ML17296B124
| ML17296B124 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/24/1980 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| References | |
| NUDOCS 8012160095 | |
| Download: ML17296B124 (8) | |
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0 00'NITED STATES NUCLEAR REGULATORY COMMISSION REGION V 1990 N. CALIFORNIABOULEVARD SUITE 20Z, WALNUTCREEK PLAZA WALNUTCREEK, CALIFORNIA94595 November 24, 1980 Docket Nos. 50-528, 50-529, 50-530 Arizona Public Service Company P. 0.
Box 21666 Phoenix, Arizona 85036 aL>
Attenti on:
Mr.
E.
E.
Van Brunt, Jr.
Vice President, Nuclear Projects.
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. Ii 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 this office.
Si ncerely, RE H. Engelken Director
Enclosures:
l.
IE Information Notice No. 80-42 2.
Recently IssUed IE Information Notices cc w/enclosures:
F.
M. Hartley, APS
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UNITED STATES NUCLEAR REGULATORY CCMMISS ION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON,D.C.
20555 SSINS halo.:
6835 Accession No.:
8008220261 IN 80-42 November 24, 1980 IE Information Notice No. 80-42:
EFFECT OF RADIATION ON HYDRAULIC SNUBBER FLUID Descri tion 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 '/ersilube 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. imoortance 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 wnen the fluid was subjected to radiation.
The following table lists the dose irradiation time and HC1 formed.
Dose (Mrad) 0 1.2 5.8 5.8 18.5 50.3 Irra )at>on Time 1 minute 5 minutes 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 11.2 minutes 15.2 minutes HC Formed (ppm) 2.78 70.3 329.
335.
555 1592 One of the recommendations by the RPI personnel was that'he 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 recorrmendation that 12.5 Mrads should be the maximum service life for Yersilube 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.
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IH 80-42 November 24, 1980 Page 2 of 2 No written response to this IE'nformation Notice is reouired.
If you have any questions regarding this matter, please contact the Director of the appropriate HRC Regional Offic.
RECENTLY ISSUED I E INFOR/1ATION NOTICES IN 80-42 November 24, 1980 Informati on Notice No.
80-41 80-40 Subject Failure of Swing Check Valve in the Decay Heat Removal System at Davis-Besse Unit No.
1 Failure Of Swing Check Valve In The Decay Heat Removal System At Davis-Besse Unit No.
1 Daze of Issue Issued to 11/10/80 All power reactor faci1 i ties with an OL or CP 11/10/80 All power facilities with and OL or CP 80-39 Mal functions Of Solenoid 10/31/80 Valves Manufactured By Valcor Engineering Corporation All light water reactor facilities holding power reactor OLs or CPs 80-38 80-37 80-36 80-35 Cracking In Charging Pump Casing Cladding Con ainmenx cooler 1eaks and reactor caviry flooding at indian Point Uni 2
Failure of Steam Generator Support Bolting Leaking and dislodged Iodine-124 implant seeds 10/30/80 10/24/80 10/10/80 10/10/80 All P'~!R facilities
,~ith an OL or CP All nuclear power acilities holding power reactor OLs or CPs All nuclear power reactor facilities holding power reactor OLs or CPs All categories G and G1 medical licensees 80-34 80-33 Boron dilution of reactor 9/26/80 coolant during steam qenerator decontamination Determination of teletherapy 9/15/80 timer accuracy All pressurized water reactor facilities holding power reactor OLs All tel etherapy (G3) licensees 80-32 Clarification of certain requirements for Exclu-sive-use shipments of radioactive materials 8/12/80 All iNRC and agreement state licensees
- Operating Licenses or Construction Permits
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