ML19345C607
| ML19345C607 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/24/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Stampley N MISSISSIPPI POWER & LIGHT CO. |
| References | |
| NUDOCS 8012050655 | |
| Download: ML19345C607 (1) | |
Text
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UNITED STATES c
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,.gpetyt?l11 CLEAR REGULATORY COMMISSION o
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101 MARIETTA ST., N.W., SUITE 3100 ej
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ATLANTA, G EORGIA 30303 19
- g gGV 26 m 3 NOV 2 41930 In Reply Refer To:
W," ' $. a1;hM5ERylCES RII:JPO, 50-416 )
3;, SUI 50-417 /
Mississippi Power and Light Company ATTN:
N. L. Stampley Vice President of Production P. O. Box 1640 Jackson, MS 39205 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 o.-
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.
Sincerely,
- sw yk
'~a dwg James P. O'Reilly Director
Enclosures:
1.
IE Information Notice No. 80-42 2.
List of Recently issued IE Information Notices cc w/ encl:
C. K. McCoy, Plant Manager f
8012050 5
I SSINS No.:
6835 Accession No.:
UNITED STATES 8008220261 NUCLEAR REGULATORY COMMISSION IN 80-42 0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON,D.C. 20555
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1b November 24, 1980 c#
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-Jolth 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 containel. < o items of prime importance to the operation of the suppressors. The fit <t result was a significant increase of the viscosity of the fluid to the extent that incipient gelation of the f1 rid 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.
18.5 11.2 minutes 555 50.3 15.2 minutes 1592 One of the recom,endations 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 l the information for possible.ipplicability 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.
I IN 80-42 Noverabe r 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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k l
IN 80-42 November 24, 1980 RECENTLY ISSUED IE INFORMTION NOTICES Information Date of Notice No.
Subject Issue Issued to 80-42 Effect of Radiation on 11/24/80 All nuclear power reactor Hydraulic Snubber Fluid facilities with an OL or CP 80-41 Failure to Swing Check Valve 11/10/80 All nuclear power reactor in the D reay Heat Removal facilities with an OL System at Davie-Besse Unit or CP No. 1 80-40 Failure Of Swing Check 11/10/80 All power facilities Valve In The Decay Heat with and OL or CP Removal System At Davis-Besse Unit No. I 80-39 Malfunctions Of Solenoid 10/31/80 All light water reactor Valves Manufactured By facilities holding Valcor Engineering Corporation power reactor OLs or cps 80-38 Cracking In Charging Pump 10/30/80 All PWR facilities Casing Cladding with an OL or CP 80-37 Containment cooler leaks 10/24/80 All nuclear power and reactor cavity facilities holding flooding at Indian Point power reactor OLs Unit 2 or cps 80-36 Failure of. Steam 10/10/80 All nuclear power Generator Support Bolting reactor facilities holding power reactor OLs or cps 80-35 Leaking and dislodged 10/10/80 All categories G and Iodine-124 implant seeds G1 medical licensees 80-34 Boron dilution of reactor 9/26/80 All pressurized water coolant during steam reactor facilities generator decontamination holding power reactor OLs 80-33 Determination of teletherapy 9/15/80 All teletherapy timer accuracy (G3) licensees 80-32
,ClariAication of certain 8/12/80 All NRC and agreement requirements for Exclu-state licensees t
.' sive-use shipments of radioactive materials 80-31 Mz1 operation of Gould-8/27/80 All light water reactor Brown Loveri Type 480 facilities holding OLs volt type K-600S and or cps K-DON 600S circuit breakers