ML20039B730

Request for Addl Info Re Equipment Environ Qualification Review of Licensees Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment

ML20039B730
Person / Time
Site:	Rancho Seco
Issue date:	12/21/1981
From:	FRANKLIN INSTITUTE
To:	NRC
Shared Package
ML20039B731	List: ML20039B730
References
CON-NRC-03-79-118, CON-NRC-3-79-118, RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.1.2, TASK-TM IEB-79-01B, IEB-79-1B, RFI-C5257-486, TAC-42507, NUDOCS 8112230491
Download: ML20039B730 (5)

Text

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.r ENC.LOSURE 1 l

REQUEST FOR ADDITIONAL INFORMATION EQUIPMENT ENVIRONMENTAL QUALIFICATION (EEQ)

REVIEW OF LICENSEES' RESOLUTICN OF OUTSTANDING ISSUES FROM NRC EQUIPMENT ENVIRONMENTAL QUALIFICATION SAFETY EVALUATION REPORTS (SER) AND TMI ACTION PLAN INSTAR.r.En EQUIPMENT Sacramento Municipal Utility District Rancho Seco Nuclear Generating Station NRC Docket No. 50-312 December 21, 1981 NRC TAC No. 42507

.FRC mailing address is as follows:

Mr. Cyril J. Crane Franklin Research Center The Parkway at Twentieth Street Philadelphia, PA 19103 Telephone No. 215/448-1353 Telecepy No. 215/448-1296 Telecopy Confirmation No. 215/448-1215 l

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. Franklin Research Center A Division of The Franidin Institute The Bergerran Frankin Pernway. Nia Pa. 19103(215)448-1000 I

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RFI-CS257-486 BACKGROUND Franklin Research Center (FRC) of Philadelphia, Pa. is providing assis-tance to the U.S. Nuclear Regulatory Commission (NRC) for the equipment environmental qualification (EEQ) review of operating reactors. FRC will perform an EEQ re tiew of the Licensee's 90-day response to outstanding issues from the NRC Equipment Environmental Qualification Safety Evaluation Report (SER) and the installed TMI Action Plan equipment. The review will be limited to safety-related equipment potentially exposed to a harsh environment. The

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results will be presented in the form of a technical evaluation report for each plant.

This request for additional information (RFI) is the result of an evaluation of the information provided by letters dated November 3, 1980 [1]

and September 8, 1981 [2].*

FRC previously requested til Action Plan information by a telephone memorandum dated August 19, 1981 (3].

A.

FRC REVIEW OF THE LICENSEE'S 90-DAY RESPONSE TO THE NRC EEQ SER Information Recuested Date Received by FRC**

1.

In reference to the Licensee's 90-day response [2] to the NRC SER [4], a legible single copy of each of the following qualification documents is requested in order that the FRC evaluation may proceeds a.

Siemens-Allis Equipment Qualification b.

Topical Report BAN-10003, Rev. 4 c.

NAMCO EA-180 Test Report, 3/1/78 d.

Westinghouse Qualification Report e.

Joy Manufacturing Company, Susmary and Discussion of Design Considerations and Simulated Environmental Testing

• Numbers in brackets refer to citations founo in the list of references.

• • This column will be completed by FRC as the requested information is received.

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RFI-C5257-486 Cate Received bv FRC**

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Conax IPS-49, dated 1/17/72

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Conax IPS-27, dated 1/4/71 h.

International Nutronics Lab No. 5527, dated 2/16/78

i. Rosemount Qualification Test Report 117415 j.

F. J. Levandowski letter to B&W Owners Group dated 6/12/80

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Beta Attenuation Calculation REFERENCES 1.

Rancho Seco Nuclear Generating Station, IE Bulletin 79-01B Response Sacramento Municipal Utility District, 03-Nov-80 2.

W. C. Walbridge Letter to J. F. Stoly, NRC. Subjects Rancho Seco Nuclear Generating Station Unit No.1 - Response to 5/29/81 letter on EEQ Sacramento Municipal Utility Di: strict, 08-Sep-81 3.

Telephone Memorandum C. J. Crane (FRC) conversatiors with M. Padovan (NRC), H. Knieries,

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and R. E.

