat.J on contained c,n USAR table 6.7-1 is inappropriate.

(8) liigh llead Flow Instrunentation (FT-( J2, 933)

These devices were intended to be used to monitor hi-head safety injection flow to hat leg A & B. Ilowe ve r , this injectien path is no longer used until 20 hrr follouing a LOCA and "JV-666A, 866B are closed with their r:otor control center breabers loched open to prevent the valves fron opening, to allow flow.

(9) Containment Purge This system was initl ally intended to purge hydrogen from the contain= cat post-LOCA. Since then, the post-accident containment vent synten with all attive conponents located outside containment has been added to perform this function. Therefore, the containment purge system has no lon;; term post-LOCA function and no further qualification is required.

(10) for the follouing containunt isolation valves, the FSAM requires position indication. Ilowever, since all valve . are norn. ally closed and have redundant valver, outside containment (either normally closed or receive an isolation .ir,nal) no indication is r(quired post-LOCA:

(a) RCS seal water Icahoff intermediate - 307 (b) Pressurizer Steam Space Sample Line -- 951 (c) Pressuri: er Liquid Space Sample Lin. - 953 (d) llot Leg RCS Sampic 955A, 955B 81 %o c)p

3-11 3.3 P.ema rk s and Justification for continued Operation 3.3-1 Tischer & Porter Company

!bde1: 13D2 4 9 '>KIw. A n h-N S Stcan Generator Level Tran witters Tag !;o: LT4 /4, 4 75, 4 76, 464, 485, 4b6, 494, 495, 496 Post-LNA operatien of the steam r,enerator icvel transmitters is required for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The indication of this instrument i n f o rr's the operator of the steam r.enerator secondary side level so he riay cont rol the level of the ste:n renerator. The avail able quali f icat ion doeurent s su~ arized on page 5-3 demanstrate th .' t this tran:mitter has been tested to conditi,s in e>: cess of thace expected following a LOCA for the first 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. In additien, the tran,nitter seas monitored for an additional 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> and remained functional. 'l h e above test resolts and an Fi'L engincering ext ra;mla t ion o f thermal effet ts denon. trite 3 that the t r an> r.i tter can operate for the required period.

Based on the above, the transmitter has an adequate cargin to ensure proper post-LUCA operation.

3.3-2 Conax Corporation Model: 300-L-SSl?-Gi4 Thernoccuples in Er..errency Cont a inmen t Pilter Air and Charcoal Tar, t;o : TE 3440 thru 3461 The purpose of these temperature elenents is to provide air and charcoal temperature indication to operator. If the charcoal temperature exceeds 325* the filter dousinr, valves will be opened b:. the operator to initiate spray cooling of the charcoal. The cr- rgency containment fil ter notors a re qualified for the period of tirm it is required following a laCA (page 5-!!).

However, if motor tailure ia det ernim o h, monitoring. notor cucrent, doar. ing would be runuall y initiated whether or not t e:r pe r a t u r e indication is available. Therefore, the indication of air and charcoal temperature is not required for the safe operation and iodine retention of the e r.e r ge n c y containment filters. It should be further noted that althouph documentation data it not available, thernoccuple caterials of this type by virtue of their application, i.e. hir.h temperature measurement, are not expected to be affected by pont-LOCA conditions. Since the thernacouple is made of metals, no radiation danago is expected.

Additionally, ultinate resolution of this device is sin =arized in Section 1.

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3-12 3.3-3 Consolidated Ohnic Devites Modelr E7.f 213-D4 POC Reference .1 unction for Energency Containment P11ter Thermocouples The purpose of thir device is to provide a nirnal used to correct the reference junctions of the th e rr.a c o u p l e s to O' C 'l h e reference junctiens at Turkey l'oint are not naintain<d at a knmen tenperature and there f ore requires conpensation to obtain accurate t erip e r a tur e signals fren thc thernocouples.

Per discussion with the runuf act urer, the .e devices are functional for arm e n t t c upe rature o f -(>5 C t o 12 '2 " C 10 0 '. h u- i d i t y , and 10"R gan .

At this tine we are still pursuing additional qualification docurtntation fIon the vendor.

As discussed in section 3.1-2, if notor failure in indicated, filter dousing would be manually initiated, hence (harcoal tenperature indiention would noi be required.

Additionally, ultimate resolution of this devi"e is sur :rized in Section 1.

3.3-4 tiagnetrol Inc.

Mode 1: A 15 3- 1 -EP / \T- X-Y-:11311-!i1311 Containrent Sump Level Suitch Tag I;o: LS-1570, LS 1571 The purpose of these level switches is to provide bacLup indication to the control room eperator concerninn containment recircula t ion sunp level aint t;PFil availobility when post-LOCA injection is to be terninated and reciculation initiated. 'lhe operator's primary indication for this procedure is level indication in the Refueling Kater Storage fant located outride th. centainnent, The Era rgency Procedure states that followin, t e rm i n a t i en of injn tiou and prior to initiation of recirculatien, the sunp level lights should be lit.

In the unlikely event that these seitches should fail to function, the operator should not be deterred fron realignine, the systen to the recirculaiion If bachup level phase in light of availability of K'MT level indication.

indication i r, required, the operator nay: (1) use a pressure sensing device in test connection 9'.2:, to deterr.ine pressure tron which level can be inferred. 'T h i s operation can be done outside containtent without opening V860A, the first isolatien outside contai n:: en t , or (2) open ei t he r Y-Se,0A and 861A or V-8(>Oll, EfilB and utiline the existing pressure indication located upstream of the Kiln purps ( P I - 159 (> , 1595) and/or the liigh llead SI purcps (P IC-9 5 7 A , 9 5 710 , o r (3) open all isolation valves, start all punps, and observe pump operation for excessive noi,se and vibration characteristic of cavitation caused by low level.

• Additionally, ultimate resolution of this device is sur:narized in Sec t ion 1.

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3-13 3.3-5 Itall Manuf acturing Cor pany Madel %.. 35003 Series D Emergency Containr.nt rilter Air r!ow Switches (FS-142?. 1423, 14 2 '. , 1425 14 M , 1427)

The purpose of these devices in t o autoru t I .Il y open the filter dousing valves upon loss of air flow. This is intended to prevint the charcoal ,

fron igniting due to decay heat buildup i ro a the absorbed iodine after loss of air flow.

