L-76-225, Letter Submits Proposed Amendment to Facility Operating License to Amend Appendix a Tech Spec, Concerning Cask Handling
| ML18227D851 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 06/24/1976 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| L-76-225 | |
| Download: ML18227D851 (17) | |
Text
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PJRC DISTR IBVTION Fon PART v0 DOCKET IVIATERIAL UOCKCT NUMOCI 50-25 51 I'ILE NVMUSA TO:
Mr, Victor Stello.IIOM:
Florida Power 8 Light Company Aiami,,Fl.orida Mr, Robert Uhrig DATC OF DOCVMCI4T 6/24/76 DATC RSCFIVSD 6/26/76 PCLSTTCA
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LiVCLOSURE
'I Amdt, to ol/change to Appendix A concerning Cask Handling tech spec i I ~
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r Office of Nuclear Reactor Regulate.on Attn:
Mr. Victor Stello, Jr., Director Division of Operating Reactors U. S. Nuclear, Regulatory Commission Washington, D.
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FLORIOA POWER 5 LIGHT COMPANY June 24, 1976 L-76-225
Dear Mr. Stello:
Re:
Turkey Point Plant Units 3 and 4
Docket Nos.
50-250 and 50-251 Proposed Amendment to Facility 0 eratin License DPR-31 and DPR-41 Pursuant. to 10 CFR 50.30, Florida Power 6 Light Company submits herewith three (3) signed originals and forty (40) conformed copies of a request to amend Appendix A of the Facility Operating Licenses DPR-31 and DPR-41.
The proposed amendment that may be moved into element cask.
Xt also fuel before a transfer pit.
limits the spent fuel transfer cask the spent fuel pit to a single sets a minimum time for decay of spent cask may be moved into the spent fuel The proposed changes are set forth in the attached revised Technical Specification page bearing the date of this letter in the lower right hand corner and as described below:
Page B-3.12-1 Add Basis for Limiting Condition for Operation, Cask Handling This proposed amendment. is being submitted upon the request of your staff.
Florida Power 6 Light Company's position is that this amendment is not necessary at this time.
Our cask onsite for our upcoming fuel transfer is a single element cask which weighs less than 25 tons, and as of June 15,
- 1976, the fuel in each spent fuel pit has decayed a minimum of fifty-nine (59) days.
Both of these values are within the limits which would be imposed by the proposed amendment.
PEOPLE... SERVING PEOPLE
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To Re:
Victor Stello, Jr.
Turkey Point Plant Units 3 and 4
Proposed Amendment to Facility 0 eratin Licenses DPR-31 6 DPR-41 June 24, 1976 Page Attached is a summary of the safety analysis performed for this proposed amendment.
The Turkey Point. Plant Nuclear Safety Committee and the Company Nuclear Review Board have reviewed the proposed amendment and safety analysis, and have concluded that the proposed amendment, does not constitute an unreviewed,safety question.
These review groups also con-cluded that, since the amendment adds limitations and does not change any existing limitations, the amendment is conser-vative and does not constitute a significant hazards consid-eration.
Very truly yours, Robert E. Uhrig Vice President, REU/GDW/hlc Attachment cc:
Norman C. Moseley Jack R.
- Newman, Esq.
3.12 Cask. Handling Applies to limitations during cask handling.
To minimize the possibility of an accident during cask handling operations that would affect the health and safety of the public.
S ecifications:
During cask handling operations:
(1)
The spent fuel cask shall not be moved into the spent fuel pit until all the spent fuel in the pit has decayed for a minimum of one thousand (1,000) hours.
(2)
Only a single element cask may be moved into the spent fuel pit.
3.12-1 6/24/76
B.3.12
BASIS FOR LIMITING CONDITIONS FOR OPERATION, CASK HANDLING Limiting spent fuel decay time to a minimum of 1,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> prior to moving a spent fuel cask into the spent fuel pit will ensure that poten-tial offsite doses are a fraction of 10 CFR 100 limits.
The restriction to allow only a single element cask to be moved into the spent fuel pit will ensure the maintenance of water inventory in the unlikely event of an uncontrolled cask descent.
Use of a single element cask which nominally weighs about twenty-five tons will also increase crane safety margins by about a
factor of four.
B.3.12-1 6/24/76
SAFETY EVALUATION INTRODUCTION The Nuclear=Regulatory Commission has requested that Florida Power
& Light Company submit a proposed change to the Tech-nical Specifications of Facility Operating Licenses DPR-31 and DPR-41 for Turkey Point Nuclear Generating Units 3 and 4 which would:
1) limit the size of the spent fuel cask which could be used in the spent fuel pit; and 2) specify a minimum fuel decay time required prior to moving a spent fuel cask into the spent fuel pool.
These changes represent additional limitations and do not change any existing limitations.
DISCUSSION The proposed amendment imposes a limit on the size of the cask which may be moved into the spent fuel pit.
The purpose of this limit is to increase the safety margin of the fuel handling crane.
The fuel handling crane was originally de-signed to handle a cask weighing 105 tons.
A single element cask weighs about twenty-five (25) tons and, therefore, the crane safety margins would be increased by about a factor of four.
The proposed amendment also imposes a limit on the minimum spent fuel decay time required prior to lifting a spent, fuel cask into the spent fuel pool.
This limit further reduces the potential radiological consequences of damaged fuel ele-ments in the unlikely event of a cask tip.
Figures 1 and 2
present the -results of analyses conducted to determine poten-tial offsite doses resulting from the damage of various numbers of fuel assemblies after varying decay times.
Additional discussion may be found in our fuel transfer safety analysis sent to the NRC on June 23, 1976.
EVALUATION The proposed amendment adds limitations and does not modify any existing limitations.
The proposed amendment may add additional margins of safety for future cask handling evolu-tions.
I It has, therefore, been determined by the Turkey Point Plant
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SAFETY EVALUATION Cont' Page.
Nuclear Safety Committee and the Company Nuclear Review Board that the proposed amendment does not involve a signi-
.ficant hazards consideration.
CONCLUSION We have concluded, based on the consideratons discussed above, that:
(2) because the changes do not involve an increase in the probability or consequences of accidents previously considered and do not invole a sig-nificant decrease in a safety margin, the changes do not involve. a significant hazards consideration; there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; and (3) such activities will be conducted in compliance with the Commission's regulations and the issu-ance of this amendment will not be inimical to the common defense and security, or to the health and safety of the public.
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Robert E. Uhrig, being first duly suborn, deposes and sayss That he is a Vice President of Florida Pover a Light. Company, the Licensee hereing i
That he has,executed tho foregoing document< that the state-ments made in this said document are true and correct to the best of his knowledge, information and belief, and that, he is authorised to execute the document on behalf of said Licensee.
Ro ert: E. Uhr g Subscribed and sworn to before me this ~~
day Qf 1976 Notary P
1 c, n an State of Florida Ny commission expires:
or the County of Dale,
~TARV PUBLIQ STATE OF FEORIPA AT EAR(P IWCOAWllSSION EXPIRES NOV, 30 1979 ION8ED THOU QENERAt, It4S, UNDERWRITERS.
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