ML19329D758
| ML19329D758 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/28/1976 |
| From: | Rodgers J FLORIDA POWER CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003170698 | |
| Download: ML19329D758 (4) | |
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Mr. John F. Stol:
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- xAn 6-d Chief, LWR Branch No. 1 Division of Project Management Office of Nuclear Reactor Regulation 7-U.S. Nuclear Regulatory Commission N3e N e
Washington, D.C. 20555
Subject:
Florida Power Corporation, Crystal River Unit 3, Docket No. 50-302; Integrated Irradiation Program for Reactor Vess'l Surveillance Specimens e
Dear Mr. Stol:
During the April 2, 1976 meeting between the Nuclear Regulatory Commission (NRC), Florida Power Corporation (FPC), and Babcock 6 Wilcox (B6W), the possibility of not installing surveillance capsules in FPC's Crystal River Unit 3 during the first fuel cycle was discussed.
At that meeting, the NRC indicated that deferring installation of the capsules until the first refuel-ing was acce, table.
The purpose of this letter is to confirm to the NRC t1at FPC does intend to defer installation of surveillance capsules until the first refueling, and to provide the bases for this decision.
The bases for deferred installation of capsules in Crystal River Unit 3 until the first refueling is as follows-1.
The Davis-Besse Nuclear Power Station (DB-1) SSHT qualifi-cation test described in B6W Topical Report BAW-10038, Supplement 1 will not be completed or evaluated prior to the time when capsules would have to be installed in Crystal River Unit 3.
Therefore, final NRC approval of the BGW 177 FA SSHT will not occur in a time frame compatible with the present Crystal River schedule.
(Refer to NRC Ictter to FPC August 23, 1976.)
2.
FPC has technical concerns regarding the proof testing of the closure device using installation and removal tools.
Resolution of these concerns prior to scheduled fuel loading appears to be impossible.
t) W General Office 3201 Tnirty-fourtn street sourn. P.O Box 14042, St Petersburg. Florida 33733 e 813-866-5151
Page 2 3.
In regard to irradiation of the Crystal River Uni't 3 capsules using representative materials, we consider that response of the reactor vessel materials to irradiation can be satisfactorily predicted based on already available information, without need to rely on data from these capsules.
The NRC, in their report of the April 2, 1976 meeting, similarly indicated that irradiation data fron these capsules is not neceesary for the first cycle.
There-fore, we consider that deferring irradiation of the Crystal River Unit 3 capsules for the one cysle is satisfactory.
4.
With regard to the one fuel cycle of operation with the six surveillance specimen holder tubes (SSHT) installed but without specimens or closures in place, B6W has concluded that no adverse affects are anticipated.
These SSHT's have been installed and are presently in the reactor based on NRC evaluation and acceptance of the B5W design described in B6W Topical Report BAW-10051, Supplement 1, for installation in Davis-Besse 1.
5.
The matter of present design of BSW 177 FA SSHT has been handled by NRC as a generic concern between B6W with NRC.
All alternatives now available will remain for evaluation during the first cycle.
For the above reasons, we would defer installation of surveillance capsules until the first refueling.
Prior to first refueling, we will submit to you for approval the specific capsule irradiation program to be implemented at the beginning of the second cycle.
In summary, we plan to operate CR3 with the new design surveillance holder tubes presently installed on the thermal shield, without capsules or closures installed.
This SSHT installation in CR3 is as approved by NRC for Prototype testing in the Davis-Besse Nuclear Power Station Unit 1.
(DB-1).
The adequacy of the holder tube design has been confirmed by exten-sive B6W analyses, NRC staff evaluation and is to be qualified by the hot functional tests at DB-1.
Installation of the 'SSHT's without closure or capsules for CR3's initial cycle of operation will allow for implementation of a specimen irradiation program at a later date without undue complications or hazards associated with installation of SHHT's I
.in an irradiated plant.
Operation during the first cycle without j
surveillance specimens in no way causes a loss of required data
..for specimen evaluation.
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Page 3 The urgency of this request is brought about by the schedule incompatibility between DB-1 and CR3 in the qualification of the new design capsules and closures.
The above summarizes our plans.and status relative to the SSilT Program for CR3.
Florida Powe Corporation stands ready for additional dialogue with NRC staff as is appropriate.
Sincerely, FLORIDA POWER CORPORATION 3
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J.[T. Rodgers Assi,stant Vice' President e