ML18153A303

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Provides Results of Specific Activity Analysis in Which Limits of Plant TS 3.1.D.4,exceeded
ML18153A303
Person / Time
Site: Surry  Dominion icon.png
Issue date: 04/22/1998
From: Christian D
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
98-157, NUDOCS 9804280041
Download: ML18153A303 (7)
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e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 22, 1998 United States Nuclear Regulatory Commission Serial No.98-157 Attention: Document Control Desk NS&L/BAG Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 ANNUAL REACTOR COOLANT SPECIFIC ACTIVITY REPORT Pursuant to the reporting requirements of Surry Technical Specification 6.6.A.2.b, Virginia Electric and Power Company submits the annual report of reactor coolant specific activity analysis for 1997. This report provides the results of specific activity analysis in which the limits of Surry Technical Specification 3.1.D.4 were exceeded.

The specific activity of the reactor coolant for Unit 1 exceeded 1.0 µCi/cc DOSE EQUIVALENT 1-131 during three events for the reporting period, but remained below the 100/E µCi/cc limit. Information required by Surry Technical Specification 3.1.D.4 when the specific activity exceeds the specified limit is provided in the attachment.

The specific activity of the reactor coolant for Unit 2 did not exceed 1.0 µCi/cc dose equivalent 1-131 or 100/E µCi/cc during the calendar year 1997 and therefore no additional information is required for the annual report.

Please contact us if you have any questions or require additional information.

Very truly yours, D. A. Christian Site Vice President Attachment Commitments made in this letter: None

::::-:~::-=;;~;-;;--:;~~~~-----,

9804280041 980422 PDR ADOCK 05000280 p PDR

cc: United States Nuer Regulatory Commission Region II Atlanta Federal Center

,61 Forsyth Street, S. W., Suite 23T85

  • Atlanta, Georgia 30303 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station

e e Docket Nos: 50-280 Serial No.98-157 Attachment 1 Page 1 of 5 UNIT 1 REACTOR COOLANT SPECIFIC ACTIVITY IN EXCESS OF TECHNICAL SPECIFICATION 3.1.D.4 This report is submitted in accordance with Surry Power Station Technical Specification 6.6.A.2.b, which requires submission of an annual report with detailed information when specific activity of the reactor coolant system (RCS) exceeds 1.0 µCi/cc dose equivalent 1-131 or 100/E µCi/cc.

A. On January 24, 1997, at 0810 hours0.00938 days <br />0.225 hours <br />0.00134 weeks <br />3.08205e-4 months <br />, the Unit 1 RCS was sampled and the 1-131 dose equivalent was determined to be 2. 73E+O µCi/cc when the unit was at 0%

power. A sample at 100% reactor power taken prior to power reduction was 3.55E-2 µCi/cc 1-131 dose equivalent. The high iodine dose equivalent level was caused by fuel cladding defects and ramping the unit offline for a Maintenance outage.

Operations personnel entered the following Technical Specification (TS) 3.1.D.3 action statement:

"With the specific activity of the reactor coolant greater than 1.0 µCi/cc dose equivalent 1-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding 10.0 µCi/cc 1-131 dose equivalent level, the reactor shall be shut down and cooled to 500 °For less within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after detection."

Appropriate RCS sampling and analysis continued and at 2045 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.781225e-4 months <br /> on January 24, 1997, the RCS 1-131 dose equivalent specific activity was restored within limits.

The following information is provided in accordance with the requirements of TS 3.1.D.4:

1. Reactor power history, clean-up system flow history, history of degassing operations, and 1-131 dose equivalent specific activity starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded:

Date Time Power Letdown Degassing 1-131 DE Flow (gpm) Operations (µCi/cc) 1/22/97 0800 100 % 110 No 1/22/97 0903 100 % 110 No 3.55 E-2 1/23/97 0800 100 % 110 No 1/24/97 0100 100 % 110 No 1/24/97 0200 93% 110 No 1/24/97 0500 42% 110 No 1/24/97 0555 30% 110 No 6.87 E-2 1/24/97 0700 15% 110 No 1/24/97 0800 0% 110 No 1/24/97 0810 0% 110 No 2.73 E+O

e Docket Nos: 50-280 Serial No.98-157 Attachment 1 Page 2 of 5

2. Isotopic analysis for radioiodine performed prior to exceeding the limit, results of the analysis while the limit was exceeded, and results of one analysis after the radioiodine activity was reduced to less than the limit:

