ML19326B252
| ML19326B252 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/15/1976 |
| From: | Rodgers J FLORIDA POWER CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19326B243 | List: |
| References | |
| NUDOCS 8003120786 | |
| Download: ML19326B252 (4) | |
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- ),.., a Ficrida Power C O ge p o a a p. o se September 15, 1976
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Mr. John Stolz e
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Division of Proj. ect Managemm t i.a
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In Re:
Florida Power Corporation jgf Crystal R.tver Unit #3 s
Docket No. 50-302 (3
Dear Mr. Stol:
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On April 14, 1976, Florida Power Corporation discovered that the reactor building dome at Crystal River Unit #3 had undergone a delamination.
Extensive evaluations have resulted in the initiation of repairs to the dome.
On June 11, 1976, Florida Power Corporation submitted to the Nuclear Regulatory Commission a report, Paactor Build-ing Dome Delamination, Florida Power Corporation Crys tal River Unit 3.
The report included relevant background in fo rma tio n, results of subsequent tests and evaluations and a description of corrective action to be taken.
Sub-sequently, Florida Power Corporation and its representatives met with Nuclear Regulatory Commission staff and revie.wed the report and the anticipated repair activities.
The staff has provided valuable commentary and our dialogue is continuing on the subject.
The dome repair ef forts are proceeding in accord with the attached schedule for completion on November 15,1976.
We wi.11 delay performance o f the Structural In tegri ty Test and Type A Integrated Leak Rate Test until such time as the dome repair is completed.
During the remaining work time, we will con tinue with balance-o f-plant activities
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There are, o f course, l a rp,e economic penaLLies associated wh SENT REGION c 8003120 gq;(,,3 w
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with the delayed start-up.
We will continue the balance-of-plant start-up activities through fuel loading in parallel with the dome repair.
Appendix J, 10CFR50 and Regulatory Guide 1.68 generally stipulate completion of the Structural Integrity Test and Integrated Leak Rate Test as a prerequisite for an operating license.
Under our particular circumstances there is suffi-cient cost-benefit opportunity without affecting safety to compel us to make this request for the early fuel loading do.te.
We have reviewed the safety analyses in the FSAR and co'n-cluded that no safety problems would exist or be created by loading fuel prior to having performed the Structural Integrity and Integrated Leak Rate Tests.
There would be.
of course', no fission products or activation products present ia the new fuel or primary coolant to constitute a signifi-cant radiation hazard.
The only radiation source involved would be the two Americium-Berylium-Curium start-up sources which are and would remain insignificant as far as posing any threat to the health and safety of the public.
In addi-f-'N tion, there are no credible mechanisms which would cause any 4' N ')
power transients to occur.
Under all normally postulated accident conditions, required shutdown margins would exist.
We also have determined that there would be no safety problems associated with the reactor during a time interval between completion of fuel loading, completion of the dome repair and subsequent reactor building testing.
This situation would in fact not be different from those which will be encountered during each future periodic Type A Leak Rate and during ex-tended plant outages except that, to this request's further advantage, no fission products or ' activation products will be present in the new fuel to pose a radiation hazard to anyone.
We request that you issue to Florida Power Corporation on or about 11/1/76 a Facility Operating License for its Crystal Rive r Unit #3 Nuclear plant subject to the fol?owing restric-tions to be applicable until NRC acceptance o f the Structural Integrity Test results and completion of the Type A Integrated Leak Ra te Te s t :
(1) Maximum Power Level -
The licensee is authorized to load fuel and pe rform suberi t ical ten ts, but a t no time shail the reactor (c) he made critical foitowing fuel loading.
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- Mr. John Stolz.
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i (2) Technical Specificatons The Technical Specifications are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifica-tions except as noted below:
(a) The reactor sh'all not be operated in any mode other than Mode 5 or 6 as specified in Tech-nical Specification Table 1.1 (Appendix A).
We realize that the above request involves a deviation from normally prescribed programs, however, the requested course of action would in no way endanger the health and safety of the public or on-site personnel.
In view of the benefits to our customers to be derived from this procedure, your granting this license is on this schedule concluded to be p.
in the public interest as well as that of our owner parti-cipants.
We would appreciate an opportunity to further discuss this es very important matter at your earliest convenience to assure (s_-)
time tor your evaluation and response on the seneduled cate.
Sincerely, 1
J.
Rodgers v
Asst. Vice President JTR/iw v
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l CRY 3TAL RIVER 83
!'UCLE.*.R STATICN SCHEDULE 9/14/76 i
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v RB D0::E REPAIRED FINAL PREPS POST ILRT COMPLETE RB LOAD FOR SI1'&
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RECOVERY &
INTERIOR WORK FUEL ILRT 8ILRT@
PREP TOR llEAT UP MINI-l!FT ZFFT 8
o SUEMITTAL & ACCEPTANCE 0F PRELIMINARY SIT TEST RESULTS
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