The emergency contair nt f il t e r unit is qual i fied f or the peried of time it is required (pare 5-11) thereby guar.mteeing air flow. In the case of a randon .innie failure tausing the ma to r to r al f un c t ion , the don:. i n .

valves t 11 be ret.a t e-r.an u al l y ac t ua t ed . Motor operation will be monitored outside the containment by measuring current on the oporating fil ter rut ors.

The FSAR co m itsq to pecifying these valves to operate with a radiation dose of 1.7 x 10'n with no requirement for testing. The specification has been reviewed and found to have been developed in accordance with this coraitnent.

The functien of thi- device is being reviewed along with the other instrumentation of the Energency Filttr Unit as nated in Section 1.

3.3-6 ASCO Solenoid Valven

'lhe ASCO solenoid valver are used oc valve operators inside the containtent to cont rol the associated valve operator during normal operation and autonatically place the val ve in the desireu position follot an receipt of a containnent isolation signal. 'l h e r e valves havt been analyzed in a gener i c 1.'es t ingheuse let ter which demonst r at ed that all failure rmdes of the valve will result in safe operation. Pot ential modes of f ailure identified for solenoid valves in the letter were loss of air supply, electrical failures of the ,olenoid, environmentally caused degradation of materialt, of construction, and plunger binding due to thermal expansion of the plunger to the core. The ShC has accepted this evaluation in a letter dated on January 31, 1979. The appltration of these solenoids is discussed in detail on the f ollowing pages in this subsection for the particular valve operator.

These discussions provide just i ficat ion for cont inued operation ar continued service in a post-I.0CA environr.c t in not required for the safe shutdova of the unit.

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4 3-14 Ilowe ve r , in order to provide additional safety mar;;in and to ensure l ov term solenoid valve operation, we have ordered replacement solenoid valves.

These replacetent valves are qualified for the pos t-LOCA envi ronmen t as evidenced by the attached data sheet (written documentation to suppert the data will be delivered with the valves). The valver. are ordered and are sc:.ed ul e d to be in.tslied oa the first available outage. See Section 3.3-6e f or qual i f icat. ion dr a on replacement solenoid valves 3.3-6a

1) Instrument Air Bleed 1 solation (CV-2819)

This is a f:.il closed valve required for containment isolation. The ASCO solenoid valve (SV-2819) regul a t e: the air supply to the operator. A generic Uestinghouse letter (SS-Cl.-7h , response to commitrent for WCAP-7410-L) d e t :a n s t ra t e s that the selenoid valve, which regulates air supply to containment i:.ala t ion ai r ope rator vi11 close (it safe pon i Lion) in all postulated modos of failure.

Therefore, it can reasonably be expected that even if the solenoid valve fails, the air operated valve will isolate the containment as designed.

It should he noted that a redundant isolat. n valve CV-2826, is provided outside the containment and will provide a backup method of isolation.

3.3-6h

2) CVCS Charging Linen to RCS (llCV-310A, 3101;)

Valve llCV-310 A is in the norral CVCS charging path to the cold leg of an RCS loop. Yalve llCV- 310 h is in the al te rn at e charging path provided to an RCS Joop hot leg Both of these ate tail open valves, with enly one required fo r post-LOCA chenical ad 'i t ion f or pil < en trol . These valve:

are not containnent isolation valvet.

Valve llCV-310A is normally open, and is the normal charging path to the RCS.

Since this valve is opea and tail: epen there will be no need to operate this valve following a postulated accident. l'u r t hermo re , potential modes of failure ideatified for the solenoid valves such as loss of air supply, electrical failure for the solenoid, environmentally caused degradatien of materials of const ruction and plunper hinding dut to thernal expansion of the plunger to the core, will not result in failure of the line valve (llCV-310a) to the non-preferred (clonedi position.

In the unlikel; event of nen-r.;e chan i s t ic failure of the solenoid valve (SV-310A) to the non-preferred position (solenoid energized valve closed) the operator will be instructed by administrative procedures to close the instrument air supply line valve (CV-2803) into containment thereby causing loss of air pressure due to bleed-off of air causing both valves to move to their preferred (open) position. .

In view of the fa.t that injection for pil control is not required for eight hours post-Lt t can reasonably be expected that such actions can provide the necessa , .undancy. 7 C O f; k ,i )

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3-15 '

3.3-6c

3) CVCS Letdown Line Isolation (CV-200A, 200B, 200C)

These are f ail closed valves required for containment isolation. The ASCO solenoid valves (SV-200A, 2003, 200C) regulate the air <:upply. A generic

! Westinghouse letter (SS-CE-755, response to cocaitrent f or WCAP-7410-L) demonstrates that the nolenoid valves, which regulate air supply to containment isolation air operators, will close (its safe position) in all postulated moden of failure.

Therefore it can reasonably he expected that even if the valve fails, it will isolate the containment an designed. It should be noted that a redundant isolation valve CV-204, is provided outside the containment and provides a redundant method of isolation.

3.3-6d

4) Containment Purge Isolation Yalves (Supply and Exhaust) (CV-2601, 2603)

These are f ail closed valves required for containment purging and isolation.

There are two ASCO solenoid valves (SV-2601, 2 8 0 '. , 2603, 28%) in serie:

which regulatt the air supply to each purge valve. both olenoids ruxt be open to supply air to the valves and closure of either solenaid valve will dump air from the diaphram. This provides ascurance that even if one of the solenoid valves were to fail, the purge valve vilI close and providt contain-ment isolation. A generi c Westinghouse letter (SS-CE-755, response to coruitment for WCAP-7410-L) demonstrates that the solenoid valves, which regulate air supply to containacnt isolation air operators, will close (i ts safe po::i t ion) in all postula t ed mode. of failure.

Therefore, it can reasonably be expected that even if the valve fails, it will isolate the c on t a i :c:e n t as designed. It should be noted that redundant isolation valver (POV2600, 2602) are provided outside the containnent and will provide a redundant method of isolation.

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'n c,e 3-16 TURKEY POINT UNITS 3 & 4 Section 3.3-6e D2VIPMEI;T Replacerent Solenoid Valves For Air Onerated Valven TAG !!U:-!!! Fits MA!!UFACTUltEH Antomatic Switch Cirnany MODL'L QUALI FICitTI O DOCID'EI;TATI O:

ASCO Tent Eeport ADS-21678/TR Q'JALI FICAT : 0" I"",' T F ^'M Acin- dei Sim.lation IE- 12 12 3 2 8 3 3 4 30 Dave Min. liR lin Min. IIR 11' Dcys Days Pi :S o 110 o to 110 to to 110 75 15 10 psil; 110 0 110 Tiz' 140 346 140 to 346 to to 346 320 250 200

• F 268 346 340 l'. 6 F. , n 1:U:'

100 100 100 100 100 100 100 100

' l CIR2' 3000 ppm Boron as Loric Acid in solution with 0.064 Malar sodiur thiosul f at e buf fered with NaOH to a pli of 10 at roon temp.

