ML17252A724
| ML17252A724 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, LaSalle  |
| Issue date: | 07/07/1981 |
| From: | Delgeorge L COMMONWEALTH EDISON CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0313, TASK-A-42, TASK-OR GL-81-03, GL-81-04, NUDOCS 8107140437 | |
| Download: ML17252A724 (3) | |
Text
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Commonwealth Edison One First National. Plaza, Chicago, Illinois Address Reply to: Post Office Box 767 Chicago, Illinois 60690 M~. Darrell G. Eisenhut. Director Div~sion of Licensing U.S. Nuclear Regulatory Commiss.ion Washington, DC 20555 I
July 7,
~ubject:
Dresden Station Untts 1, 2 and 3 Quad Cities Station Units l and 2 LaSalle County Station Units 1 and 2 Response to Generic Letter Bl~D4 Concer~ing the I~plementation of NUREG-0313, Rev. 1.
NRC Docket ijos. 50-10/237/249, 50-254/265~and 50*373/374 R ef e r e n c e. s ( a ) :
D
- K. D a v i s l e t t e r t o R
- L
- B o l g e r.
September 15, 1977.
( b) :
M. s. Tu rb a.k letter to D. K
- Davis dated January** 10, 1978.
( c) :
M. s. Turbak letter to D. K
- Dav.is dated February 3, 19 78..
( d) :
D. G. Eisenhut l ett*e r to* A 11 BWR
. Licensees dated February 2 6,. 1981 (Generic Letter 81-04).
(e):
LaSalle County Station FSAR Response t~ Question 121.8 (Amendment 37).
Dear Mr.. Eisenhut:
Reference (d) requested a revi~w of all ASME Code Class 1 and 2 pressure boundary piping, safe ends and fitting material at operating boiling water react-0rs to determine if it meets the material selection, testing and processing guidelines set forth in NUREG~0313, *Rev. 1.
Augmented ISi requirements, revised Reactor Coolant Leakage Technical Specifications, and Replacement Schedules for Nonconforming "Service Sensitiv~" lines.were the items specifically requested to be addresse~.
The following Commonwealth Edison ~esponse to this reque~t is applicable to Dresden, Quad Cities and LaSalle stations.
8107140437' 810707 PDR ADOCK 05000010 P
- e e
D. G. Eisenhut 2 -
July 7, 1981 Commonwealth Edi~on ~rovided, fn Refertnce (b), oui fespon~e to t~e earlie~ (Reference (a)) NRC request for Technical Specification changes to ~eflect the requirements of NUREG 0313, Rev. O.
In this response we indicated that although pipe cracking problems are undesirable from a plant aiailability standpoint, they do not pose a significant safety hazard to the public.* This position is based on the leak-before-break nature of stainless steel and the demonstrated adequacy of our leak detection systems..
We concluded that Technical Specification changes to augment the currently existing !SI program are unnecessary, and the beriefits
- from performing* the inspection specified iri NUREG-0313 did not justify the additional 60-120 mahrem exposures per refueling outage whith we estimated.would be required to perform the inspections.
- Since NUREG-0313j Rev. l still concludes that BWR pipe cracking is not a significant safety ccincern, Commonwealth Edison believes that our Referehce(b) response remains appropriate today.
Our Dresdeh and Quad Cities experience with intergranular stres~
corrosion tracking (IGSCC) to date does not warrant an extensive program beyond ASME XI.
- Implementation of supplemental irispection
- will *be decided by weighing the.incremental plant availability improvemeht against the cost of the inspection.
This cost includes radiation manrem, man-hours~ and.the cost of any incre~ses in plant outages.
Additionally, Comm~nwe~ith Edison maintains that the current Dresden, Quad Cities and (proposed) LaSalle County technical Specifications are completely a.dequate in the sections pertaining to primary coolant leakage.
The justification for this position was*
provided in References (c) and (e) for Dresden/Quad Cities and L a Sa l l e Co u n t y s tat i on s, r e*S p e ct i v e l y.
- Commonwealth Edison has also previously addressed the issue of nonconformihg materials in "service sensitive" lines.
Reference (b) provided on our policy on replacing nonconforming materials at Dresden and Quad Ci.ties stations, and Reference (e) provided a summary of the cha~ges which have been made at LaSalle County Station to minimiz.~ the possibility of IGSCC.
In summary, w~ believe that the increased inspections and leakage detection requirements of NUREG-0313, Rev. l are not warranted.
Our pr~sent ISi (ASME XI) program and supplemental inspections to improve availability along with our history of being able to identify problems in a timely fashion demonstrate that we already adequately minimize the impact that IGSCC has on the safe operation of our BWR facilities.
Please address any questions ~ou may have concerning this matter to this office..
!e
- 0. G. Eisenhut 3 -.
J u 1 y 7 ' 1 g.g 1 One sign:ed* orig.inal and seventy-nine (79). copies of this transmittal ~re p~ovided for *your use.
Very truly your~
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L. 0. DelGeorge *'"
Dir~ctor *of.Nuclear Licensin~
cc.:
Region III Inspect~r - Dresden Region III Inspettar - Quad Cities Region III Inspector*
LaSalle*
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