ML18127B094
| ML18127B094 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie |
| Issue date: | 03/21/1977 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| L-77-85 | |
| Download: ML18127B094 (5) | |
Text
IIMCFO~~ 196 U.S. NUCLEAR REGUI "ATORY COM 'ON I2-7$ )
NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL DOCKET NUMBER FILE NUMBER TO"Dennis L. Ziemann, FROM@PL Miami, FL.
33101 Robert E. Uhrj.g DATE OF DOCUMENT 0 -.21-DATE RECEIVED 03-25"77 ETTE 8 ORIGINAL Q COPY 0 NOTOR IZ E D MNCLASS IF I E D PROP'NPUT FORM NUMBER OF COPIES RECEIVED DESCRIPTION Ltr. Ref. our 01.-17-77 ltr and. their 10-17-77 ltr..;Furnishing info regarding the ability of St. Lucie Unit $1 and. others to acc refueling accident within containment...
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FLORIDAPOWER 8( LIGHTCOMPANY March 21, 1977 L-77-85 Office of Nuclear Reactor Regulation Attn:
Dennis L. Ziemann, Chief Operating Reactors Branch N2 Division of Operating Reactors U.
S. Nuclear Regulatory Commission washington, D.'.
20555
Dear Mr. Ziemann,
Re:
St. Lucie Unit 1 Docket No.
50-335 Postulated Refueling Accident, O~
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8 MAR25 1977~ -0 u.S. NVIIIIIMuLATOS<.Q.
COMMISSION A4dl ScctIoa
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Your letter of 17 January 1977, relayed to us a concern expressed by Mr. Robert D. Pollard regarding the ability of St. Lucie Unit No.
1 and others to accommodate a refueling accident. within contain-ment.
This issue was previously reviewed by the Staff during the development of the St Lucie Unit No.
1 Technical Specifications.
(See Florida Power
& Light Company letter L-75-506 dated 17 October 1975, at item 42 of the attachment.)
The upper limit dose was evaluated and provided at that time.
The maximum thyroid dose is 40 rem and the corresponding whole body dose is 0.17 rem, which are small fractions of the 10 CFR 100 guideline limits of 300 rem thyroid and 25 rem whole body.
The principal assumptions used in this evaluation were in accordance with Regulatory Guide 1.25 and are as follows:
i)
A rupture of an entire fuel assembly and release of the gap inventory in accordance with RG 1.25 was assumed.
ii)
The effective DF of shielding water was 100 for iodine and 1 for Kr-85.
i'ii)
No credit for dilution or mixing within the containment or reactor shield building annulus was assumed.
iv)
No credit for charcoal filters was assumed.
v)
Containment isolation was not assumed.
vi)
The 2-hour accident meterological dilution factor was assumed.
7 ~OPP'O~~p PEOPLE... SERVING PEOPLE
To: Dennis L. Ziemann, NRC Re: St. Lucie Unit No.
1 Docket No.
50-335 Postulated Refuelin Accident March 21, 1977 Page 2
Since the bounding evaluation assumed that radionuclides emerging from the pool are transported immediately to the receptor under adverse meterological conditions with the resultant doses being small fractions of 10 CFR 100 guideline values, and a more realistic evaluation. would yield significantly smaller doses, Mr. Pollard's concern is clearly not relevant to the St. Lucie facility.
Accord-ingly, we believe further evaluation of this issue is unwarranted.
Xf you require any additional clarifying data, we would be pleased to furnish it.
Yours very truly, Robert E. Uhrig Vice President REU/LLL/bb
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