IR 05000341/1984023
| ML20215C227 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 11/28/1984 |
| From: | Schweibinz E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Davis A, James Keppler, Phillips M NRC |
| Shared Package | |
| ML20215C208 | List:
|
| References | |
| FOIA-86-373, FOIA-86-A-124 NUDOCS 8610100178 | |
| Download: ML20215C227 (21) | |
Text
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, % UNITE 3 STATES
> [p**# "8 $8, , NUCLEAR REGULATORY COMMISSION
; 4 s>( $ RECION 111 D E 799 ROOSEVE LT ROAD
,, oLEN rLLys. ILUNOIS SOW e....
NOV 2 81984 i MEMORANDUM FOR: See Below FROM: E. R. Schweibinz, Chief, Technical Support Staff SUBJECT: SALP BOARD MEETING - FERMI l
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The attached Draft SALP Report for Fermi 2 will be used as the basis for l the Board Meeting scheduled for November 30,1984, at 9:30 a.m. in Conference Room A.
To ensure all comments are incorporated into the report, each responsible person is expected to review the report prior to the Board Meeting.
Comments should also be solicited from those staff members who had inspection responsibility during the assessment period.
Should you be unable to attend the Board Meeting, please arrange for appropriate representation by a member of your staff.
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E. R. Schweibinz, Chief J' Technical Support Staff
Attachment:
As stated ,
REGION III== SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE 50-341/84-23 Inspection Report No.
DETROIT EDISON COMPANY Name of Licensee FERMI 2 Name of Facility OCTOBER 1, 1983 - SEPTEMEER 30, 1984 Assessment Period
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. DRAFT
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SALP 5 . III. SUMMARY OF RESULTS Rating Last Rating This Trend Within Functional Areas Period Period the Period A. Soils, Foundations, and NR 2 None Related Subjects E. Containment and Other Safety-Related Structures 2 2 Same C. Piping Systems and Supports 2 2 Same D. Electrical Power Supply and Distribution NR 2 Sane E. Instrumentation and Control Systems NR 2 Same F. Licensing Activities 2 G. Quality Assurance 3 2 Improved H. Preoperational Testing 3 2 Improved I. Radiological Controls 2 2 Same
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. . .. .. . .. ....................._...........................-.m.........._...~. . . . . . . . . . . . . . *
DRAFT l
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SALP 5 o J. Fire Protection 2 3 Improved K. Emergency Preparedness NR 2 Same L. Security and Safeguards NR 2 Same
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M. Operational Readiness NR NR None
*NR = not rated
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DRAFT
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SALP 5
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2. Conclusion The licensee is rated Category 2 in this area based on the managenent improvements in implementation of corrective actions.
The licensee was rated Category 3 in the previous assessment period. Licensee performance has generally improved over the course of the SALP assessment period.
3. Board Recomrendations None.
I. Radiological Controls 1. Analysis Five inspections were performed during the assessment period by region based inspectors. These inspections included pre-operational radiation protection; preoperational gaseous, liquid, and solid radwaste; preoperational environmental mor.itoring; confirmatory ceasurements; and TMI Action Plan Itens. The resident inspectors also reviewed this area during g-6D FOust inSpcCtions. No items of noncompliance were identified.
In response to NRC concerns that few in-house health physics techr.icians had significar.t nuclear power plant experience, and most of the experience possessed was PWR experience, the licensee
,. 31 - . _ -._ _ _ __ _ _ .
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DRAFT SALP 5
sent in-house health physics technicians to an operational BWR during a refueling and maintenance outage. Staffing, training, and qualifications of the radiation protection organization appear adequate.
Delays have been experienced in calibrating and preoperationally testing effluent and process monitors, and in preoperationally testing gaseous, liquid, and solid radwaste systems. The licensee has applied additional resources in the last half of this assessment period in an effort to expedite calibrations and testing, and to prevent these itens from impacting on the fuel load date.
Several potential problems were identified during the latter part of this assessment period regarding licensee equipment and procedures intended to satisfy certain NUREG-0737 cction items in the radiation protection and radwaste areas, and regarding certain drain systems. Licensee efforts to re-solve these issues are in progress.
The licensee has made satisfactory progress in developing the chemistry and radiochemistry measurements program.
Laboratory administration, including responsibilities, has been clearly established. Procedures for sampling, analysis, instrument calibration, and quality control have been developed and satisfactorily implemented. A quality control cross
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,' DRAFT SALP 5 J check program for nonradiological and radiological samples has been established, using samples provided by an outside vendor. Results have been satisfactory.
The licensee achieved all agreements in gama analysis of a spiked liquid sample, particulate filter, and charcoal absorber, as well as beta analysis of a spiked liquid.
The training program for chemistry personnel appears good and the licensee expects to meet its comitment to have three chemistry technicians fully qualified oy Fuel Load Operating License (FLOL) issuance. Trie chemistry training program appears well-managed and the subject material comprehensive.
The January-February 1984 inspections (84-03) revealed that significant progress had been made to resolve problems and open items concerning the Radiological Environmental Program (REMP) identified during a previous SALP period (82-04). Management controls for implementing the REMP were decidedly strengthened by establishing the Environmental Engineer position responsible for managing the contract with huclear Utilities Services Inc. (NUS).
Sample collection and analysis perfomed by NUS appeared satisfactory.
This REMP contractor also perfomed an adequate Environmental Protection Agency inter-laboratory cross check program. In mid 1984, the licensee was arranging to change the REMP contractor since the NUS laboratory in Pittsburgh was being shutdown. .l l
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' . DRAFT SALP 5 . '
Management support in these programs appears adequate.
Responsiveness to NRC concerns has improved during the assess-ment period and now appears adequate.
2. Conclusion The licensee is rated Category 2 in this area. This is the same rating as was given in the previous assessment period. Licensee performance has remained the same during this assessment period.
3. Board Recommendations None.
J. Fire Protection 1. Analysis During this assessment period one team inspection was conducted by Region III personnel to assess conformance of the as-built plant conditions to FSAR cernitments, fire protection program
- implementation and post fire safe shutdown capability. A l comprehensive programmatic assessment of the total fire protection program was not made during this assessment period. However, an assessment of the applicant's post fire safe shutdown capability
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/ O RACEABLE TO N D S.
@DATED TESTSEPT.
No. DG8118183 29,1983 VICTOR E EN, INC. + PTW CHAMBER MODEL 30 f 10101 Woodland A SERIAL NUMBER N23361 14 Cleveland. Ohio 441["* vscTOREEN (216) 795 8200
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RESPONSE TEST DATA To: hrft?ci r [Oises) Date: hfe t), ( 9K- sr Victoreen a b40 /56C Serial # 3FOR Model * 690 i Customers P.O.# / jab 3 W 3/( a-RAY TECHN10tlE (Maderately Filtered X-Rays) Tctal Filtratior Kev hv1 Technicue KVCr rr Al m- Cu Eff. m- Cu m- M H 60 4 0 32 0.09 2.E 1 76 4 0 34.5 0.11 3.4 J 100 5 0 42 0.20 5.1 K ISD 5 0.25 64 0.6E 10 L 200 5 0.5 84 1.3 13 M" 250 5 1.0 111 2.2 1E M1 25D 5 3.2 140 3.2 12 Cs 137' 660 Co 60* 1250 Corre: tion factors for these techniques are obtained by intercomparison with instruments whose calibrations are traceable to the US National Bureau of Standards. We believe they agree with these standards to an . ' uncertainty of less than + 25. Use of the instrument at a temperature ' other than 220 C or pressure other.than 760 m Hg requires the resp @se QLLEh be corrected for air density per attached table. g i LiC Gt ' Mode and Cor ction Factor (multiplier) for Technique
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Serial No.
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Fonn: 90648-1-78 - b J l I l
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. TRACEABLE TO N.B.S.
U TEST No. DG8118183 DATED SEPT. 29,1983
. -/f Q~ VICTOREEN* INC* PTW CHAMBER MODEL 30 343 ' 4;b/m /~We . 10101 Woodland Avenue SERIAL NUMBER N23361 142 / gQJ j Cleveland. Ohio 44104 [2g79g2ggX:J1g4218287 A, rrw[vscrosters , ,
a~ ,- RESPONSE TEST D'ATA l
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To: Df-rerner Enisw Co. Date: 19a iz ierc Victoreen # /cw 39/9 Serial i MOA Pbdel # 6 90
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Customers P.O.S /}P - /)C R'O X-RAY TECHNIQUE (Moderately Filtered X-Rays) Total Filtration Key hvi Technique KVCP rrrn Al mm Cu Eff. m. Cu m Al H 60 4 0 32 0.09 2.8 1 76 4 0 34.5 0.11 3.4 J 200 5 0 42 0.20 5.1 K 150 5 0.25 64 0.66 10 L 200 5 0.5 84 1.3 13 M" 250 5 1.0 111 2.2 16 MI 250 5 3.2 140 3.2 18 Cs 137' 660 Co 60* 1250 Correction factors for these techniques are obtained by intercomparison with instruments whose calibrations are traceable to the US National Bureau of Standards. We believe they agree with these standards to an uncertainty of less than + 21. Use of the instrument at a temperature other than 220 C or pressure other.than 760 mm Hg requires the response ' egrrected for air density per attached table.
g m(36/2- Pbdel and ection Factor (multiplier) for Technique itdL Serial No.
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y , P /M (- / O'/ 5 */ce.s > _?0 - T - J C M _ Y_ d 693 i o %n "'/e -w i 1tA 3 - 2 S K ' d / Y PO S' / //9 - -
* Standard Points for gh Energ Cha er pn robes ** Standard Points Data Taken By (14. P #/
Victoreen Production Lab l Checked by [ w-, v - .N/# 78 .' /
- l - h(O The response of any int $rument might be altered by shock or other external conditions. For this reason, Victoreen cannot guarantee a correction factor af ter it has lef t our premises.
Form: 90648-1-78
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TRACEABLE TO N.B.S.
i i TEST No. DG8118183 VICTOR EEN, INC. DATED SEPT. 29,1983 10101 Woodland Avenue PTW CHAMBER MODEL 30 343
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M' Cleveland. Ohio 44104 SERIAL NUMBER N23361 142 vicronsErw [2g79g200, 9 g:J1g21-8287 RESPONSE TEST D'ATA To: 57t'n/T ff)/.S&1 0o Date: NR IV; 19F(- Victoreen #_ I,o 3 '//9 Serial #
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3 P dJL Model i 69o Customers P.O.R /V/2 * /.)f/ N() X-RAY TECHN]QUE (Moderately Filtered X-Rays) Technique Total Filtration Kev hv1 KVtP m Al m Cu Eff. m Cu m- Al H 60 4 0 32 I 0.09 2.8 76 4 0 34.5 J** 0.11 3.4 100 5 0 42 K 0.20 5.1 150 5 0.25 64 0.66 10 L 200 5 0.5 84 M** 250 1.3 13 5 1.0 111 2.2 16 MI 250 5 3.2 140 3.2 18 Cs 137' 660 . to 60* 1250 Correction factors for these techniques are obtained by intercomparison with instruments whose calibrations are traceable to the US National Bureau of Standards. We believe they agree with these standards to an uncertainty of less than i 21. Use of the instrument at a temperature other than 220 C or pressure other.than 760 m Hg requires the response be corrected for air density per attached table. , Model and Correction Factor (multiplier) for Technique Serial No.