D- t w i ., e v 2W#F o.,. first tr-,"r ien t , con t inued f o r en t i re t e ;t )

liAD 8 2 x 10 Rads QUALIFICATIO:: I:!UHOD3 Therraal acin; then radiatfon, then wear aginc.. then scismic, then accident radiation, then synergistic test for prens., teep.,IIumidity, chemical spray - all on same valves.

.,3 Note: This test valid for scaled entrance to solenoid housing to

• s prevent entry of humidity or chemistry. Such sealant materials are under investigation. n (-)

Note: Theaboveresultsareasummaryprovidedforreviewerconvenience.h

3-17 3.3-7 Autonatic Switch Conpany Model No. X8 21 1 - B '. 6 S'.! (llV-164-196)

Emergency Containment rilter Dousing Valves (SV - 2905 thru 2910)

Post-1.0CA operation of these valves is required until the decay heat load from the radioactive iodine has suf ficiently dininished. The available documen tation demonst rates that this solenoid valvt h:n. been tested to conditions generally in excess of the expceted environment following a LOCA for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. FPL 1:nr,inee ri or F.nalysis of ASCO's <tated design, test reports, and published infornation on the effects of radiation shows that the valves wil 1 per f orr.. their intended function for 6 days, which is in excem of the required post-LOCA service period.

3.3-8 NAMCO Linit Switchen The N/N O limit suitches used on valves located inside the contain:"ent serve to provide valve position indication durin, nor:ul eperation and as verification of valve posit. ion following containment i sol a t ion . They are not used for any associated control function.

Follouing containn;nt isolation there are backup position indication nethods avail abl e to the control roon operator to verity that the containcent boundary is naintained and isolation completed, should the linit switche, inside coatainnent f ail under post-acciden t conditions. These methods are discussed in Jetail en the following pages in this subsection for the particular valves ascociated with these nitches. These discussians provide justification for continued operation as continued service in a post-LOCA environnent is not required for the safe shutdown of the unit.

Ilowe ve r , in order to provide additional safety ra:c,in and to ensure post-LOG valve position indication we are orderin;- replacement l ir.i t switches.

These replacenent switches will be qualified for the post-LOCA environnent as evidenced by the attached data sheet in section 3.3-8e (written docurentation to support the data will be delivered with the switches). The switches will be installed on the first available outage fe: lowing receipt.

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3-18 '

3.3-Sa

1) CVCS to RCS Loop A Cold Leg and Loop C llot Leg (HCV-310A, B)~

The charging line valves to RCS Loops A and B (llCV-310A and B) are used for post.-LOCA chemical add i t ion to control the pH of the sunp water and do not serve containment isolation functions. The 1imit switche<, are not used for control, and indication would be desirable only during chemical injection.

It has been stated in a previons submittal that the valves required for post-LOCA pil cont rol of containment sump water have position indication on the control reon board for the operator to observe that either valve (llCV-310A or IICV-310B) is open.

There are two flow transnitter (17-110 and IT-122) out side containnent in the chargin;; line with indicat ion in the control room (F1-110 and F1-122).

This indication will serve as verification that either valve 310A or 310B is in the open position.

The operatinr, proceduro specifically instructs the operator to manitor both flow indicators to assure there la adequate flow durinr, chemical iniection.

The flou transmitter will positively provide i nd i ca t ion that either of the valver is in the open positien.

Furthermore the operator will be instructed to remote-nanually initiate opening of the valve foiloving receipt of CIS.

3.3-8b

2) CVCS Letdown Line Isolation (CV-200 A, B, C)

These are the CVCS letdown line isolation valves inside containment which are parallel to each other. Valv< dV-200A and CV-200h art norc '1 v closed. Yalve 200C is normally open. These valves are solenoid opc"ates valves which fail closed on receipt of containment isolation signal.

The second isolation valve (CV-20'.) on this line is located outside containment, fails closed and closcson receipt of containment isolation signal. Therefore, indication of the outside valve position serves as a backup indication of containment isolation.

Furthermore, the operator will be instructed to initiate rema t e-raa n u al closure of these valve: following, receipt of CIS.

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3-19 3.3-8c

3) Containment Purge Isolation Valves (CV-2601, CV-2603)

These valves are located within containment on the containment purge <:n p p l y and exhaust lines Each isolatic valve inside containment is redund.in t to one outside containment which will not he subiected to the post-13R5 environment. These valves iail closed and clore on CIS and high activity (f rom air particulate detect or or radiogas detector). Failure of the position indicator does not affect the ab il i t'/ of the valve to close, Assuming position indication failure for the valves inside containment, the redundant valve outside in the supply and exhaust lines which are not located in a hostile environment will provide indication of outside valve closure and thus verification of containn ut isolation.

Furthermore, the operator will be instructed to initiate remote-manual closure of these valves upon receipt of CIS or high activity, 3.3-8d

4) Instrument Air Bleed Valve (CV-2819)

This val ve is located within containment on the instrument air bleed line.

The isolation valve inside containment is redundant to one outside containment which will not be subjected to the post-LOCA environment.

This valve fails closed and closes on CIS. Failure of the position indicator does not affect the ability of the valve to close.

Assuming position indication failure for the valve inside containment, the limit switch on the redundant valvt outside containment which is not located in a hostile environment, will provide indication of outside valve closure and thus verification of containn.ent isolation.

Furthermore, the operator will be inst ructed to initiate remote-manual closure of this valve upon receipt of CIS.

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b2U TURKEY POINT INITS 3 E, 4

. Section 3.3-8e D2VIPME;iT Replacement Limit Switches For TAG NU:<BER:s CV-200 A, B, C; llCV-310 A, B; CV-2601, 2603; CV-2819 MAinlFACTURER NAMCO MODEL EA18011302 QUALIFICAT10I; DOCll:4EiTAT10N Per telecon between FPL's B.N. Corodetzer and NMiCO, the replacement limit switches are qualified to the IEEE-323 LOCA profile. A copy of the test report will be furnished with the switch purchase.

