ML042880520
| ML042880520 | |
| Person / Time | |
|---|---|
| Site: | Pennsylvania State University |
| Issue date: | 10/01/2004 |
| From: | Sears F Pennsylvania State Univ |
| To: | Mendonca M, Witt K Office of Nuclear Reactor Regulation |
| References | |
| Download: ML042880520 (2) | |
Text
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1.5-2M4 09:36 P.05/06 From: Fred Seers ccfsnuc@ongrpgu.edu>
To: Mendonca, Marvhi' MMMlnrc.gov>, Kevin Wit. .dkrnw~nrc.gov>
Dle~t: 1011(04 9:03AM Subjoct: PSBR TS 4.1.1 Chengo Requect Penn State Breazeale Reaclor. LICense RP2 Facility Docket fNumbe 50005 Request for Change/Extension o1 Allowable Time Peod forTS 4.1.
This email requesis a change to the allowable time period for Tech Spec 4.1.1. PReaclor Power Calibraion, for the Penn Slate Breazoalf t Roactor, Ucenuo R-2, Facility Docket Number 50.005. It tris change is not possible a one-time' three (3)month extension of the allowable - U I;mo period Is requested. 0 Tech Spec 4.1.1 requires 'A thermal poweor caIbration shal be madrr La on the linoer power level monloring channol annuaqj, not to exceed c J .S 15 months. CCP-2, Reactor Thermal Power Cadbratlon, Isthe Implermrnlng procedure for accompishlng Tech Spec 4.1.1. Our last thermal power calibration was porformned on July 6th and 151h, 2003.
As we ware upgrading our reactor consolo computers (beginning of August, 2004) and moving to a new fuel loading (mid-August, 2004), Ye vs C 2 delayed performanceo ol CP-2. Reactor Thermal Power Caltibraliont n after those two evolutions were performed sinCe the new fuel loading would have requirud another thermal power catibratlon. When we undertook Iho performanco of CCP-2 on August 271th. 2004, our prim; try V f1 flow measurement Instrumentation suffered an electrical failure. This , J Instruentaltion ki i a nagnotic flow measurement device. Other Instrumenlallon such as flow orfices and turbIne flow meters have proven unreliable duo lo the extremely ahort uns of pipe and many bends of our primary coolant hoat exchanger system. The magnotic fIw n
device Is somewhat unique since is designed for the high purity water used Inour primary system. To dale we have been unable to obtain appropriate repair or replacement of that flow device. The -1 current efforts to return thD flow measurement system to service and , -(9,.- V perform CCP-2 may not be completed Intime to meot the 15ronthn inlorval. u t In conjunction with the new fuel loading the steady stale reactor power has been administratively linited to B50 kW with a reduction of RSS overpower astpoints trom, 108% to 93%Y. This reduction was put bto ~)'>fj effect upon completing the core loading change and will remain In effect until CCP.2 Iscompleted and any necossary changes to the ) c IUnour power level mnoniloring channel aro comnpleted. The effect of R .
the new fuel loading on measured power was prediced to be less than Y%.The best estimate of change in Indicated power was expected to b Y within the measuremont uncertainties. The 15% reductIon Inpower level and selpoints was thus conservative. Operations to date based on both measured fuel temperatures and Irradiation results have not shown any noticeable variation between Indicated power and eopected result3 for that power level. Tl1us we have reasonable assurance that the Indicated power Isvery close to the actual power.
Initially we only intended to ask for on extension of the allowable time period but upon reviewing the history of thermal power t
(573)-445-7607 p. 2 Oct 13 04 06:44a ho1iday inn Select Ut-13-z204 09:36 P. 06'06 caribralions 4 was lound that our experience base over the last fiv years eupported an overall change to Ih9 affowabo llmo period fro n
'annually, not to exceed 15 months" to "every 24 months, not to excoed 30 months' Review 0oour records sho- that the last t1ne we needed to adjust indicated power to the thermal power maasursments was 1998. Si ice that tIme alt thermal power calibrations have met the acceptance criteria and no adjustments were made. Thus we have a five-year history showing that annual dJusatmant Is not needed and this In tu n supports Increasing the required surveillance Interval from 12 mont is to 2A months.
t-Since we have reasonable assurance as to actual power level and ire operating with restricted power level due to moving to the new core loading we believe eiiher a change or an extension Is appropriate. I Ve have significant educatIon, research, and eorvice work that would b i negalively Impacted It we had to shutdown the reactor. Every elfor eLO has been and Is being made to complete our Instrumentation repair/replacement In time to be In comphance with the existing TS 4.1.1.
This change request has been reviewed with the Chairman of the P inn 0 State Reactor Saleguards Commitsoo. Due to the emerent nature iIt C,0 this issue there Is Wsullicient time to got the funl conrmrltea review. The Chalrman has approved the submital of this change request. The change request will be reviewed with the full commnittot during their scheduled meetlng on October 19, 2004.
r/
It there are any questions regarding Ihis request please contact me.
Your acknowledgement ol receIpt of this change/extension raquest 1; requested.
CJ C9 Fred Sears Director, Radiallon Science & Engineering Center Breazea!e Nuclear Reactor The Pennsylvania Slate Unirersity University Park, PA 16802-2301 Ph 814-865-6351 Fax 863-4840 CC: Terry Flinchbaugli dhlnuceungr.psu.odu5., Tom Ul ringer daime9engr.psu.eduw, Larry Burton .-. Burton4engr.psu.edu>. 'Eva i. PeW' 'eIp~psu.edu>. 'Ori Roun, Thomas, cTFlO)irc.gotV>,
Mac Bryan .cmobnucengr.psu.9du:
TOTAL P.06