ML20028G194

Total Integrated Dose to GE Stations.

ML20028G194
Person / Time
Site:	Waterford
Issue date:	02/01/1983
From:	Yang T EBASCO SERVICES, INC.
To:
Shared Package
ML20028G190	List: ML20028G194 W3P83-0335, Forwards Total Integrated Dose to GE Stations, Radiation Analysis Rept,Submitted as Addl Info Re Environ Equipment Qualification,Per NRC 830127 Request.Addl Relevant Info Also Provided
References
NUDOCS 8302070507
Download: ML20028G194 (17)

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ATTACHMENT 2 APPENDIX I 1

EQUIPMENT DOSE MAP USER' S GUIDE D

i l

l 1-1 Rev. No. 1 (1 !!3

. 134 6W-1 APPENDIX 1 WATERFORD-3 EQUIPMENT DOSE MAP USER'S GUIDE USERS GUIDE FOR RADIATION DOSE MAPS Saf ety-related equipment must be qualified f or the radiation environment to

! which it may be subjected. To satisf y the requiremente of NUREG-0588, the engineer must compare the actual or "specified" radiation dose to the

" qualified" radiation dose found in the vendor's test report. If the qualified dose is higher than the specified dose, by the appropricte margin, the equipment is qualified. If the qualified dose is not higher than the specified dose, or if data is not available; alternate qualification methods may be utilized. NO EQUIPMENT SHOULD BE REJECTED AS UNQUALIFIED WITHOUT CONSULTING THE APPLIED PHYSICS' ENGINEER.

The engineer obtains the "specified" radiation dose from the attached dose maps. The following is a description of how to use the dose maps, and an analysis flow chart for radiation qualification is shown on Figure 1-1.

STEP I - INITIAL DATA Before using the dose maps the engineer must know two things about the f'5 equipment he is qualifying - (1) its location in the plant and (2) the time af ter an accident that it is required to f unction. If the engineer does not know the exact location, or if the equipment is located in many places (such as cables); he must select the highest dose of any possible location. For example, a purchase order may include many limit switches used in many areas inside the containment; then, the highest dose in the containment must be selected. If the time required for the equipment to function after an accident is not known, the dose f or one year should be used.

NOTE: Four zones inside the plant have very high radiation doses. Ihese are:

j a) Reactor Cavity - Zone AA j b) Purification Filter and Preconcentrator Ion Exchanger Cubicle - Zone H c) Spent Resin Tank Oubicle - Zone I d) Solid Waste Storage and Purification Ion Exchanger Dubicle - Zone J For equipment such as cable or switches that have multiple locations, it might be advantageous to eliminate the above four zones from consideration, if possible, bef ore selecting the maximum dose. These zones are quite small, and, except f or the reactor cavity, should not contain sensitive safety-related equipment.

1-1 Rev. No.1, (1/83)

13468-2 .

STEP 2 - DETERMINE THE RADIATION ZONE Locate the equipment on the dose map and determine the zone (indicated by letters) corresponding to that location. If equipment is in more than one location, the zone corresponding to the highest dose will be used. The caps show all elevations of the Reactor Building, Auxiliary Building and the Fuel Handling Building. If equipment is located elsewhere (e.g., Turbine Building) then it is in a non-harsh radiation environment and does not need radiation qualification.

STEP 3 - DETERMINE THE SPECIFIED DOSE Use the zone number found in Step 2 to find the dose in the appropriate Table 1-2 or I-3. The dose for each zone is given in rads for forty year normal life plus three time periods after an accident (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, 30 days and 1 year).

The spe.ified dose is the sum of the forty year dose plus the appropriate Post-accident dose. This summation or total dose is shown on the right hand side of the table. If a dash appears in any column that means the dose is negligible and can be disregarded.