2 2 % - 12
/3b) (- ) () () () # /7 M9 //% / 30-f). 2 5 # 1 M 9'1 f). 'f'/v * Standard Points for igh Energy C mb rs a Probes ** Standard Points Data Taken By Wff) M/// ' tl Victoreen Production tab Checked by a-t v # !/e/ f( ,_
hf-h h The response of any instrument might be altered by shock or other external conditions. For this reason, Victoreen cannot guarantee a correction factor af ter it has left our premises.
Fom: 9064B-1-78
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l VICTOREEN, INC. * 10101 WDDDLAND AVE., CLEVELAND, OHID 44104. ,
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l VICTOREEN '" " ' ' ' ' ' ' ' ' ' ' * * * * -" * ' ' ' * ' ' ' ' ' ' ' ' l MODEL 570 CONDENSER R-METER VOLTAGE SENSITIVITY VOL~Tm&7E2- USEO
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Serial Number 8802 Customer P.O.f A'/iA. /2(/fel) SEE et loEOB3 5 victoreen nee ir * 39/9 115 \l B 2.1 F t G D Pe2 p@ ras C_oaceR.SYR@ N Nh Voltage Change Between Major Voltage at Major Scale Divisions Scale Divisions (Percentage of Fullscale) (Percentage of Fullscale) AS FOUND Date /-2 2-k 0 .N .$. O ~ [( ), O
. 0 - 20 20 L} 7[, Q ._,
20 - 40 49,9 40 92 .$ .3, 40 - 50 2 L/, / 50 WC 0 a $ _.
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, 50 - 60 2J.O 60 .7 7 8. [ _,
60 - 80 d O . (- 80 $2$ ? ,.h. O, 8 80 -100 100 2 7.E,, O
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j AS LEFT Date A b #8[o O 525 0 20 Lf 7f, Q 0 - 20 [0. O , j 20 - 40 4 9, b 40 L/1 b a 5 40 - 50 2 (-/, 7 50 WD 0. $ , 50 - 60 ,2 U , O 60 .5 .).).
. $ .,s . 60 - 80 J O, O 80 $15. $
80 -100 [O, 100 -) 7 .5 ,. O
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Voltage change between zero and fu11 scale should be between 248 and 252 volts Calibrated by . c~e
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SG A Shoner Giobe Corporation Sues.o.ary
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VICTOREEN INC, s g 10101 WoodLsnd Avenue deveLind. Ohio 44104
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VICTOREEN (216) 79&B200 TWX: 810-421 8287 A Steller41ste Carperetsen hhldlety AIR DENSITY CORRECTION TABLE This instrument is calibrated in International Roentgens corrected to 0 C 0 when used at 22 0Cand 760 mm mercury (lig) barometric pressure. For temperatures other than 2200 and pressures other than 700 mm lig, multiply the scale reading by the factor obtained from the*following table.
f. 40.8 44.4 48.0 73.4 73.2 78.8 82.4 84.0 89.A 93.2 94.8 100.4 104.0 i.a . . u. c. le it 20 22 24 24 28 30 32 34 34 38 40 19.48 300 1.489 1.499 1.309 l.320 9.330 1.348 8.35l 1.34l 1.378 1.382 f.39 2 9.402 1.483 20.08 550 1.460 1.449 I.479 l.490 1.499 1.310 l.320 I.330 l.340 1.331 8.343 1.373 l.381 20.47 s20 9.43: 1.441 1.45i 1.448 1.478 1.481 s.498 8.300 1.3 i 0 1.320 3.330 1.340 3.33o 20.87 330 l.403 l.414 8.424 1.434 1.444 1.453 1.463 1.473 1.482 1.492 l.302 1.312 1.31l 28.26 340 l.378 3.388 8.397 1.407 l.414 1.426 1.435 1.445 1.4J 4 3.444 1.474 8.483 1.493 28.45 550 1.354 1.363 1.373 1.382 1.391 f.401 1.410 1.419 f.429 1.438 8.448 l.457 8.444 22.05 360 1.329 8.338 I.348 1.357 1.366 1.375 1.384 1.394 1.403 1.482 9.423 8.438 3.439 22.44 370 l.204 8.3l5 1.324 l.333 l.342 4.358 l.360 l.369 I.378 l.381 1.394 1.403 8.494 32.83 300 8.283 8.292 1.3'31 1.310 9.389 1.328 8.337 I.345 1.354 1.34J I.372 1.388 l.389 23.13 390 8.242 1.270 1.219 8.248 1.297 l.303 l.314 l.323 1.333 1.340 1.349 8.338 8.344 23.42 600 8.248 1.249 1.258 1.247 1.275 1.284 1.293 1.301 1.309 l.388 I.327 8.336 1.344 24.02 450 1.220 l.229 1.237 . l.246 1.254 1.243 I.278 1.379 1.288 l.397 8.305 1.344 1.333 24.41 420 1.200 8.208 1.287 1.223 8.233 l.242 l.249 1.258 1.244 8.273 1.383 1.392 1.299 24.80 430 1.188 l.189 1.198 1.204 l.214 8.222 8.230 8.239 5.347 1.233 9.243 1.278 l.279 23.20 440 1.164 l.l71 0.580 8.888 1.194 1.204 1.213 1.220 8.228 8.336 8.244 8.232 8.340 25.39 e50 1.145 1.133 1.let l.849 l.177 1.895 1.193 1.208 1.208 1.214 1.224 1.332 1.240 25.98 440 1.l37 8.l35 l.143 1.151 1.839 1. l e 7 1.174 1.182 1.189 1.l98 f.204 1.213 1.33l 26.38 470 l.ll t 1.819 5.526 8.434 l.142 1.149 1.137 8.144 5.872 4.880 1.188 1.193 1.203 24.77 680 1.095 b.IO3 1.110 I.IIS 4.125 * 8.133 I.843 l.let 1.134 1.!a3 1.171 1.379 8.l84 27.44 490 1.078 1.086 l.093 1.105 l.108 1. I l e 3.123 8.l38 B.8 38 8.844 l.133 1 lel I.348 27.36 700 l.044 l.078 1.079 1.086 l.093 1.101 1.l08 1.515 8.823 f.8 30 1.137 8.845 l.lat 27.95 780 8.048 l.035 1.043 1.070 1.077 1.084 1.092 l.098 1.104 f.Il3 1.528 5.828 8.835 28.33 720 1.033 0.041 3.048 1.055 1.062 1.069 1.076 1.083 1.098 1.098 1.105 8.852 1.5B9 28.54 725 l.027 1.034 4.041 1.048 1.055 8.042 1.069 l.076 1.043 I.091 1.098 8.103 3.142 14.74 730 l.019 l.027 1.034 1.048 1.048 l.055 1.042 3.049 l.076 1.08) 1.090 1.097 1.105 28.94 735 L.0 8 3 l.089 1.027 1.034 1.041 l.048 1.055 1.062 1.049 1.074 l.083 1.090 1.097 29.13 740 1.004 l.083 5.020 1.027 1.034 4.048 8.048 1.055 1.062 1.049 1.075 1.083 3.089 29.33 745 .999 1.004 l.013 1.020 8 027 l.034 1.040 1.048' l.054 1.048 8.048 1.075 1.043 29.53 730 .992 .999 1.004 1.083 l.020 1.027 l.033 1.040 1.047 1.034 1.04l l.068 1.073 29.72 735 .984 .993 1.000 8.007 l.014 1.021 l.027 l.034 I.041 l.048 1.055 1.042 1.048 29.92 760 .980 .986 .993 1.000 1.007 1.014 4.020 1.027 1.034 8.04l I.047 1.034 1.04l 30.12 745 .912 979 .986 .993 .999 1.004 I.083 8.020 1.024 ' t.03 3 1.040 8.047 1.054
. J0.31 770 .967 .973 .980 987 994 8.000 1.007 l.084 1.020 1.027 1.034 1.041 3.047 30.51 173 .948 .968 .974 .948 .987 .994 4.005 l.007 1.014 1.021 3.027 1.034 1.048 30.71 780 .954 .96l .967 .974 .980 .947 .994 4.000 l.007 l.014 1.020 1.027 1.033 30.90 185 .948 .955 .948 .968 .974 .981 .988 .994 8.004 l.'0 07 1.014 1.028 8.027 31.10 790 .942 .949 .955 .962 .968 .973 .981 .988 .994 1.001 1.009 1.014 1.024 .
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VICTOREEN, INC.
10101 Woodland Avenue
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Cleveland, Ohio 44104 CUSTOMER PO
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. vsCT('; A E;;iN ] (2 7 8200 g
TWX 810 421 8287 VICTOREEN REP #_393 9
, VICTOREEN FAILURE REPORT'
CUSTOMER Detroit Edison Co.
INSTRUMENT MODEL 570 S/N 3802 ..
'" **
330 :39Q9 - 2 77 :3959 333 33950 633 33606 70-5 33923 CUSTOMERS STATEMENT OF FAILURE , Calibration only.
. VICTOREEN'S STATEMENT OF INSTRUMENT FAILURE AND INITIAL TEST RESULTS.
. 670 tri+mer condenser needed some ediustnent.and focus was off.
CORRECTIVE ACTIONS TAKEN BY VICTOREEN Adjusted trimmer condenser and adjusted focus.
. COMPONENTS REPLACED: PART# DESCRIPTION FAILURE PART8 DESCRIPTION FAILURE ,
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REPAIRED BY: t. ), h ' DATE /-28 I b Q.A. APPROVED [ dd DATE.d" 8 d d l
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TEST No. DG8118I83 DATED SEPT. 29,1983
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VICTOR EEN, INC.
' 10101 Woodland Avenu* SERIAL NUMBER 9 PTW N23361CHA 142 Cleveland. Ohio 44104 VicTontem (216) 795-8200
^ Wiler-close career 7.7, Mig 421-8287 RESPONSE TEST DATA To:hrft?oir 8~Ossm) Date: bre. tr 19Pc/
Victoreen # bAo /56C Serial # 'dFO.R Model # 690 i Customers P.O.# /JM 3 W f/d ,
(Pbderately Filtered X-Rays)
Total Filtration Kev hv1 Technique KVCP m. A l m- Cu Eff. m Cu m Al H 60 4 0 32 0.09 2.8 1 76 4 0 34.5 0.11 3.4 J" 200 5 0 42 0.20 5.1 K 150 5 0.25 64 0.6E 10 L 200 5 0.5 84 1.3 13 M" 250 5 1.0 111 2.2 16 M1 250 5 3.2 140 3.2 12 Cs 137' 660 Co 60* 1250 Correction factors for these techniques are obtained by intercomparison with instruments whose calibrations are traceable to the US National Bureau of Standards. We believe they agree with these standards to an uncertainty of less than i 21. Use of the instrument at a tenperature - other than 220 C or pressure other. than 760 mm Hg requires the resp @se 9LL @ be corrected for air density per attached table. N , CO D E Model and Cr ction Factor (multiplier) for Technique k
,y Qg,s.)
Serial No.
/ 7/-/MR
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** Standard Points db Data Taken By M . E Af)$FR Victoreen Production Lab \
d CLORCf. - ,~ l7 Checked by /N /?' / 1V
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The response of any instrument might be altered by shock or other external conditions. For this reason, Victoreen cannot guarantee a correction factor after it has lef t our premises.
Form: 9064B-2-78 l __ _ __
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/ *CEastE To N.e.s. !