QUALIFICAT]O" ENVIRO 2'E:;7 IEEE 323 Curve Given For Reference TII:E O 5 Min. 3 Hr. 5 lir. Slir. 5Mir 6 lir. 10 lir . 4 Days to to to to to to to to 5 Min, 3 lir. 5 Hr. 5 Hr.5Mit 6 Hr. 10 Hr. 4 Days 30 Days PiCSS 0 40 0 to 40 to to 40 25 25 5 psig 62 0 40 Tm 0 300 140 300 300 to 250 210 167

'F to to to 250 300 140 300 RF,L. HU.".

+ Steam Autoclave -+

CHU First 24 hrs spray with H B0 3pH 3 of 10.5 wm NaOH.

and Na S 0 . cre 223 HAD

+ 2 x 10 Rads -+

QUALIFICATIO;: 'GT110DS Testing was done in accordance with IEEE 323 - (curve riven above reference). Testing was done with conduit brought out of the test chaiber. This will require [ealinn the limit switch conduit entry point with a qualific'd sealant material. Such scalant materials are being investigated. t EOE \

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' g Jl J Note: The above results are a summary provided for reviewer convenience.

For complete details, see the above referenced report document (s).

3-21 3.3-9 Thermocouple Extension Wire Thermo Electric Co. Inc. E/GS/CVGS TW-20Ei'.X Post-LOCA operation of this thermocouple extension wire is required for a periou of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. Although there is a lack of written qualification documentation for this extension wire, FPL Engineering Analysis of the materials of the thermocouple extension wire demonstrates that this wire is qualified for the time period of operation required following a LOCA. This analysis considered the effects of radiation, pressure, temperature, humidity and chemical sprays. Furthermore, this component is included in accident des i;;n verification effort focused on the Emergency Containment Filter unit and related components as discussed in Section 1.

3.3-10 Terminal Blocks General E]ectric EB-5 These General Electric EB-5 terminal blocks are presently installed on the circuits for the following components: Emergency Containment Filter air flow switches, containment recirculation sump level switches, Emergency Containment Filter charcoal dousing valves, Emergency Containment Filter thermocouples and thermocouple reference junctions.

FPL has performed tests and analyses on the GE EB-5 terminal blocks. Based on the tests and analyses it is concluded that the test environment is generally more severe than that which the terminal blocks are expected to see following a LOCA. Based on the above it is expected that the terminal block design has an adequate margin to ensure its satisfactory operation for the operation period required following a LOCA.

Furthermore, this component is included in the post-accident design verification effort focused on the Emergency Containment Filter ano related components as discussed in Section 1.

3.3-11 Penetrations Crouse-llinds Company In addition to the qualification data, FPL analys's of the ef fects of tempera-ture, pressure, humidity radiacion, and Boric acid on the materials involved in the construction of the penetration, concluded that the penetrations will continue to function for 31 days f ollowing a LOCA.

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4-1

4. Conclusions The review of the written evidence of the qualification of electrical equipment required to function under accident conditions has been completed with the majority of do umentation successfully located. Tur_ kev Point 364 did not contain a licensing commitment to test electrical equipment for chemical spray environment, therefore the matter is discussed on a generic basis in Section 2.2.

Generic problems with the quali fication of NAMCO limit switches (as developed from I6E Circular 78-08) and qualification for extende?

post-LOCA operation of ASCO solenoid valves (raised in ILE Bulletin 79-01A) have been identified. An engineering evaluation was performed on each application of these devices to determine whether replacenent or requalification was necessary, and whether the sa fe operation of the unit could be assured with the existing equipment. The results of this evaluation are contained in the appropriate subsection of Section 3 and indicute that continued operation of Turkey Point Units 3 6 4 is justified. In those places where the replacement option was chosen, it was done so in an effort to increase the margin of saf ety, and provide the ability for extended post-LOCA operation.

We have uncovered several areas where documentation did not exist to adequately support qualification of the electrical devices. These devices will be replaced; the schedules involved and qualification of the replacements are noted in the appropriate subsection in Section 3.

In the case of the instrumentation f or the Emergency Containment Fil ter Unit, an engineering design verification will be performed for the entire system in an effort to optimize the unit design and ensure post-LOCA operation of all required components. In all of these areas, a detailed review was performed to ensure that the safe operation of the plant could be reasonably assured during the interim period prior to replacement or resolution of the design verification and subsequent actions.

Therefore, we feel assured that continued operation of Turkey Point 364 will not be inimical to the health and safety of the public.

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S 5-0 SECTION 5 QUALIFICATION DATA SHEETS

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5-3 l'une ,

TURKEY POINT UNITS 3 6 4 I'QUII'1C:IT PrecsurJ7er Pressure Transmitters TAG liU'GERS PT-455, 456, 457

!!ANUFACTURER Fischer & Porter Company IGDEL 50EP104]ECXA-SS U/"Special Modi f cations" (scaled unit ,coqtaining USC/ AMP i'805U241U01 or f 805B230U01 QUALIFICATI0:1 DOCUE?.~I'ATION

1) Fischer & Porter Co. Test Report 2204-51-B-006

2) Fischer 6 Porter Co. Engineering Report DP #2224-1, RPT #002

3) UestinghoUse WCAP 7410-L (containing FIRL Report F-C2639)

4) Westinghouse letter NS-CE-1586 to NRC dated Oct. 28, 1977

5) Fischer & Porter Co. letter to FPL dated May 29, 1979

6) Ameron letter to FPL dated Nov. 20, 1972 QUALIFICA"'IC:! E' VIRO?,R::T ii i Oual. Doc. el Il Qual. Doc. 23 (3 Tests) 1 0-1 1 Min to 1-3 3d 2 d2 -7 2 Hours Min. I 11r 11r lir Hr PRESS 0 to 75 45 5 35 60 (Rise 6 5 sec) psig 75 TE'!? gm to 320 293 227 281 290 (82-293 in 5 sec.)

• F 320 *

• REL. HU.'1

% 100~; 100; 1007; 100'. 100~; 100*;

s Q. C H E". Transmitter coating tested for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> under 0.17. NaOH, l'.

