ML19284B787
| ML19284B787 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/24/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8101060318 | |
| Download: ML19284B787 (1) | |
Text
CENTRAL FILES UNITED STATES PDR:HQ NUCLEAR REGULATORY COMMISSION 1,
-h[/ l REGION tv NSIC
- 5. _
,5 611 RYAN Pt.AZA DRIVE, SUITE 1000 ARUNGTON. TEXAS 76011 STATE November 24, 1980 Docket Nos.
50-313 50-368 Arkansas Power and Light Company ATTN:
Mr. William Cavanaugh III Vice President of Generation and Construction P. O. Box 551 Little Rock Arkansas 72203 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 the'r 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 recomend or request specific licensee actions.
If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Sincerely,
' /'Cigf7 Karl V. Seyfrit [
Director
Enclosures:
1.
IE Information Notice No. 80-42 2.
List of Recently Issued IE Information Notices cc:
James P. O'Hanlon, Plant Manager Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 8101 O G 03(T q
'P 4 W" n ;,N" J
S SSINS No.:
6835 Accession 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 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 c jo.cras of approximately 50 Mrad.
The viscosity increased linearly for exposures up to 20 Mrad and then increased exponentially for exposures greati" than 20 Mrad.
The second result showed that hydrochloric acid (HC1) was formea in significant quantities when the fluid was subjected to radiat. ion.
The following table lists the dose irradiation tin: 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 minute!,
555 50.3 15.2 minutes 1592 One of the recommendations by the RPI personne 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 visecsity 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.
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 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.
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.
IE Information Notice No. 80-42 November 24, 1980 LISTING OF RECENTLY ISSUED 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 licensaes 80-36 Failure of Steam 10/10/80 All nuclear power Generator Support Bolting reactor facilities holding Operating Licensees (OLs) 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 redctor 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 (OLs) 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-tion Permits (cps) 80-40 Excessive Nitrogen 11/7/80 All power facilities Supply Pressure with an Operating License Actuates Safety-Relief (OL) or Construction Valve Operation to Permit (CP)
Cause Reactor Depressuriza-tion 80-41 Failure of Swing Check 11/10/80 All power reactor Valve in the Decay Heat facilities with an Operating Removal System at David-License (OL) or Construction Besse Unit No. 1 Permit (CP)
Enclosure