ML20137A194
| ML20137A194 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/18/1997 |
| From: | Hernan R NRC (Affiliation Not Assigned) |
| To: | Kingsley O TENNESSEE VALLEY AUTHORITY |
| References | |
| TAC-M96598, TAC-M96599, NUDOCS 9703200234 | |
| Download: ML20137A194 (3) | |
Text
'
4 4
8 March 18,1997 Mr. Oliver D. Kingsley, Jr.
President, TVA Nuclear and Chief Nuclear Officer Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - TECHNICAL SPECIFICATION CHANGE REQUEST TS 96-07 FOR SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 (TAC NOS. M96598 AND M96599)
Dear Mr. Kingsley:
The staff is reviewing the subject proposed Technical Specification change requests submitted-by the Tennessee Valley Authority in a letter dated August 28,1996, " Pressurizer Safety Valve and Main Steam Safety Valve Setpoint Tolerance Increase." To complete our review of your request, the response to the attached request for additional information is needed.
I Please contact us if you have any questions.
Sincerely, i
Original signed by Robert Martin for Ronald W. Hernan, Senior Project Manager Project Directorate II-3
,N Division of Reactor Projects - I/II t
Office of Nuclear Reactor Regulation
/
J
~,
.t Docket' Nos." 50-327 and 50-328
.Enclosur$:1;Requeftjor Ad,11tional Information
,cc W/snclosure:e See next page
, Di stributio~n:
1
- " " Docket Filet PUBLIC SQN Rdg. File S. Varga a
J. Zwolinski '
}\\P, C. Jackson
' +
M. Shannon, RII u
NBC FBICENER COPY DOCUMENT NAME: 5:\\SQN\\SQ96598.RAI l
I TO GET e copy of this document, Indicate in the box:
"C" = Copy wtthout attachment / enclosure "E"
- Copy with attachment / enclosure "N" s No copy 0FFICE PDIl-4/ $ y ~
PDII-4/LA PDII-4/D,)
c, NAME RHernanl/ v/
BClayton FHebdon W DATE
' 3 / /8 797 3/If /97 1 / 19 /97 0FFICIA[RECORDCOPY 9703200234 970318 PDR ADOCK 05000327 P
l WATTS BAR NUCLEAR PLANT I'
cc:
Mr. Oliver D. Kingsley, Jr.
Mr. Richard T. Purcell, Plant Manager i
President, TVA Nuclear and Watts Bar Nuclear Plant Chief Nuclear Officer Tennessee Valley Authority Tennessee Valley Authority P.O. Box 2000 6A Lookout Place Spring City, TN 37381 1101 Market Street Chattanooga, Tennessee 37402-2801 Regional Administrator U.S. Nuclear Regulatory Comission Mr. O. J. Zeringue, Sr. Vice President Region II Nuclear Operations 101 Marietta Street, NW., Suite 2900 Tennessee Valley Authority Atlanta, GA 30323 6A Lookout Place 1101 Market Street Senior Resident Inspector Chattanooga, TN 37402-2801 Watts Bar Nuclear Plant U.S. Nuclear Regulatory Comission Mr. Jack A. Bailey, Vice President 1260 Nuclear Plant Road Engineering & Technical Services Spring City, TN 37381 Tennessee Valley Authority 6A Lookout Place County Executive 1101 Market Street Rhea County Courthouse Chattanooga, TN 37402-2801 Dayton, TN 37321 Mr. J. A. Scalice, Site Vice President County Executive Watts Bar Nuclear Plant Meigs County Courthouse Tennessee Valley Authority Decatur, TN 37322 P.O. Box 2000 Sp ing City, TN 37381 Mr. Michael H. Mobley, Director Division of Radiological Health General Counsel 3rd Floor, L and C Annex Tennessee Valley Authority 401 Church Street ET 10H Nashville, TN 37243-1532 400 West Sumit Hill Drive Knoxville, TN 37902 Mr. Raul R. Baron, General Manager Nuclear Assurance and Licensing Tennessee Valley Authority 4J Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. Pedro Salas, Manager Licensing and Industry Affairs Tennessee Valley Authority 4J Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. Paul L. Pace, Manager Licensing and Industry Affairs Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381
e.
s
.v REQUEST FOR ADDITIONAL INFORMATION i
l REGARDING PRESSURIZER SAFETY VALVE AND MAIN STEAM i
l SAFETY VALVE SETPOINT TOLERANCE INCREASE i
2 1
Q1)
Justify the following chtnges in assumptions from the current FSAR analysis:
a) Current -
Initial RCS Temperature is assumed at its maximum j
value consistent with steady-state full power.
i New -
Initial RCS Temperature was set to its nominal value minus four degrees for control band and measurement uncertainty.
b)
Current -
Initial RCS Pressure is assumed at a minimum value 4
l consistent with the steady state full power operation.
New -
Initial RCS Pressure is assumed at its nominal value consistent with steady-state full power operation.
I c)
Current -
Initial RCS Power is assumed at its maximum value l
consistent with steady-state full power.
New -
Initial RCS Power is assumed at its nominal value consistent with steady-state full power operation.
Q2)
In the August 28, 1996 submittal, you indicated that +3% and +5%
tolerances were used for the MSSVs_and PSVs respectively. However, the Mark-BW Fuel Assembly Topical Report indicates that 6% and 5% tolerances were used for the MSSVs and PSV respectively.
Provide a discussion of the actual tolerances used for the peak pressure analysis. Al so, discuss and justify your modeling of (or assumptions for) valve lift characteristics.and accumulation.
Q3)
Current TS require the PSV lift setpoint to be set at 2485 psig (2500 psia). According to Table 6.1-3 of the Mark-BW Fuel Assembly Topical Report, the high pressurizer pressure reactor trip setpoint can be as high as 2425 psig including instrumentation channel error and setpoint error. For the proposed negative tolerance change of -3% show that the change does not result in lifting the PSVs at or before the reactor trip.
Provide a similar discussion for the effects of the -3% tolerance for the PSVs on the operation of the pressurizer PORVs and -3% tolerance for the MSSVs on the steam generator relief valves, i
Q4)
What initial pressurizer level was assumed in the analysis? Justify your answer with respect to peak pressure considerations.
Q5)
What were the peak primary and secondary pressures achieved in the analysis?
ENCLOSURE