O T No. DG8118I83 DATED SEPT. 29,1983 l VICTOR EEN, INC. PTW CHAMBER MODEL 30 343
. ~" SERIAL NWBER N23361 142 ' 10101 Woodland Avenue Cleveland. Ohio 44jo4 ""N ?h?h. h R,gJ1g421-8287 , i RESPONSE TEST DATA I l
To; SDno/0 fffot7 Date: ()ce. n /9iy Victoreen d V1/MO Serial # ~$ROA Model # 69D i Custcnners P.O.# A/2- 3l/$3/6, ,
(Moderately Filtered X-Rays)
Total Filtration Kev hv1 Technicue KVCP r. Al m- Cu Eff. m Cu m Al H 60 4 0 32 0.09 2.E 1 76 4 0 34.5 0.11 3.4
,
J 200 5 0 42 0.20 5.1 K 150 5 0.25 64 0.6E 10 L 200 5 0.5 84 1.3 13 M" 250 5 1.0 111 2.2 16 M1 250 5 3.2 140 3.2 18 , Cs 137' 660 Co 60' 1250 s' Correction factors for these techniques are obtained by intercompari%n c3 , with instruments whose calibrations are traceable to the US Nationaly o .p Bureau of Standards. We believe they agree with these standards to Rn to
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uncertainty of less than i 21. Use of the instrument at a tenperatu e other than 220 C or pressure other.than 760 mm Hg requires the resp se > be corrected for air density per attached table. a> 2(m .-< s_.
' Model and Correction Factor (multiplier) for Technique Serial No.
_29 9 -IR /if7'h) () () () () t / TFM /./'fA
/30- o. M K # /3999 d 945 ' Standard Points for Hi Energy Chambers a Pro **5tandard Points Data Taken By d&jo ,
Victoreen Production Lab ] Checked by I. /p i? ?Y '
'
The response of any instrument might be altered by shock or other external conditions. For this reason. Victoreen cannot guarantee a correction factor af ter it has left our premises.
Form: 90648-1-78
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VICTOREEN, h o . E BYT g 10101 Woodland Avenue M-w Cleveland. Ohio 44104 D 85-j vecTosaEEN 1216) 795-8200 TWX: 810 421 8287 a sanit.r.um c ,9.r.88 simiei rF l Health Physics Supenisor AIR DENSITY CORRECTION TABLE
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This instrument is calibrated in International Roentgens corrected to O C when used at 220Cand 760 mm mercury (lig) barometric pressure. For temperatures other than 220C and pressures other than 760 mm IIg, multiply the scale readingby the factor obtained from the'following table, f. 40.8 44.4 40.0 71.4 75.2 78.8 82.8 $ 4.0 89.4 93.2 94.8 100.4 Mm. C.14 104.0 Indes 18 20 22 24 24 2 11 30 32 34 34 38 40 ! 19.48 500 1.489 1.499 1.509 1.520 1.330 1.548 1.551 1.541 1.571 1.582 f.592 1.402 l 20.08 510 1.440 1.469 1.413 1.479 I.490 1.499 I.510 1.520 3.530 1.540 1.551 1.548 1.578 1.584 20.47 520 1.431 1.443 1.453 1.441 1.471 1.481 3.491 1.500 3.580 1.520 3.530 1.540 1.550 20.87 530 1.405 1.454 f.424 1.434 1.444 1.453 1.463 1.473 1.482 1.492 f.502 3.582 1.528 21.24 540 1.378 1.388 f.397 I.407 I.414 1.426 1.435 1.445 1.454 1.444 8.474 1.483 3.493 24.65 550 1.354 8.343 f.373 1.382 1.398 1.401 1.410 1.419 f.429 1.438 f.448 1.457 I 444 22.05 540 1.329 f.338 f.348 I.357 1.346 8.375 1.384 1.394 1.403 1.412 22.44 570 1.304 5.355 t.4 21 1.438 l.439 1.~3 2 4 1.333 l.342 8.35l I.360 1.349 1.378 1.387 f.394 1.405 1.414 22.83 500 1.283 1.292 1.300 1.310 3.319 3.328 I.337 3.345 1.J 54 f.343 1.372 f.388 1.389 23.23 590 1.242 1.270 1.279 f.2 8 8 1.297 1.305 8.314 f.323 1.333 1.340 f.349 1.358 1.364 23.42 400 1.241 1.249 1.258 1.247 1.275 1.284 1.293 1.308 1.309 1.334 I.327 f.336 24.02 410 1.220 1.344 1.229 1.237 1.244 1.254 1.243 1.278 1.279 1.288 1.297 1.305 8.314 24.41 420 1.200 1,200 4.322 1.217 1.225 1.233 1.242 f.249 1.258 1.266 1.275 1.283 1.292 1.299 24.80 630 1.188 1.189 f.198 1.204 1.214 1.222 1.230 1.239 1.247 1.255 1.243 1.278 25.20 440 1.279 1.164 1.178 1.100 1.188 1.196 1.204 1.232 8.220 8.228 1.234 I.244 1.252 f.240 25.59 450 1.145 1.153 1.f41 1.149 1.177 1.185 1.193 8.201 1.208 1.284 1.224 9 232 1.240 25.98 440 l.127 1.135 1.143 1.158 1.139 1.167 1.174 1.182 1.189 8.198 1.204 1.213 24.38 470 f.III 1.119 1.124 1.134 1.142 1.149 I.857 1.328 g L 9.944 8.172 1.100 1.188 8.195 f.203 i F 24.77 400 1.095 1.103 1.500 l.IIS I.125 * l.333 1.141 1.948 1.154 1.143 1.171 9.l79 27.16 490 f.184 1.078 1.084 I.093 1.101 1.108 1.114 1.123 f.83f I.138 1.144 1.153 1.148 f.140 27.54 700 1.044 1.071 1.079 8.084 f.093 1.101 1.108 1.115 f.123 1.130 3.137 27.95 1.145 f.852 710 1.048 1.055 l.043 1.070 8.077 1.004 1.092 1.098 1.104 1.113 1.124 1.128 1.133 28.35 720 1.033 1.049 1.048 I.055 1.042 1.069 f.076 1.003 1.095 1.098 1.105 1.182 8.199 28.54 725 1.027 1.034 f.041 1.048 l.055 I.042 3.049 1.07d 1.083 1.098 1.098 28.74 730 f.105 8.112 1.0i 9 I.027 1.034 l .04 l 1.048 I.055 1.042 1.049 1.074 8.083 1.090 1.097 1.105 28.94 735 L.0 8 3 1.019 1.027 1.034 1.048 1.044 f.0 5 5 1.042 1.049 1.074 8.003 29.83 3.090 1.097 V40 1.004 1.013 l.020 1.027 8.034 f .04 8 8.048 8.033 3.062 1.049 8.075 1.003 29.33 745 3.089 999 1.004 1.013 l.020 1.027 1.034 f.040 1.048' l.054 f .04 8 8.044 8.075 1.082 29.53 750 .992 .999 1.004 1.013 1.020 9.027 1.033 1.040 1.047 1.054 29.72 755 .984 .993 1.000 1.048 1.048 f.075 1.007 1.014 1.021 1.027 1.0J 4 1.041 1.048 1.055 1.042 0.044 29.92 740 980 .984 .993 1.000 1.007 1.014 l.020 1.027 8.034 1.047 30.82 1.048 1.054 1.041 745 .972 979 .986 .993 .999 8.004 I.013 1.020 3.024 f.040 30.31
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. 10101 Woodland Avenue Cleveland. Ohio 44104 VICTOREEN (216) 795-8200 TWX: 810-421 8287 A She11er. Globe Corporation Subsidiary MODEL 570 CONDENSER R-METER ' VOLTAGE SENSITIVITY DUST. S.D- ~pfk ~W65/6 Vico S.6. @#'#- ^'# # - SERIAL NUMBER __876),2 DATE Utb.1 1 1004 CALIBRATED BY M U, VOLTAGE CHANGE BETWEEN MAJOR SCALE DIVISIONS (PERCENTAGE OF FULLSCALE) AS FOUND 0 - 20 Y $P' 7 20 - 40 VV, j 40 - 60 50,2 60 - 80 80,7 80 - 100 N,[ SUM 282,[ AS LEFT -
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Y$[ 40 - 60 5 0. Q , He Ith Physics Supery;so, 60 - 80 Y{{ 80 - 100 3 (_2 7 SUM 2fO,0 i Voltage change between zero and fullscale .- should be between 248 and 252 volts
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VICTOREEN VICTOREEN, INC.
Date 12/14/84 Detroit Edison Fermi 2 6400 N. Dixie Hwy.
Newport, MI 48166 Attn: Ed Kokosky 116 OSB Health Physics Reference: Customer Purchase Order NR-346316 VICTOREEN Sales Order Rep 1560
.
Dear Sir:
In accordance with your recent purchase order referenced above, I am submitting the required documentation.
s If there are any questions regarding this matter, please feel free to call me at 216-795-8200 Ext. 345.
Very truly yours, VICTOREEN, INC.
MW MN ' Harry Anderson Quality Assurance Specialist HA/sk NIEWE
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' . VICOREEN, INC. O-10101 Woodland Avenue g' Cleveland. Ohio 44104 VICTOREEN (216) 795 8200 TWX: 810 421 8287 .
A W iler. Globe Corporation h istory CUST. S.0- ,, 3 _ .. 3 / 4 VICTOREEN FAILURE REPORT - - - vsCb S.O.A;p# 'TGo CUSTOMER Detroit Edison INSTRUMENT MODEL 570 S/N 3802 CUSTOMERS STATEMENT OF FAILURE Calibrate only.
VICTOREEN'S STATEMENT OF INSTRUMENT FAILURE AND INITIAL TEST RESULTS.
131 chamber was very leaky.
. CORRECTIVE ACTIONS TAKEN BY VICTOREEN - Cleaned citamber and replaced condenser insert. Calibrated 570.
COMPONENTS REPLACED: FAILURE MODE: - PART # 131-2 IDENTITY # cnndenser innere Leaky.
131-3 Thimble stripea.
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REPAIRED BY: c p DATE /2-NV O.A. APPROVED :, DATE / ' "#'8
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Date 12/14/84 l Detroit Edison Customer P.O. NR-346316 2000 Second Avenue Detroit, Michigan 48226 VICT0REEN Sales Order Rep 1560 j (1) S/N 3802 Model 570 (5) Probes S/N's 13999, 13959, 13808, 13921, and 13950 CERTIFICATE OF CALIBRATION It is hereby certified that the measuring and/or test equipment supplied has been calibrated and is traceable to the National Eureau of i Standards. This documentation is on file at VICTOREEN, INCORPORATED and
,
is available for your review.
Sincerely, ,
.
VICTOREEN, INC.
Q: Reger Zimmerman Manager, Quality Assurance RZ/sk REVlw gy
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10101 Yhodland Avenue Cleveland, OH 44104 21677954200 TWX 8:0/4218287 A Subsidiary of Sheller 41obe Corporation
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r.esma t.e pr. as u December 13, 1984 EF2-72030 4 0 Director of Nuclear Reactor Regulation Attention: Mr. B. J. Youngblood Licensing Branch No.1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555 References: 1. Fermi 2 NRC Docket No. 50-341 2. Detroit Edison to NRC Letter, " Action Plan for Completing NRC Open Items Related to PRMS and PASS", EF2-70036 dated October 31, 1984.
3. Detroit Edison to NRC Letter, "Clarifi-cation of Position Regarding NUREG-0737 Post-Accident Sampling and Monitoring Capabilities", EF2-72006 dated November 1, J 1984.
