REGULATIPY INFORMATION DISTRIBUTIO@YSTEM (RIDS)

ACCESSION NbR:8301040557 DC.DATE: 82/12/30 NOTARIZED: NO FACIL:50*305 Kewaunee Nuclear Power Plant, Wisconsin Public Servic AUTHNAME AUTHOR AFFILIATION GIESLERC, lisconsin Public Service Corp. RECIP,NAMt RECIPIENT AFFILIATION . VARGAS,A, Operating Reactors Branch 1

DOCKET # 05000305

SUBJECT: Forwards addl info re environ qualification of safetyrelated welectrica equipmentihigh energy line break analyses in response .to 821130 request.

DISTRIBUTION CODE: A048S CQPIES RECEIVED:LTR ENCL SIZE:. TITLE: OR/Licensing Suomittal: Equipment Qualification

NOTES:

RECIPIENT 10 CODE/NAME

NRR OR1 18C 12

COPIES LTTR ENCL

1 0

RECIPIENT ID CODE/NAME LICCIARDOR. 01

COPIES LTTR ENCL

1

INTERNAL: ELO/HDS3 IE FILE NRR/DE/EQB NRR/DL/ORAB NRR/DST/GI6B RGN3

12 09 07 06

I 1 2 1 1 1

1 1 2 1 1 1

GC NRR CALVOJ NRR/DL DIR

E F E

13 1 1

14 1 1

04 1

EXTERNAL; ACRS NRC PDR NTIS

TOTAL NUMBER OF COPHES REQUIRED: LTTR

15 02

1 1 1 1 I

88 1 1 1 1

LPDR NSIC

03 05

1 1

1 1

26 ENCL

* )NRC-82-225

WISCONSIN PUBLIC SERVICE CORPORATION

A 0. Box 1200, Green Bay, Wisconsin 54305

December 30, 1982

Mr. S. A. Varga, Chief Operating Reactors Branch #1 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Varga:

Docket 50-305 Operating License DPR-43 Kewaunee Nuclear Power Plant Environmental Qualification of Safety - Related Electrical Equipment: High Energy Line Break Analyses - Request for Additional Information

References: 1. Letter to C. W. Giesler of WPSC from S. A. Varga of the NRC dated November 30, 1982.

2. Letter to E. R. Mathews of WPSC from S. A. Varga of the NRC dated June 18, 1981.

3. Letter to S. A. Varga of the NRC from E. R. Mathews of WPSC dated September 21, 1981.

4. Letter to S. A. Varga of the NRC from E. R. Mathews of WPSC dated December 15, 1981.

5. Letter to E. R. Mathews of WPSC from S. A. Varga of the NRC dated February 22, 1982.

6. Letter to S. A. Varga of the NRC from E. R. Mathews of WPSC dated March 18, 1982.

7. Letter to E. R. Mathews of WPSC from S. A. Varga of the NRC dated February 16, 1982.

6301040557 821230 PDR ADOCK 05000305 P PDR

Mr. S. A. Varga December 30, 1982 Page 2

In your letter of November 30, 1982 (reference 1), you requested additional information in order to complete your review of the High Energy Line Break (HELB) analyses performed for the Kewaunee Nuclear Power Plant (KNPP). Enclosed, is the requested information for your review.

In addition, you stated that our earlier submittals concerning this subject (references 3 and 4) did not fully address your request in Item 3.4 of the Safety Evaluation Report transmitted by reference 2. Wisconsin Public Service Corporation (WPSC) does not agree with this statement and takes exception to it. In reference 3, we responded to your letter of June 18, 1981 and the attached Safety Evaluation Report. In regards to Item 3.4, we described our ongoing program to specify the temperature, pressure and humidity environments resulting from HELB's outside of containment and provided a schedule for the submittal of this information to you. In accordance with this schedule we submitted the results of our analyses on December 15, 1981 (reference 4). This submittal consisted of completed system component evaluation worksheets (SCEWS) for all the equipment needed to mitigate HELB's outside of containment and a discussion of the results of our analyses. The areas subjected to HELB's were identified on the individual SCEWS by the location of the component and the designation of "Harsh: HELB Yes" on the bottom of the sheets. This identified the component as being subjected to a harsh HELB environment. The harsh environmental parameters were also designated using your nomenclature (T, P, H, CS, R, S). The actual service conditions to which the components would be exposed and the corresponding documentation references were listed in the environmental and documentation specification columns on the SCEWS.

Furthermore, in your letter of February 22, 1982 (reference 5), you requested that we provide additional information to your consultant, Franklin Research Center, in order to facilitate their review of the environmental qualification of safety-related electrical equipment at the KNPP. The requested information was transmitted to Franklin Research Center by copy of our letter of March 18, 1982 (reference 6), per the instructions given in reference 7. Part of this request included additional information on the environmental service conditions specified at the various equipment locations (section A, paragraph 2). Documentation reference number 111 was provided in our response to this request. This reference contained a description of the HELB analyses performed including node and junction diagrams, input parameters, and the results presented in both tabular and profile form. Therefore, we do not agree with the statement that our earlier submittals did not fully address your requests.

Very truly yours,

C. W. Giesler Vice President - Nuclear Power

is Attach. cc - Mr. Robert Nelson, US NRC

Enclosure to Letter from C. W. Giesler

To S. A. Varga

Dated December 30, 1982

HELB Analyses

Request for Additional Information

Y~.

