ML19323B470

Forwards Sys/Component List & Environ Profile for Electrical Equipment.Sodiumdichromate Is Used in Containment Spray Sys.Solution Causes No Detrimental Effect

ML19323B470
Person / Time
Site:	Oyster Creek
Issue date:	05/07/1980
From:	Finfrock I JERSEY CENTRAL POWER & LIGHT CO.
To:	Crutchfield D Office of Nuclear Reactor Regulation
References
TASK-03-12, TASK-RR NUDOCS 8005120409
Download: ML19323B470 (50)

Text

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. . Jersey Central Power & Light Company Mac. son Avenue at Punch Bowi Road

['f ff Mornstown. New Jersey 07960 (201)455-8200 MAY 0 7 i330 Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Operating Reactors United States Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20555 Cear Mr. Crutchfield:

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 ,_ . - y Environmental Qualification of Electrical Equipnent - -C/

During our meetings (March 10-13, 1980) with the NRC staff at Oyster Creek Muclear Generating Station concerning the above subject , the Plant Emergency Procedures were reviewed and a list of safety related systems essential to mitigate postulated accidents and safely shutting down the plant was generated.

Subsequently, JCP&L develcped a list of components in these systems. The letter dated March 28, 1980 frora D.L. Ziemann (Chief, Operating Reactors Branch

42) to I. R. Finfrock, Jr. requested a list of systems to mitigate the postulated events. The system / component list and and environmental profile for each piece of equipment are enclosed as attachments to this letter. Please note tnat the attached component list does not includes those pieces of equipment inside containment. A list of these components were transmitted to the NRC in our letter dated December 19, 1978. The summary of the analysis to define environmental conditions is given in Attachment 1. The results of the analyses are shown in Table 1 ( Attachment 2) . Integrated radiation exposure inside containment is still being evaluated. Temperature profiles for each component are provided in Table 2 and Figure 1 through 18 ( Attachment 3) . Although not shown on Table 1, a conservative assumption of 100% relative humidity was used in the analysis.

The only chemical spray used at Oyster Creek Nuclear Generating Station is sodium dichromate solution in the containment spray system. An evaluation by GPU System I4coratory concluded that this solutien causes no detrirantal effect as identified in Attachment 4.

We are continuing to pursue qualification documentation evidence through in-house analyses, direct vendor contact, NSSS contact and contacts with other utilities having similar equipment. To date there is no evidence to show any safety related equipment will fail under the anticipated accident environment.

l V% 1 jrs,m; CWai Rysr ". L gri Ccr"pany S a Me'"cer et tre G+ eral %cic Ut !.t es 3nte'"

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! We will submit by September,1980 tne list of electrical equipment as i required by this program with either references to qualification reports, tecnnical justification for continued use of existing components using plant

specific conditions, probabilistic considerations and more realistic assumptions, or a schedule of testing and/or replacing. Parts of Table 1 in Attachment 2 were developed using the NRC's guidance document NUREG-0578.

Recognizing this represents generic guidelines enveloping worst case conditions which include conservative assumptions, plant specific analyses will be l developed, where required, to demonstrate acceptability of components.

i l Enclosure 2 to the aforementioned March 28, 1980 letter also requested j data necessary for the staff calculation of containment temperature and pressure decay time. The data is provided in Attacnment 5.

In view of redundant containment spray systems available at Oyster Creek Nuclear Generating Station, we believe that using 340 F for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> as the basis for judging whether individual component qualifications meet the guidelines is overly conservative. We are in the process of performing a plant specific

analysis of the main steam line break to define the representative temperature profile for Oyster Creek Nuclear Generating Station. It is anticipated that the results of this analysis will be available by the end of June,1980. Therefore, the information necessary for staff review of plant specific containment analyses (Enclosure 3 to the March 28, 1980 letter) will be provided at that time.

Very truly yours, J/g 4R Ivan R. Finf k, r.

Vice President Sworn and subscribed to before me this day of , 1980.