4. USNRC Region III Inspection Report No. 50-341/84-27, dated August 10, 1984.
Subject: Additional Clarification of Position Regarding NUREG-0737 Post-Accident Sampling and Monitoring i Capabilities
Dear Mr. Youngblood:
The reference (3) submittal contains several items identi- , fled by Detroit Edison for your review and concurrence. The ' purpose of this letter is to identify an additional 5 items relating to NUREG-0737 Post-Accident Sampling and Monitoring Capabilities which also require your review and concurrence.
The items are summarized as follows: l a. Enclosure 1: Empirical Determination of ' Sample Line Loss Correction Factors b. Enclosure 2: Effluent Radiation Monitors - Main ' Control Room Displays c. Enclosure 3: Heat Tracing of SGTS Sample Lines i b
%ntyms L a qq l, . ._ , - - -
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Mr. B. J. Youngblood
'?' December 13, 1984 EF2-72030 Page 2
d. Enclosure 4: Location of Containment Area High Range Monitoring System (CAHRMS) Detectors e. Enclosure 5: Isokinetic Conditions If you have any further questions please contact Mr.-O. K.
Earle (313) 586-4211.
Sincerely, Enclosures ec: All with Enclosures Mr. P. M. Byron Mr. C. Gill i Mr. L. Heuter USNRC, Document Control Desk Washington, D.C. 20555
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* . * . Mr. B. J. Youngblood ,
December 13, 1984 ; EF2-72030 i Page 3
^ < ' bec: F. E. Agosti*
R. L. Andersen* J. P. Bobba* - L. P. Bregni W. F. Colbert* R. R. Eberhardt O. K. Earle W. J. Fahrner W. R. Holland R. S. Lenart* E. Lusis P. A. Marquardt* W. W. McNeil* T. D. Philli M. S. Rager*ps* R. J. Salmon * L. E. Schuerman , A. A. Shoudy G. M. Trahey R. A. Vance 7 A. E. Wegele NOC Approval Control - ARMS Coding * O. K. Earle (Bethesda Office)* Secretary's Office NRR Chron File *
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. . . , . ENCLOSURE 1 EMPIRICAL DETERMINATION OF SAMPLE LINE LOSS CORRECTION FACTORS NRC Region III raised the following concern during a ,_
g( previous inspection (1): The licensee has not-yet arrived at correction factors for sample line losses due to iodine plateout and particulate deposition. As clarified in footnote 12 of Table 3 of Regulatory Guide 1.97 (Revision 3),
" collection of represent'ative samples" means obtaining the best samples practicable given the exigencies that attend the accident environments. Line losses or line deposition should be empirically pre-determined and appropriate loss correction factors should be applied.
It has been noted by Detroit Edison that NUREG-0737 does not contain a specific requirement or recommendation for empirically determining sample line loss correction factors.
In addition, Detroit Edison's commitments (in the Fermi 2 FSAR) refer to Revision 2 of Regulatory Guide 1.97.
Detroit Edison has reviewed a recent article relating to the plateout of radioiodine in sample lines (2). Included in this article is a method for calculating potential sample line losses for various iodine chemical species. Detroit Edison has used this method to e,st.i_ mate eKEe_cted lod _ine sample lifut losses of appro.xi,mately 10%.
~ . One assumption which was used in estimating the iodine sample line loss regarded the anticipated distribution of iodine chemical species. The basis for this assumption was taken from an EPRI study of BWR radioiodine sources (3). It is noted that this study refers to routine operating -
conditions. However, no credible reference could be found with regards to the distribution of radiciodine chemical species expected during accident conditions.
. ' In addition, Detroit Edison has calculated expected p.artJrula.te samole line los.ses using the methods described in ANSI N13.1 (4). Thes.e_lin.e losses are estimated at less than 20%. Sample line loss correction factors, based upon these calculated values, are being incorporated intoZidlated procedures.
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Enclosure 1 Page 2
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Detroit Edison has agreed to develop a test scope for empirically determining sample line losses prior to' March 31, 1985 (5). In addition to selecting an acceptable and
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cost-effective test method, an evaluation is being made regarding the applicability of test results, in light of the a lack of quantitative data regarding iodine chemical species and particulate size distribution A expected deci_ sign during design regarding_the actual basis accident conditions.
pSrfnrmance of tha test will be_ based upon sound engineering g and_ economic considerations.
_ In summary, it is Detroit Edis.onds position that the e2 sting system design and . proc 3du_res, taking_J.nto_atenant b to NUBEG-0137_with the A ove nnmments, meet th_e,_ commitment,s_diolodings_a_nd r,egards to representative.samp.l_ing of ra , particu,l'h(es.
(1) USNRC Region III Inspection Report No. 50-341/84-27, Dated August 10, 1984.
(2) M. T. Kabat, Deposition of Airborne Radioiodine Epecies on Surfaces of Metals and Plastics, Proceedings of the 17th DOE Air Cleaning Conference, 1982.
(3) EPRI NP-495, Sources of Radioiodine at Boiling Water Reactors, prepared by Science Applications, Inc., February 1978.
(4) ANSI N13.1-1969, Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities.
(5) Detroit Edison to NRC Region Letter, " Action Plan for Completing NRC Open Items Related to PRMS and PASS," EF2-70036 Dated October 31, 1984.
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. ENCLOSURE 2 . EFFLUENT RADIATION MONITORS-MAIN CONTROL ROOM DISPLAYS A permanent waiver is requested from NUREG-0737, Item II.F.1, Attachment 1 which requires the monitor display and
*' recording be in terms of uCi/cc of Xe-133 equivalent or -
actual noble gas mix.
The waiver is requested to acknowledge the acceptability of main control room displays which include: 1. An on-demand digital display for the Eberline System Particulate, Iodine and Noble Gas (SPING) monitors and AXM accident monitors capable of reading uCi/cc of " pseudo noble gas"* for each of the two noble gas channels. (Three noble gas channels on the SPING-4, Reactor Building Exhaust Plenum).
2. Recording by digital data system of detector readings in uCi/cc of pseudo noble gas.
The weighted sensitivities to this " pseudo noble gas" will be programmed into the Eberline microprocessor as uCi/cc of Xe-133 equivalent.
Calculations in the microprocessor using channel sensitivity and counts per minute will yield uCi/cc of " pseudo noble gas". The digital display located in the control room will be able to retrieve from the microprocessor the following information: 1. Counts per minute 2. Concentration of " pseudo noble gas" (uCi/cc).- This waiver is requested because the offsite dose assessment models used by Detroit Edison for accident cases are based on effluent noble gas monitor readings of " pseudo noble gas" (as Xe-133 equivalent). The models provide the capability to include the time dependence required to account for the decay of the actual mix relative to the " pseudo noble gas".
Radiological Emergency Response Preparedness (RERP) Imple-menting Procedure EP-540, " Manual Off-Site Radiological Dose Assessment Calculational Procedure - Airborne Releases - Overview" uses a series of curves of release rate of Xe-133
*" Pseudo noble gas" at Fermi 2 is defined as the,. isotopic mix of the weekly grab sample of noble gases calculated as Xe-133 equivalent.
_ _ -_ . __. .__ . , Enclosure 2 Page 2 equivalents which are calculated from post-LOCA noble gas mix, conversion factors and, in some cases, sample analyses
. to correlate effluent monitor readings to an estimated noble gas release rate following an accident. This procedure was found acceptable as noted in NUREG-0798, Supplement 4, Section 13.3.2.9.
The computerized model, an integral part of the Emergency Response Information System (ERIS), also incorporates the use of the " pseudo noble gas" as Xe-133 equivalent and per-forms the required calculations to provide release rate based on default isotopic mixes or actual sample analyses.
A permanent waiver is requested.
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l , ENCLOSURE 3 HEAT TRACING OF STANDBY GAS TREATMENT SYSTEM (SGTS) SAMPLE LINES
, , Installation, preoperational testing, procedures and training in the use of the SGTS sampling and monitoring equipment is complete. The SGTS sample lines will be heat traced to enhance the post-accident sampling capabilities of the equipment. This heat tracing will be completed prior to exceeding 5% power. A waiver is requested.
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a
. ENCLOSURE 4 LOCATION OF CONTAINMENT AREA HIGH RANGE MONITORING SYSTEM (CAHRMS) DETECTORS The CAHRMS detectors at Fermi 2 are located in the drywell.
' ' Radial placement has positioned the detectors at _ approximately 6-7 feet from the sacrificial shield wall.
- The present location of the CAHRMS is considered to be optimum when considering the latge amount of equipment, structures, and piping in the drywell.
The locations of the CAHRMS monitors are presently being evaluated taking into account the as-built geometry in the drywell and the instrument calibration factors for gamma ray energy. If necessary, instrument response factors will be included in accident-type RERP implementing procedures, and models for off-site dose calculation, as well as other associated RERP implementing procedures, that may involve the CAHRMS monitors.
The evaluation and necessary procedural modifications will be completed prior to 5% power. A waiver is requested.
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ENCLOSURE 5 6' ISOKINETIC CONDITIONS Detroit Edison has installed isokinetic probes which sample the radioactive gaseous effluent releases from the. Fermi 2
< ' plant. Due to the balancing of the heating, ventilation, , --.- - - ... .
and air conditioning (HVAC) system, and physical changes in building pathways currently taking place, flows in these effluent stacks and ducts are changing. These changes yield depar-tures from isokinetic conditions as initially designed.
As changes in the HVAC system continue, Detroit Edison has set up a program to measure effluent flows periodically.
These data will be evaluated and sample flows will be changed if necessary to maintain reasonable isokinetic con-ditions per ANSI N13.1-1969. This program will remain in affect for a minimum of one year, at which time it is pre-dicted that the flows will have stabilized.
The above is submitted for clarification of Detroit Edison's planned effort for maintaining isokinetic conditions.
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' RE,1RDICEgsm. W =is g ARM 3 INFOPr,tATTN SY li ~.* * *. l DTC .d M M [.M.. D.'N...N.N.h hhth.h..h _ m .. REV. . .,_.. . . P I S. _ l PAGE dtI ! , FFR 0 3 mi I PG _ . . . . . . _..................._.. * RDi r.aG T
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Initials'/Date i
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dTft>Mf.#. 4?tw Gut +M) l 1. All procedural steps have been completed.
'Yfvf p /_6-A 2. Test equipment called out in the procedure has ,#2rt" S-/#6
been used.
' 3. Test equipment used is within its calibration ' 47-/ff[ cycle.
4. Independent verification performed by someone other /ff E-/f-ff than the person performing the surveillance. '~ ' 5. The Icad Person has resolved all discrepancies [
'
f[/ 7 /f-I encountered while performing the surveillance.
~ 6. Review all referenced drawings to ensure the pf,p_/S-ff latest revisions do not negate the Technical , . U _?, _ _? ,Y"r. n.., '
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as ,,,w-e- w %)
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NOTE: List both the drawing / revision from the existing procedure revision and the latest drawing revision. If a later revision has occurred, state the resolution ie. impact on procedure, Tech Sper requirements, etc.
7. Trend parameters as designated by th,e Technical 7Fa-/f-ff Engineer or designee.
8. Technical Specification Requirements have been met. p'S /C/S' 9. Verify that appropriate requirements and criteria have been incorporated from the final Tech Specs. ,pp /P 6 10. List all TCR's written either during or just after j
- the credit run of the procedure. Assess impset M74' a -/f-[[ ,
s on test results and state resolution.
ofppj TCR'V/,;17/f 7ej'Ut?ep A)/MALs M'l?>9W**4WC /W perwogs 7W/c?C 'G CE'D'Y R'M .
