ML18139A881
| ML18139A881 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 11/24/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Ferguson J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 8012080018 | |
| Download: ML18139A881 (4) | |
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R~CtJ¥r~~lgrl~~Wl9feA~ R~~~~~~~A;~~OMMISSION REGION II 101 MARIETTA ST., N.W., SUITE 3100 19'd0 NO\\! 26 2
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NOV 2 4 1980 In Reply Refer To:
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Virginia Electric and Power Company ATTN: J. H. Ferguson Executive Vice President-Power P.O. Box 26666 Richmond, VA 23261 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 actions.
If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Enclosures:
Sincerely,
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James P. O'Reilly Director
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IE Information Notice No. 80-42
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List of Recently issued IE Information Notices cc w/encl:
W.R. Cartwright, Station Manager P. G. Perry, Senior Resident_ Engineer J. L. Wilson, Manager t
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- UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON,D.C.
20555 November 24, 1980 SSINS No.:
6835 Accession No.:
8008220261 IN 80-42 IE Information Notice No. 80-42:
EFFECT OF RADIATION ON HYDRAULIC SNUBBER FLUID Description of Circumstances:
On August 1, 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 on the General Electric Versilube F-50 fluid that was provided in Anker-Holth shock suppressors mounted on the reactor coolant pumps.
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 the fluid was subjected to radiation.
The following table lists the dose irradiation time and HCl formed.
Dose Irradiation HCl Formed (Mrad)
Time (ppm) 0 2.78 1.2 1 minute 70.3 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 1592 One of the recommendations by the RPI personnel was that the fluid be replaced before a limit of approximately 6 Mrads was reached.
FPC reported that 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 Technical 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 provided as an early notification.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.
l IN 80-42 November 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 appropriate NRC Regional Office.
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- Information Notice No. 80-42 80-41 80-40 80-39 80-38 80-37 80-36 80-35 80-34 80-33 80-31 RECENTLY ISSUED
- IE INFORMATION NOTICES Date of Subject Issue Effect of Radiation on 11/24/80 Hydraulic Snubber Fluid Failure to Swing Check Valve 11/10/80 in the Decay Heat Removal System at Davie-Besse Unit No. 1 Failure Of Swing Check 11/10/80 Valve In The Decay Heat Removal System At Davis-Besse Unit No. 1 Malfunctions Of Solenoid 10/31/80 Valves Manufactured By Valcor Engineering Corporation Cracking In Charging.Pump 10/30/80 Casing Cladding Containment cooler leaks 10/24/80 and reactor cavity
.flooding at Indian Point Unit 2 Failure of.Steam 10/10/80 Generator Support Bolting Leaking and dislodged 10/10/80 Iodine-124 implant seeds Boron dilution of reactor 9/26/80 coolant during steam*
generator decontamination Determination of teletherapy 9/15/~0 timer accuracy Clarification-of certain 8/12/80 requirements for Exciu~
- :sive-use shipments of radioactive materials Haloperation of Gould-8/27/80 Brown Boveri Type 480 volt type K-600S and K-DON 600S circuit breakers
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IN 80-42 November 24, 1980 Issued to All ~uciear power reactor facilities with an OL or CP All nuclear power reactor facilities with an OL or CP All power facilities with and OL or CP All light water reactor facilities holding power reactor OLs or CPs All PWR facilities with an OL or CP All nuclear power facilities holding power reactor OLs or CPs All nuclear.power reactor facilities holding power reactor OLs or CPs All categories G and Gl medical licensees All pressurized water reactor facilities holding power reactor OLs All teletherapy (G3) licensees All NRC and agreement state licensees