ML19319D490
| ML19319D490 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/15/1976 |
| From: | Rodgers J FLORIDA POWER CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003170618 | |
| Download: ML19319D490 (5) | |
Text
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NRC DISTR!DUTION *Os PART 50 DOCKET MATERIAL
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To:
Mr Stolz F R0r.t:
DATE o OCU Florida Power Corp g5 N J T Rodgers St Petersburg. Fla DATE "CC10-18-76 eLETTER O N OTO RIZ E D PROP IMOTFORM NUMBE R OF COPIES RCCEIVED DOnlGsN AL SUNC L AS$1F IE D 1 g {gggd,
CcoPv OESCntPT'e4 ENCLOSURE Ltr fuenishing info concerning hydraulic snubber tech specs.....
PLANT NAME:
Crystal River #3 SAFETY FOR ACTION /INFORMATION ENVTRn 1U-41-/0 eht
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,.o.,.. e. r October 15, 1976 lil Mr. John Stol:
Branch Chief f
Light Water Reactors Branch I Division of Project Management U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Crystal River Unit #3 C'
Docket No. 50-302 Standardized Technical 7
Specification
/
Dear Mr. Stol:
Crystal River Unit #3 Technical Specification 4.7.9.1 (b) specifies a visual inspection every 31 days of snubbers with seal material not approved by the NRC.
This visual inspection includes inspection of the hydraulic fluid reservoir, fluid connections, and linkage connections to the piping and anchors.
The hydraulic snubbers at CR# 3 to which this specification presently applies are the Reactor Coolant Pump Snubbers which contain seals made of Viton-A material.
Unlike seals made from Ethylene Proylene material, Viton-A seal material has no't been given a generic approval by the NRC, but has been approved by the NRC for use in specific operating environments at other nuclear units.
The operating environment for the Viton-A seal material con-tained in the Reactor Coolant Pump Snubbers at CR#3 is as follows:
(1) Hydraulic Fluid - Versilube F-50 Silicone Lubricant.
(2) Radiation Dose Rate at Snubber Location - 30 R/hr (Documentation supporting 30 R/hr is attached)
(3) Temperature at Snubber Locations - 150 F-170 F.
s.
General Office 320i rn,rty fourtn street souin. P O Box 14042. St Petersburg Fionca 33733 813 - 856-5151
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i Mr. John Stolz October 15, 1976 It is hoped.that the information supplied above will enable members of your staff to determine that the Viton-A seal
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material contained in the Reactor Coolant Pump Snubber at CR# 3 is compatible with its operating environment and as such approved by the NRC.
If you or members of your staff require additional informa-tion or discussion in order to make this determination, please do not hesitate to contact this office.
Very truly yours, J.
T. Rodgers Asst. Vice President JTR/iw Attachments.
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Babcock & Wilcox go,c c.,auenc,cu, P.o. Box 1260. Lynchbu,g, Va. 24505 Te!cohone: (804) 384 5111
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October 7, 1976 T1.2 620/0007 SOM 281 Mr. J. Alberdi Project Manager Florida Power Corporation Post Office Drawer 1057 Crystal River, Florida 32629
Subject:
Expected Radiation Dose Rates at the Reactor Coolant Pumps
Dear Mr. Alberdi:
In response to a request by Messrs. J.
L. Harrison and R. M. Bright of your staff, B & W has calculated the dose rate expected at 100% FP in the area of the Reactor Coolant Pumps.
The calculations are from a general study and are based on 1% leaking fuel and N16 associated with 1005 FP operation.
The dose rates were calculated with the particle transport "ANISN" computer code using' fission pr3 duct source terms consistent with those shown in Crystal River III FSAR tables 11-2 and 11-3 and N16 activity of approximately 1 x 107 disintegrations /second/
f gram of coolant.
The results of the calculations, which have been given verbally to Mr. R. M. Bright, show that a conservative estimate of the dose rate at 100% FP at or near the reactor-coolant pumps on the outside pipe surface is 75 R/hr.
At two feet away from the pipo surface (in air) the dose rate reduces to 30 N/hr.
It should be noted that the reactor coolant pump motor equipment specification, CS-3-16, references a design radiation dose rate for the motor at 100 R/hr at rated thermal power.
This value, which was generated approxi-The Babcock & Wilcox Conauny / Establie.hed 18G7
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Babcock & Wilcox Mr. J. Alberdi October 7/ 1976 mately 10 years ago, was based on extremely conservative analysis techniques and assumptions.
The more recent cal-culations reported herein are considered to be adequately conservative and much more realistic than the older E-Spec value.
If we can be of any further assistance.in this matter, please do not hesitate to call.
Very truly you s, l
ELL:SPM:STK Edwin L. Loga.
Site Operations. Manager cc:
R. J. Baker, Jr.
C. E. Barksdale G. P. Beatty R. M. Bright y.
J. E. Colby
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J. C. Hobbs, Jr.
J. L. Harrison C. E. Jackson J. S. Laing P. F. McKee D. Rusic W. H. Spangler R. P. Williamson
. J. R. Wright SIP 07/126 2A382 File 4
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