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Detroli-
;'MSOn SuRvEIttANcE PERPORMANCE 10RM Pr (2) SURVEILLANCE (3) SCHEDULED 4, ogo, a o(, ETION IIMBER Soco394 {URE p
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(4) Personnel Protective Tagging Required (5) Radiation Work Permit Required
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OYES i FN-21 Number (if yes) 85- l c e 6
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j , y _ y3 RWP Number (if yes) NO auk a e_ v /Y /-29-5 Lead Person f/ ' Date ALARA Review O YES ffA$ Ope (rator t-z u s Date 0 ,1. /jpg Health Physics Reviewer lite (6) Lacd Person Ferforming Surveillance - a... V Lead Person 8'
'ermission to Start Surveillance t/' e[
{ uclearShift5uiervisor
/ d f-f[ vt N Date Time (B) Surveillance Procedure Completed NwO# I-SI-Yf ?%C Time Ledd Person Date (9) Tech Spec Requirements Met /-5/- d O NO liuclear Shift Supervisor Date (10) ISI Review b JgI n er r e -
y me Pg /rd7/7/ it
.
Date[ 3 83 '( 11) Reviewed By P Mb J-/9 f I esignaddReviewei([ Date
[ l 12) QA Review p -> 8 l Reviewer [,/ Date l COMMENTS
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,. DOCgy 10 44.080.206 a
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. Safety-Designation I! P.7 A a r'n ;n ,
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0'4 FEPJfI 2 POM PROCEDURI - II: f'J.*VIILLANCE
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i c9-v TITLE: REACTOR BUILDING EXHAUST PLDIUM PROCESS RADIATIC MONITORING SYSTEM CALIBRATION Dil-R610, D11-P28 [g
""'t 'S CONTROU.ED PROCEDURE NUMBER: 44.080.206 V0') AFTER 7 DA w REVISION NUMBER: 1 I
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w: a . ,,ii k , F,,, PREPARED BY: J. R. Orgeron DATE:12-28-84 TECHNICAL REVIEW BY: h j DATE: /-13-[[
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SUBMITTED BY: f DATE: 01/16/95 (Respopiblet$ectionHead/ Delegate) RECOMMENDED BY: U. E. Miller /s/ DATE: 01/18/85 (Supervisor-Operational Assurance / Delegate) APPROVED BY: Jr.cech H. Plc..a /s/ DATE: 01/18/95 (Responsible Section Head / Delegate)
* RECOMMENDED BY: C. R. Overbeek /s/ DATE: c' /1 F /95 (OSRO Chairman / Alternate) * APPROVED BY: G. F . Overbe ck /s/ DATE: O'/'E/EE (Superintendent-Nuclear Production / Delegate) * Signatures required for Saf ety-Related or Superintendent-Designated procedures.
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7.1 Vccuum Grga Data Sh2et
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Instrument # D11-R427
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OUfPUT ADJ U5It,U OUTPUT CORRSP. INPUT 3% OF FULL SCALE 2% OF FULL SCALE
% F.S. UNITS UNITS AS FOUND TOLERANCE AS FOUND AS LEFT TOLERANCE AS LEFT
- + READING -
+ READING
~112 0 VAC il2 0 VAC ~l12 0 VAC ~I12 0 VAC ~l120 VAC
% "Ilg VAC "Ilg VAC "Ifr,VAC /PS IG "ligVAC ,,Iko Um "HgvAC/PSIC ligVAC.
0 -12.24 12.Z4 - 8.16 8 16 ' 0 0 0 .44 .9 () .29 .6 M4 108.84 96.60 121.05 100.65 117.00 26.67 8 8 7.1 8.9 l11 7.4 8.6 MA 204.0/3 191.53 216.32 195.91 212.Z4 50 15 15 14.1 15.9 7.10 14.4 15.6 gA 299.31 Z87.07 311.55 291.15 307.47 73.33 22 22 21.1 22.9 S[o 21.4 22.6 AJA
* * * 3s2.91 * 303 5'2. * 3aa.30 *100 30 23 3n MA ~
299.31 237.07 311.55 291.15 307.47 73.33 22 22 21.1 22.9 3oy 21.4 22.6 MA 204.075 191.83 216.32 195.91 212 24 50 15 15 14.1 15.9 2ii 14.4 15.6 UA 108.84 96.60 121.08 100.68 117.00 26.67 8 8 7.1 8.9 IL% 7.4 8.6 MA 0 -12.Z4 1Z.24 - 5.16 M.lO O O O .44 .9 O .29 .6 MA _
. * llaximum Vacuum Input Achieved. ;
Tbc An Found Tolerance + .9 "lin/+ 12.24 "110 2 and the As Lef t tolerance + .6 "lig/+ 8.16 "11 20
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must be calculated af ter the MaxTmum Vacuun "Hg/"H2 O is determined. , NOTE: Wallace & Tiernan pneumatic calibrator
"H2 O x .0735 = "ilg ~1I2 0 = PSIC , .o :r. Conversions S ;; Z/./0 _
an
~S "Hg x 13.605 = "H 2O "l! E$
o2 . - PSIG :: o'
" "g Performed by b ,,_ ) ,, _
o G \ ' N Date l -29- %
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7.2 Flow Indicating Switch Data Sheet -
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a--- Instrument # D11-N537
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OUTrUT ADJUM r.u ! ' CORRSP. INPUT 3% OF FULL SCALE 2% OF FULL SCALE OUTPUT AS LEFT UNITS AS FOUND TOLERANCE AS FOUND AS LEFT TOLERANCE
% F.S. UNITS + KEADING, ]
- + READING -
"H2O "H2O "H2O "H2O
% LPH "H2O VAC l -
i 0 0 0 .75 +.75 . t.40 .50 4.50 )R . 40 6.25 5.50 7.00 5.(oo 5.75 6.75 t)A I 50 __ ! 11.82 11.07 12.57 1l.lio 11.32 12 . 2 A)A _ ! 68.75 55 87.50 70 19.14 18.39 19.89 l9.% 18.64 19.64 $
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80 25.0 24.25 25.75 25.20 24.50 25.50 Ah j 100 19.14 18.39 19.89 N.co 18.64 19.64 A)k ,, _ 87.50 70 68.75 55 11.82 11.07 12.57 /l.20 11.32 12.32 $ 50 40 6.25 5.50 7.00 5,(.o 5.75 6.75 'A1A _ _ , 0 0 0 .75 +.75 .20 .50 +.50 MA_,_
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LPH ZZ OF FULL SCMI LPH ll/I TCH St.a r0 INT SWI TCH 3% OF FULL SCALE AS FOUND AS LEFT TOLERANCE AS LEFT NUtillER UNITS ACTION AS FOUND TOLERANCE
- + READING - + READLlid i LPM Open Dec. 47.6 52.4 50 48.4 51.6 AJA Trip 1 50 N/A N/A 60.5 N/A N/A MA
! Reset 1 > Trip 1 Close Inc Open Inc 67.6 72.4 70 68.4 71.6 A/A Trip 2 70 en
< Trip 2 Close Dec. N/A N/A [4).5 N/A N/A A/k
's G Reset 2 E$
~ Performed by d 3 *
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Date l .29_ % "
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44.080.205
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* Rt...Chen Equipmer.t Checklist Furnished for I&C Surveillance ( Date Required /-298[
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. Initials 1. Data Table comoleted for all sources used. -
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Also the 109 C'd (55 uCi) short half life. dM 2. Data listed on this Table is accurate and valid for 30 days with the exception of 109 Cd which should be recalculated daily. ST) ! 3. Source holders (2) for Stick and transfer sources for Mid-Range Noble Gas detector Channel #7 ready for issue. N 4. Sources organized and ready for issue. $0f) 5. 1 Ring Stand ready for issue or equivalent. M 6. The sources furnished do satisfy Tech Spec Requirement 4.3.7.12-1 Note (2). (Any substitutes shall be the esme physical geometrical shape and size or new detector efficiencies will be furnished.)
RadChem personnel organizing, issuing and reviewing
- the checklist M Printed name *
Date of Current Signature ,DI I Calculations /-27-Fy ENCL #11/#1 ENCLf11/#2 Nominal H .P . Source Current Detector Source Serial Activity Assay Original Activity Efficiency epm Number uCi Isotope Date Activity uCi eps/uCi value F873 1.0 137Cs 8-1-84 1.115uci 1.102. 23.9 2. 6 3v r+l 84-078 10.0 137Cs 8-1-84 10.78uci 10M Et/ 23.9 2.5Y7 E+2 84-062 100.0 137Cs 7-1-84 101.OuCf 7.94Ff*l 23.9 2 3f2E+3 7-1-84 1,124.Ouci I,lof E +3 23.9 1. 49 E M 84-063 1000.0 137Cs l
'- 9.67 2 l
W' '6 N- 10"7 55.0 109 Cd 10 -17-1Y *sof t 400 #fs y.sist+1 fr%x10 if.7F/.E+0 nu s M-SS l l Attachment 4 Page 2 of 2
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6 % T. .,,e-7.4 Mid Range Noble Cas Data Shyat . Instrument # D11-K610, D11-P280 Channel 0107 sh* ' .,8 i, ! , 6.2.6 ,,j. ~ i.,..,.t.. . . .6 ** 5.1.1 5.1.1 6.9.7 6.9.11 6.9.8 6.2.4 As Found 3.8 ASSAY REFEHENCE Parameter NOMINAL uCi AS FOUND ENCLOSURE 11 File 0107 S0tJRCE ASSAY SOURCE READING + 48% of point ACTIVITY DATE uCi/cc uC1/cc AS FOUND TOLERANCE 01 Y G.a s , APPLIED INPlfTS SD i-2iar
- + O2 AC /cc.
13,Fqp4 #19t gC; 6.2.6 Display + Tolerance 03 _+ 2.95 E-3 uCi DATE 6.9.7 Printer - Tolerance 04 g 137 Cs I.IIr 7. 7 7 E -2. (,. 79 E-2. + f. l 6 6-( 05 4 3.Ct.E +o I.o :-t- Fv 7. 89 E-2. i.oo E-1 - 4.og E-2. 06 o , a sics so.,s 7.5 t c -l l?.87 E-1 + I. I I E+0 07 o so .o s-s-n 7.53 2 -l AM - 3.92E-I 08 +t-l.co E-l t 17 Cs nos.o 7. 0 3 E * * to. 98 E+O + ). 0 4 E & I
. s ee.o 7 -I-e 4 7.o3 E+o NM - 3% E40 I,stwo 7.s? s +1 M.97 6[ + / .R, E+ 2. 6.3.4
n7 cs 20 4,.co E 44 ' s ~..e 7 -t-tv ~7 82Ett / Fsf - 4.07 E+f 107 C.( 56.13 1. V o E - 2. /.066 2 + 2.ig E-2 ST.o 10-17- 74 1.OE -2. .i.or F-2 - 7 45 E-3 Attach Copy of *
+ Printer Parameter
- File Here. 0107 .
