ML19290D376
| ML19290D376 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 02/06/1980 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Goodwin C PORTLAND GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 8002210300 | |
| Download: ML19290D376 (1) | |
Text
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- e.e WALNUT CREEK, CALIFORNf A 94596 February 6, 1980 Docket flo. 50-344 Portland General Electric Company 121 S. W. Salmon Street Portland, Oregon 97204 Attention: Mr. Charles Goodwin Assistant Vice President Gentlemen:
Enclosed is IE Bulletin fio. 80-03, which requires action by you with regard to your reactor facility 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.
Sincerely, ff
,aO R. H. Engelken Director
Enclosures:
1.
IE Bulletin flo. 80-03 2.
List of Recently Issued IE Bulletins cc w/ enclosures:
F. C. Gaidos, PGE J. W. Lentsch, PGE 80"9210 3o6 q
SSIfiS flo. : 6820 UNITED STATES Accessions No.:
NUCLEAR REGULATORY C0!!11SSION 7912190669 0FFICE OF IflSPECTION AND ENFORCE!!ENT WASHINGTON, D.C.
20555 February 6, 1980 IE Bulletin flo. 80-03 LOSS OF CHARCOAL FRO?t STANDARD TYPE II, 2 If!CH, TRAY ADSORBER CELLS Description of Circunstances:
Durinq prelininary leak tests of charcoal adsorber cells in certain ventilation systens at Sequoyah Nuclear Plant, it was deternined that on certain adsorber cells the spacing between rivets securing the perforatea screen to the casing was too areat 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 cerforated screens to the cell casing were approxinately 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 nay oass initial freon leak tests but degrade significantly during operation thus reducing the nargin of safety during postulated accidents.
The resoonses 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 charccal adsorber cells in use, or nroposed for use, have the potential for a loss of charcoal incidental to handling, storaqe or use (as anprooriate). 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 defomation causing loss of charcoal and/or channeling. Either of these itens could result in a degraded filtration system incapable of performirg its intended function.
The preferred method of this determination is a visual inspection of the filter housing and adsorber cells as described in Section 5 of ANSI N510-1975.
If this nethod is not feasible, state 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 systen (after cell replacenent)
IE Bulletin No. 80-03 February 6, 1980 Page 2 of 2 denonstrated by leak testing within 7 days. Preferred method of leak testing is as described in Regulatory Guide 1.52 and Section 12 of ANSI N510-1975.
3.
For normal ventilation exhaust filtration systems which employ charcoal adsorber cells and for which radioactive renoval efficiency has been assumed in determining conpliance with the "as low as reasonably achievable" design criteria of 10 CFR 50, Anoendix I, any identified defective cells shall be replaced as soon as nossible but at least within 30 days.
After replacement, the system should be demonstrated operable by leak testing within an additional 30 days.
Preferred nethod of testina is as described in Regulatory Guide 1.140 and Section 12 of ANSI "510-1975.
4.
F. ) ort in writing within 45 days of the date of this Bulletin the results
- o. the determination required by Paragraph 1.
The report shall include the type of cells enoloyed (nanufacturer and cell design), systen containing the cells, observed cell condition (dearadation/saaging) 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 resul ts.
Reports shall be sent to the Director of the approoriate NRC Regional Office listed in Appendix 0 of 10 CFR 20 uith a copy of the Director, Division of Fuel Facility and Materials Safety Insnection, Office of Inspection and Enforcement, USNRC, Washington, D.C.
20555.
Aporoved by GAO, B180225(R0072); clearance exof res, 7/31/80. Aporoval was given under a blanket clearance specifically for identified aeneric problens.
IE Bulletin No. 80-03 Enclosure February 6,1980 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
80-02 Inadequate Ouality 1/21/80 All BWR licenses with Assurance fer Nuclear a CP or OL 80-01 Coerability of ADS Valve 1/11/80 All BWR power reactor Pneunatic Supply facilities with and OL 79-018 Environnental Qualification 1/14/80 All oower reactor of Class IE Equipnent facilities with an OL 79-28 Possible !!alfunction of 12/7/79 All power reactor Nanco l'odel EA 180 Linit facilities with an Switches at Elevated OL or a CP Temperatures 79-27 Loss Of Non-Class-1-E 11/30/79 All oower reactor Instrunentation and facilities holding Control Power Systen Bus OLs and to those During Operation nearing licensing 79-26 Boron Loss From BWR 11/20/79 All BWR power reactor Control Blades facilities with an OL 79-25 Failures of Westinghouse 11/2/79 All power reactor BFD Relays In Safety-Related facilities with an Systens OL or CP 79-17 Pipe Cracks In Stagnant 10/29/79 All PWR's with an (Rev. 1)
Borated Water Systen At OL and for information PWR Plants to other power reactors 79-24 Frozen Lines 9/27/79 All oower reactor facilities which have either OLs or cps and are in the late stage of construction 79-23 Potential Failure of 9/12/79 All Power Reactor Emerqency Diesel Facilities with an Generator Field Operating License or Exciter Transformer a construction permit