ML20049J288

Forwards Request for Addl Info Re Reactor Sys.List of Agenda Items Which Instrumentation & Control Sys Branch Wished to Discuss in Upcoming Meetings Encl

ML20049J288
Person / Time
Site:	Catawba
Issue date:	02/25/1982
From:	Adensam E Office of Nuclear Reactor Regulation
To:	Parker W DUKE POWER CO.
References
NUDOCS 8203120400
Download: ML20049J288 (4)

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FEB 2 01982 Docket File Nos. 50-413/414 LB #4 r/f DEisenhut bcc: TERA KJabbour L PDR Docket Hos.: 50-413/414 EAdensam NRC PDR MDuncan NSIC SHanauer TIC RTedesco ACRS (16)

Mr. William O. Parker, Jr.

RVollmer Vice President - Steam Productiuon JKramer P.O. Box 33189 RMattson Charlotte, North Carolina 28242 RHartfield, MPA 0 ELD

Dear itr. Parker:

01&E (3)

Subject:

Request for Additional Information - Catawba Nuclear Station In the perfornace of the Catawba station licensing review, the NRC staff has identified the need for additional information in the Reactor Systems area as stated in Enclosure 1.

We request that you provide the information requested no later than March 15, 1982. contains a list of additional agenda items which the Instrumen-tation & Control Systeas Branch (ICSS) would like to discuss with you in forthcoming meetings. These items are in addition to those enclosed in our letters to you dated December 21, 1981, and January 12, 1982.

If you require any clarification of these matters, please contact the project nanager, Kahtan Jabbour, at (301) 492-7821.

The reporting and/or recordkeeping requireuents contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing

Enclosures:

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Mr. William O. Puker g Vice President - Steam Production stiuke Peger Cocpary

" 0. Box 33189 Charlotte, fiorth Carolina 28242 cc:

William L. Porter, Esq.

North Carolina Electric. shership Duke Power Corpany Corp.

P.O. Box. 33189 3333 North Boulevard Charlotte, North Carolina 28242 P.O. Box 27306 Raleigh, North Carolina 27611 J. Michael McGarry, III, Esq.-

Debevoise & Liberman Saluda River Electric Cooperative, 1200 Seventeenth Street, N.W.

Inc.

Washington, D. C.

20036 207 Sherwood Drive Laurens, South Carolina 29360

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North Carolina MPA-1 P.O. Box 95162 James W. Burch, Director Raleigh, North Carolina 27625 Nuclear Advisory Counsel 2600 Bull Street Mr. f. J. Twogood Columbia, South Carolina 292C1 Power Systems Division Westinghouse Electric Corp.

Mr. Peter K. VanDoorn P.O. Box 355 Route 2, Box 179N Pittsburgh, Pennsylvania 15230 York, South Carolina 29/45 Mr. J. C. Plunkett, Jr.

James P. O'Reilly, Regional Adm.nistrator-HUS Corporation U.S. Nuclear Regulateey Comission, 2535 Countryside Boulevard Region II' Clearwater, Florida 33515 101 Marietta Street, fuite 3103 Atlanta, Georgia 30303 Mr. Jesse L. Riley, President Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28208 Richard P. Wilson, Esq.

Assistant Attorney General S.C. Attorney General's Office P.O. Box 11549 Columbia, South Carolina 29211 Walton J. McLeod, J r., Esq.

General Counsel South Carolina State Board of Health J. Marion Sims Building 2600 Bull Street Columbia, South Carolina 29201

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o REACTOR SYSTEMS BRANCH REQUEST FOR ADDITIONAL INFORMATION LOCKED REACTOR COOLANT PUMP ANALYSIS The analyses of a locked reactor coolant pump rotor and a sheared reactor coolant pump shaft in the FSAR assumes the availability of offsite power throughout the event.

In accordance with Standard Review Plan 15.3.3 and GDC 17, we require that this event be analyzed assuming turbine trip and coincident loss of offsite power to the undamaged pumps.

Appropriate delay-times may be assumed for loss of offsite power if suitably justified.

Steam generator tube leakage should be assumed at the rates specified in the Tech-nical Specifications.

The event should also be analyzed assuming the worst single failure of a safety 5

system active component.

Maximum technical specification primary system activity and steam generator tube leakage should be assumed.

Th'e analyses should demon-strate that offsite doses are less than the 10 CFR 100 guidelines values, t

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ADDITIONAL CAW'BA AGLfDA IIEMS

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IfiSTRUMLiiTATION AND CONTROL SYSTEf5 BP.ANLH 117.

Using detailed schematics describe the operation of ci,cui*

sed for the Diesel Building Ventilation System.

Discuss the starting of the e:r.ergency fans and shutting-off of the normal fans.

Discu<

r.ua l initiation of the Emergency Ventilation Systen.

118.

Using detailed schematics and logic Jiagra es, descr ibe the ope r. Lion and initiation of the Cont rcl ko r. Area H^ating, Ventilation and Air Conditioning Sys tem.

Discuss t.hich ESFAS signal is used to initiate the systm.

Discuss chlorine riunitors, radiation r.onitors, and < d e detectors.

their interfaces with the Control Room Area iF.1C systora.

119.

Using detailed schematics, describe the circuits for automatic connection of t c a:iliary Shutdown Panel Room A/C Systems to the Class if '

i'ower during accident conditions.

Discuss which ESFAS signal is used to initiate the action.

120.

First r,rt. graph on page 7.6-36 of FSAP, states: "Upon high radiation the air flow is automatically directed through the filter train".

First paragrach on page 9.4-7 of FSAR states: "Upon indication of h igh radiation level it.

> unit vent, the Auxiliary Building supply and cxhiont f ans are automatically stopped" Please clarify this apparent discre *cy.

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