IR 05000277/1985019

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Insp Repts 50-277/85-19 & 50-278/85-15 as Followup Review to Insp on 840820-23.No Violation Noted.Major Areas Inspected: Results of Licensee Dosimetry Performance Tests
ML20127E465
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 06/13/1985
From: Holsopple K, Pasciak W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20127E463 List:
References
50-277-85-19, 50-278-85-15, NUDOCS 8506240559
Download: ML20127E465 (20)
v • d • e


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. U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report Nos. 50-277/85-19 50-278/85-15 Docket Nos. 50-277 50-278 License Nos. DPR-44 Priority - Category C DPR-56 Licensee: Philadelphia Electric Company 230 Market Street Philadelphia, Pennsylvania 19101 Facility Name: Peach Bottom Atomic Station, Units 2 and 3 Report Prepared by: M //&#aopp/A -' 6- 4S- 85' K. Holsoppis,' Radiation Specialist date Approved by: M aAE T Yld b _4 - 4 -#f W. Pastfak, Chief,'BWR A diological date Protection Section, EmVrgency Preparedness and Radiological Protection Branch Inspection Summary: . Dosimetry Performance Tests (Report Nos. 50-277/85-19 50-278/85-15) Areas Inspected: This report contains the results of the performance tests of the licensee's Harshaw and Eberline dosimeters used in their personnel dosimetry progra Licensee dosimeters were irradiated by the Dosimetry Branch of Radiological and Environmental Sciences Laboratory (RESL) at the Idaho National Engineering Laboratory. The licensee processed these dosimeters, and provided the results to Region I for evaluation. The evaluation involved 12 inspector-hours at the Region I office by two region-based inspector Results: Within the areas inspected, no items of noncompliance were observe $DR ADOCK 05000277 PDR 

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DETAILS 1. Persons Contacted Licensee Personnel D. Smith, Assistant Station Superintendent A. Hillsmeyer, Senior Health Physicist N. Gazda, Applied Health Physicist NRC Personnel T. Johr'an, Senior Resident Inspector H. Williams, Resident Inspector 2. Performance Test As a followup to a previous inspection conducted on August 20 - 23, 1984, Combined Inspection Report Numbers 50-277/84-25 and 50-278/d4-21, one hundred of the licensee's dosimeters, fifty made by Harshaw and fifty made by Eberline, were performance tested. The dosimeters were sent to the Dosimetry Branch of the Radiological and Environmental Scier.ces Laboratory (RESL) at the Idaho National Engineering Laboratory for irradiation and then returned to the licenste for processing. The results provided by the licensee are contained in Attachment A and The dosimeters were evaluated with respect to their responses (i.e., shallow dose which was measured at a depth of 7mg/cm2 and deen dose which was measured at a depth of 1000 mg/cm2) to four types of radiation field These include: (1) beta radiation; no gamma radiation (shallow dose only), (2) beta radiation and gamma radiation with the beta-to gamma radiation ratio >0.9, (3) beta radiation and gamma radiation with the beta-to gamma radiation ratio <0.9 and (4) gamma radiation; no beta radiation. All irradiations were performed with point sources with the exception of those which were performed with a uranium slab source which tested the response of che dosimeters to a non perpendicular field of beta radiation. The sources were chosen to test the dosimeters' responses to various emission spectra. The Harshaw dosimeters contain two lithium fluoride elements. Element one is unshielded and data from this element is not normally used. Element two is shielded and is used to measure gamma doses. When the Harshaw dosimeters are processed on a daily basis, the data from the unshielded element is not routinely used to estigate beta dose. The Eberline dosimeter is also a two-element lithium fluoride dosimeter, very similar to the Harshaw dosimete Eberline reports its doses in terms of " gamma dose" and " beta dose."