Date Time 1-131 1-132 1-133 1-134 1-135 1-131 DE 1/24/97 0555 3.91E-2 6.17E-2 7.82E-2 2.56E-2 6.93E-2 6.87E-2 1/24/97 0810 2.07E+O 9.08E-1 2.01E+O  ::;;1.20E-1 9.92E-1 2.73E+O 1/24/97 1025 1.61E+O 4.09E-1 1.57E+O 2.54E-2 6.47E-1 2.10E+O 1/24/97 1240 1.58E+O 2.96E-1 1.25E+O  ::;;2.62E-2 4.58E-1 1.97E+O 1/24/97 1445 1;37E+O 2.43E-1 9.84E-1  ::;;1.48E-2 3.13E-1 1.67E+O 1/24/97 1635 1.11 E+O 1.92E-1 7.90E-1  ::;;4.31 E-3 2.17E-1 1.35E+O 1/24/97 1845 8.79E-1 1.74E-1 5.65E-1  ::;;4. 71 E-3 1.35E-1 1.05E+O 1/24/97 2045 7.12E-1 1.64E-1 4.45E-1  ::;;3.22E-3 9.28E-2 8.46E-1

3. Graph of the iodine-131 and iodine-133 activity analysis performed prior to exceeding the limit, results while the limit was exceeded, and results of one analysis after the radioiodine activity was reduced to less than the limit:

10 120

  • 1-131 "1:--~
  • 1-133

-*-%Power 100 1

\ 80 c.)

\ .

GI g \ 60 3:

0 0 D.

\ ~

0 0.1 40 20 0.01 0 1/20/97 1/22/97 1/24/97 1/24/97 1/24/97 1/24/97 1/24/97 1/24/97 1/24/97 1/24/97 0105 0903 0555 0810 1025 1240 1445 . 1635 1845 2045

  • e Docket Nos: 50-280 Serial No.98-157 Attachment 1 Page 3 of 5 B. On February 20, 1997, at 0112 hours0.0013 days <br />0.0311 hours <br />1.851852e-4 weeks <br />4.2616e-5 months <br />, the Unit 1 RCS was sampled and the 1-131 dose equivalent was determined to be 1.14E+O µCi/cc when the unit was at 0%

power. A sample at 100% reactor power taken prior to power reduction was 8.53E-2 µCi/cc 1-131 dose equivalent. The high iodine dose equivalent level was caused by fuel cladding defects and from manual trip of the unit from 53% reactor power at 2259 hours0.0261 days <br />0.628 hours <br />0.00374 weeks <br />8.595495e-4 months <br /> on February 19, 1997. Operations personnel entered the action statement in Technical Specification (TS) 3.1.D.3. Appropriate RCS sampling and analysis continued and at 0519 hours0.00601 days <br />0.144 hours <br />8.581349e-4 weeks <br />1.974795e-4 months <br /> on February 20, 1997, the RCS 1-131 dose equivalent specific activity was restored within limits.

The following information is provided in accordance with the requirements of TS 3.1.D.4:

1. Reactor power history, clean-up system flow history, history of degassing operations, and 1-131 dose equivalent specific activity starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded:

Date Time Power Letdown Degassing 1-131 DE Flow (gpm) Operations (µCi/cc) 2/18/97 0100 100% 110 No 2/19/97 0050 100% 110 No 8.53 E-2 2/19/97 0100 100% 110 No 2/19/97 2200 91 % 104* No 2/19/97 2259 53% 104* No 2/20/97 0112 0% 104* No 1.14 E+O 2/20/97 0316 0% 109 No 1.11 E+O 2/20/97 0519 0% 109 No 1.00 E+O

  • Last recorded reading
2. Isotopic analysis for radioiodine performed prior to exceeding the limit, results of the analysis while the limit was exceeded, and results of one analysis after the radioiodine activity was reduced to less than the limit:

