ML18139A138
| ML18139A138 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 02/06/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Proffitt W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| GL-80-11, NUDOCS 8004090358 | |
| Download: ML18139A138 (5) | |
Text
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In Reply Refer RII:JPO 50-338, 50-50-339 0-405 50-281 To:
e UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 FEB 6 1980 Virginia Electric and Power Company Attn:
W. L. Proffitt Senior Vice President, Power P. 0. Box 26666 1chmond, Virginia 23261 Gentlemen:
Enclosed is IE Bulletin No. 80-03, which requires action by you with regard to your reactor facility(ies) with an operating license or a construction permit.
Should you have questions regarding this Bulletin or the actions required of.
you, please contact this office.
Enclosures:
- 1.
- 2.
List of Recently Issued IE Bulletins
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James P. O'Reilly
- Director
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W.R. Cartwright, Station Manager Post Office Box 402 Mineral, Virginia 23117 P. G. Perry Senior Resident Engineer Post Office Box 38 Mineral, Virginia 23117 W. L. Stewart, Manager Post Office Box 315 Surry, Virginia 23883 6 1980
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 February 6, 1980 SSINS No.:
6820 Accessions No. :
7912190669 IE Bulletin No. 80-03 LOSS OF CHARCOAL FROM STANDARD TYPE II, 2 INCH, TRAY ADSORBER CELLS
, Description of Circumstances:
During preliminary leak tests of charcoal adsorber cells in certain ventilation systems at Sequoyah Nuclear Plant, it was determined that on certain adsorber cells the spacing between rivets securing the perforated screen to the ~asing was too great to ensure adequate contact between the casing and the screen, thus allowing charcoal to escape.
The problem was discovered when a visual inspection detected loose charcoal on the floor of the filter housings and on the outside horizontal surfaces of the adsorber cells.
Loss of charcoal was also indicated by observation of light penetrating through the cells.
Additional inspection revealed that the rivets securing the perforated screens to the cell casing were approximately six inches apart and the screen appeared to be sagging away from the casing between rivets.
The particular adsorber cells being tested at Sequoyah Nuclear Plant were Flanders Type II pre-1974 fabrication.
There is a possibility that design of adsorber cells with wide spacing between screen rivets may pass initial freon leak tests but degrade significantly during operation thus reducing the margin of safety during postulated accidents.
The responses from this Bulletin will be used by the NRC to evaluate need for more frequent inspection/testing.
For all power reactor facilities with an Operating License:
- 1.
Determine if charcoal adsorber cells in use, or proposed for use, have the potential for a loss of charcoal incidental to handling, storage or use (as appropriate).
Particular attention should be directed to examina-tion of a) rivet spacing resulting in separation of screen and cell housing and b) adsorber cell or filter housing deformation causing loss of charcoal and/or channeling.
Either of these items could result in a degraded filtration system incapable of performing its intended function.
The preferred method of this determination is a visual inspectio~ of the filter housing and adsorber cells as descriped in Section 5 of ANSI NSl0-1975.
If this method is not feasible/Ji.ate in the report required by Paragraph 4 how the determination was made.
- 2.
For ESF filtration systems, any identified defective cells shall be replaced and the operability of the system (after cell replacement)
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- i.
I IE Bulletin No. 80-03 February 6, 1980 Page 2 of 2 demonstrated by leak testing within 7 days.
Preferred method of leak testing is as described in Regulatory Guide 1.52 and Section 12 of ANSI NS 10-1975.
- 3.
For normal ventilation exhaust filtration systems which employ charcoal adsorber cells and for which radioactive removal efficiency has been assumed in determining compliance with the "as low as reasonably achievable" design criteria of 10 CFR SO, Appendix I, any identified defective cells shall be replaced as soon as possible but at least within 30 days.
After replacement, the system should be demonstrated operable by leak testing within an additional 30 days.
Preferred method of testing is as described in Regulatory Guide 1.140 and Section 12 of ANSI NSl0-1975.
- 4.
Report in writing within 45 days of the date of this Bulletin the ~esults of the determination required by Paragraph 1.
The report shall include the type of cells employed* (manufacturer and cell design), system containing the cells, observed cell condition (degradation/sagging) and a discussion of visual inspection procedure and results.
For all Power Reactor Facilities with a Construction Permit:
- 1.
Visual inspection shall be conducted only if the charcoal adsorber cells have been purchased and shipment received.
A representative number (approximately 5) of each type of cell design/manufacturer shall be visually inspected for such deficiencies as rivet spacing and screen/casing separation which could lead to loss of charcoal incidental to handling, storage, or use.
- 2.
Report in writing within 45 days of the date of this Bulletin the results of the inspection required by Paragraph 1.
The report shall include the type of cells (manufacturer and cell design), observed cell condition (degradation/sagging) and a discussion of the inspection procedure and results.
Reports shall be sent to the Director of the appropriate NRC Regional Office listed in Appendix D of 10 CFR 20 with a copy of the Director, Division of Fuel Facility and Materials Safety Inspection, Office of Inspection and Enforcement, USNRC, Washington, D.C.
20555~
Approved by GAO, Bl80225(R0072); clearance expires, 7/31/80.
Approval was given under a blanket clearance specifically for identified generic problems.
IE Bulletin No. 80-03 February 6, 1980 Bulletin No.
80-03 80-02 80-01 79-0lB 79-28 79-27 79-26 79-25 79-17 (Rev. 1) 79-24
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RECENTLY ISSUED IE BULLETINS Subject Loss of Charcoal from Standard Type II, 2 Inch, Tray Adsorber Cells Inadequate Quality Assurance for Nuclear Date Issued 2/6/80 1/21/80 Operability of ADS Valve 1/11/80 Pneumatic Supply Environmental Qualif~cation 1/14/80 of Class IE Equipment Possible Malfunction of 12/7/79 Namco Model EA 180 Limit Switches at Elevated Temperatures Loss Of Non-Class-1-E 11/30/79 Instrumentation and Control Power System Bus During Operation Boron Loss From BWR 11/20/79 Control Blades Failures of Westinghouse 11/2/79 BFD Relays In Safety-Related Systems Pipe Cracks In Stagnant 10/29/79 Borated Water System At PWR Plants Frozen Lines 9/27/79 Enclosure Issued To All power reactor facilities with an 01 or a CP All BWR licenses with a CP or 01
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All BWR power reactor facilities with and OL All power reactor facilities with an 01 All power reactor facilities with an 01 or a CP All power reactor facilities holding 01s and to those nearing licensing All BWR power reactor facilities with an 01 All power reactor facilities with an 01 or CP All PWR's with an OL and for information to other power reactors
.-All power reactor
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facilities.which have either 01s or CPs and are in-the late stage of construction