Attached are the results of the performance tests of the Harshaw and Eberline dosimeters used at Peach Bottom (see attachment C). Based upon a review of the results of these tests the following observations are made: 

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l 3 The most common current industry criteria for acceptance performance of personnel dosimetry systems are contained in ANSI N13.11. These criteria form the basis for the performance testing in the National Bureau of Standards National Voluntary Laboratory Accreditation Program (NVLAP). This standard requires, for doses in the protection range, that the sum of the absolute value of the average bias plus the relative standard deviation of the individual biases of the reported doses be 1 css than or equal to 0.5. Based on this criterion, the performances of both the Eberline and Harshaw dosimetry systems were acceptable with the following exceptions: Both systaus failed to meet this criterion for the T1-204 irradiations when the beta / gamma ratios exceeded 0.9 (shallow dose). These constitute situations where there is a significant beta component and probably reflect the effect of the thickness of the lithium fluoride chips. The results indicate a severe under-response to lower energy beta radiatio The Harshaw system failed marginally to meet the criterion for the uranium slab irradiation (beta only, shallow dose). The Eberline system marginally passed the uranium slab irriadiatio This performance could reflect both the energy dependence and directional dependence of the unshielded lithium fluoride chip Both systems failed to meet the criterion for the combired Cs-137/Sr-90 irradiation (deep dose) when the beta / gamma ratio exceeded 0.9. This may be due to the response of the under-shielded gamma chip to the highly penetrating Sr-90/Y-90 beta radiation, and the system was effectively recording betas as gamma radiation The response of both dosimeters to Cs-137 gamma radiation appeared to be adversely affected by the presence of Sr-90/Y-90 beta radiation but not by T1-204 beta radiation. This was probably for the reason discussed in 1.c abov . The under-response of the dosimeter to a depleted uranium slab source may be indicative of the directional dependence cf the dosimete Normal incident radiation is used to calibrate the dosimetry system to determine beta dose. Since the slab source results in radiation incident on the dosimeter over a wide range of directions, the response of the dosimeter is different than that normally expecte Whether normal radiation incidence is representative of actual field conditions depends on the orientation of the worker relative to the beta radiation fiel . Both dosimetry systems appear to respond to Cs-137 gamma radiation as they respond to Co-60 gamma radiatio These matters will be examined in a future inspection (50-277/85-19-01; 50-278/85-15-01).

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3. Exit Interview Dr. M. Pasciak, Chief, BWR_ Radiological Protection Section and Costello, Senior Radiation Specialist, discussed the results of this inspection in a telephone conversation on June 5, 1985, with the licensee representatives denoted in paragraph . 

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l ' . o' Page 1 of 2 ' Attachment A 

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PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION R. D.1. BOX 208 DELT A. PENNSYLV ANI A 17314 Septeraber 26, 1984 The attached list of Harshaw Badges were sent to the Department of Energy in Idaho Falls as instructed by the Nuclear Regulatory Commissio Included are the badge numbers and the corrected exposure to each chip. All readings are in mr 

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Attachment A Badge Number TLD 1 TLD 2 . 717064 .5 717046 .8 716421 .2 718032 11 .0 717000---- -2 .8-717349 63 .6 718179 34 .3 717204 15 .9 717769 51 .6 714677 6 .1 714483 31 .1 715165 65 .5 717203 42 .1 717796 47 .6 719274 175 .2 715764 31 .8 717015 .4 715732 188 .0 717634 106 .5 715141 22 .8 714983 28 .6 714485 72 .2 714471 14 .5 715125 45 .6 717600 69 .3 717975 248 .7 . 717220 176 .3 714929 197 .0 717044 46 .5 715040 102 .3 716952 10 .8 714341 4 .1 718095 2 .5 714752 -189 .2 718738- 53 .4 715202 .6 - 714982 179 .9 719292 31 .2 716474 36 .1 718824 254 .5 717132 175 .6 714220 10 .5 718121 29 .6 713879 41 .4 714369 .2 714496 185 .8 714368 .2-718245 27 .1 716611 .0 718739 174 .0 717368 10 .1 713400 140 .7 

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*     Page 1 of 2 Attachment B PHILADELPHIA ELECTRIC, COMPANY PEACH BOTTOM ATOMIC POWER STATION R. D.1, BOX 208 D ELTA, PENNSYLV ANI A 17314 October 30, 1984 The attached lis.t of Ebertine Badges were sent to the Department af Energy in Idaho falls as ins tructed by the Nuclear Reguta. tory Commission. Included are the badge numbers and the corrected exposure to each chip as repor.ted by Eberiine Instrument Corporation, Santa Fe, N Att readings are in mre '
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Attachment B 

