ML20030D326
| ML20030D326 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 10/15/1980 |
| From: | Mclain D, James Smith VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20030D322 | List: |
| References | |
| NUDOCS 8109010184 | |
| Download: ML20030D326 (22) | |
Text
.
Attachment No. 2 Containment Shielding and Radiation Survey Nor th Anna Unit 2 Oc.tober 15, 1980 i
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-SU-a
'L VIRGINIA ELECTRIC AND PCWER COMPANY Revisien Nc.'
o Date:
05-03-79 ERTH m POWER STATICN UNIT #
2 STARTUP TEST PROCEDURE FCR TITLE:
C0tran: Mar:' samING Mm pmmt e-mm __
(Plant Cenditien)
Precared Sv:
J. P. SMI-s Date:
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e_,o Engineering Recermended Acoroval:
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Date:
04-26-79 3TATION NUCLEAR S AFETY AND OPERATING COMMIT EE *P:ROVAL OF PROCECURE:
Cha i.- an 's S i gnature:
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Date:
05-03-79 e
1:
All personnel cenducting actual :esting in acecreance wi:5 :his prececure will veri fy ':y tneir signa:ure that they have read i t in its entire:y prior :c cerrmencing any tes:ing:
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'd-in, Chair an's Signature:
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2-SU-6 Page 1 of 5 05-03-79 VIRGINIA EI.ECTRIC AND POWER COMPANY NORTH ANNA POWER STATION L3IT 2 CONTAINMF.NT SHIEI. DING AND RADIATION SURVEY
REFERENCES:
1.
Vepco Startup Procedure 2-SU-1 2.
FSAR Table 14.1-2, II.2; III.12 3.
Health Physics Radiation Protection Manual 4
ADMIN-5.0 1.0 Pureose 1.1 To measure the dose rate levels at pre-selected locations inside r
I and cutside the containment due to neutron and gama radiation and to verify the effectiveness of the plant shielding at prior to criticality, hot zero power, 30*.,
50",
75*., and 100*. condi-tions.
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2-SU-8 Page 2 of 5 05-03-79 itials 2.0 Initial Conditions fU)h(b-2.1 Immediately prior to the performance of this test, the Test Engineer has reviewed the latest revisions of the applicable references in order to improve his familiarity of this procedure of the test.
(i.e. Changes to the system, equipment or com-ponent since the procedure was approved will not affect its testing.)
.a 2.2 Verify that all test equipment to be used in the performance of this test is operational and in calibration, and record on the attached TEST EQUIPME. I DATA SHEET.
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2.3 Notify the Shift Supervisor on duty of the impending test and coc;dinate its performance through him.
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2.4 The survey instruments response and battery condition shall be checked at the beginning and end of the survey.
7;fv' 2.5 The plant is at the power level prescribed by Reference 1
( \\cc) %) and has been in steady state conditions at this power level for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the survey.
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2.6 Survey teams will consist of a minimum of two personnel, of which one must be a member of the Health Physics Department.
b N 2.7 Trior to performing the survey, the survey teams have reviewed the areas and locations to be surveyed.
h 2.8 Air samples shall be obtained prior to the survey and analyzed for radioactive contamination levels.
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2.9 A Radiation Work Permit has been issued (if applicable).
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2.10 The guidelines contained in Reference 3 shall be followed during the survey.
2-SU-8 Page 3 of 5 05-03-79 itials 3.0 Precautions 3.1 Care shall be exercised at all times during the survey to minimize dose received by the surveyors. Whenever possible exposure to r2diation shall be divided between the members of each survey team so that dose received by each member will be nearly the same.
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3.2 Prior to entering any area the survey meters will be read while the surveyors are still shielded behind existing barriers.
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3.3 The plant should remain a steady state conditions throughout the performance of the survey.
If a change in plant power level is required, the survey team must be notified prior to the change.
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2-SU-8 Page 4 of 5 05-03-79
- nitials 4.0 Instructions C.N 4.1 Utilizing Attachment 6.2 take neutron and gamma readings at the specified locations.
4.2 General area survey locations (designated by a
) will be takan by scanning over 360 degrees at waist level and logging the maximum reading obtained. General area survey locations (designated by a b ) will be taken facing the reactor vessel.
Contact area locations (designated by a O ) will de taken at the single point desienated.
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4.3 All readings obtained will be logged on the enclosed survey maps (Attachment 6.2) adjacent to the numbered symbol described in step 4.2 in mr/hr for gamma and in mrem /hr for neutron.
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survey data sheets.
b" Y-4.5 Recheck the calibration of the survey instruments used and record on Attachment 6.1.
4'. 6 Inform the Shift Supervisor that the radiation survey at this power level is complete.
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- -SU-8 Page 5 of 5 05-03-79 5.0 Acceutance Ciiteria 5.1 Dose rate levels for the power level of concern have been ob-1 tained. Any inconsistencies in the obtained data shall be resolved by Health Physics and need not stop further testing unless deemed necessary by the Supervisor - Health Physics and i
Operating Supervisor.
6.0 Attachments 6.1 Test Equipment = d Data Sheet 6.2 Survey Maps 1
1 i
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2-SU-8
'.1 Page 1 of 1 05-03-79 TEST EQUIP."hT DATA SHEET l
TEST EQUIPMENT CESCRIPTION*
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