I l i 01-07 HORMAL 01 4 GR5 i 02 FL/CC 03 CAL.00h5inNT +2.ME-03 ' 04 EkG81 Cn# 8 05 EKGal FAciGR +3.56E+00 06 EKGt2 Cril 0
.o > 6.7.2 As Found Background 1.. SA-13 4436-3 uCi/cc Channel 7 07 BKG42 FACTGR +0.00E+00 08 FIX.Br;G.5UB.' +4.00E-01 <E N +3.10E-01 "E 6.9.6 As Found Background Count Rate (location) -5.N 6-3 uCi/cc 09 HI 6LH SET ~ 10 ALT nuit SET +2.75E-01 N' t o ?b ; E$" 6.9.7 Background Dif ference 7. 2 o E - Q uC1/cc 11 TH Alit D.<tt3 +2.00E+01
' 16 LOGGED? YE5 E
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19 SArt.Ft5.6L0k 00-00 Performed by___ ls 20 FLOW LCC<n] +6.00E+04 S 21 ret.FLO.aLCh 00-00
+0.00E+00 i
4 Dnte /-29-fW 22 REL.Fo0.FhC.
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7.3 Low Raige Noble Caa Dzte Sheet * Iectrumett f D11-K610, D11-P280 Ch:nnel 0105
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5.1.1 5.'1.1 6.2.6 6.8.9 6.2.6 6.2.4 As Found 3.7 ASSAY REFERENCC Parame t,er NOMINAL uCi AS FOUND ENCLOSURE 10 File O M5 SOURCE ASSAY SOURCE READING + 32% of point . ACTIVITY DATE uC1/cc uC1/cc AS FOUND TOLERANCE 01 g5 CrA s APPLIED INPUTS READING -
+ O2 u C /c.c.
SoTcPc, uCi Display + Tolerance 03 't(o.66 E-6 ' uC1 DATE Printer - Tolerance 04 8 , 90Sg.Y 't . 9 ^f 9 6 - 3 on + l.36 E -4 05 + 4. 32 6 e t o.cl ' n-t-sq f.03 5 *Y 4.I3 E S' - 7.co E -5- 06 O
- _9 05 ft - V '
9.8496-2 I. 0X ,3 f.e fe 3 + l.3rc-3 07 o
.I 9.r.By ,v g -
,,,.w g.4 08 + 2 87Etl
_9 0sa - v 3.332c-1 3.*ibE '$ + .f . 54 6-3 o,3 9. -94 3.44E-3 ga _ 3,3q e-3 70sg-y 3.n59 3. u c -> + y,7e-t 6.3.4 3.o 9 - 1 -v '1 3.11 E-A on - 2.isc-c 20 + 6.co E + V Tc. - 9 't . oo t t.lf W + 1 5 3 E-f
.oo a y- 9-23-8I I .4 E'S 4./ O E-(a -
7. bM- 4 01-05 NORMAL
+ 81 P GAS
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82 W CC 03 CAL.CONST6HT +6.68E-03 04 BKG81 C.H# 8
05 B.NGil FACIGE +4.32E+02 06 BKG82 Cnt 0 0? BKG82 F6CTOR +0.00E+00 08 FIX.BKG.3US. +2.17Et01 6.7.2 As Found Background in SA-13 -1.4 3 E- f uC1/cc Channel #5 09 HI ALM SEi +3.10E-04 10 All 6LM SE1 +2. IGE-04
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11 1H ALM D./fD +2.00E+01 5" Performed by
*R ~ A 16 LOGGED? YE3 19 SAM.FLG.6 LOR 00-00 "E Date / ~3l-AV 20 FLOW LCCa0 +6.00Et04 I $ f u" 21 AEL.FLO. ALDR 00-00' * P,, ,
22 REL.FLO.F AC. ta.00E+00 ~P
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44.080.206
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f RadChem Equipment Checklist Furnished for IEC Surveillance Date Required / -3/-
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Initials I 1. Data Tal-le co:nlered for all sources used.
~ M 2. Data listed on this Table is accurate and valid for 30 days. Jith 3. Particulate filters ready for issue (3 ea) (47 mm diameter filter for SPING) or equivalent. M 4. Iodine filter cartridge ready for issue (1 as) (Eberline No. IC-1) or equivalent. /8O 5. The sources furnished do satisfy Tech Spec Requirement 4.3.7.12-1 Note.(2). (any -obstitutes shall be the same physical geometrical shape and size or new detector efficiencies will be furnished.)
RadChem personnel organizing, issuing and reviewing j the checklist M Printed name . DALE A. SAMAN Date of ; _y_ qg-( Current I-2 7-D.Afg Signature 8d #Z h Calculations 1-1945' ENCLf10/#1 ENCL #10/f2 Nominal ll .P . Source Current Detector Source Activity Assay Original Activity Efficiency epm Serial Number uCi Isotope Date Activity uCi cpm /uCi value
#
15869-50 .01 90Sr-Y 9-1-84 368.1dps S. 352 e -3 1.56x10 l . F37 E 4 7 15882-50 .1 90Er-Y 9-1-84 3644 dps f.753 E-? 1.56x10' l.FZI E+4 84-OS2 .3 90Sr-Y 9-1-84 12,330dps 7.3 co E-l 1.56x10' F. lYf E f Y
84-084 3.0 90Sr-Y 9-1-84 113,200dps 30MEd l.56x10 9 . 'M E 6 ! cos s443 / cp.se y,95 g 82-055 3*d-ag 0025 Tc-99 9-23-81 295 *"n 2III b3 7r99x10 l .7Yl/E f 2.
Da em s-3s-9f g-te-g5-
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- Attachment 3 Pare 2 of 2
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44.080.206
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R2v. 1
- Surveillance Checklist Step Number Initials Data
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3.0 Required Equipment
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3.1 Eberline Equipment 3.1.1 Portable Terminal with keyboard enable key 3.1.2 CT-2 Keyboard Enable Key 3.2 Stopvatch b kTestEquip.No.
ygCalib. Due Date No.
3.3 Vacuum pump b 3.4 Wallace and Tiernan k Test Equip. No.
4-ngCalib. Due Date Model 65-120 3.5 0-30 "H2O Test Instrument Test Equip.
3.6 Variator (vacuum) 3.7 Transfer Sources 90Sr-Y QM
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3.8 Stick Sources 137Cs b
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3.9 Source holders (Radchem) b 3.10 3 Particulate Filters (Radchem) 3.11 1 Iodine Charcoal Filter Cartridge (Radchem) 3.12 Mass Flowmeter qh Test Equip. No.
(,gCalib. Due Date 3.13 Hiscellaneous hardware dk
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3.14 Ring Stand 5.0 Prerequisites j 5.1 Current Activity uCi and the source cpm values are calculated, documented, and evaluated.
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Attachment 5 Page 1 of 8 i
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R2v. 1 i-l St.veillance Checklist ( Step Number Initials- Data 5.1.1 Ra'dchem Tech scheduled and S'ource . Activities data documented on Attachments 3 and 4, Page 1 of 1 Ch 3.1.2 Radchem notified if applicable 5.2 Radiation Work Permit number documented b 5.3 Requirements of 41.000.11, 4.3.1 to 4.3.9 satisfied N 5.4.1 NSS Acknowledgement k 5.4.2 NSS Permission \Ah 5.5 Control Roon NSO Informed 5.6 Dil-P280 Located b 6.0 Proce' dure
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6.1 Initial Conditions 6 .1.1 Control Terminal 2 (CT-2) Dil-K610 Alarn lights are @)or one If No yes (cirle N/A off. 6.1.2 to 6.1.5 6.1.2 Keyboard Enabled A k 6.1.3 Command Sequence performed AA 6.1.4 No interferring Alarms Mk 6.1.5 Keyboard disabled and key removed kW 6.2 As Found Parameter files - 6.2.1 Portable Terminal connected and in local control b 6.2.2 Keyboard Enabled PLK 6.2.3 Cor. mand Sequences performed Qb 6.2.4 Parameter file data documented B and attached on Attachments 3 & 4 6.2.5 Keyboard disabled @
/ 6.2.6 Values calculated and documented G-/(b
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6.3 As Found Flow 6.3.1 As Found Vacuum % "Hg 6.3.2 As Found Flow Meter Indication 956 Qi,q LPM Present Standard Flow Condition Ws I 6.3.3 57,l't LPM t Attachment 5 l Page 2 of 8
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44.080.206 Rsiv. 1
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Surveillance Checklist
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Step Number Initials Data
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6.3.4 As Found Parameter File Data on line 20 File 0105 and File 0107 . documented
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6.4 Precalibration Preparation 6.4.1 Calibrate switch ON, Maintenance lights ON 6.4.2 Request issued % 6.4.3 Filters changed and the pump is OFF Cih 6.5 Vacuum Gauge Calibration 6.5.1 Lines disconnected b 6.5.2 Hose fitting removed, tube fitting installed % 6.5.3 Vacuun gauge manifold inlet plugged 96 6.5.4 Instruments connected GC6 - 6.5.5 As Found data documented G1b f Attachment 1. Recalibration necessary? % (Circle One) YesordIo)IfYes'
[ 6.5.6 Cover removed AA complete steps 6.5.6 to 6.5.12.
6.5.7 15 "Hg applied d4 If No N/A steps 6.5.8 Indicating needle removed UA 6.5.6 to 6.5.12 6.5.9 Indicator repositioned MA under initials.
6.5.10 Calibration Data reverified MA 6.5.11 As Left Data documented kW Attachment 1.
6.5.12 Cover reinstalled NA 6.5.13 Supply pressure and test equipment recoved % 6.5.14 Plug removed % 6.5.15 3/8" ss tube reconnected W 6.6 Flow Indicating Switch Calibration l 6.6.1 Photohelic lines disconnected b , 6.6.2 High side vented and test QA l instrucents connected , ! Attachment 5 Page 3 of 8 l l
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1 ( Surveillance Checklist Data Step Number , Initials l 6.6.3 As Found Data documented on b Attachnent 2 hecalibration Necessary? N (Circle'One) Yes or M If Yes complete steps 6.6.4 to 6.6.7. If No N/A steps 6.6.4 to 6.6.7 6.6.4 Zero "H 2 O applied MA 6.6.5 Photohelic zeroed MA 6.6.6 Calibration Data reverified NA 6.6.7 As Left Data documented MA Attachment 2 6.6.8 Valve #2 closed, Valve #5 open Satisfactory Flow sia21ated and CALIBRATE switch 0FF h 6.6.9 As Found Low Flow trip documented Rb on Attachment 2 6.6.10 As Found Low Flow reset documented @ on Attachment 2 6.6.11 As Found High Flow trip documented M on Attachment 2 (' 6.6.12 As Found High Flow reset @ documented on Attachment 2 6.6.13 Setpoints recalibrated b Yes or N Circle 6.6.14 As Left data docunented on d Attachment 2 6.6.15 CALIBRATE Switch ON @ 6.6.16 Test equipment disconnected from V{h Photohelic 6.6.17 Photohelic lines reconnected b 6.7 As Found Background Data 6.7.1 Filter Element replacements completed 6.'.2 Second Cycle Data from the Portable Terminal Printer uCi/cc documented for Channel 05 on Attachnent 3 and Channel 07 on Attachment 4.