STEP 4 - BETA DOSE For zones in the Reactor Building, the accident dose in Table I is broken down into beta (g) and gamma (7) contributions. Normally the beta dose does not affect the equipment because of its low penetration power. The engineer must f decide whether the equipment being considered has its sensitive components (non-metallic or electronic) covered by at least 10 mils of steel, 30 mils of aluminum or 80 mils of elastomer (plastic). These material thicknesses will reduce the beta dose to one percent of the unshielded dose. This inforcation is given in 79-01B, Section 4.1.2, and it is supported by independent calculations. If this is the case, then the beta dose can be ignored and only the gamma dose need be used. This should be documented by either the engineer or vendor.

For containm'ent areas, numerous equipment will be difficult to qualify if the beta dose is included since originally only gamma dose was considered.

However almost all equipment has a cover thick enough to qualify by the above criteria, so it should be the normal case to disregard the beta dose. The engineer and/or the vendor must make this determination. Applied ?hysics can provide further backup material on this matter if a problem arises, since the doses can vary over a wide range within the volumes used on the dose maps.

NOTE: If the beta dose cannot be disregarded by the above method, then the specified dose is the sum of the 40 year dose, accident beta dose and accident gamma dose.

STEP 5 - COMPARE WITH TEST REPORT t I

4 The specified dose found in Step 3 or 4 must be compared to the vendor's test report. The NRC requires that the engineer exanine the actual test report and not just a vendor's qualification certification. The engineer is concerned I-2 Rev. No. 1, (1/83)'

1346W-3 with the total dose (rads) that the equipment was subjected to, and not the dose rate (rads / hour, etc.). NUREG-0588 requires a margin of 10 percent for the accident dose. Thus to be qualified the test dose must be greater than the spscified dose by this margin.

If the specified dose is greater than the test dose, or if no test data is available, then the subject equipment is an open item.

STE? 6 - OPEN ITEMS If an item does not qualify, in Step 5, alternate methods are available, and the Applied Physics' Engineer should be consulted on these methods. The dose maps are conservative and cover wide areas using the highest dose. The Applied Physics' engineer may be able to considerably reduce the specified dose of an individual item, by taking further shielding or geometry credits.

In addition, it may be possible to qualify an item that has no test data by other means. These include:

a) Material Breakdown - Identifying critical (most susceptable) materials, and using generic test reports to demonstrate qualification. AP has a large library of these generic reports.

b) Sensitivity Analysis - Showing that an item has no sensitive components.

7 c) Similarity - Using test reports of identical or similar equipment.

1 1-3 Rev. No.1, (1/83)

1349W-1 TABLE I-1 TOTAL CDRE INVENTORIES Dilution  % Of Total Core Inventories

• Volume /Are a No ble Halogens All Ge se s Others cc/cm2 Primary Loop Volume 3.14 X 108 10 0 50 1 (Small Break)

SIS Sump Water Volume 1.97 X 109 10 0 50 1 (Large Break)

Gaseous and Airborne 7.09 X 1010 10 0 25 0 Volume 4.0 3 + 108 0 25 1 Plateout Area (Rb & Cs) only A

• Tbtal core inventories were obtained from Table 4.3-1 of Combustion Engineering, " Radiation Design Guide, System 80, SYS80-PE-RG, Revision 4",

Issued July 12, 1979.

1 1

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I.6 Rev. No.1. (1/83) I

START k

LOCATE E PMENT US tBLE LOCAT D E NO LOCATION Z T THAN REACTOR, DOSE MAP UNKNOWN MAP HIGHEST DOSE AUX OR FUEL HAND BLD. THIS IS NON HARSH RADIATION ENVIR.

DETERMINE ZONE LETTER & _

REFER TO TABLES 1. II, Ill 37 ,

STOP l RADIATION OUALIF.

