ML19345C596
| ML19345C596 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/24/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Mcdonald R ALABAMA POWER CO. |
| References | |
| NUDOCS 8012050614 | |
| Download: ML19345C596 (1) | |
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o UNITED STATES g
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NUCLEAR REGULATORY COMMISSION 8
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- E 19 REGION 11 101 MARIETTA sT N.W SUITE 3100
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a ATLANTA, GEORGIA 30303 NOV 2 41980 0
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In Reply Refe,".To:n C3 tRE' RII;JP0 0-348) 0-364-Alabama Power Company 1
ATTN:
R. P. Mcdonald Vice President-Nuclear Generation P. O. Box 2641 Birmingham, AL 35291 i
Gentlemen:
The enclosed Information Notice is provided as an early notification of a possibly significant matter. Recipients of this Notice should review the information for possible applicability to their facilities.
However, no specific action or response is requested at this time. If further NRC evaluations 'so indicate, an IE Circular or Bulletin will be issued to recommend or request specific licensee j
actions.
If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Sincerely, Q
gr James P. O'Reill?
4 Director
Enclosures:
1.
IE Informatic*: Notice No. 80-42 2.
List of Rec nJy issued IE Informatia Notices l
I cc w/ encl:
W. O. Whitt, Executive Vice President F. L. Clayton, Jr., Senior Vice President H. O. Thrash, Manager-Nuclear Generation O. D. Kingsley, Jr., Manager, Nuclear Engineering and Technical Services J. W. McGowan, Manager-Operations i
Quality Assurance W. G. Hairston, III, Plant Manager W. C. Petty, Manager-Quality Assurance j
(Design and Construction)
R. E. Hollands, Jr., QA Supervisor T
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SSINS No.: 6835 Accession No.:
UNITED STATES 8008220261 NUCLEAR REGULATORY COMMISSION IN 80-42 0FFICE OF INSPECTION ANL ENFORCEMENT WASHINGTON,D.C. 20555 C
November 24, 1980 IE Information Notice No. 80-42: EFFECT OF RADIATION ON HYDRAULIC SNUBBER FLUID Description of Circumstances:
On August 7,1980, Florida Power Corporation (FPC) filed a report in accordance with 10 CFR Part 21 that identified an upper service limit of 10 Mrad (megarad) of radiation en the General Electric Versilube F-50 fluid that was provided in Anker-Holth shock suppressors mounted on the reactor coolant pump &.
This upper limit was obtained from the results of a study performed for FPC by Rensselaer Polytechnic Institute (RPI). These results contained two items of prime importance to the operation of the suppressors. The first result was a significant increase of the viscosity of the fluid to the extent that incipient gelation of the fluid occurred at exposures of approximately 50 Mrad. The viscosity increased linearly for exposures up to 20 Mrad and then increased exponentially for exposures greater than 20 Mrad.
The second result showed that hydrochloric acid (hcl) was formed in significant quantities when L e fluid was subjected to radiation. The following table N
lists the dose irradiation time and hcl fo ned.
Dose Irradiation hcl Formed (Mrad)
Time (ppm) 0 2.78 1.2 1 minute 70.3 y
5.8 5 minutes 329.
5.8 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 335.
18.5 11.2 minutes 555 50.3 15.2 minutes P 92 One of the recommendations by the RPI personnel was that the 1;mia be replaced before a limit of approximately 6 Mrads was reached. FPC reported tLat the fluid in service at Crystal River No. 3 plant had absorbed doses ranging from 2.3 to 3.6 Mrads,these values were determined by comparing the viscosity of the fluid in service to that of the test samples at RPI. The ischnical Instruction Manual that is provided by the vendor for these suppressors contains a recommendation that 12.5 Mrads should be the maximum service life for Versilube F-50.
This IE Information Notice is pro,ided as an early noti 11 cation of a possibly significant matter that is still under review by the NRC staff. Recipients should review.' the information for possible applicability to their facilities.
No specific action or response is requested at this time.
If NRC evaluations so indicate, further licensee actions may be requested or required.
IN 80-42 Yov nber 24, 1980 Page 2 of 2 No written response to this IE Information Notice is required.
If you have any questions regarding this matter, please contact the Director of the e
appropriate NRC Regional Office.
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IN 80-42 November 24, 1980 RECENTLY ISSUED IE INFORMATION NOTICES 1
_Information Notice No.
Subject Date of 80-42 Issue Effect of Radiation on Issued to Hydraulic Snubber Fluid 11/24/80 All nuclear power reactor 80-41 facilities with an OL or CP Failure to Swing Check Valve in the Decay Heat Removal -
11/10/80 All nuclear power reactor System at Davie-Besse Unit facilities with an OL No. I or CP 80-40 Failure Of Swing Check Valve In The Decay Heat 11/10/80 Removal System At Davis-Besse All power facilities Unit No. I with and OL or CP 80-39 Malfunctions Of Solenoid Valves Manufactured By 10/31/80 Valcor_ Engineering Corporation All light water reactor facilities holding 80-38 Cracking In Charging Pump power reactor OLs or cps Casing Cladding 10/30/80 80-37 All PWR facilities Containment cooler leaks with an OL or CP and reactor cavity 10/24/80 All nuclear power flooding at Indian Point facilities holding Unit 2 80-36 power reactor OLs Failure of. Steam or cps Generator Support Bolting 10/10/80 All nuclear power reactor facilities 80-35 holding power reactor Leaking and dislodged OLs or cps Iodine-124 implant seeds 10/10/80 80-34 All categories G and Boron dilution of reactor G1 medical licensees coolant during steam 9/26/80 generator decontamination All pressurized water reactor facilities 80-33 Determination of teletherapy hc1 ding power reactor OLs timer accuracy 9/15/80 80-32 All teletherapy Clarification of certain (G3) licensees requirements for Exclu-8/12/80 l sive-use shipments of All NRC and agreement radioactive materials state licensees 80-31 Maloperation of Gould-
-Brown Boveri Type 480
-8/27/80 volt type K-600S and All light water reactor K-DON 600S circuit facilities holding OLs or cps breakers O
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