Sodium Thiosulfate by weight, 15,000 ppm Boric Acid at pli 10.5 1.5 x 10 Rads 2.16 x 10 Rads (Qual. Doc, d2) (Qual. Dac. # 3)

• Temperature from steam tables based on saturated steam at. respective pressures QUALIFICATI0:; ETi!ODa - enF i ~' 7

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1) S'nergistic test on press., temp., humidity (contained OSC/ AMP l'8W>B 2 30U01 )

2) Radiation test ou d'ifferent instrunent than 1)(centained OSC/ AMP iibu a n.' 30001 )

3) Synergistic test on press., temp., humidity, followed by

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seismic, on FAP SOEP, 50EQ, and 10H2496 transmitters, the 10B a,

transmitter which uses elec t ioo n locata.o te tue 5u.a uc ; . v.a . , %. 3, u .t . .

Notd YSN'ab resuN7 kirb#a#" s"tl'E::f:1Y)NYNd)[f QOgggg) convenlence.

For complete details, see the above referenced report document (s).

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TURKCY POINT UJITS 3 & 4 1:QUll'IC:IT Steam Generator Steam Flov Trannmittern TAG llV:'!O:R3 FT-474, 475, 484, 485, 494, 495 MMiUPACTU!:ER Fischer & Porter company MODF.L Jn2496PnnAnim-N9 (not soa!od)

QUA!.IFICATIO:: DOCU:E::TATIO:1

1) Fischer F.

Porter Co. 1:noi neering Pe port DP

• 2224-1, FPT #002 (containing FIRL Renort F-c2815)

2) Westinghous$ WCAP 9157

3) Fischer & Porter Co. letter to FPI. dated Mav 29, 1974

4) Ameron letter to FPL dated Nov. 20, 1972 QUALIFICATJ0~: 12NIRO D'.1";T (Oual. Doc. 2)

T]!iM 6 min.

PHiLS 66 psig Ti2iP - M'B to 280

• F in 3 s e c . , 350*F in 15 sec., > 300*F for 6 min.

RUL. HU.'1 100%

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C H L" f Transmitter coating tested for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> under 0.17; NaOH, Qual. 1 S dium Thiosulfate by weight, 15,000 ppm Boric Acid at Doc. #4 pH 10.5 NSU 8.2 x 10 5 Rad; (Qual. Doc. #1) 4 x 104Rads ,(Qual. Doc. #2)

QUALIFICAT3 0:1 ICPODS

_ll__Padiation tocta n cornloto lon2'45 trm anitter which unes same electronics as F6P 101U'.96 (Kef. Qual. Doc. f3)

2) Padiation test, then svnorqistic tent for procc., temn.,

humidity - on same.inEtrunents.

Note: 'Ihe above results are a sumary provided for reviewer convenience. c, For comple te de tailt., see the above referenced report document (s),

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Paf.c 5-3 TURKEY POINT UNITS 3 & 4 1;QUJ PI- CIiT Steam Generator I.evel Transmitters TAG liU:!BlT.S LT-474, 475, 476, 484, 485, 486, 494, 495, 496 liAffUFACTURER Fischer 6 Porter Company ICDEL 13D24951:BBARBB-MS w/ 'ynec'al Modifications" (Sealed unit containing OSC/ AMP #805B241UOL or #805B230U01)

QUALIFICATION DOCUMEI;TATIO!!

1) Fischer & Porter Co. Test Report 2204-51-B-006

2) Fischer & Porter Co. Engineerlag Report DP #2224-1, RPT #002

3) Westinghouse WCAP 7410-L (containing FIRL Report F-C2639)

4) Westinghouse letter NS-CE-1586 to NRL dated Oct. 28, 1977

5) Fischer & Porter letter to FPL dated May 29, 1979

6) Ameron letter to FPL dated Nov. 20, 1972 QUALIFIC/zTJE:_X: IIEm'L .

I Qual. Doc. el Qual. Doc. v3 (3 Tests) :

T]!ii' 0-1 1 Min to 1-3 3 -6bd-7' 2 2 2 Hours Min 1 Hr Hr Hr Hr PRESS 0 to 75 45 5 35 60 (Rise in 5 sec) psig TiMP AMB to 320 293 227 281 290 (82-293 in 5 sec.)

.F 370 REL. HU:'.

% 100 100 100 100 100 100%

CHDI Transr.itter coating tested for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> under 0.1% NaOH, 1 *,

Qual. Sodium Thiosulfate by weight, 15,000 ppm Boric Acid at pH 10.5 Doc. #6 NEU 1.5 x 10 Rads 2.16 x 10 Pads (Qual. Doc. #2) (Qual. Doc. #3)

• Temperature f rom steam tables based on saturated steam at respective pressures QUALIFICATIO:3 METHODS (contained OSC/ AMP

1) Synergistic test on press, temp, humidity #805B230001)

(contained OSC/ AMP

2) Radiation test on different instrument than 1) 080w.21n"01)

3) Synergistic test on press, temp, humidity; followed by seismic; then radiation - all on same instrument This test was on F6P.SOEP and 10B transmitters which use same electronics as the 13D t ransmitters (Ref. Qual. Doc. 45)

These transmitters contained UM./ W e bo m .'4 10 0 1 Note: 'Ihe above results are a summary provided for reviewer convenience. gq}

document (s). \R For complete details, see tha above referenced report C)O,p 3

ID D - -

TURKEY POINT UNITS 3 & 4 Pressurizer Level Tansmitters EQU11'I EilT TAG liU: !!!:RG y,T- a sg . a rs o , a r,1 MAlfUFACTU!(I'R j p - Earton IDDIL 380/351 QUALIFICATI0:1 DOCUEIITATIOli

1) Westinghouse letter NS-CE-1586 to ?JRC dated Oct. 28, 1977

2) Westinghouse WCAP 7410-L (contains FIRL F.eport F-C2667)

QUALIFICATI0:I E!:VJHO"'it::iT Qual. Doc. #2 lTl!!E 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> l'ilESS

% 60 psig (0-60 psig in 7 sec.)

TE!iP 288*F REL. IlU.'I. 1001 N'-

' Cill:-!

None ryJ) 2.4 x 10, Rads QUALIFICATl0:1 METil0D3 -

Synergistic test on press., temp., humidity, followed by seismic, then radiation - on same instrument.

n

'Ihe above results are a sumnary provided for reviewer convenience, Note:

For complete details, see the above referenced report document (s). , \ v()

e on t-) ;J

l'a:N M __ .