Daniels (SMUD).

Subject:

Request for Information, EEQ Review - TMI Action Plan Items, Rancho Seco Nuclear Generating Station, 19-Aug-81 4.

Office of Nuclear Reactor Regulation Safety Evaluation Report for Rancho Seco Unit 1 Environmental Qualification of Safety-Related Electrical Equipment NRC, 29-May-81 5.

J. J. Mattimoe Letter to D. G. Eisenhut, NRC.

Subject:

Amendment 1 to the s

Submittal of October 31, 1980 on IE Bulletin 79-OlB Sacramento Municipal Utility District,13-Jan-81 6.

NUREG-0737, " Clarification of IMI Action Plan Requirements" NRC, November 1980

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RE UEST FOR PROFILES INFORMATION FOR Please provida PIPE ON BREAKS PRESSURE En losure 2 c

brek the following ilocation (the basis, a OUTSIDE AND a

CONT TEMPERATURE such AINMENT ssumptions as a nform tion.uxiliary feed 1

With r a

and an e pect s

Type to the pipe t w ter pump roanalysis a

a.

of fluid (watero be broken; om) thata typical of in ludespipe b.

c Tempera ture; or s team);

c.

Pressur ;

e d.

Sour ce of Flow the fluid; e.

r te (or a

f.

Pipe intern l assum d e

flow Wetted diameter; ra te);

a g.

h.

perimeter Tota l of pipe intern l the bre k (fe i.

a Exit et);

a v lum ;

flow o

e j.

Are a rea, i f the break was a of k.

flow Dif ferentia l res tric tion not in the pipe if 1

Tota l eleva ti any; flow on fr

, just de re istan om the ce (o ly if source to the pi scribed above; m.

s Means to n

stop flui n.

1.m is flow (n the fluid pe break; If d

is co fficient, v lv lve, the one, gate wa ter);

e a

a v lv a

e n the v lve, globe With r closure. a closur a

ve v lv a

espect e time, e 's open throat arevalve, etc.);

to the and a.

delay tim a, full Number compartm and of e

Fo compartm ents being an l initia tioopen flow until r each ent anal a yzed:

n of 1

compartm yzed; and ent:

init ial ii.

temper ture a

init ia l

'i.

pressur init ia l e

humidity p/

s 2

iv.

free air volume (cubic feet) v.

number of vents and vent areas (sq vi, minumum pressure to initiate ficw tuare feet) for each vent; an 3

All assumptions used, including b o the next compartment (paia)

Orifice coefficient for the "end effut not limited a.

b.

Fluid expansion factor ects" for the discharded fluids; and

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Enclosura 2 REQUEST FOR INFORMATION ON PRESSURE AND TEMPERATURE PROFILES FOR PIPE BREAKS OUTSIDE CONTAINMENT Please provide the basis, assumptions and an analysis of a typical pipe break location (such as auxiliary feedwater pump room) that includes the following information.

1.

With respect to the pipe to be broken:

a.

Type of fluid (water or steam);

b.

Temperature; c.

Pressure; d.

Source of the fluid; e.

Flow rate (or assumed flow rate);

f.

Pipe internal diameter; g.

Wetted perimeter of the break (feet);

h.

Total pipe internal volume;

i. Exit flow area, if the break was not in the pipe, just described above;

j. Area of flow restriction, if any; k.

Differential elevation from the source to the pipe break; 1.

Total flow resistance (or.ly if the fluid is water);

Means to stop fluid flow (none, gate valve, globe valve, etc.); and m.

If 1.m is a valve, then the valve's oper, throat area, full open flow n.

coefficient, valve closure time, and delay time until initiation of valve closure.

2.

With respect to the compartments being analyzed:

Number of compartment analyzed; and a.

b.

For each compartment:

1.

initial temperature ii. initial pressure 111.

initial humidity

2-iv.

free air volume (cubic feet) v.

number of vents and vent areas (square feet) for each vent; and vi. minumum pressure to initiate flow to the next compartment (psia).

3.

All assumptions used, including but not limited to the:

a.

Orifice coefficient for the "end effects" for the discharded fluids; and i

b.

Fluid expansion factor.

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