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44.080.206
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R2v. 1 Surveillance Checklist Step Number Initials Data 6.8 Low Range Noble Gas Ch #5 6.8.1 B:'c connector disconnected for Mid k - Range Noble Gas Detector 6.8.2 Detector removed (Channel 07) % 6.8.3 Detector stored (Channel 07) % N/A this step if
. 6.8.4 RDS-1 Removed O./A dual calibrations 6.8.5 To 6.8.11 As Found Data steps are being done.
completed and documented on Attachment 3 Q[h 6.8.12 Last transf er source removed Q//$ 6.8.13 Filter and Filter Dise Retainer effA f reinstalled 6.8.14 RDS-1 reinstalled in its original O position 6.8.15 RDS-1 reterminated O!b
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6.9 Mid Range Noble Gas Ch #7
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6.9.1 Source holders obtained $7O 6.9.2 Mid Range Noble Gas Detector BNC / connector reterminated 0 43 6.9.3 Area established ()f/'y
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6.9.4 Source holder and ring stand attached to the detector ()/M 6.9.5 Channel select thumbwheel set on I' Channel 07 Q
6.9.6 Location Background documented (uCi/cc) (~) 6.9.7 Modified Source uCi/cc documented /l)f/) 6.9.8 Tolerances Calculated 6/4
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6.9.9 To 6.9.12 As Found Data steps completed and documented on Attachment 4 h[h 6.9.13 Source holder and source removed 6.A/) 6.9.14 Ring Stand Removed Q 6.9.15 BNC Co nector disconnected 6./j) 6.9.16 Mid Range Noble Gas Detector @y?)
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reinstalled 6.9.17 BNC connector reconnected O[j3 6.9.18 Detector retainer secured O/,)) 6.9.19 All detectors reinstalled and reterminated /O[h
'I 6.9.20 Keyboard enable removed and por-table terminal disconnected hh
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( Attachment 5 Page 5 of 8 i
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44.080.206
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Surveillance Checklist Step Number _ , Initials Data 6.10 Leak Test
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6.10.1 Vacuum pump and Hanual Isolation Valve Connected O 6.10.2 Manual Valve #1 closed (VF 6.10.3 Motor operated valve #2 closed and / MOV #5 open 94 6.10.4 Manual Valve #3 and #4 closed 69 6.10.5 Isolation Test Valve open Mis 6.10.6 Motor operated Valve #5 open ol, a 6.10.7 Vacuum Regulation Valve open d in 6.10.8 Vacuum pump started and regulated 1 f or 10 "Hg @9) 6.10.9 Stabilized and isolated JtMh 6.10.10 Leak Test OK C@ 6.10.11 Test Equipment removed GM 6.10.12 Tube Fitting replaced with original F hose. fitting G4) 6.10.13 Tygon Tubing Reconnected 66 f f 6.11 Sample Flow Calibration 6.11.1 Leak Test Complete Cbb 6.11.2 Valve #1 closed f 10 6.11.3 Valve #2 open, Valve #5 closed @-f6 6.11.4 Clean filters installed Mb 6.11.5 Mass Flowmeter Connected d]A 6.11.6 Mass Flowmeter stabilized Unb 6.11.7 Puup started 3/fd 6.11.8 1/4" Plug Removed VfD 6.11.9 RAP-3 Adjusted Q/h 6.11.10 Present Vacuum (M6
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% "Hg Limits (2 to 7"Eg)
6.11.11 Observed flow setting NO /M LPH 6.11.12 Orifice adjusted to the observed / flow rate calculation G[D 6.11.13 As Left observed flow and vacuum %-/ 6 lo'l LPM 3 "Hg / ! 6.11.14 Standard flow of 60 LPH 9/D
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6.11.15 1 g r place [h 6.11.16 Mass flovmeter disconnected 97D
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6.12 System Return to Normal 6.12.1 Valve #1 open
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f Attachnent 5 Page 6 of 8 l
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R2v. 1 Surveillance Checklist Step Nunber Initials Data 6.12.2 Valve #2 closed, Valve #5 open 04 6.12.3 Valves #3 and #4 closed 'Qf/) ' 6.12.4 Calibrate switch 0FF M
~6.12.5 Normal Status verified Off)
6.12.6 Radchem notified 6#W
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7.0 Acceptance Criteria ,
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7.1 Data on Attachment 1 is b/6 aatisfactory /' 7.2 Data on Attachment 2 is 0/A satisfactory /' 7.3 Data on Attachment 3 is Qb
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satisfactory 7.4 Data on Attachment 4 is 6)/h
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satisfactory 7.5 All steps completed, acknowledged OM
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by initials and all other data f request completed Rccarks Jfff em i in .srep6f Ti .e Co: lete? 2230
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l Dtte Completed l - 31 - % ( Attachment 5 Page 7 of 8 i
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44.080.206
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_ Surveillance Checklist-f
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Test Team Per'sonnel: . Printed Name Initials Signature , n ',\ p a k o m_ / JeL9 & #. / ya Qd d NOTE: Following completion of this test, ensure requirements of 4.4.9 through 4.4.18 of Ref erence 2.8, and 3.3 of Reference 2.5, where applicable are satisfied. Inform the NSS that this surveillance is complete.
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44.080.206 Q. . R2v. 1 Independent Verification Sheet
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Date l- 5 / - T5 ,
* Starting Time 9 *3 f5
_ In?tial/r e .
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l. All test sources removed #E# /AF Y5 2. All test equipment removed .fff? //-5/-75 l
3. Keyboard disabled and portable 9/SP // J+ts terminal removed 4. All detectors reinstalled #E 9 //-7-15 5. All detector cables reterminated fff9 / /-y-C5 6. Process sample flow through the monitor ff8 / /-h-f5 sample chamber 7. Monitor Alarms Clear for Channels 5 and 7 '(D11-P2 ) 9/A //~l II 8. Monitor operating with Alarms Enabled "H" Maintenance Light OFF. //-//-:i (
#f[ Initials #//r4*' [ 8MN Printed Nane and I
I d I M u ,', Signaturc cf Indiciduni Perf orming Indepindsnt Verification.
. Attachment 6 PaEe 1 of 1 END
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.' h EF-2 FSAR *' 7"*h' N
.' the operational phase were identified in letters EF2-53674, dated in 45 June 15, 1981; EF2-67767, dated March 9, 1984; and EF2-69175, dated June 18, 1984.
13.1.4.3.3 Minimum Qualification Requirements for Nuclear Plant Personnel During the selection of personnel and the scheduling of tra.in-ing assignments for the plant staff, the requirements of Re g u-latory Guide 1.8, Personnel Selection and Training, will be met. The combined experience and education and an assigned training program are such that the criteria in Section 4 of 40l ANSI N18.1 (1971), " Selection and Training of Nuclear Pe rson-
*
nel," are met at the time of the initial Fermi 2 core loading or are appropriately modified for special plant design features or operational considerations.
35 For these determinations, the following plant staff positions are identified with the classifications contained in Section 4 of ANSI N18.1: Fermi 2 Staff Position ANSI N18.1 Classification Superintendent - Nuclear Plant Manager (Section 4.2.1) Production Assistant Superintendent - Plant Manager (Section 4.2.1) Nuclear Production
'
Assistant Superintendent - Plant Manager (Section 4.2.1).
,Startup Supervisor - Operational None Assurance Quality Control Inspectors ANSI N45.2.6 ,
Rad ia tion Protection - Chemical None Engineer 6Q General Supervisor - Chemistry Chemistry and Rad iochemist ry (Section 4.4.3) Chemist None Chemical Engineer None R1 51 General Supervisor - Radiation Protection Manager Health Physics (Reg. Guide 1.8 - 1975)
General Supervisor - Radwaste Supervisor not requiring NRC license (Section 4.3.2) Health Physics Supervisor - Supervisor not re quir ing NRC
. Dos ime t ry license (Section 4.3.2)
13.1-20 Po s t-O L Re v . 1 - March 1985
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EF 2-FSAR Fe rmi 2 Staff Position ANSI N18.1 Classification V Health Physics Supervisor - Supervisor not requiring NRC Operations license (Section 4.3.2) Radwaste Operations Supervisor not requiring NRC Engineer 51 60 ' license (Section 4.3.2) ' l Radwaste Supervisor - Supervisor not requiring NRC Contamination Control , license (Section 4.3.2) l60 Radwaste Supervisor - Shipping Supervisor not requiring NRC license (Section 4.3.2)
.
Reactor Engineer Reactor Engineering (Section 4.4.1) 35 Assistant Reactor Engineer None l51' Operations Engineer Operations Manager (Section 4.2.2)
.
Assistant Operations Engineer Supervisor requiring NRC license (Section 4.3.1), except that requirements for this position shall include 6 years of re spon-sible power plant experi-ence, 2 years of which shall be nuclear power plant experience Nuclear Fuel-Handling Supervisor requiring NRC Supervisor license (Section 4.3.1), modified for limited assignment to fuel handling
- Nuclear Shife Roparviaer supervisor requiring MRC license (Section 4.3.1)
Nuclear Assistant Shift Supervisor requiring NRC Supervisor license (Section 4.3.1) Nuclear Supervising Operator Supervisor requiring NRC license (Section 4.3.1) Nuclear Power Plant Operator Operators not requiring NRC license (Section 4.5.1) Nuclear Assistant Power Plant Operators not requiring NRC Operator license (Section 4.5.1) Maintenance Engineer Maintenance Manager (Section 4.2.3) 13.1-21 Amendment 60 - December 1984 _ _. _.
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At the time of initial core loading or appointment to tion protection at a nuclear reactor facility. A mini.
the active position. such a supervisor shall hold an mum of two years of this 6ve years experience should appropriate AEC license. be related technical training. A maximum of four years of this Eve years experience may be ful611ed 4.3.2 Supervisors Not Requiring AEC ' by related technical or academic training. , Licenses l
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At the time of initial core loading or appointment to 4.5 Operator . Technician . Repairman
, the active position, a supervisor in this category shall 4.5.1 Operatera have a high school diploma or equivalent and a . At the time of the initial core loading or appointment minimum of four years of expenence m, the ereft or - , to the active position, operators to be licensed by disciphne he supervises.
, the AEC shall have a high school diploma or equi.
4.4 Professional . Technical valent and two years of power plant experience of The professional . technical groups shall include which a minimum of one year shall be nuclear power individuals with the following quali6 cations in the Pl ant experience. Further, before being acceptable indicated disciplines. A single individual may be for full responsibility in the job, they shall hold an qualified and perform in more than one discipline. . AEC Reactor Operator's License.
Suitable organizational depth should exist to provide All operators, whether or not they are to be licensed for an absence of the principal. by the AEC should have a high school diploma or 4.4.1 Reactor EnFi neering and Physics equivalent, and should possess a high degree of man.
ual dexterity and mature judgement. Selection inter-At the time of initial core loading or appointment
'I'** ***'"I"I "' should be used for all oper-to the active position, the responsible person shall
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neering or the Physical Sciences and two years ex. gmst gh levds of mpomMty and to eventual
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perience in such areas as reactor physics, core mea.
surements. core heat transfer, and core physics test. 3 4.5.2 Techm. .esans ing programs.
Technicians in responsible positions shall have a 4.4.2 Instrumentation and Control minimum of two years of working experience in At the time of initial core loading or appointment to their speciality. These personnel should have a mini.
the active position, the responsible person shall have mum of one year of related technical training in a minimum of Sve years experience in instrument. addition to their experience.
ation and control, of which a minimum of six months shall be in nuclear instrumentation and control. A 4.5.3 Repairmen minimum of two years of this hve years experience Repairmen in responsible positions shall have a should be related technical training. A maximum of minimum of three years in one or more crafts. They four years of this hve years experience may be ful. should possess a high degree of manual dexterity and filled by related technical or academic training. ability and should be espable of learning and apply.
