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- J NUCLEAR REGULATORY COMMisslON I
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WASHINGTON. D C.E7 ll/ 7 NOV 8 i
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MEMORANDUM FOR:
R. L. Tedesco, Assistant Director for PTant Systerhs I b,f y Q r.I,..
Division of Systems Safety
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D. G. Eisenhut, Assistant Director for Operational :h;_,[.-
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Technology, Division of Operating Reactors
SUBJECT:
10 CFR PART 21 NOTIFICATION BY REGARDING SAFETY-RELIEF VALVE DISCHARGE LOADS w
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On October 18, 1977 OI&E formally transferred the lead responsibility
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for followup actions associated with the subject notification to NRR.
i A copy of the " Transfer of Lead Resportsibility" agreement is enclosed for your information.
As we have discussed, we believe that the responsibility for the long-term generic review of safety-relief valve (SRV) loads for application to the Mark I, Mark II, and Mark III BWR containment system designs appropriately belongs to DSS. Accordingly, we believe that the lead responsibility for the long-term resolution of this particular concern, with respect to load definition, resides within DSS and that it should be addressed within the scope of the Task Action Plan for NRR Category A Technical Activity No. A-39.
Similarly, we believe that the responsi-bility for the structural evaluations associated with this long-tem review resides within D0R for affected operating facilities and within DSS for affected facilities which are not yet licensed for operation.
On the other hand, 00R will continue to perfom a short-term evaluation of the new information as it relates to continued safe operation of operating BWRs with the Mark I containment systems to ensure continuing safety while the long-term review is being conducted.
Since this action item will be tracked and reported as a " Transfer of Lead Responsibility from IE to NRR" and as a Part 21 review, it will from time to time be necessary to establish schedular information for this review. We will be in contact with you as the need for such information arises.
J --
. Eisenhut. A:: h t:r. Directer for Operational Technology Division of Operating Reactors
Enclosure:
As stated 8604020437 860114 PDR FOIA FIRESTOB5-665 PDR g
Date:
OCT a G 1577 i
Serial No.:
IE-RCI-77-01 TRA'!SFER OF LEA:
RESPONSIBILITY
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o E. G. Case, Acting Director, NRR 1
Subject:
GE RELIEF VALVE C0iTROL SYSTEM Responsible IE Individual:
N. C. Moseley Descriotion of Iter Recuirine Resolutio n:
By letter dated October to IE 11, 1977 less c,onservative than originally predpursuant to relates to control of reactor coolant syst n of a design condition ccpy attached).The condition is de from at-po er closure of S4R mainste The condition is reported to be generic to SWRs b am isolation valves.er pressure tran The condition Recommendations and Proposed Course otn in operaticn of Action:
1.
The Officc of Nuclear Reactor Regulati a generic basis, the significance of theon (NRR) will de the adequacy of the proposed correcti resorted situation, and 2.
ve action.
NRR will modify individual licenses 3.
as appropriate.
for compliance to any requirementsThe Of that may be imposed by NR Concurr Yljnce?
/$~Wc? r horman L, noseiey, vir,ector, u/ h.k, IE g/
y tvision of neactor m
construction inspection, /t/-
Edson G. Case, Acting Director 2.
Dat i
Enclosure:
, Office of Nuclear Reactor Regulation ala G.E. ltr datec Oct.
iDatt 11,1977 w/ encl.
cc:
R. S. Boyd, NRR V. Stello, NRR J. G. Davis, IE K. R. Goller NRR H. D. Thornbur J. G Ke0Pler
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D.G.Eisennu,t,f,RR/
J. H. Snierek, g, IE E. !*. Howare,. RIII IE RIV g
S. A. Varga ::RR K. V. Seyfrit, IE R. H. Engelken, RV W. F. Kane,,.lRK G. W. Reinmutn, IE Ji. K. Shepar, ELO i
L, P. Crocker, WRR B. Grier, RI A. F. Abell, MIPC
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J. P. O'Reilly, RII
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