Date Time 1-131 1-132 1-133 1-134 1-135 1-131 DE 2/19/97 0050 3.86E-2 8.78E-2 1.16E-1 1.13E-1 1.23E-1 8.53E-2 2/20/97 0112 7.21 E-1 5.12E-1 1.24E+O 9.05E-2 6.98E-1 1.14E+O 2/20/97 0316 7.62E-1 2.87E-1 1.06E+O 1.71 E-2 5.44E-1 1.11 E+O 2/20/97 0519 7.09E-1 2.04E-1 9.37E-1 ~8.94E-3 4.08E-1 1.00E+O 2/20/97 0727 6.01 E-1 1.38E-1 7.38E-1 ~5.68E-3 2.66E-1 8.28E-1

e Docket Nos: 50-280 Serial No.98-157 Attachment 1 Page 4 of 5

3. Graph of the iodine-131 and iodine-133 activity analysis performed prior to exceeding the limit, results while the limit was exceeded, and results of one analysis after the radioiodine activity was reduced to less than the limit:

10 120

  • 1-131

~- ..... - '\

  • 1-133

-A-% Power 100

\

1 80

...GI

-u u

u:l 60

~

0

==

0 C.

0.1 40 2/17/97 2/18/97 2/19/97 2/20/97 2/20/97 2/20/97 2/20/97 2/20/97 0025 1255 0050 0112 0316 0519 0727 0935 C. On March 7, 1997, at 0505 hours0.00584 days <br />0.14 hours <br />8.349868e-4 weeks <br />1.921525e-4 months <br />, the Unit 1 RCS was sampled and the 1-131 dose equivalent was determined to be 1.05E+O µCi/cc when the unit was at 0% power. A sample at 96% reactor power taken prior to power reduction was 7.28E-2 µCi/cc.

The high iodine dose equivalent level was caused by fuel cladding defects and from ramping the unit offline at 0349 hours0.00404 days <br />0.0969 hours <br />5.770503e-4 weeks <br />1.327945e-4 months <br /> on March 7, 1997 for a refueling outage. The fuel containing cladding defects was removed from the core. Operations personnel entered the action statement in Technical Specification (TS) 3.1.D.3. Appropriate RCS sampling and analysis continued and at 0838 hours0.0097 days <br />0.233 hours <br />0.00139 weeks <br />3.18859e-4 months <br /> on March 7, 1997, the RCS 1-131 dose equivalent specific activity was restored within limits.

The following information is provided in accordance with the requirements of TS 3.1.D.4:

1. Reactor power history, clean-up system flow history, history of degassing operations, and 1-131 dose equivalent specific activity starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded:

e Docket Nos: 50-280 Serial No.98-157 Attachment 1 Page 5 of 5

' )

Date Time Power Letdown Degassing 1-131 DE Flow (gpm) Operations (µCi/cc) 3/05/97 0010 95% 110 No 7.28E-2 3/05/97 0500 95% 110 No 3/06/97 0500 94% 110 No 3/07/97 0100 53% 110 No 3/07/97 0415 0% 110 No 8.80E-1 3/07/97 0505. 0% 110 No 1.05E+O 3/07/97 0645 0% 110 No 1.07E+O 3/07/97 0838 0% 110* No 9.41 E-1

  • Last recorded reading
2. Isotopic analysis for radioiodine performed prior to exceeding the limit, results of the analysis while the limit was exceeded, and results of one analysis after the radioiodine activity was reduced to less than the limit:

Date Time 1-131 1-132 1-133 1-134 1-135 1-131 DE 3/07/97 0415 5.89E-1 4.53E-1 8.77E-1 4.37E-2 4.54E-1 8.80E-1 3/07/97 0505 7.17E-1 4.44E-1 1.02E+O 3.12E-2 4.81 E-1 1.05E+O 3/07/97 0645 7.50E-1 3.16E-1 9.85E-1 ~1.15E-2 3.91 E-1 1.07E+O 3/07/97 0838 6.96E-1 1.88E-1 7.97E-1 4.05E-3 '2.80E-1 9.41 E-1

3. Graph of the iodine-131 and iodine-133 activity analysis performed prior to exceeding the limit, results while the limit was exceeded, and results of one analysis after the radioiodine activity was reduced to less than the limit:

120

  • 1-131
  • 1-133

-A-%Power 100 80

...CD 60 0 C.

40 3/03/97 3/05/97 3/07/97 3/07/97 3/07/97 3/07/97 3/07/97 3/07/97 0415 0010 0415 0505 0645 0838 0917 1300

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