ML20005A920
| ML20005A920 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/05/1981 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Hancock J FLORIDA POWER CORP. |
| Shared Package | |
| ML20005A921 | List: |
| References | |
| IEB-79-01B, IEB-79-1B, TAC-42512, NUDOCS 8107060035 | |
| Download: ML20005A920 (5) | |
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Tois D fotv r valuation i den t i f i c e. the spaci fic i nfor' >etion requirod by ti e st pf and the ac tione, nn vour nart, necessarv to comol v wi'b - n f arenco (a).
o rennost that vno nrovido the infornation i den ti fi e in sec+inos 7,na e cf d
this Safoty ! valuation to oc within QG davs.
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e ifr. J. A. Hancock It rer.iains your responsibility to assure that the qualification deadline is met for all safety-related electrical equiprnent. The staff's review of your response to this letter should not delay any action which is required in order to meet the deadline.
Sincerely.
\\,70s7.STOLTZ" John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing
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,e June 5, 1981 Docket No. 50-302
.Mr. J. A. Hancock Director, Nuclear Operations Florida Power Corporation P. O. Box 14042, Mail Stop C-4 St. Petersburg, Florida 33733
SUBJECT:
ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT RE:
Crystal River Unit No. 3 Nuclear Generating Plant; License No.
DPR-72 Reference (a) - Order for Modification of License Concerning the Environmental Qualification of Safety-Related Electrical Equipment dated October 24, 1980
Dear Mr. Hancock:
This letter transmits the Safety Evaluation for the Environmental Qualiff'ition of Safety-Related Electrical Equipment at your facility. This evaluation las based on your submittals dated April 21, June 30 and October 31, 1980. Our letter of February 23, 1981, which forwarded our preliminary results, indicated -
that an item-by-item re-evaluation would be required at a later date. This Safety Evaluation identifies the specific infonnation required by the staff and the actions, on your part, necessary to comply with Reference (a). We request that you provide the information identified in Sections 3 and 4 of this Safety Evaluation to us within 90 days.
This Safety Evaluation addresses only the safety-related electrical equipment.
exposed to a harsh environment resulting from an accident (i.e., the IEB 79-01B review). Reference (a) requires that all safety-related electrical equipment be qualified by June 30, 1982. The NRC review effort for the equipment in mild environments will be addressed by reparate correspondence.
Your response may present alternatives to the staff positions in the evaluation.
The staff will consider alternative approaches if these methods are within
^5e 00R Guidelines or NUREG-0588, as appropriate. For example, an acceptable alternative to the NRC staff's temperature criterion used for the service conditions (i.e. Section 3.3) must base that service condition on the FSAR analysis or other NRC approved analysis, provided that the specific analysis, together with reference to the previous NRC acceptance of that analysis, accompanies the 90 day response.
In addition, some of the information in the Safety Evaluation may require clarification. Contact your project manager for assistance in these matters.
a Mr. J. A. Hancock -
It remains your responsibility to assure that the qualification deadline is met for all safety-related electrical equipment. The staff's review of your response to this letter should not delay any action which is required in order to meet the deadline.
Sincerely, l
LLl Jo in F. Stolz, Chief Op trating Reactors Branch #4 vision of Licensing
Enclosures:
1.
SER 2.
TER cc w/ enclosures:
See next page e
1
Crystal River Unit No. 3 50-302 Florida Power Corporation ccw/ enclosure (s):
Mr. S. A. Brandimore Mr. Robert B. Borsum Vice President and General Counsel Babcock & Wilcox P. O. Box 14042 Nuclear Power Generation Division St. Petersburg, Florida 33733 Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Mr. Wilbur Langely, Chairman Board of County Commissioners Mr. Tom Stetka. Resident Inspector Citrus County U.S. Nuclear Regulatory Commission Iverness, Florida 36250 Route #3, Box 717 Crystal River, Florida 32629 U. S. Environmental Protection Agency Region IV Office Mr. Dan C. Poole ATTN: EIS COORDINATOR Nuclear Plant Manager 345 Courtland Street, N.E.
Florida Power Corporation Atlanta, Georgia 30308 P. O. Box 219 Crystal River Florida 32629 Bureau of Intergovernmental Relations 660 Apalachee Parkway Crystal River Public Library Tallahassee. Florida 32304 668 N. W. First Avenue Crystal River, Florida 32629 Mr. J. Shreve The Public Counsel Room 4 Holland Bldg.