4 t

Notary Public i

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T DOCKET NO. 50-219 ATTACH 5ENT 1 OYSTER CREEK NUCLEAR GENERATING STATION ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIP 5ENT SU) NARY OF ANALYSIS MAY,1980

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i The Nuclear Regulatory Commission (NRC) has recently man-

, dated in letters to utilities that the environmental qualification of electrical equipment required to ftmetion subsequent to certain postulated accidents be reviewed. The postulated ac-cidents include a LOCA inside containment or a High Energy Line Break (IIELB) inside or outside of containment.

t j The qualification conditions to be considered include the following:

1. Post accident presrure, temperature, and humidity conditions

2. Post accident radiation exposure

3. Exposure to post accicent chemical spray

4. Submergence .

l l At a 31 arch 17,1980 meeting, the Jersey Central Power and i

Light Company (JCP&L) requested EDS to execute the analyses necessary to adequately define the post accident service con-

) dition profiles for electrical equipment whose designation and 4

plant location were specified by JCP&L. The EDS scope of

, work included the following tasks:

~{ 1. Develop pressure and temperature time histories for plant areas outside of containment based upon postulated line breaks in the following systems specified by JCP&L:

l Alain Steam System j -

Alain Feedwater System i

Reactor Cleanup System l

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)

Page 2 1

Emergency Condenser System

2. Calculate radiation levels at component locations selec-ted by JCP&L in plant areas outside of containment.

3. Calculate radiation levels inside containment.

The thermal-hydraulic analysis to develop the pressure and temperature service condition profiles was performed utilizing the EDS proprietary comouter code EDS FLOW.

4 The thermal-hydraulie results are summarized on Table 1 and

supporting Figures 1 through 1S, which indicate the various 4

temperature time history profiles. A temperature profile was generated in cases where compartment temperature exceeded 1000F.

Radiological analysis was conducted utilizing source terms furnished by JCP&L. the computer code QAD-5PA, and in some cases hand calculations. Table 1 indicates the total in-tegrated radiation exoosure one year subsequent to a LOCA at a number of component " targets" specified by JCP&L.

Table 2 summarizes analysis executed to define the total one year integrated radiation exposure to equipment located inside contaimnent subsequent to a LOCA. The exposure is divided I into the following contributoiy components:

1. Reactor Vessel Streaming

2. Containment Airborne Activity

3. Torus Streaming

4. Drywell Sump Activity The above components are algebraically summed in total or partially dependent upon the equipment specific location withLn containment.

Page 3 The results of the above discussed analyses, as summarized on Tables 1 and 2 and Figures 1 through 18, provide JCP&L with an accurate prediction of enviromnental conditions exist-ing in plant areas subsequent to cer:ain postulated accidents.

This information can be used to assess the capability of exist-ing equipment in terms of qualification, and/or as the source document for preparing an equipment qualification specifica-tion.

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DOCKET NO. 50-219 ATTACHMENT 2 OYSTER CREEK NUCLEAR GENERATING STATION ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT ELECTRICAI. EQUIPMENT ENVIRONMENTAL CONDITIONS l

l MAY, 1980

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• Indecates that equiprnent is not regtdred to mit!Cate the TA)]l C I consequentes e,f the acenftnt outsas!c of containment or M ' ail,ft CP,f Fis M r't t 11' (W lt.a TNG 51 \ ris W 4.e achtete a safe shutet.mn for that acesdent. For a E 1 LCllt1C AI. 7 (p (PMF vl F N\ pts p% M). v) gg Co. gia q.,x3 lerud. insulu o nt.umnent, astcrisked items am neeled to on.tiga:c tfic atesant, however, the environmental e..n.l.teons sur thet.u pterisktd items wouldIm normal amhaent cor.dat6ohh.

l at. .t tw .y. 1 Approximat e Peak Tempe r atu re Irg g s, ept s .n l ocato.n co..rihiate s Worst Case Temperataare t l'eak Total tnte g rate f t h utt ri tardite l'rcstas te y m. g%3, J0F) Ra4atiatwn Eq->su re (t Yr.)

