ML19345D564
| ML19345D564 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 11/24/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Koester G KANSAS GAS & ELECTRIC CO. |
| References | |
| NUDOCS 8012160078 | |
| Download: ML19345D564 (1) | |
Text
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. ['3 NUCLEAR REGULATORY COMMISSION eq
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611 RYAN PLAZA DRIVE. SUITE 1000 ARLINGTON TEXAS 76011 In Reply Refer To:
November 24, 1980 RIV M
Docket No. STN 50-482/IE Information Notice No. 80-42 f_,
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N' Kansas Gas & Electric Co.
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Attn: Mr. Glenn L. Koester MS Vice President-Nuclear i.;
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Post Office Box 208 0
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Wichita, Kansas 67201 J
Gentlemen:
The enclosed IE Information Notice is provided as an early notification of a possibly significant matter.
Recipients of this notice should review the infor-mation for possible applicability to their facility.
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.
Sincerely, 7
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l V vy Karl V. Seyfrit
Director
Enclosures:
I 1.
IE Information Notice l
No. 80-42 l
2.
List of Recently Issued IE Information Notices cc: w/ enclosures Messrs. N%1as A. Petrick, SNUPPS D... McPhee, Kansas City Power and Light Company l
Gerald Charnoff, Shaw, Pittman, Potts & Trowbridge E. W. Creel, Kansas Gas and Electric Company 8 012160 67f
SSINS No.:
6835 Acce'sion No.-
UNITED STATES 8008220261 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Information Notice No. 80-42 Date:
November 24, 1980 Page 1 of 2 EFFECT OF RADIATION ON HYDRAULIC SNUBBER FLUID Descriotion 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 nbtained from the results of a study performed for FPC by Rensselaer Polytechnic Institute (RPI).
These results contained two items of prima importance to the operation of the suppressors.
The first result was a significant i1 crease of the viscosity of the fluid to the extent that incirient gelation of the fluid occurred at exposures of approximately 50 Mrad.
The viscosity ir. creased linearly for exposures up to 20 Mrad and then increased exponentially for exposures greater than 20 Mrad.
The second result showed that hydrcchloric acid (hcl) was formed in significant quantities when the fluid was subjected to radiation.
The following table lists the dose irradia+. ion time and hcl formed.
Dose Irradiation hcl Formed (Mrad)
Time (ppm) 0 2.78 l
- 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 l
One of the recommendatiors 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 I
from 2.3 to 3.6 Mrads, ;hese values were determined by comparing the viscosity l
of the fluid in service to that of the test samples at RPI.
The Technical l
Instruction Manual that is provided by the vendor for these suppcessors i
contains a recommendation that 12.5 Mrads should be the maximum service life for Versilube F-50.
1 I
I L
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1 IE Information Notice No. 80-42 November 24, 1980 Page 2 of 2 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 app'icability 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.
No written response to this IE Information Notice is required.
If you have any questions regardir.g this matter, please cratact the Director of the appropriate NRC Regional Office.
1 9
IE Information Notice No. 80-42 November 24, 1980 LISTING 0F RECENTLY ISSUE 3 IE INFORMATION NOTICES Information Subject Date Issued To Notice No.
Issued 80-35 Leaking and Dislodged 10/10/80 All categories G and Iodine-124 Implant Seeds G1 medical licensees 80-36 Failure of Steam 10/10/80 All nuclear power Generator Support Bolting reactor facilities holding Operating Licensees (0Ls) or Construction Permits (cps) 80-37 Containment Cooler Leaks 10/24/80 All nuclear power and Reactor Cavity facilities holding Flooding at Indian Point power reactor Operating Unit 2 Licenses (OLs) or Construction Permits (cps) 80-38 Cracking in Charging 10/30/80 All Pressurized Water Pump Casing Cladding Reactor Facilities holding power reactor Operating Licenses (0Ls) and Construction Permits (cps) 80-39 Malfunctions Of Solenoid 10/31/80 All light water reactor Valves Manufactured By facilities holding Valcor Engineering Corporation power reactor Operating Licenses (0Ls) or Construc-l tion Permits (cps) 80-40 Excessive Nitrogen 11/7/80 All power facilities Supply Pressure with an Operating License Actuates Safety-Relief (0L) or Construction i
Valve Operation to Permit (CP) l Cause Reactor Depressuriza-l tion 80-41 Failure of Swing Check 11/10/80 all cower reactor Valve in the Decay Heat
- 1; ties with an Operating Removal System at David-Licerse (OL) or Construction l
Besse Unit No. 1 Permit (CP)
Enclosure 1
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