ML19345C590
| ML19345C590 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/24/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| NUDOCS 8012050599 | |
| Download: ML19345C590 (1) | |
Text
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UNITED STATES EM.,, cgf NUCLEAR REGULATORY COMMISSION
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,o KING OF PRUSSIA, PENNSYLVANIA 19406 November 24, 1980 Docket No. 50-244 Rochester Gas and Electric Corporation ATTN:
Mr. John E. Maier Vice President Electric and Steam Production 89 East Avenue Rochester, New York 14649 Gentlemen:
The enclosed IE Information Notice No. 80-42, "Effect of Radiation on Hydraulic Snupber Fluid," is forwarded to you for information.
No written response is j'
required.,,,If you desire additional information regarding this matter, please contactthlisoffice.
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Sincerely, id a
f 8 ce H. Grier Director
Enclosures:
1.
IE Information Notice No. 80-42 2.
List of Recently Issued IE Information Notices CONTACT:
- 0. L. Caphton (215-337-5266) cc w/encls:
B. A. Snow, Plant Superintendent J. Bodine, QC Engineer Harry H. Voigt, Esquire J. T. St. Martin, Technical Assistant, Operations Engineer l
80120 soSW nW
SSINS N3.:
6835 Accassien No.:
UNITED STATES 8008220261 NUCLEAR REGULATORY COMMISSION IN 80-42 1
0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON,0.C.
20555 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 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 (HC1) 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.
19.5 11.2 minutes 555 50.3 15.2 minutes 1592 One of the recommendations by the RPI personnel was that t.1e fluid be replaced before a limit of approxiinately 6 Mrads was reached.
FPC eparted that the fluid in service at Crystal River No. 3 plant had absvrbed 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 !?-' 12.5 Mrads should be the maximum service life for Versilube F-50.
This IE In' formation 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.
IE Information Notice No. 80-42 November 24, 1980 RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued to Notice No.
Issued 80-41 Failure of Swing Check 11/10/80 All holders of Valve in the Decay Heat a power reactor Removal System at OL or CP Davis-Besse Unit No. 1 80-40 Excessive Nitrogen 11/6/80 All holders of Supply Pressure a power reactor OL Activates Safety-Relief or CP Valve Operation to Cause Reactor Depressurization 80-38 Cracking in Charging 10/30/80 All holders of Pump Casing Cladding a PWR power reactor OL or CP 80-37 Containment Cooler 10/24/80 All holders of a Leaks and Reactor power reactor OL Cavity Flooding at or CP Indian Point Unit 2 80-36 Failure of Steam 10/10/80 Ali holders of a Generator e,; port power reactor Bolting OL or CP 80-55 Leaking and Dislodged 10/10/80 All holders of a Iodine-125 Implant Category G or G1 Seeds Medical License 80-34 Boron Dilution of 9/25/80 All holders of a Reactor Coolant During PWR Power Reactor OL Steam Generator Decontamination 80-33 Determination of 9/15/80 All holders of Teletherapy Timer a teletherapy Accuracy license 80-32 Clarification of 9/12/80 All holders of Certain Requirements an NRC or Agreement for Exclusive-use State License Shipments of Radioactive Materials