. Badge Number Gamma Beta 4794~ 1640 230 4746  0 0 4724  0 0 4665  1496 268 4651  34 131 4581  1618 0 4558  246 0 4517  0 0 4465  525 517 9049  1625 0 9025  26 70 9002  1472 0 4986  1607 0 4925  301 0 4899  335 90 4887  '329 151 3181  1804 527 3170  0 0 3165  0 152 3106  37 .61 2981  303 55 2973  1400 190 2966  90 218 2958  0 80 2938  83 26 2911  437 250 2863  267 0 2817  1581 0 2778  324 169 2702  1494 0  -

2685 322 129 2537 0 65 2321 257 0 4402 453 479 

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4308 0 0 4302 357 450 4295 0 15 4258 322 0 4192 35 . 156 4191 1699 . 635 4153 0 25 4152 213 465 4008 71 222 3548 356 " 270 3546 199 156 3402 340 125 3371 306 31 3208 0 0 3204 242 0' 

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11ESL Delivered Dose Ebert ino Dose lia r ste..w Dose Shallow Qeep Dosimeter Shallow Deep Dosimeter Shallow peej 100 0 4153 25 0 717000 21 6 100 0 4295 15 0 718095 25 7 300 0 2537 65 0 714341 is6 7 300 0 2958 80 0 714677 66 6 

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700 0 2938 109 83 71:4220 109 7 700 0 3163 152 0 717368 106 6 Bias = -0.791 B ia s = -0. 812 Standa rd Deviation = 0.Ol 48 Standa rd Devia tion = 0.041 

 /Blas/+Standa rd Devia tion = 0.838*  /Blas/+Standa rd Deviation = 0.852'  y c+

c+ os Notes: Ebert Ine shallow doses a re interpreted as the sum of the reported beta and gamma dos Eberline deep dose is interpreted as the reported gamma doso, s r+ Ha *shav shallow doses are interpreted as the reported TLD 1 dos Harshaw deep n doses a re interpreted as the reportisd TLD 2 dos * Asterisk indicates failure to meet ANSI N13.11 criterion that /B/ + Standard Deviation less than or equal to p w V tD ct 

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RESL . . Delivered Dose Ebert ine Dose Ha rsti..w Dose Shaiinw Deen Dosimeter ShalIog Deep, Dosimeter Shaiiow 00e0 300 0 4192 191 35 714471 145 56 300 0 4651 165 34 717204 154 52 Blas = -0.407 . Blas = -0.502 Standa rd Deviation = 0.061 Standa rd Devia tion = 0.021 

 /Blas/+Standa rd Devia tion = 0.468 ,
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Notes: Eberline shailow doses are interpreted as the sum of the reported beta and gamma 3, Ebert ine deep dose is interpreted as the reported gamma dose, r+ dos * 

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_ Dos i metf ShaIIov De_ep Dos imne r Shailow Den 309 3 58 8 626 356 718 r:85 722 la64 ' 609 309 2911 687 437 7173fa9 634 451 609 309 lif 02 932 453 7150r40 1025 667 1009 10:42 525 717631s 1063 613-1009 309 4846 5 Blas = +0.028 +0.433 Blas = +0.074 +0.776 Standa rd Deviation = 0 . 0 88: 0. 2 21 Standa rd Deviation = 0.076 0. 3 r:9 

 /Bla s/+ Standard Deviation = 0.112  0.657* / Bias /+ Standard Deviation = 0.150 1.125*
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RESL ll.i rsli.iw Dose Del ivered Dose Eberline Dose Shallow Deep Dosimuler Shallow Deep Shallow peep Dosimeter 309 3371 337 306 714:483 319 306 609 309 4258 322 322 717203 425 346 609 1009 309 2685 451 322 7170t4 4 468 341 2778 493 324 717796 477 343 1009 309 Blas = -0.496 +0.031 Bias = -0.460 +0.081 Standa rd Deviation = 0. 0887 0.027 Standa rd Deviation = 0.109 0.061 

  / Dias /+Standa rd Deviation = 0 . 58:2* 0.058 /Blas/+Standa rd Devia tion = 0.569* O.142
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   [berline Dose   lia rst..,w Dose Delivered Dose     ,

Shallow Deep Dosimeter Shillow Deep Dosimeter Shallow Deep 609 309 3402 465 340 717769 515 399-609 309 4887 480 329 718738 531 381 Blas = -0.224 +0.083 B ia s = -0.141 +0.262 Standa rd Deviation = 0.017 0.025 Standa rd Devia tion = 0.019 0.041 

