ML20248B996

Forwards Request for Addl Info Re 890810 Tech Spec Change Request 88-03 Re Low Temp Overpressurization Protection Sys. Requests Info within 45 Days of Ltr Receipt

ML20248B996
Person / Time
Site:	Sequoyah
Issue date:	08/02/1989
From:	Black S Office of Nuclear Reactor Regulation
To:	Kingsley O TENNESSEE VALLEY AUTHORITY
References
TAC-R00430, TAC-R00431, TAC-R430, TAC-R431, NUDOCS 8908090391
Download: ML20248B996 (3)

Text

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Distribution Doc M Nos'. 50-327 emDocketdHe OGC arnd 50-328

. NRC PDR BGrimes i Local PDR EJordan ADSP. Reading MSimms Mr. Oliver D. Kingsley, Jr. DCrutchfield Edordan Senior Vice President, Nuclear Power TQuay ACRS(10) l Tennessee Valley Authority BDLiaw GPA/CA I 6N 38A Lookout Place RPierson ACRS(10) {

1101 Market Street SBlack SQN Rdg. File . j Chattanooga, Tennessee 37402-2801 BWilson (

LWatson

Dear Mr. Kingsley:

JBrady

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATIGL, TECHNICAL' SPECIFICATION CHANGE '

REQUEST 88-03(TACN05.R00430/R00431)-SEQUOYAHNUCLEARPLANT, UNITS 1 AND 2 By letter dated August 10, 1988, the Tennessee Valley Authority (TVA) submitted proposed changes to the Sequoyah Technical Specifications- (TS), adding ~ opera- i i

bility and surveillance requirements for' the low-temperature overpressurization protection (LTOP) system. This is TVA s TS change request 88-03. Additional information was provided by TVA in its letter dated May 18, 1989.

We can not. complete our review of the proposed TS changes until'you provide responses to the enclosed request for additional information. To keep to our schedule, you are requested to provide this information within 45 days of recoipt of this letter.

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

Sincerely,

• Original signed by Gerald E. Gears for Suzanne Black, Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation Er. closure:

Request for Additional DFOI' Information i I

cc w/ enclosure:

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i Mr;., Oiiver D. Kingsley, Jr. '

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Ceneral Counsel Mr. Kenneth M. Jenison Tennessee Valley Authority Senior Resident Inspector 400 West Summit Hill Drive Sequoyah Nuclear Plant ET 118 33H U.S. Nuclear Regulatory Commission Knoxville, Tennessee 37902 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 Mr. F. L. Moreadith Vice President, Nuclear Engineering Mr. Michael H. Mobley, Director l Tennessee Valley Authority Division of Radiological Health 400 West Summit Hill Drive T.E.R.R.A. Building, 6th Floor WT 12A 12A 150 9th Avenue North Knoxville, Tennessee 37902 Nashville, Tennessee 37219-5404 Dr. Mark 0. Medford Dr. Henry Myers, Scienta Advisor Vice President and Nuclear Committee on Interior Technical Director and Insular Affairs Tennessee Valley Authority U.S. House of Representatives 6N 38A Lookout Place Washington, D.C. 20515 Chattanooga, Tennessee 37402-2801 Tennessee Valley Authority -

Manager, Nuclear Licensing Rockville Office and Regulatory Affairs 11921 Rockville Pike Tennessee Valley Authority Suite 402 SN 157B Lookout Place Rockville, Maryland 20852 Chattanooga, Terressee 37402-2801 Mr. John L. LaPoint Site Director l Sequoyah Nuclear Plant l' Tennessee Valley Authority P. O. Box 2000 Soddy Daisy, Tennessee 37379 Mr. M. Burzynski Acting Site Licensing Manager Sequoyah Nuclear Plant P. O. Box 2000 Soddy Daisy, Tennessee 37379 County Judge Hamilton County Courthouse Chattanooga, Tennessee 37402 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W.

Atlanta, Georgia 30323 w _---___ - _ _ _ _ - - - - - - - - -- - . _ _ _ _ - _ _ _ _ _ _ _ - - -A--

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. ENCLOSURE l ~, . . .

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. REOUEST FOR ADDITIONAL INFORMATION

_ TECHNICAL SPECIFICATIONS CHANGE REQUES TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 l In reviewing the licensee's submittals dated August 10, 1988 and May 18, 1989, the staff can not find documentation that the proposed or the lift setting pressurizer power operated relief valves (PORV) will ensure ure/

that the temperature (PT) limits in Figures 3.4-2 (heatup) and 3.4 .

of the (cooldo 2 cooldown.

Sequoyah Technical Specifications thermal stresses should be included in the Sequoyah low temperat (TS) r are n overpres-surization protection analyses, the staff requests the following scf

1. j sensing devices and the PORV. Identify the instrument error fo .

2.

Discuss if the proposed PORY lift settings include instrument e the effect of these settings on plant operations.

3. ,

For a 60'F per hour heatup from startup temperatureant to a reacto water temperature corresponding to a reactor vessel metal RT tempe; fa$tIrs+ 90'F, provide the thermal stresses and the stress intensity  ;

(primary flaw sized membrane according and thermal) to Paragraph'G2120 at the 3/4 in Appendix G T vessel locati

\

III. l

. ASME Code Section 1 4.

For finite cooldown rates identified in Figure 3.4-3 of the TS from i operating temperature to a steady state shutdown temperature, p thermal stresses and stress intensity factors (primary membrane a thermal Paragrap)hat the 1/4G2120 T vesselin location for a flaw Appendix G,sized according ASME Code to Secti 5.

Discuss if the proposed PORY lift settings ensure that the lim ss and temperature transients do not result in reactor coolant press temperatures in Figures 3.4-2 exceeding and 3.4-3 of PT limits, with finite heatup and the TS. own rates, coold Provide curves comparing the proposed cooldown PORV rates. lift settings with the PT curves for the finite heatu 6.

Discuss the effect of the lift settings in Item 5 on plant n.

operatio

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