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2. V 4'i 16" Emer Cund. 239 l ag. 4 terywell Vent & purge 16 14t\ 1.4 % Nf M Vab e Hg x If f 2F 3.9 % l'0d DJs W Drpstt Vent & Ivr6,e 7[ -

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DOCKET NO. 50-219 1

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ATTA001ENT 4 OYSTER CREEK NUCLEAR GENERATING STATION I

ENVIRON >! ENTAL QUALIFICATION OF Ei.ECTRICAL EQUIPS!ENT j EFFECT OF CilR051 ATE SOLUTIONS l

I I

l i

STAY, 1980 l

l l

(5)

EFFECT GF CHROMATE SCLUTIONS ON SOME ELASTOVERS AND METALS AT OYSTER CREEK Cable Insulating Materials Regardi ng the e f fect of the chromate ions in the torus water at Oyster Creek cn cable insulating materials such as polyethylene, polyvinyl chieride and ethylene propylene, it is reported in the literature that these materials will be unaf fected in neutral or alkaline chromate solutions up to 150 F for typical short term test exposure periods ( 6 months). All these materi al s, however ,

4311 suf fer some form of mild degradation such as loss of strength or hardening

• Ith Icng term continuous exposures. This generally dces not af fect performance in the early stages and therefore many years of exposure can be tolerated.

Metals in general, chromates are primar t ly used to inhibit the corrosion of metals and alloys wh ich demonstrate active passive trans i t ions . Metals undergoi ng these transitions are nikel, silicon, chromium, titanium and alloys containing these metals. Therefore, these metals should become more corrosion resistant when exposed to a chromate sol ution.

A corrosion data survey revealed the following metals to experience very low corrosion rates ( 2 mpy) when imersed in a 10% sodium chromate solution at temperatures up to 180 F:

(1) Cast iron (gray, nickel, silicon)

(2) Mild steel (3) Austenitic stainless steels (302, 304, 316, 317, 321, 347)

(4) Martensi"Ic stainless steels (405, 410)

(5) Copper base alloys (copper 85-99.9, brass 70-80 Cu + Zn, Sn or Pb, brass 59-93 Cu + AI , Zn or As, Cupro-nickel 66-88 Co, 11-33 NT)

(6) Nickel base al icys ( nicke l 99, Ni-Cu 66-32, N3-Cr-Fe 76-16-7, NT-Fe-Cr 32-47-20, Ni-Mo 62-23 + Fe, V; Ni-Cr-Mo 54-15-16 + Fe , W)

(7) Aluminum (3) Lead

(9) Titanium (10) Zine (11) Cada.ium Therefore, one would expect the corrosion rates of these metals to be no greater than 2 mpy when sprayed with 150 F torus water containing 900 ppn sodium enromate. Thus the short term exposure of containment metal to chromates will prcduce negligible corrosion.

l

1 DOCKET NO. 50-219 ATTACIl>fENT 5 OYSTER CREEK NUCLEAR GENERATING STATION ENVIRON 5! ENTAL QUALIFICATION OF ELECTRICAL EQUIP 5fENT DATA NECESSARY FOR TllE STAFF CALCULATION OF i

CONTAIN5fENT TE>tPERATURE AND PRESSURE DELAY TI51E u

SIAY, 1980

(

DATA NECESSARY FOR THE STAFF CALCULATION OF CONTAINMENT TEMPERATURE AND PRESSURE DECAY TIF.

I DATA REQUIREMENT RESPONSE I. 1. Reference the most current 1. The containment design LOCA analysis on the docket basis LOCA for Oyster Creek that defines the service is discussed in the FDSAR, conditions to be used in Section XIII-2. This was equipment qualifications. reanalyzed in Amendments No. 32 and 68, response to ques-tion 3. Mass and energy data for this DBA LOCA are not available on the docket, but are being provided herein.