 /Blas/+ Standard Deviation = 0.242 0.108 / Bias /+Standa rd Devia tion = 0.160 0.303 Notes: Eberline sha l low doses a re Interpreted as the sum of the reported beta and gamma dos Eberline deep dose is interpreted as the reported gamma dos r+
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RESL Del ivered Dose Eberline Dose . liarsh.w Dose Shallow Dee2 Dosimeter Shallow Deep Dosimeter shallow Deeg 409 309 35864 355 199 716474 361 344 409 309 4925 307 307 718179 348 351 1645 1545 2702 1494 1494 714982 1796 1643 1645 1545 9002 1472 1472 717132 1759 1699 18t:5 1545 4986 1607 - 1607 718739 1743 1709 1845 1545 90'9 1625 1625 719274 1759 1704 2285 4 1545 2973 1590 1400 715732 1885 1666 717220 1767 1667 2245 1545 4581 1618 1618 ff on Bias = -0.175 -0.050 Bias = -0.073 +0.097 [ Standa rd Deviation = 0.084 0.134 Standard Deviation = 0.109 0.023 m 

 /Blas/+ Standard Deviation = 0.258 0.184 /Blas/+Standa rd Deviation = 0.182 0.120 a
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RESL Delivered Dose Ebert ino Dgse . Lia rslutw Dose Shallow Deep Dosimeter shallow Deep Dosimetor Shallow JI ggg 258 258 2321 257 257 714983 280 295 258 258 2863 267 267 718121 294 291-Bias = +0.016 +0.016 Blas = +0.112 +0.136 Standa rd Deviation = 0.027 0.027 Standa rd Deviation = 0.038 0.011 

  /Blas/+Standa rd Deviation = 0.043 0.043 /Bies/+Standa rd Deviation = 0.151 0.147 Notes: Eberline shallow doses are interpreted as the sum or the reported beta and gamma dos Eberline deep dose is interpreted as the reported gamma dos ,

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RESL Delivered Dose Ebertine Dose tiarstiaw Dose Shatlow Deen Dosimeter Shallow Deeg , Dosimeter Shallow peep 250 250 3204 242 242 715141 230 255 250 250 4558 242 242 718245 276 263 Bias = -0.032 -0.032 .. = +0.012 +0.036 Standa rd Deviation = 0.000 0.000 Standa rd Deviation = 0.130 0.023 

 /Blas/+Standa rd Deviation = 0.032 ,0.032 / Bias /+Standa rd Devia tion = 0.142 0.059 Notes: Eberline shallow doses are interpreted as the sum of the reported beta and gamma   3, dos Eberline deep dose is interpreted as the reported gamma dos r+

r+ liarshaw sha t tow doses are interpreted as the reported TLD 1 dose. Harshaw de,ep $ doses are interpreted as the reported TLD 2 dose, g{ Asterisk indicates failure to meet ANSI N13.11 criterion that /8/ + Standard $ Deviation less than or equal to r+ 

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. 300  0 4192 191 35 714471 145 56 3 300  0 4651 165 34 717204 154 52 re 609 309 35L8 626 356 714485 722 464 g*

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. .-    Attachment C to Inspection Report No. 50-277/85-19 ,

- 50-278/85-15 Page 12 of 12 Q e e- e n e0 N A C @ O% C @ N e eO C NNNN O N= N.3* * COO O 3 e O O - O30@ @@e O - C @ M P* @ N On e NNNN 

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L MNN e 

=  WCC-e0-.0 10 34 L

c .s 

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C EON ## 0W E @ *= w N 00 

- 3 IO @ co e weee Du o NNNN LL Q  es VU CC bb MM
  +     .

N e O m N Q NNNN e ec c 

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 - NNNN 3N@ O O t - @@33 w@O ~ C C to NNNN  M
- E  N. N. be to G
- M  CCO = b L

o e > e D e 3 nRN D W W WCC V L e0 

  .- - .0 L e q a L 399 g e C  .e. . C u  eg . C e n s so >> 4 e E N@ce c@ w O
 -

m eO N D 00 D e NNM3 V O VV C 3 O LL e e na C tU to e CC e 6 ee = = M ed D M MM 

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m .C- to C 

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  - - y 10 E C N 6 e 0 e 40 0 0  .Ca e G @@@@  G C G NNNN  D ~

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