ML20046B153

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Addresses Long Term Corrective Actions in Response to Generic Ltr 92-04
ML20046B153
Person / Time
Site: Oyster Creek
Issue date: 07/30/1993
From: Keaten R
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
5000-93-0052, 5000-93-52, C321-93-2208, GL-92-04, GL-92-4, NUDOCS 9308030181
Download: ML20046B153 (2)


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GPU Nuclear Corporation l a i pan , e Je s y07054 201-316-7000 ,

TELEX 136-482 1 Writers Direct Dial Number July 30, 1993 C321-93-2208 5000-93-0052 U. S. Nuclear Regulatory Commission 'i Attn: Document Control Desk Washington, DC 20555

Dear Sir:

Subject:

Oyster Creek Nuclear Generating Station i Docket 50-219 Response to Generic letter 92-04 Generic Letter (GL) 92-04 dated August 19, 1992, requested licensees to determine  ;

the impact of potential level indication errors after a rapid depressurization event on how the plants are operated. GL 92-04 also requested licensees to take .

short term compensatory measures to mitigate the consequences of potential level indication errors after a rapid depressurization event and provide the staff with plans for long term corrective actions including any proposed hardware modifications. Short term corrective actions were addressed in GPUN letter dated  !

September 29, 1992. The purpose of this letter is to address long term corrective actions. i Backaround i

On August 28, 1992, the BWR Owner's Group submitted to the NRC a Generic Report  !

which identified that BWR's use hot reference leg level instrumentation, cold  :

reference leg instrumentation, or a combination of both for safety system  !

actuation. By letter dated September 29, 1992, GPUN identified that concerns -

relative to noncondensible gases coming out of solution have no impact on OCNGS -  !

automatic safety. system response during licensing basis transients or accidents. ,

The lo and Lo-Lo reactor water level signals associated with the RPS and ECCS are  :'

sensed by the hot leg Yarway instrumentation, which are not susceptible to the noncondensible gas phenomenon due to their geometric configuration. The OCNGS '

emergency operating procedures (E0Ps) direct the operator to flood the reactor ,

whenever confidence is lost in the level indication. In addition, the operator '

practice of verifying level indication prior to termination of injection for i level control has been reinforced.  !

)  !

9308030181'930730 W! I l

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ADDCK 05000219 PDR N'

{ gl GPU Nuclear Corporation is a subsid;ary of General Pubhc Utikties Corporation

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I C321-93-2208 Page 2 j

4 By the letter dated June 14, 1993, GPUN summarized reactor vessel water level  !

measurement capability at OCNGS and associated protective functions, and j concluded that the concerns raised by NRC Bulletin 93-03, dated May 28, 1993, ,

" Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in .

BWRs" did not apply to OCNGS. The draindown scenario during cooldown conditions addressed by NRCB 93-03 is precluded at OCNGS by the fact that drywell isolation i valves for the shutdown cooling system and the reactor water cleanup system are j actuated based on Lo-Lo RPV water level. As noted above, Lo-Lo water level is sensed by Yarways, which are not susceptible to the noncondensible gas, i Lona Term Corrective Actions  ;

Although OCNGS does not rely upon cold reference leg instrumentation for safety l system actuation, GPUN recognizes the importance of maintaining all instrumentation as accurate as possible, and of accounting for those situations .

which impact instrument accuracy. j In order for errors due to entrainea noncondensible gases to occur, two ,

, conditions must be present: 1) a concentrating mechanism which occurs when gases are stripped from condensate returning to the reactor vessel by inlet steam to the chamber, and 2) reference leg leakage enabling concentrated noncondensible i 2

gases dissolved in the condensate to be drawn into the reference leg. To  !

preclude the possibility for this type of error at OCNGS, GPUN intends to modify ,

2 the steam line/ condensing chamber configuration so as to eliminate the  !

counterflow of steam and condensate, thereby eliminating the concentrating mechanism. GPUN intends to install this modification consistent with the l Integrated Scheduling Plan. At present, this plan calls for installing the  !

modification during the 15R refueling outage, scheduled to begin in October 1994.

Should you have any questions, please contact Brenda DeMcchant, Licensing Engineer at 609-971-4642.  :

Very Truly Yours, l 1 i l Robert W. Keaten Director, Technical Functions SMK/mev

! cc: Administrator, Region 1 4

NRC Oyster Creek Project Manager Sr. Resident Inspector i i i

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