2. With respect to that analysis, provide the following:

A. Containment Met Free A. Drywell: 180,000 FT3 Volume Netwell: 213,300 FT3 B. Passive Heat Sinks B. Passive heat sinks were not utilized in the DBA LOCA containment analysis. However, heat sink information for the containment wall surfaces is provided in Table 1 which is attached to this document.

C. Initial Containment C. Drywell Wetwell Atmosphere Conditions for: Temp. ( F) 135 120 Press. (PSIA) 15.5 15.5

1. Temperature Humidity 1003 100%

2. Pressure

3. Relative Humidity D. Containment Spray System

1. Parameters and their 1. Vessel Level: double low setpoints to activate Drywell Pressure: 2 psig spray.

i

. .' 2 DATA REQUIRE 1ENT RESPOMSE

1. D. Containment Spray System (Continued)

2. Spray System Activa-tion Time:

a. time elapsed until 2a. Double low level:

signal te '.ctivate 2 psig drywell spray is re ched. pressure: .85 sec.

b. instrumentation 2b. 500 msec.

lag

c. time required for 2c. 18 sec.

diesel generator to attain full operating speed

d. time required for 2d. 40 sec. _+ 15% time loading of contain- delay.

ment spray pump

e. time required to 2e. Valve normally open open isolation valve

f. time required for 2f. To be supplied later containment spray pump to achieve full speed

g. time required to 2g. To be supplied later fill spray system and deliver water to spray header

3. Identify the spray heat 3. Shell and tube heat ex-exchanger type. changer with four pass flow on the tube side and two pass flow on the shell side. Water from the wet-well flows on shell side and raw service water is on the tube side. See attached Figure 1.

r

3 DATA REQUIREMENT RESPONSE E. Fan Cooler System E. Not applicable F. Other containment heat F. Not applicable removal system G. Provide a discussion of G. The analysis assumes the single failure a loss of offsite assumed in the analysis power and a failure of a diesel generator.

H. Provide the mass and H. This data has been energy release data for obtained recently the postulated pipe break from General Electric considered Company and is pro-vided in Table 2 attached to this document.

II. Provide a figure which repre- II. A figure (Figure 2) describing sents the ECCS and spray the Oyster Creek core spray systems relied on to miticate and containment spray systems the consequences of a pipe and the pertinent data asso-break. Provide pertinent ciated with these systems is information for these attached to this document.

systems. Indicate whether The containment spray flow the values given assume a represents the flow from a single failure and specify single pump which would the single failure assumption. experience a runout flow con-dition since the loop is designed for two pump flow.

This represents one half of one loop only. The remaining loop is assumed to be in-operable. The core spray flow shown represents the flow from one of the two loops available as well.

1 l

l l

, _ 1

TABLE 1 OYSTER CREEK PASSIVE HEAT SINK DATA Thickness Areg Geom.

• bterial Inch ft- Type

1. Biological Shield - Lower Concrete 48 443. Cyl.

2. Biological Shield - Middle Concrete 60. 185. Cyl.

3. Biological Shield - Upper Steel 0.25 1044. Cyl.

Concrete 29.4 Steel 0.31

4. Drywell - Floor Concrete 11.25 1374. Slab

5. Drywell Sphere - Lower Steel 1.154 2542. Spher.

Insulation 2.5 Concrete 78.

6. Drywell Sphere - Middle Steel 0.770 4210. Spher.

Insulation 2.75 Concrete 78.

7. Drywell Sphere - Upper Steel 0.722 3085. Spher.

Insulation 2.75 Concrete 78.

8. Drywell Transition Steel 2.56 1433. Spher.

Insulation 2.5 Concrete 78.

9. Drywell Cylinder Steel 0.640 1287. Cyl.

Insulation 2.5 Concrete 78.