TURKEY POIllT UNITS 3 6 4 EQUIPME:IT RCS AT-Tavg Temperature Elements TAG liU:GERS TE-412B, 412D, 422B, 422D, 432B, 432D IMilUFACTURER Rosemount Incorporated MODEL 176 KF QUALIFICATI0:: DOCUMEiiTATI0Il Westinghouse WCAP 9157 QUALIFICATI0:! E!; VIRO:;ME: T T1!!E 6 Days PRESS 66 psig TEIIP - 50*P to 290*F in 5 sec., 320 F for 20 min., Decline to 220 F in 24 hr., 220*F for 5 Days REL. 11U" loot

\\ CilE'1 None RAD 1 x 108 Rads QUALIFICATI0:1 METil0DS .

Radiation test, then synergistic test for press., tern.,

humidity - on same sensors.

Note: The above results are a surnary provideo for reviewer convenience.

For complete details, see the above referenced report document (s). c. a t. . s9 7

\tl i/J

s Page }-6 TUIO;EY POINT UNITS 3 & 4 EQUll'I41::lT RHR to RCS Inlet Isolation Valve Operators TAG 1;U:4h!:RS Mov-4-744A & MOV-4-744B 14AllUFACTURER Limitorque Corporation 140 DEL SMB-3 (Class II Insulation)

QUALIFIC/sTION DOCU:4EI:TATIO:1

1) Limitorque Letter to FPL dated May 23, 1979

2) Limitorque Test Report 600198 (containing FIRL Report F-C2232-01)

3) Westinghouse Letter NS-CE-692 to NRC dated July 10, 1975 (References FIRL Report F-C3441)

4) FPL letter from M.S. Gonzalez to S.G. Brain dated June 27, 1979 QUALIFICATI0:1 E?iVIRO:;.4E:!T Qual. Doc. #2 T114E O - 14 14 sec. 1-3 3-5 5 - 24 1-6 sec. to 1 hr. hr. hr. hr. Days PRESS psig 15-90 91 70 40 20 15 Tgip "F 142-329 329 312 287 272 - 256 250 to 247 REL. HUM.

% 100 100 100 100 100 100

s. CHCl See Note Start at 40 min., end at 4 hr. 40 min.

Below RAD 2 x 10 eRads (Qual. Doc. #3)

QUALIFICAT10:1 Fi!N' HOD 3

2) Synergistic tent for press., temp., humidity, chem. spran

3) Letter s g es that radiation tents in F-C-3tQpf l y g motors tested by Limitorque Report 600198.

Note: Chemical Spray Solution:

1.5% boric acid solution prcspred by dissolving 7 lbs. tech. grade boric acid in 55 gal. ~

(46C lb.) demineralized water. A 506 solution of reagent grade Naoll wan used to titrate dt $ h$ $o $"rh$uYN. a"e 'a stf ahry provided for reviewer convenience.

For complete details, see the above referenceu report document (s). g.

J/J 'i

I'"f2' 5-7 -

TURITY POINT UNITS 3 & 4 FQUllR:iT lli-11ead ST t o RCS 110 t 1.en Isol ation_ Val ve opercit ors TAG 1:U:'J0:Rfi Mov-866A, fm63 11AtlUFACTURER Limitorque Corporation

!!DDI:L SM-00 (Class B insulation)

r. .

QUALIFICATIO 1 DOCU:!E: TATIO:!

' lo7o Liru tomue__le t t nr to FPI +tted Mr. .3.

,}icat inahoun" WRAP 7410-L (containinq FTP1 Prnort F-r?4ns_n])

QUALIFICATI0:! 1" VJHO:: 'c::!T II D' 0-20 20-60 1-3 3-4 4 -512 571-7 7-8 8- 9 min, min. hr. ht. hr. hf. hr. hr.

PRE 3f; 0-40 40 psig 40 15 5 50 60 5 M 7 sm IU 112 to 230 285 250 298 307 283 227

• r 280 RI'L. 1:U:'

100 100 100 100 100 100 100 100 g

\[ CH L"4 See Note Spray from 20 min. to 4 hr. 20 min. and 5 hr. 20 min. to 6 hr.

nn i m. 30 min.

RAD 2 x 108 Rads '

QUALIFICAT10:1 i:T,'li3DS -

Synergistic test for press., temp., humidity, chen spray Radiation tect on different operator.

Note: Chemical Spray Solution ,

7 lbs. technical grade tauric acid in dd ya1. Hbo Ab) auainera12:ed water.

50% solution of reagent grade sodium hydroxide was used to titrate the borie acid solution to pit of 7.ca.

Note: 'Ihc above results are a summary provided for reviewer convenience.

For corplete details, see the above referenced report document (s). s o]

(. f)

PalN 5 -' 8 .

TURKEY POINT UNITS 3 & 4 EQUJI';-U NT RCS to RIIR Inlet Isolation Valve Operators TAG liU:4f tERS Mov-750. 751

!!AfiUFACTUICR Limitorque corporation MODEL SMn-1 (Clasn a insulation)

o. -

QUALIFICATI0:; DOCU:C :TATIO:l Limitorque letter to FPL dated May 23, 1979 Westinghoue.e WCAP 7410-L (containinc FIRL Report F-C243S-01)

QUALIPICATI0:1 E!NIRO:::C:!T T11iB 0-20 min.

20-60 min.

1-3 hr.

3-4 hr.

4-h hr. hr.

-7 7-8 hr.

8-9 br.

-4 40 15 5 50 60 40 5 ps 9 (in 7 sec.)

TiliP 112 to 230

• F 280 285 250 298 307 283 227 REL. llUM 100 100 100 100 100 100 100 100 s

\, CHLN See Notc Spray from 20 min. to 4 hr. 20 min. and 5 hr. 20 min. to 6 hr.

Below 30 min.

PJD 2 x 108 Reds QUALIFICAT]O:i ME"110D3 Synergistic test for press., temp., humidity, chem. spray Radiation test on different operator.

Note: Chemical Spray Solution .

,7 lbs. technical grade boric acid in 55 gal . (460 lb.) demineralized water.

50s solution of reagent grade sodium hydroxide was used to titrate the boric acid solution to pH of 7.85.

Note: The above results are a summary provided for reviewer convenience.

For complete details, see the above referenced report document (s). s .]

