ML19345C612

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Forwards IE Info Notice 80-42, Effect of Radiation on Hydraulic Snubber Fluid. No Written Response Required
ML19345C612
Person / Time
Site: Atlantic Nuclear Power Plant PSEG icon.png
Issue date: 11/24/1980
From: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Collier A
OFFSHORE POWER SYSTEMS (SUBS. OF WESTINGHOUSE ELECTRI
References
NUDOCS 8012080001
Download: ML19345C612 (1)


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UNITED STATES NUCLEAR REGULATORY COMMISSION o.

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ATLANTA, GEORGIA 30303 NOV 2 41980 In Reply Refer To:"

1 RII:JP0 c1GT437) i Offshore Power Systems ATTN:

A. R. Collier, President P. O. Box 8000 Jacksonville, FL 32211 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. 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, x i 3

~9/ m James P. O'Reilly Director

Enclosures:

1 1.

IE Information Notice No. 80-42 2.

List of Recently issued IE Information Notices 6

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SSINS No.: 6835 Accession No.:

UNITED STATES 8008220261 1

NUCLEAR REGULATORY COMMISSION IN 80-42 OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON,D.C. 20555 g

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 t%e 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.

18.5 11.2 minutes 555 50.3 15.2 minutes 1592 One of the recommendations 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 [the information for possible applicability to their facilities.

No specific action or response is requested at this time.

If NRC evaluations 1

so indicate, further licensee actions may be requested or required.

r.

.IN 80-42 Novreber 24, 1980 Page.2 of 2-7.

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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IN 80-42 Novenbar 24, 1980 RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No.

Subject Issue Issued to 80-42 Effect of Radiation on 11/24/80 All n,uclear 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 Decay Heat Removal facilities with an OL System at Dcvie-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 32 Clarification of certain 8/12/80 All NRC and agreement

. requirements for Exclu-state licensees j

.' <sive-use shipments of radioactive materials 80-31 Maloperation of Gould-8/27/80 All light water reactor Brown Boveri Type 480 facilities holding OLs volt type K-600S and or cps K-DON 600S circuit breakers

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