832670

The following information is gathered in response to the NRC letter from SA Varga to C. .1. Giesler, of WPS, dated November 30, 1982, requesting additional information on the analysis of pipe breaks outside containment. The information is provided in accordance with the items shown in the Request,for Additional Information sheet (see Attachment).

la. Saturated steam

1b. 5470 F

ic. 1020 psia

1d. Steam generator at stand-by.

2 le. From the Hoody correlation, the mass velocity is 2100 ibm/sec-ft2 .

For a large break in BI the corresponding blowdown rate is 1753.5 lbm/sec

and that for a small break in D is 104.4 1bm/sec.

Both blowdown rates are assumed to be constant.

if. 1191.4 Btu/bm constant.

2a. See Fig. 1 and Fig. 2. The remote nodes indicated with asterisks in

Figure 2 were not mod eled in the analysis.

2 h. i, 80o for all nodes

ii, 14.7 psia for all nodes

iii, 30% for all nodes

iv,

v, Fig. 3 (total of 4 sheets) and Fig. 4 (total of 9 sheets)

vi,

Fig. 1 and Fig. 2.

-2

3a. The discharge coefficient for the break is 1.0 and the shape factor for

the interconnected compartments is assumed to be 2.9 (see diagram 4-9,

Handbook of Hydraulic Resistance by Idelchek).

3h. Not used in the analysis

3c. For the compartment in which the break is postulated, Tagami's blowdown

heat transfer model is used. And Uchida's condensing heat transfer model

is used for the rest of the compartments. The input specification is

described in CONTEMPT4/MOD 2 program.

4a. Fig. 5 and Fig. 6

4b. The pressure transients are very moderate with peak pressures of less

than 1 psi. Therefore, no pressure transient curves are plotted.

4c. Following the break, all compartments are at 100% relative humidity.

IITL

12/21 /82

832670

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UNITED STATIES fYUCLE-AR RECULLATORY COMMISSION

WWMiNTON 0. C. 2055s

November 30 M MULAR PtO;E[R PLNT '

cket No. 50-3M5 0WAQ -34 TI ROEIL cA AGN 7 JA TA WIEAf

JJ LULA Wt. C. W. Giesler Li CHAPY0LI

RIN ONES Vice President - Ycle-ar Porwer PL LN Wisconsin Public Service Corporation F AISHAR

Poit Office Box 1200 LOBtu?;, G4eABay. Wisconsin 54305 LP RZELS

CA SOUKUP NM EODD

Dear Mr. Gesler; SE BLATT FPS TASK

On J)une 18, 1981 w sent you a letter with an~ttached auto Report ( SER) regarding the Envirornental Qual1fication of: aeyfeae Equirr~ent for the Kevaunee Nuclear Pwer Plant. We requested that you provide us with the Information identified in Section~s 3 ar~d 4 of this SER. within 90 dayS.

Iten 3.4 Tem~perature, Pressure, and liwidity Conditions Outside Contairuint re-aJs as, follows:

*MThe licensee has an ongoing program to specify tmnperature. pressure. and humidity environm~ents as a result 3f IIELBS outside containmient. The licensee's submiittal cintaining these should identify the speific Areas where tI10LB5 can occur a~ well as the envirornental conditions for~ the areas_. A schedule should be subitted as soon as possible regarding the submilttal of this Inomto.

your responses dated Septber 21 and December I.S. 1981 did not fully address this request in r*9ard to Itea 3.4. In order to cm7plete our review of this iss-ue we need the information identifiel in the encloture to this letter. We request that you provide the informiation within 30D dars of the date of this letter-.

(K e,~~~ e Vrg ef GgeatngReact3tr rarnth #1

Division of Licaanslng

Enclosure: Request for Additional

cc-trco~urt:)ee ntxt page

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Mr. C. W1. Giesler Wisconsin Public Service Corporation

r, r Steven E7. Keane. Esquire Foley and Lardner 777 East Wisconsin Avenue Milwaukee. Wisconsin 53202

Stanley LaCrosse, Chairmuan Town of Carlton Route 1 Kewaunet, Wisconsin 54216

. a'. Nuclear Regulatory Cmission Resident Inspectorz. Office Route 0~, Box 99'9 Kawaune#, WISC~nsin 54216

James G. K~pple' negional Administrator - Region III Ui. S. Nuclear Regulatory CoawusSfon 799 Roosevelt Rtoad Glen Ellyn, Illinois 60137

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REOUEST FORADDITION4ALINFORMATION~4

RES~M AND TFPUTU PROFILES FOR PIPE BREAKS OVTSIDECONTAIN!

The fOllwlng Information is require for' each pipe bre~ak analysis ty the applicants. perforwo

1. With respect to the pipe to be broken. we need to knmo the:

a. Type of fluid (water or stemi); 6. Teature;, c. Pressure; d. Source of the fluid-, e. Flow rate (or assumed flow rate) versus time; and f. Enthalpy versus tim

2. With respect to the c artmeits being analyzed:

a. Number of coqiartment analyzed; b. Fer ea ch 'a~ertt:*

i. initial tvqwature ii. initial pressure

M~.. Initial humildity Iv. floor area 'Including floor space taken by equipuwnt (square feet) v. number of vents and vent ar*as (square feet) for each -vent; and vi. cowqartuent wall height (feet) and

c. Simle coaruant and lntercunmwvtion diagram.

3. All a~suiptions used. including but not limited t* the:

a. Orifice coefficient; b. Fluid expansion facton *d c. -Heat transfer coefficit for heat through the wells

4. litilities analysis results:

a. Temperature versus time curve (peak tooeraturt specified); b. Pressure versus time cuveY ipeak pressusre specified); and c. Humidity versus time curv eak Ihimdity specified)

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