ML19330A365

Operating Procedure 2-OP-12.2, Post-Accident Containment Atmospheric Sampling Sys.

ML19330A365
Person / Time
Site:	North Anna
Issue date:	07/11/1980
From:	Harvey S VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML19330A354	List: ML19330A353 ML19330A360 ML19330A365
References
2-OP-12.2, NUDOCS 8007170189
Download: ML19330A365 (5)

Text

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2-OP-12.2 Page 1 of 4 e

07-11-80 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION LWIT 2 POST ACCIDENT CONTAINMENT ATMOSPEERIC SAMPLING SYSTEM References

1. D.C. 80-S12

2. 1-ST-24

3. 2-0P-63.2 REV. PAGE DATE APPROVED NOT A CONTROLLED .

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' CRAIR$ STATION NUCLEAR SAFMY AND OPERATING COMMITTEE DATE: 07-11-80 SAFETY RELATED 8007170189 . . .

2-OP-12o2 Page 2 of 4 07-11-80 Initials 1.0 Purpose 1.1 To provide a post-accident containment atmospheric sample.

2.0 Initial Conditions 2.1 The containment is at sub-atmospheric pressure.

2.2 A graduated syringe with a needle approximately 7 inches is available to obtain a sample of about 1 cc.

3.0 Precautions and Limitations 3.1 Extremely high radiation levels are expected in the vicinity of the containment penetrations, where some of 'the manual isolation valves are located. Precautions should be taken to avoid excessive radiation exposures to personnel.

3.2 Radiatica levels on contact with the sample syringe may be as high as 5 Rem /hr. A small container (tool box, etc) should be used to transport the sa:ple, 3.3 Health Physics will generate a special radiation work permit to obtain and analyze the coolart sa=ple based upon current radio-logical conditions a a anticipated radiological hazards.

Consider use of special dosimetry; e.g. extremities, head, etc.

3.4 Health Physics will provide continuous dose control coverage while obtaining and analyzing the reactor containment sample.

3.5 Individuals shall not exceed 2.5 rem whole-body and/or 15 rem extremity exposure for the current quarter in the performance of this prc<;edure.

3.6 Reactor containment samples will be obtained and transported in the appropriate shielded cask.

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• 2-OP-12.2 Page 3 cf 4 07-11-80 Initials 4.0 Procedure 4.1 Line up the hydrogen analyzer (HC-200) to sample th'e Unit 2 containment atmosphere in accordance with 2-0P-63.2.

4.2 Close or. check closed, 2-HC-T-1 (This valve is located on the south wall in the drumming area).

4.3 Open valves 2-HC-T-2 and 2-HC-T-3 (located on the south wall in the drumming area).

4.4 Close 2-HC-T-4 (located behind the Unit 2 hydrogen analyzer.

4.5 For proper dilution, the sample volume (at temp & press.) must be determined. This assures analyzing a 1 cc sample at 75 F

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and 1 atmosphere pressure. Refer to nomogram (Attachment 6.1):

4.5.1 Read containment ambient pressure and convert to atmos-phere's.

4.5.2 Read contain=ent ambient te=perature and convert to "K.

4.5.3 Connect these points on the nomogram, and read on sample volume line, the equivalent sample volume which results in a ICC sx=ple at 75 F and 1 atmosphere.

4.6 After a suffic ent ti=e has elapsed to purge the sample line with contain=ent air cellect the sa=ple as follows:

4.6.1 Open valve 2-HC-T-1 (located on the south wall in the drumming area).

4.6.2 Using a graduated syringe with approximately a 7 in.

needle, insert the needle through the syringe cap.

4.6.3 Obtain the proper sample volume as determined in step 4.5.

4.6.4 Remove needle and close valve 2-i!C-T-1.

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2-OP-12.2

.~ Page 4 of 4 07-11-80 Initials 4.0 Procedure 4.7 Remove syringe, with ICC sample, to laboratory for dilution and analysis using existing equipment.

N_0U: Radiation levels on contact with the sa=ple syringe may be as high as 5 Rem /hr. Therefore the sample should be placed in a small container (tool box etc.) to provide some distance and shielding during transport of the sample to the lab.

4.8 Remove the hydrogen analyzer (HC-200) from serrice as per 2-OP-63.2.

4.9 Open 2-HC-T-4 and close 2-HC-T-2 and 2-HC-T-3.

Completed By:

Date:

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