\

'l c

{\ -O'[)

"IN M TURKEY POINT UNITS 3 & 4 EQUIP;C:lT Emergency Containment Filter Douninn Valve TAG IIU:'JERS SV-2905, 2906, 2907, 2908, 2909, 2910 li*dlUFACTUHER Automatic Switch Company JODEL X8211 - B46 - SW (HV-164-196)

QUALIFICATI0:1 DCCU:Eiri'ATIO:I 1)Autonatic Switch Co. Test Report No. TP-2-06R 2)Wyle Laboratories Report No. 42086-1 ELIFICATIO:I E' VIHO:C'JJ:T Qual. Doc.'#2,l T Te s t ri i Tcne n TIIE 10 sec 24 Ilrs 1 1/2 Hrs 1 lir 8 Hrs 10 Sec to 1 Hr 13 sec .

p}<g33 Rise O to 58 psig l AM3 to 60 psig A33 58 psic to 65 psic l 60 psig 65 psin '

I TFJLa 122*F 122 F 293 F  ;

122*F to 284*F AFB to to 311*F .

284*F l293*F 311

• F .

t REL. HU:1  ?

60% 100% 100% 80% 100% 100% 100%

I

\ -

' CHE'!

None PdD None QUALIFICATIO:: METHODS -

Synergistic for Temp, Press, Humidity Both tests on same valve.

. a Note: The above results are a summary provided for reviewer convenience. '

g For complete details, see the above referenced report document (s) . ,

8

\ .)

(

cc l

Page 5-10 TUltKEY POINT UNITS 3 & 4 EQU]p;.;p;;T Fmergency containment Coolers (Motor) 3V30A, B, C ; 4V30A, D, C TAG DU:.'J1FRS IMilUPACTURER J y Manuf acturing ccnpany I-DDEL 38-26.5-1170 QUALIFICATI0:1 DOCUE.7ATIO:7 Joy Manufacturing Test Report (1969)

QUALIFICATI0:1 l'!! VIRO:JMr::JT TJIE 110 30 2 3 2 2 2 2 2 2h 1 3/, 2 4 Total Time hr. min. min. hr. hr. hr. hr. hr. hr. hr. hr. hr. hr. 25 hr.

0 > 7- >  % Add'l. Tests paws 7 psig AMB. to to 70 10 75 10 75 10 78 10 75 10 0-80 psig in 7 83 8 sec. 300 70 '200 250 300 300 300 TFi'P , 3

• F to to to 300 220 300 200 310 to 300 to to to 400 200 280 200 250 320 200 REL. }IU.s'.

% 100 100 100 100 100 100 100 100 100 100 100 100

\

\ Cill:4 See Note No No Yes Yes Yes Yes Yes Yes Yes Yes Yes n e l e- YeslYes TIAD s

^

l x lO RadsMinimum QUALIFJ CAT 10:1 METHODS

1) Synergistic - Pressure, temperature, humidity, cl:enical spray -

n, nrnentgro unir.

2) Radiation by analysis referencing previous tests on various

" ^ ~

Note: Chemical Spray Solution Sodium Ilydroxide . . . 0.1% by wt. .

Sodium Thiosulfate . . 1.04 v3 vh..

PotassiumIlydroxide . 4 ppm Boric Acid . . . . . . AC3 g . ,

pH 6.8 -

Note: The above results are a summary provided for reviewer convenience.

For complete details, see the above referenced report document (s) . \J

-c )

• Page 5-11 TUR13:Y POINT UNITS 3 5 4 EQU]IIli:!lT Emergency Containment Filters (Motor)

TAG liU:GERS 3v3A, B, C 1 4v3A, B, C IWli1FACTUHER Joy Manuf acturing Co mpany MODEL 42.25-26.5-1170 QUALIFICATI0:1 DOCU:EI;TATIOil Joy Manufacturing Test Renort (1969)

QUALIFICATI0:1 E!!V2iiO:;KE:iT 1 3 T]IE 110 30 2 3 2 2 2 2 2 2h 14 2 4 Total Time hr. min. min. hr. hr. hr. hr. hr. hr. hr. hr. hr. hr. 25 hr.

PRESS 7  ;,dd'l. tests 0  %

> 7- >

78 10 75 10 0-80 psig in psig AMD to to 10 75 10 7 83 73 10 75 g g ,., c ,

TE!U' 300 70 200 > 250 > 300 300 300

• F to to to 300 220 300 200 310 to 300 to to to 400 200 2RO 200 250 320 200 REL. IlU:!. _.

% 100 100 100 100 100 100 100 100 100 100 100 100

\

\ ClllM See Note e s Yes Yes Yes Yes Yes Yes Below llAD 1 x 10S Rads QUAL 1FICATIO:3 MICT110D3

1) Synergistic - Pressure, temperature, humidity, chemical spray -

on prototype unit.

2) Radiation by analysis referencing previous tests on various materials used.

Note: Chemical Spray Solution Sodium Hydroxide . . . O.1% by wt. .

Sodium Thiosulfate . . 1.0% by wt.

Potassium llydroxide . 4 ppm Boric Acia . . . . . . 7 000 ppm

• Ph . . g.g. g. g,c' [hbits are a summary provided for reviewer convenience, s i

J For complete detailu, see the above re ferenced repot t document (s) . O C;3

Pul',e ,512 TURKEY po1NT UNITS 3 & 4 EQUII;C;lT 600V Power & control cables TAG liU' LIERS N47, N50, N52, 53, 54, 55, 56 lailUFACTUltEll okonite Company j.ge)pgg X-Olene/ Okoscal QUALIFICATI0:: DOCU:Ei!TATIO:1 l') Okonite letter to Bechtel dated March 22, 1971

2) IEEE Transactions Paper Vol. PAS 88, No. 5 May 1963 QUALIFICATJ 0:1 1:!; VIRO:UC:IT TJ I'I' 32 Days lHFOS 40 psig T1211' 288'F liL'L , llU.' :.

100%

A' CllD1 None 1 x lo s Rads -

QUALIFICAT]O;! !!hil!0DS -

Irradiated samples were tested synergistically for press.,

temp., humidity.

Note: 'Ihe above results are a summary provided for reviewer convenience. ,, 4 For complete details, see the above referenced report document (s). ( j" I

Q)

TURFEY POINT UllITS 3 & 4 ,,

EQUIl'IC:IT Instrumentation Cables TAC liU::EErtS 60, 61 MAllUFACTURER General Electric Company MODEL Vulkene QUALIFICATIOtt DOCUME!!TATIO:1

1) GE Letter to Bechtel Dated May 30, 1979 (Containinr. the rollowing)

2) Technical Review of Vulkene Insulated Cables by F.M. Precopio, Ph.D.