Tallahassee, Florida 32304 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304 Dr. William R. Stratton Los Alamos Scientific Lab Box 503 Los Alamos, New Mexico 87544 i
&c ATTACHMENT 1 Fixboro, MA 03 35 U.SA The Foxboro Company sm sc.873o 12 March 1981
Subject:
Potential Deficiency Af fecting Foxboro Transmitters, Model Numbers N-Ell, N-E13 or Ell, E13 with suffix Codes /MCA, /MCA/RRW, ot /MCA/RR Gentlemen:
Our records indicate that you have received one or more of the Foxboro model nu=bered transmitters listed above.
This letter is to notify you that two deficiencies have been discovered in some of these transmitters which may exist in the units shipped to you.
The transmitters in question operate at a signal level of 10-50mA.
Similar model numbered units operating at 4-20mA are not affected.
The first issue involves the possible use of incorrect insulating sleeving on transistor and zener diode lead wires in the ann 1.ifier. The secord issue itvolves the use of a specific vendor's cdpacitor which is not hermetically sealed (although claimed to be so).
As a result, the capacitor electrolyte can leak under adverse service conditions, specifically heat and time.
The failure mode is a decrease in resistance across the capacitor resulting in electrical leakage.
The transmitter operation can be affected by limiting the output to something less than full value which, in time, can degrade to no output at all.
I Insulating Sleaving - Radiation resistant sleeving consisting of a silicone coated glass fiber braid has been substituted by a teflon sleeving in some transmitters.
Tests have shown that teflon will become brittle and deteriorate l
l with a substantial integrated radiation dose.
Foxboro testing has demonstrated that the teflon sleeving used in these devices will withstand an integrated dose of 10 megarads with no noticeable deterioration.
Tests to 200 megarads produce the brittle conditions which can result in the teflon flaking from the wires.
Based on these tests, operating plants not expected to exceed an integrated dose of 10 megarads have no potential problem and no action is required.
Where the integrated doce rate could exceed 10 megarads, then units in service should be inspected to determine if the proper insulating material has been used.
This can be accomplished by opening the transmitter in accordance with Foxboro >bster Instruction MI 20-145.
The amplifier cover must be removed exposing the amplifier assembly.
At one end of the asse=bly, a transistor and a zener diode are counted in the'bcse casting which serves as a heat ; ink.
The insulating material in question is a sleeving slipped over the lead sites from these two components.
The proper material is white and heavy looking.
Positive foXBoffd asumummer
Page 2 12 March.1931
Subject:
l identification can be made by inspecting one end of the material to establish that the outer material covers an inner braid.
Teflon, if used, will be a single layer material and could be either clear or white.
If improper insulation is present, then the corrective action is to replace the-amplifier (Foxboro P/N N0148PW).
Replacement amplifiers can be purchased from your local Foxboro Sales or Service Representatives.
If you prefer to have Foxboro Service Personnel inspect the equipment and, if necessary, replace the emplifier, this can be arranged at standard service rates.
Capacitor - The capacitor degradation problem was discovered over time thr'ough tracking failure situations.
Internal corrective action has been taken to remove the vendor involved from the qualified vendor list and to purge all stock
' of capacitors from this vendor.
Degradation of this capacitor is a function of time and service conditions with heat being a primary contributor.
This phenomenon was observed in recent tests of transmitters using those capacitors.
The espacitor in question is manufactured by Cornell-Duebilier and can be specifically identified by a type number in the form TX-65-XXXX as well as a monogram in a box followed by a date code, e.g. lCs2 0874]
It is assigned Foxboro part nu=ber N0141MF.
To determine if this capacitor is present requires a visual inspection of the amplifier which can be accomplished as J?shriLcd above for the insu.'ating sleeving inspection. The recomzended corrective action should the above described capaciter be present is to replace the amplifier (Fcxboro PIN N0148PW) although is is pcssible to replace the capacitor with a Foxboro provided substitute.
Use of Foxboro Service personnel to perform the inspection and replacement, if necessary, can be arranged at standard service rates as described above.
Due to lack of knowledge of specific application, redundancy, and the like, Foxboro cannot determine if the NRC reporting requirements of ICSFR Part 21 are applicable.
This determination is the responsibility of the user and any such reporting would l
be made by them after completing their evaluation of the situation.
If you have any questions regarding the above, please contact the undersigned directly.
Very truly yours, l
THE FOIBORO COMPANY l
l l
William Calder,.
ager Corporate Quality Assurance joy 120381 Enclosure MI 20-145 fOXBORO M
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