NOT NEEDED THE SPECIFit!D DOSE IS THE SUM OF 40 YEAR l NORMAL + APPROPRIATE ACCIDENT DOSE. RIGHT SIDE OF TABLE SHOWS TOTAL DOSE FOR 3 ACCIDENT TIMES. FOR THE CORRECT ZONE, SELECT THE TOTAL DOSE CORRESPONDING TO TIME AFTER THE ACCIDEN' THAT THE EQUIPMENT MUST FUNCTION. IF TIME IS UNKNOWN, USE 1 YEAR ARE U SENSITIVE gg PARTS COVERED BY A BETA AT LEAST 10 MILS STEEL,30 g YES DOSE LISTED MILS ALUMINUM OR FOR THAT B0 MILS ZCNE?

PLASTIC?

b '

1rNO SPECIFatiD DOSE 40 YEAR DOSE BETA DOSE IS IGNORE

^

G[MMA ) OSE f

SPECIFIED DOSE IS 40 NO - "

YEAR DOSE + ACCIDENT -

BETA ($) AND GAMMA (7)

DOSE y TEST REPORT CANNOT SE OBTAINED COMPARE SPECIFIED DOSE WITH QUALIFIED DOSE - ,

FROM VENDOR TEST REPORT l l

U y i OPEN ITEM IS CONSULT WITH QUALIFIED AP ENGINEER DOSE GREATER THAN FOH ALTERNATE m NO SPECIFIED DOSE BY OUAllFICATION AT LEAST A MARGIN  !

METHOD OR EQUAL TO 10%

POSSIBLE DOSE OF ACCIDENT REDUCTION DOSE YES STOP EQUIPMENT IS RADIATION QUALIFIED

. REV. NO.1. (1/83)

LOUISIANA I Figure POWER & LIGHT CO. R ADI ATION OUALIFICATION FLOW C' HART Waterford Steam I-1 Electric Station

- KTTACEME::T 3 I. MECHANICAL Total No. To File 3e Reviewed ODIFs 3.1W3 12 931, 933, 935, 1006, 1031, l"36, 1138, 1142, 1146, 2101, 210 E, 2141 3.2W3 23 808, 810, 812, 814, 827, E3C, 842, 902, 905, 907, 911, 913, I

l 916, 920, 1040, 1044, 1077,

! 1080, 1128, 1129, 1163, 119E 4.2W3 2 859, 881 4.3W3 1 872 4.11W3 1 2146 4.12W3 1 2125 .

4.13W3 1 2128 4.14W3 1 2143 9.lW3 16 940, 941, 950, 995, 1010, 1024, 1043, 1048, 1072, 1083, 1091, 1096-1112, 1201, 1249, 2134 9.2W3 16 801, 802, 803, 826, 840, 1055, 1059, 1101, 1148, 1154, 1166, 1215, 1222, 1226, 1234, 2120 35.lW3 7 925, 955, 966, 968, 1120, 1150, 1217 35.6W3 4 851, 854, 855, 1107 Total 85 1

1 J

Page_2 of ~ ,

III I&C Total No. To File Be Reviewed ODEFs 8.lW3 21 101, 103, 108, 110, 122, 123, 132 151, 158, 170, 185, 189, 192, 193 200, 212, 216, 2725, 2733, 4719, 4722

8. LAW 3 3 207, 221, 5128 8.2W3 5 450, 464, 482, 5022, 5112 36.lW3 5 400, 414, 417, 418, 2064 36.5W3 2 350, 355 39.2W3 18 502, 505, 510, 511, 512, 523, 525, 531, 536, 539, 541, 546, 550,.555, 559, 563, 2008, 2054 Total 54 IV HVAC 4.9W3 6 857, 1114, 875, 1185, 862, 864 4.10W3 1 990 10.2W3 1 1186 42.1W3 2 1192, 1236 42.2W3 2 956, 959 72.lW3 1 870 Total 13 V AP 8.3W3 10 1600, 1601, 1604, 1605, 1607, 1626, 1630, 1631, 1620, 1621 Total .10 TOTAL NO. REVIEWED: 162 which represents approximately 24% of the total number

,-,