ML18150A241: Difference between revisions

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| number = ML18150A241
| number = ML18150A241
| issue date = 07/10/1987
| issue date = 07/10/1987
| title = Forwards Results of Spiked Samples Anlayses,Per NRC 870504 Ltr.All Analyses Completed by 870630.Tritium Analyses Performed at Station & Fe-55,Sr-89 & Sr-90 Analyses Performed by Teledyne Isotopes,Inc
| title = Forwards Results of Spiked Samples Anlayses,Per NRC .All Analyses Completed by 870630.Tritium Analyses Performed at Station & Fe-55,Sr-89 & Sr-90 Analyses Performed by Teledyne Isotopes,Inc
| author name = Stewart W
| author name = Stewart W
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
Line 11: Line 11:
| contact person =  
| contact person =  
| document report number = 87-266A, NUDOCS 8707220533
| document report number = 87-266A, NUDOCS 8707220533
| title reference date = 05-04-1987
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
| page count = 2
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=Text=
=Text=
{{#Wiki_filter:e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART                             July 10, 1987 VJCE PRESIDENT NuCLEAH  OPERATIONS United States Nuclear Regulatory Commission               Serial No.
{{#Wiki_filter:"
* 87-266A Attention: Mr. J.B. Kahle                                 NO/RMK:jmj Suite 2900                                               Docket Nos.
e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VJCE PRESIDENT NuCLEAH OPERATIONS July 10, 1987 United States Nuclear Regulatory Commission Attention:
* 50-280 101 Marietta Street, NW                                               ~ 50-281 Atlanta, GA 30323                                                         50-338 50-339 License Nos. DPR-32 DPR-37 NPF-4 NPF-7 Gentlemen:
Mr. J.B. Kahle Suite 2900 101 Marietta Street, NW Atlanta, GA 30323 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 NORTH ANNA POWER STATION UNITS 1 AND 2 NRC CONFIRMATORY MEASUREMENTS PROGRAM RESULTS OF SPIKED SAMPLES ANALYSES As specified in your letter of May 4, 1987, liquid samples spiked with radionuclides were received at our Surry Power Station on May 12, 1987, and at our North Anna Power Station on May 18, 1987. All analyses were completed by June 30, 1987, that is, within 60 days of receipt of the samples.
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 NORTH ANNA POWER STATION UNITS 1 AND 2 NRC CONFIRMATORY MEASUREMENTS PROGRAM RESULTS OF SPIKED SAMPLES ANALYSES Serial No.
The liquid samples have been analyzed for tritium (H-3), iron-55 (Fe-55),
NO/RMK:jmj Docket Nos.
strontium-89           (Sr-89), and strontium-90 (Sr-90) in accordance with your instructions. The tritium analyses were performed at the station with a liquid scintillation counter, an4 the Fe-55, Sr-89, and Sr-90 analyses were performed by our vendor, Teledyne Isotopes, Inc., as called for by station procedures.
License Nos.
* 87-266A 50-280
~
50-281 50-338 50-339 DPR-32 DPR-37 NPF-4 NPF-7 As specified in your letter of May 4,
: 1987, liquid samples spiked with radionuclides were received at our Surry Power Station on May 12, 1987, and at our North Anna Power Station on May 18, 1987.
All analyses were completed by June 30, 1987, that is, within 60 days of receipt of the samples.
The liquid samples have been analyzed for tritium (H-3),
iron-55 (Fe-55),
strontium-89 (Sr-89),
and strontium-90 (Sr-90) in accordance with your instructions.
The tritium analyses were performed at the station with a liquid scintillation counter, an4 the Fe-55, Sr-89, and Sr-90 analyses were performed by our vendor, Teledyne Isotopes, Inc., as called for by station procedures.
The results of our analyses are provided in the attachment.
The results of our analyses are provided in the attachment.
If you have any questions regarding these results, please contact us.
If you have any questions regarding these results, please contact us.
Very truly.yours,
Very truly.yours,  
      ,"- \-",-*- **. >\
,"- \\-",-*- **. >\\  
        ."--.J ' - \ ;A,~~:-) .
."--.J '-\\ ;A,~~:-).
W. L. Stewart Attachment cc:     Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Mr. J. L, Caldwell NRC Senior Resident Inspector North Anna Power Station 97012~0 5~
W. L. Stewart Attachment cc:
PDR " 00 g~bl,gao PDR p
Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Mr. J. L, Caldwell NRC Senior Resident Inspector North Anna Power Station 97012~0005~ g~bl,gao PDR PDR p  


