ML20236L558

Discusses Ph Johnson of Region V Ltr Requesting NRR Interpretation of Applicability Footnote Re Several Containment TS for BWRs

ML20236L558
Person / Time
Issue date:	07/26/1994
From:	Charemagne Grimes Office of Nuclear Reactor Regulation
To:	Quay T Office of Nuclear Reactor Regulation
Shared Package
ML20236J990	List: IA-98-155, Responds to 980513 Request from Duquesne Light Co to Provide Written Interpretation of Beaver Valley Power Station,Unit 1 & 2 TSs Requirements for Channel Calibration of Rtds & Thermocouples IR 05000482/1991021 ML20236J987 ML20236K746 ML20236K751 ML20236K780 ML20236K784 ML20236K803 ML20236K816 ML20236K840 ML20236K853 ML20236K883 ML20236K902 ML20236K916 ML20236K936 ML20236K963 ML20236L549 ML20236L558 ML20236L563 ML20236L580 ML20236L584 ML20236L590 ML20236L597 ML20236L653 ML20236L921 ML20236L955 ML20236L971 ML20236M014 ML20236M020 ML20236M034 ML20236M057 ML20236M117 ML20236M138 ML20236M148 ML20236M911 ML20236M924 ML20236M966 ML20236M983 ML20236M996 ML20236N007 ML20236N047 ML20236N052 ML20236N066 ML20236N221 ML20236N240 ML20236N257 ML20236N271 ML20236N288 ML20236N323 ML20236N333 ... further results
References
FOIA-98-155 NUDOCS 9807130070
Download: ML20236L558 (1)

Text

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' l , h , l' .1 MEMORANDUM FOR: Theodore R. Quay, Pro; Director V, PD5 Division of Reactor .'roje ts, NRR FROM: Christopher I. Gr* mas, Chief Technical Specifications Branch Division of Op<r.,'ing Reactor Support, NRR

SUBJECT:

CONTAINMENT b flh PoiENTIAL FOR DRAINING THE REACTOR VESSEL By note of June 3, 1993. Phillip H. Johnson, Region V, requested NRR's interpretation of an APPL!r ABILITY footnote that applies to several containment Technical Specif44tions far BWRs. The footnote is "when l

irradiated fuel is being handled in ti.e secondary containment and during CORE All[RA110NS and operation? with a potential for draining the reactor vessel."

At issue is the use "of the phrase " operations with a potential for draining the reactor vess.

In the 15, the - i

• potential" means "something that exists in a state of potency or possib ity for changing or developing into a state of actuality."

It follows from this definition that even thnugh features are provided to prevent draining the reactor vessel, the potential for such draining can continue to exist. The operation described was the use of the residual heat removal (RHR) sy tem to lower the water level in the reactor cavity. Two independent s.ction valves .rere designed to satomatically isolate at a specified water level. However, since the failure of both is possible, this is an "operatson with a potential for :frain mq the reactor vessel."

If a licensee believes that any conditio- dtscribeu by *noerat tuns ."h a potenttal for draining the reactor vessel" shou'. not require the establishment of secondary containment, a request for change along with justification (e.g., compensatory action) should be made i the staff. f. good avenue to propose the change is through the Owners Groups in the implementation of improved Standard Technical Specifications.

s o:n. c : , P m v. o. t" Christopher.1. Grimes, Chief Technical Specifications Branch Division of Operating Reactor Support, NRR DISTRIBUTION: ,

0158 R/f DORS R/F N Central files BKGrimes SHWeiss AEthaffee i GHMarcus CIGrimes RJBarrett RCJones RHLo CWMoon Clifford JBradfoote CSSchulten l l

l DOCUMENT NAME: G: DRAIN.CWM

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