ML20084L139
| ML20084L139 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 05/03/1984 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM P-84131, TAC-57944, NUDOCS 8405140354 | |
| Download: ML20084L139 (2) | |
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May 3, 1984 Fort St. Vrain Unit #1 P-84131 3 11@ KMf/ +
Mr. E. H. Johnson, Chief W., g g Reactor Project Oranch 1 U. 5. Nucioar Regulatory Commtssion W
611 Ryan Plaza Drive, Sutto 1000 Aritngton, TX 76011
$UBJECT: NUREG-0737 Item !!.F.1.1, Noble Gas Accident Monitoring Instrumontation
Dear Mr. Johnson:
As stated in our lotter P-79299, dated December 12, 1979, we do not have anyspostulated accident condition that will result in our present noble gas radiation stack monitors going off scale) This analysis was concurred with by personnel from BattoIIe ' Pacific Northwest Laboratorios, under contract to the NRC.
The Somt portablo Monitors currently in place woro put into service as agrood upon with the NRC as an interim measure only untti the NRC ruled on the appitcability of Item !!.F.1.1 to fort St. Vrain.
Although we continue to fool that our outsting nobio gas stack radiation monitors are adequato, your position in your,he feasiblitty
, letter dated April 3, 1984 (0-84110) will require us to(evaluato t of obtaining an installed permanent nobio gas stack monitor with an upper range of 10' wl/cc with roCout in the Control Room. We are currently in the process of contact'ng other plants to determine their method of complying with this item.
We anticipate that w' thin 60 days from the date of this letter, we will have determined how best to moet the 10' pct /cc upper range capability and address the concerns ralned in your letter. At that time we will inform you of our intended action, k
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With respect to the concerns raised in your letter, calibration of the semi portable instruments is performed via Health Physics Procedure HPP-20, and the supporting analyses are contained in HPP-56. Mr. Ron Baer of your office is on controlled distribution for these procedures.
Of course, the only way to verify the performance of the semi portable monitors would be to release radioactive noble gas at a concentration of 10' uci/cc up the stack to the environment. We do not feel that this is appropriate, nor, since our primary coolant noble gas concentration at 100% power is approximately 2.1 X 10 2 pci/cc, achievable.
I trust that this letter is responsive to your concerns; we will as always strive to keep you informed of our intent and actions on this matter.
Please contact Mr. Ted Borst of my staff with questions or comments at (303) 571-7436.
Very truly yours, h WW Don W. Warembourg Manager, Nuclear Production Fort St. Vrain Nuclear' Generating Station-DWW/djc cc: Ted Borst J
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