ATTACHMENT NRC CONFIRMATORY MEASUREMENTS PROGRAM SPIKED LIQUID SAMPLE ANALYSIS RESULTS SURRY POWER STATION Activity     Uncertainty Sample Isotope                  (µCi/ml)       (µCi/ml)
Sample Liquid Sample Liquid ATTACHMENT NRC CONFIRMATORY MEASUREMENTS PROGRAM SPIKED LIQUID SAMPLE Isotope H-3 Fe-55 Sr-89 Sr-90 Isotope H-3 Fe-55 Sr-89 Sr-90 ANALYSIS RESULTS SURRY POWER STATION Activity
Liquid  H-3                      2.2 E-5       +/-  0.4 E-5 Fe-55                    1. 6 E-5      +/- 0.2 E-5 Sr-89                    3.1 E-5       +/- 0.1 E-5 Sr-90                    3.1 E-6      +/- 0 .1 E-6 NORTH ANNA POWER STATION Activity    Uncertainty Sample Isotope                  (µCi/ml)        (µCi/ml)
(µCi/ml) 2.2 E-5
Liquid  H-3                      2.0 E-5      +/- 0.3 E-5 Fe-55                    1.4 E-5      +/- 0.1 E-5 Sr-89                    2.9 E-5      +/- 0.1 E-5 Sr-90                    2.7 E-6      +/- 0.1 E-6}}
: 1. 6 E-5 3.1 E-5 3.1 E-6 NORTH ANNA POWER STATION Activity
(µCi/ml) 2.0 E-5 1.4 E-5 2.9 E-5 2.7 E-6 Uncertainty
(µCi/ml)
+/- 0.4 E-5  
+/- 0.2 E-5  
+/- 0.1 E-5  
+/- 0.1 E-6 Uncertainty
(µCi/ml)  
+/- 0.3 E-5  
+/- 0.1 E-5  
+/- 0.1 E-5  
+/- 0.1 E-6}}

Latest revision as of 20:12, 5 January 2025

Forwards Results of Spiked Samples Anlayses,Per NRC .All Analyses Completed by 870630.Tritium Analyses Performed at Station & Fe-55,Sr-89 & Sr-90 Analyses Performed by Teledyne Isotopes,Inc
ML18150A241
Person / Time
Site: Surry, North Anna, 05000000
Issue date: 07/10/1987
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Kahle J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
87-266A, NUDOCS 8707220533
Download: ML18150A241 (2)
v • d • e


Text

"

e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VJCE PRESIDENT NuCLEAH OPERATIONS July 10, 1987 United States Nuclear Regulatory Commission Attention:

Mr. J.B. Kahle Suite 2900 101 Marietta Street, NW Atlanta, GA 30323 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 NORTH ANNA POWER STATION UNITS 1 AND 2 NRC CONFIRMATORY MEASUREMENTS PROGRAM RESULTS OF SPIKED SAMPLES ANALYSES Serial No.

NO/RMK:jmj Docket Nos.

License Nos.

  • 87-266A 50-280

~

50-281 50-338 50-339 DPR-32 DPR-37 NPF-4 NPF-7 As specified in your letter of May 4,

1987, liquid samples spiked with radionuclides were received at our Surry Power Station on May 12, 1987, and at our North Anna Power Station on May 18, 1987.

All analyses were completed by June 30, 1987, that is, within 60 days of receipt of the samples.

The liquid samples have been analyzed for tritium (H-3),

iron-55 (Fe-55),

strontium-89 (Sr-89),

and strontium-90 (Sr-90) in accordance with your instructions.

The tritium analyses were performed at the station with a liquid scintillation counter, an4 the Fe-55, Sr-89, and Sr-90 analyses were performed by our vendor, Teledyne Isotopes, Inc., as called for by station procedures.

The results of our analyses are provided in the attachment.

If you have any questions regarding these results, please contact us.

Very truly.yours,

,"- \\-",-*- **. >\\

."--.J '-\\ ;A,~~:-).

W. L. Stewart Attachment cc:

Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Mr. J. L, Caldwell NRC Senior Resident Inspector North Anna Power Station 97012~0005~ g~bl,gao PDR PDR p

Sample Liquid Sample Liquid ATTACHMENT NRC CONFIRMATORY MEASUREMENTS PROGRAM SPIKED LIQUID SAMPLE Isotope H-3 Fe-55 Sr-89 Sr-90 Isotope H-3 Fe-55 Sr-89 Sr-90 ANALYSIS RESULTS SURRY POWER STATION Activity

(µCi/ml) 2.2 E-5

1. 6 E-5 3.1 E-5 3.1 E-6 NORTH ANNA POWER STATION Activity

(µCi/ml) 2.0 E-5 1.4 E-5 2.9 E-5 2.7 E-6 Uncertainty

(µCi/ml)

+/- 0.4 E-5

+/- 0.2 E-5

+/- 0.1 E-5

+/- 0.1 E-6 Uncertainty

(µCi/ml)

+/- 0.3 E-5

+/- 0.1 E-5

+/- 0.1 E-5

+/- 0.1 E-6

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