3) Wire and Cable for Nuclear Power Plants, A Status Report on the GE Wire and Cable Department Conprehensive Testing Program 9

QUALIFICATI0:1 E!! VIRO: ME:IT Oual. Doc. 3 T]!IE 10 lirs 300 lirs PilESS 70 psig 5 psig TDT

• 310*F 150*F REL. HU:1 100% 100%

\ -

CHD1

' 200Gppm H B0 -Na0li - pil9 (Sprayed on Cables) 3 3 1

PJW 8 i 2 x 10 rap I

I QUALIFICAT10:1 MET)!ODS Radiation Exposure, then Synergistic Test for Press, Temp, ilumidity Chem. Spray on Same Cable. Reference 1 states that the cabics tested by Refirence 3 could be representative of the cable supplied for Turkey Point.

Note: 'Ihc above results are a sumary provided for reviewer convenience. s' ') ',

For complete details, see the above referenced report document (s).

( 'J;b

l'ar.e* 5-14 TURKEY POINT UNITS 3 & 4 t

EQU11';!UNT Thermocouple Extension Wire TAC 1:U:.lB"Tts N77 IdANUPACTUltER Thermo Electric Co., Inc.

JODEL E/GS/CUCS - Ta' EEX QUALIFICiTION DOCU:'i'I."TATIO:1 Thermo Electric letter to FPL dated June 4, 1979 QUALIFICATIO:! E!IVIRO:::'E:!T T11IE PRESS TDiP.

REL. IlU.'!.

\

\' CHD1 RAD ,

l QUA1,IPICAT10:1 METl!ODS - I By analysis f rom data supplied by '1hermo Electric in above ,

Ictter, Bechtel P.O. 5610-E-55, and Thermo Electric Quotation WS-0038 alt. dated May'9, 1968. See Section 3.3-9.

Note: 'the above results are a summary provided for reviewer convenience.

• For complete details, see the above referenced report document (s). '

C O r. 1 i

j/J lJO

l'q;e 5-15 TURKEY POINT UNITS 3 & 4

~

EQUll'M'. ilT IIcat Shrink Insulation TAG !iU:4!s!:RS 11AllUFACTURER Raychem Corporation MODEL WCSP QUALIFICATIO:t DOCU:4EIITATIO:1 Franklin Institute Research Laboratories Final Report F-C4n33-3 QUALIFICATI0:1 E?iVIRO:!'n::17 Tll!E 10-12 12 hr. to 4 Days ti 7 Days 0- 5 min. 5 min. to 10 hr. hr. 4 Days 30 Days PRESS 0 to 70 psi 9 70-+31 psig Not 31 psig  % 10 psig (in 10 sec.) > 70 psig (in 1 hr.)

TE!?P 140-280*F 302*F (in 25 sec.) 357*F 3 57-27 5* r 275'a 212*r to 357*P REL. HU:L Not 1001 100% 100s 100% 100%

s Measured

\ CHE"! Chemical Spray Solution: 3000 ppm Boron as Boric one Acid, 0.064 Molar Sodium Thiosulfate adjusted with

%nn en pn e r19_5 n r c ,- t_ g u tyr; RAD 7 5x 10 Eads .

s 1.5 x lo Rads (For a 8total of

? x 10 R)

QUALIFICAT10:1 METHODS Synergistic - All parameters.

r-Note: 'Ihe above results are a r.umary provided for reviewer convenience.

For complete details, see the above referenced report document (s) .

,n.xe

\J

Pal;c .2-15 TURFIY POINT Uti1TS 3 & 4 EQUIPl:ENT Terninni Blocks TAG !!UMBEE

}{AllUFACTURER Ceneral Electric Company MODEL EB-5

~ .

QUALIFICATION DOCU:EllTATION

1) FPL Material Test Section Test Report No. R238-1354

2) PSL 1 FSAR 3.11.5.3 QUALIFICATI0!! ENVIRONMENT Test No. ?

TII'I 1 month PRESS 0 psig TE!!P 250*F REL. HU:!.

100%

Q. CHD!

2000 ppm Boron as boric acid RAD 1 x 10 R, QUALIFICATION METHODS

1) Blocks were tested for temp., humidity, and intermittent chemical spray for.one month. 'Ihere were no f ailures at

,e 12 6V \C o r l'_%'DC .

2) Radiation test was on GE CR151 block. which is same material as the EB-5 block.

3) See analvais on Section 3.1-10.

Note: The above results are a suc=ary provided for reviewer convquippcc.IJ t=g For complete details, see the above referenced report document (s)J '/ J

l'abe 5-17 TURKEY POINT UNITS 3 & 4 1:QUJ PT!.: lT Penetrations TAG llU:'Jil:RS 14AllUPACTURER Crouse-111nds Company 140 DEL QUALIFICATION DOCU CUTATIO:J FPL dated May 17, 1979

1) Crouse-liinds 1ctter to

2) NRP Penetration Steam Incident and llelium Leakage Report QUALIFICATIO:1 121VIRON:0:: T 0-5 5-8 8-16 16-25 25 sec 10-30 30-60 60-100 see 10 min min min min sec see see

>68 75-82 82-58 58-31 31-8 0-69 69-78 >75 psig psig psig psig psig psig psin psig 318 r i

320*F 315*F 310*F 297*F 270*F 283*F 296*F to T12L[ to to to to to to to 320*F 315 F 310*F 297*F 262*F

>q3*r 296*F 318'F HEL. HU:!. 100%

100% 100% 100% 100%

100% 100% 100%

's A

s CHl:4 No RAD

• No QUAL 1FICAT10:1 M'dTl!ODS

2) Tested prototype unit for press, temp, humidity (synergistic)

Note: 'Ihc nhove results are a summary provided for reviewer convenf ence. , 'j)

For complete details, see the above referenced report document (s). \

(

c ' , ' .)

TURKEY POINT UNITS 3 6 4

. E2UIPMEliT Penetrations _

TAG NUM3FRS It%'UFACTUllER Crouse-Ilinds Company

~

MODEL QUALIFICATION DOCUMENTATI0:.

3) Teleconv f rom b'estinchouse to FPL dated June 12, 1979. _

QUALIFICATION ENVIRO?:".E"T Qual. Doc. #3 TI!IE 18 Hours 6 Hours PF. CSS Not Recorded 56 psig TE U' 320*F to 250*F 340*F REL. IIU:'.

100% 100%

Ci!F.'1 No No H/d1 No No QUALIFICATI0:7 MFTiiODS

3) Not specified Note: h e above results ... {9b .

Note:

ne above results are a sumery provided for reviewer convenience.

For complete details, see the above referenced report document (s).