10. Drywell Head Steel 1.188 428. Spher.

11. Torus Steel 0.385 7476. Cyl.

MATERIAL PROPERTIES Volumetric Thermal Conductivity Heat Capacity Material (BTU /hr-ft F) (BTU /FT3 _07)

Concrete 0.92 22.62 Steel 27 58.8 FIRE-BAR 0.02 3.74 (Asbestos fiber -

magnesite cement)

TABLE 2 OYSTER CREEK DBA LOCA (CE)

MASS / ENERGY RELEASE DATA I

Vessel Liq. Liquid Lgg Liquid LBM Vessel Tine (Sec) Temp. F Blowdown, IRRi Blowdown, see Pressure. PSIA 0 548.8 3 72 E + 4 0 1035 0.5 548.2 3.713 E + 4 0 1030 1.0 547.5 3.705 E + 4 0 1024 1.5 546.7 3.697 E + 4 0 1018 2.0 546.0 3.688 E + 4 0 1011 2.5 545.3 3.680 E + 4 0 1006 3.0 544.8 3.675 E + 4 0 1002 3.5 544.5 3.671 E + 4 0 999.4 4.0 544.3 3.669 E + 4 0 997.4 4.5 544.1 3.666 E + 4 0 996.3 5.0 543.9 3.664 E + 4 0 994.7 5.5 6.0 543.i 3.658 E + 4 0 991.2 6.5 7.0 54?.0 3.651 E + 4 0 986.7 7.5 8.0 542.2 3.641 E + 4 0 980.5 8.5 9.0 541.2 3.628 E + 4 0 972.2 9.5 540.2 1.882 E + 4 4.995 E + 3 964.1 10.0 534.7 1.752 E + 4 4.94 E + 3 920.8 10.5 528.9 1.627 E + 4 4.863 E + 3 877.3 11.0 523.0 1.507 E + 4 4.768 E + 3 833.8 11.5 516.9 1.391 E + 4 4.653 E + 3 790.6 12.0 510.5 1.287 E + 4 4.547 E + 3 747.7 12.5 503.9 1.188 E + 4 4.429 E + 3 705.1 13.0 497.1 1.09 E + 4 4.282 E + 3 663.1 13.5 490.1 9.947 E + 3 4.115 E + 3 621.9 14.0 482.9 9.063 E + 3 3.945 E + 3 581.8 14.5 475.5 8.276 E + 3 3.786 E + 3 542.6 15.0 467.9 7.534 E + 3 3.621 E + 3 504.6 15.5 460.2 6.784 E + 3 3.423 E + 3 467.8 16.0 452.4 6.078 E + 3 3.217 E + 3 432.7 16.5 444.5 5.442 E + 3 3.020 E + 3 399.4 17.0 436.5 4.851 E + 3 2.819 E + 3 367.9 17.5 428.5 4.31 E + 3 2.623 E + 3 338.1 18.0 420.4 3.819 E + 3 2.431 E + 3 310.3 18.5 612.4 3.387 E + 3 2.254 E + 3 284.2 19.0 404.3 3.026 E + 3 2.104 E + 3 259.7 I 19.5 396.1 2.702 E + 3 1.962 E + 3 236.6 20.0 387.8 2.4111 E + 3 1.827 E + 3 214.7 l

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i OYSTER CREEK CORE SPRAY MID CCNTAINSE !T SPRAY FLCW DRYWELL FLOW FRACTIO::

= 0.95 DayWELL SPRAYS 0 hm j ong hv1 /r" A O n ,

TORUS 3 6 A A CCOLI :G FLOW /,rg / s't /'81 4'{

WATER FLOW FRACTION

= 40 PM* = 0.05

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SPRAY HX U = 287 ,

_A__= 6 2 0 0 FT HX

,, 1 SREAK DRYWELL CC::TAIUMENT 10 I 130 F il r

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S PW5Y DRYWELL SPRAY

+ BPEAK FLOW TORUS ' PITURNS TO TORUS e  % b, yo. -

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= 3400 GPM I

• ACTUAL PERFOPJ! MICE OF 1000 GPM PUMP UNDER RUNOUT CONDITIONS CC::SISTENT WITH SINGLE PUMP OPERATION.

FLOW = 6000 GPM FOR TWO PUMP OFERATION. ,

FIGURE 2