4.4.3 Radiochemistry ing basic, skills in maintenance operations.
, At the time of initial core loading or appointment 4.6 Technical Support Personnel i to the active position. the responsible person shall have a minimum of five years experience in chemis. 4.6.1 Engineer in Charge
try of which a minimum of one year shall be in The engineer in charge shall have a minimum of radiochemistry. A min: mum of two years of this 6ve a Bachelor's Degree in Engineering or the Physical years experience should be related technical training. Sciences and have a minimum of three years of ! ' A maximum of four years of this five years experi. professional level experience in nuclear services. nu-enee may be ful611ed by related technical or academic clear plant operation, or nuclear engineering and the necessary overall nuclear background to deter.
traininF.
mine when to call consultants and contractors for 4.4.4 Radiation Protection dealing with complex problems beyond the scope of At the time of initial core loading or appointment owner organization expertise.
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COURSE APPROVAL APPROVALS Radiation COURSE TITLE: Protection Theory TECHNICAL /DATE h,./ / 4/'h FILE NO: 01 09 00 00 CLIENT /DATE /J r 5"~ REV. NO: 2 TRAINING MGMT/DATE J /c6 sf NQA CONCURRENCE /DATE /4 Sj' V PURPOSE: . The purpose of this course is to provide in-depth specific information and knowledge on radiation and radiation protection required of personnel in Health Physics.
This course is designed to meet the intent of NUREG 0761 and INPO 82-006.
. DESCRIPTION: The course includes theory and practical knowledge in the following areas.
Unit 1. Atomic Structure j~, ,' a Unit 2. Type of Radiation I Unit 3. Type of Radiation II Y~".' Unit 4. Radioactive Decay Schemes .e . Unit 5. Interactions of Radiation with Matter (Particulate) N
.
Unit 6. Interactions of Radiation with Matter (Electromagnetic) - Physical Decay of Radioactive Material
-
Unit 7.
Unit 8. Radiation Dosimetry Ouantities and Units ' Unit 9. *a"*-aa-aa*=1 *=dia*iaa end Radinactivity Unit 10. Cell Chemistry and Acute Effects Unit.11. Biological Effects of Ionizing Radiation ( W l', M ~ ' M nit 12. Internal Dosimetry (Part I) 1%. . I >q @ Unit 13. Radiation and Shielding Unit 14. Gas Ionization Detector Theory Unit 15. Scintillation Detector Theory Unit 16. Neutron Detector Theory , Unit 17. Instrument Operating Characteristics Unit 18. Health Physics Instruments Unit 19. Counting Systems Unit 20. Counting Statistics Unit 21. Contamination Control Unit 22. Radiation Surveys
Unit 23. Airborne Radioactivity Surveys 1 - ,1-
'-
Unit 24. Shipment and Transport of Radioactive Materials
,,. Unit 25. Respiratory Protection ~.
, NT/R296C/40.0 Page 1 of 2 ' 030285 j bI
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I COURSE APPROVAL - CONTINUAT E Radiation COURSE TITLE: Protection Theory
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FILE NO: 01 09 00 00 REV. NO: 2 DESCRIPTION: (Continued) Unit 26. BWR Systems (The Direct Cycle BWR Steam System) Unit 27. Decontamination Unit 28. Radioactive Materials' Control Unit 29. 10 CFR 19 , e Unit 30. 10 CFR 20 - 0 "' * - Unit 31. AIARA ----- sw.a. 3.,' 4 A e. A e c" O
.
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Unit 32. Radioactive Waste Cor! trol Unit 33. Thermoluminescent Detector Theory Unit 34. Semiconductor Detector Theory Unit 35. BWR Auxiliary Systems . Unit 36. Internal Dosimetry (Part II) g u .3 ,, DELIVERY MECHANISM / DURATION: Interactive components system (PLATO). Duration is 80 hours.
EVALUATION MECHANISM AND CRITERIA: There is a pre- snd post-test for each module. For successful completion of the module either the pre-test or the post-test must be passed with at least an 80%. Successful completion of the course is successful completion of all modules.
' TRAINEE PREREQUISITES: None DEVELOPMENTAL REFERENCES: Developmental references have been footnoted at the end of the appropriate modules.
NT/R296C/40.1 Page 2 of 2 030285 _ _. _ _ _ -
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,'.' FLUKE 5100B CALIBRATOR C, . . . .(. ' '~"~~- , C:
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REPORT OF CAllBRATION l REPORT NO. 6347-310-010 DATE D APRIL 24. 1985 PAGE: 1 OF 1 DETROIT EDISON - FERMI-2 - WAREHOUSE B - 6400 DIXIE HIGHWAY - NEWPORT, MICHICAN 48166 MANUFACTURER: FLUKE NOMENCLATURE: METEL MODEL NUMBER: 8021B SERIAL #: 3045323 CALIBRATION POINTS OF STD. (SOURCE): ACTUAL READING OF UNIT UNDER TEST: 100 mv DC 100.0 190 mv DC 190.0 1 v DC 1.000 1.9 v DC 1.900 10 v DC 10.00 19 v DC 18.99 100 v DC 100.0 190 v DC 189.9 ' 500 v DC 500.0 1000 v DC 1000.0 .
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OUR STANDARDS ARE TEST REPORTED ACCURATE AND TRACEABLE TO THE UNITED STATES NATIONAL BUREAU OF STANDARDS.
METROLOGY SE RVICES GROUP TEST INSTRUMENTS DIVISION 4800 E AST DRY CREEK ROAD P.O BOX 5227 DENVE R. COLOR ADO 80217 771 4700 ARE A CODE 303
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May 16, 1985 l g g g o 1385 NE-85-0708 _
l Director of Nuc1 car Reactor Regulation Attention: Mr. B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555
,
Dear Mr. Youngblood:
Reference: (1) Fermi 2 NRC Docket No. 50-341
- N NRC License No. NPF-33 lE5 i
i
! ! $ ! (2) Detroit Edison Letter to NRC Region III, " Transmittal of Action Plan for Completion of Certain NRC Open Items", Ef2-70036, dated ' ;y October 31, 1984 h (3) Detroit Edison Letter to NRR, " Additional ' < Clarification of Position Regarding NUREG-0737 '
g Post Accident Sampling and Monitoring s- ,, a Capabilities", EF2-72030, dated December 13, 4 *
% 1984
S (4) Detroit Edison Letter to NRR, " Clarification of
" Position on Silicone Duct Sealant and Other s lj j e Issues", EP2-72039, dated January 8, 1985 m . .. Iu $ N 5 8 d S 5.'.. (5) NRC Region III Inspection Report No. -
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50-341/85-017 (DR5S), forwarded on Lei.i.er dated April 1, 1985
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6' Subject: Post-Accident Sampling and Analysis of Plant E.filnents_{ Rad o.iodpes and_ Ear _ticulAtes) This letter is to confirm Detroit Edison's response to Item II.F.1 of Supplement 5 to the Fermi 2 Safety Evaluation Report and Condition P.C(17) of the Fermi 2 License, as discussed by telephone between Messrs. R. L. Andersen and A. E. Wegele of Detroit Edison and C. A. Willis and C. R. Nichols of NRC METB, April 10-22, 1985.
These items relate to Detroit Edison's commitment to demon-strate, prior to startup after the first refueling.-outage, that i the iodine / particulate sampling subsystem of the Standby Gas ' Treatment System (SGTS) will perform its intended function.
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Mr. B. J. Youngblood
.- May 16, 1985 '
NE-85-0708 Page 2
The following items were discussed: 1. The Fermi 2 SSER 85 includes the statement: It is the applicant's position that the noble gas monitor can be used to project the magnitude of radioiodine and particulate releases in the event that an accident occurs during the first fuel cycle.
It was agreed between Detroit Edison and the NRC that no such position has been taken by Detroit Edison and that the statement in the SSER 45 is in error.
2. The Fermi 2 SSER 45 includes the statement: However, in Report No.50-341/85-27 cited in the preceding section of this supplement, we stated that the applicant had not yet developed correction factors for sample line losses due to iodine plateout and particulate depositions so as to assure the collection of representative samples.
It was agreed between Detroit Edison and the NRC that Detroit Edison has developed such correction factors, as described in Reference (3), and that these correction factors have been incorporated into approved plant procedures, as confirmed by NRC Region III in its closure of Open Item No. 341/84-43-04 Reference (5).
' 3. The Fermi 2 Facility Operating License, Reference (1), includes the statement - Prior to startup following the first refueling outage, ' Detroit Edison shall demonstrate that the operating iodine / particulate sampling system will perform its intended function. , Detroit Edison confirmed its pos_i_ tion that, through..ihe use of calcula~t_e1 samle_line loss factors in approved prqcedures, as
"descr1Ded in Reference (3), Detroit Edis_pnis_cammi.tments to NURES;p],37, Item II.F.1(2), and the applicable items of NRC Qq"n' latpry Guide 1.97,~ Revision 2, have baan "=at,a68'Therefore that the License"C65'61 tion has been satisfied.
! 4. Previous letters to NRC Region III and NRR References (2) and (3), included a commitment tq_submi_t_a scope for_ a sample line loss test, including an.eyalgation of__.the applicabiTfty or~ performing such a tes_t.
_ , l 1__ -_ -
a Mr. B. J. Youngblo.
May 16, 1985 l' - NE-85-0708 Page 3 It was agreed betwer. . Cetroit Edison,and,t_he_NRC that the need fo__rsuch until submittal time as orthe_Ent this scope hasand e.va_Luation a reviewwill. be _ deferred
.
NRC completed and_Lc.sponse
-
to the above, including rnakTng any_ne_ces_sary_ changes to th_e Fermi 2 SSER.
Should you have any questions, please contact Mr. O. K. Earle at (313) 586-4211.
Sincerely, ,
'
illd (IV) cc: Mr. P. M. Byron b
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Mr. W. Gammill Mr. M. David Lynch Mr. C. A. Nichols USNRC Document Control Desk Washington, D.C. 20555 I . ,
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May 16, 1985 NE-85-0708 Page 4 bcc: Approval Control F. E. Agosti R. L. Andersen L. P. Bregni W. F. Colbert O. K. Earle R. R. Eberhardt W. J. Fahrner ' ' W. R. Holland W. H. Jens R. S. Lenart E. F. Madsen P. A. Marquardt A. Papadopoulos T. D. Phillips T. Randazzo L. J. Simpkin G. M. Trahey A. E. Wegele 0. K. Earle (Bethesda Office) Secretary's Office (2412 WCB) NRR Chron File NOC Satellite Service Center
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[ .ro l l l On two occasions between April 23 and 25, 1985, Iethnical Sycification 13.7.11.b was violat9J in that grab samples were not taken within the required eight hour period when discharging affinent from the Circulating Water Reservoir decant line with the radiation monitor inoperable, j
The en ies of these violations were failure to recoaniz_e the reouframant to sa:'oie in one instance and failure to allow ror delays in obtaining the SATale IILitle q(h,qt, h instance. . i f Personnel involved either have or will be reautred to review the events ang l their gusti. s In addition, a crocedure_to oovern the performanca nf tf.f.bnical j l c sRgci.fication surveillances aa,d action statements by Chemistry Section personnel l has been written and approved. ~
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LICENSEE EVENT REPORT (LEH) TEXT CONTINUATION amoveoove osm ( l tapingt Seat et l
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oocat?aswwega180 ten ms.ese ses paos a3, I
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w ,,- . w .. -.e 5. ma. ., in, 010 On April 23, 1985, at 1655 hours, the Circulating Water Reservoir Decant Pump was started to provide dilution water for a discharge from the radwaste sample tanks.
This discharge is also monitnred by the Liquid Radwaste Effluent Line monitor which is upstream of the decant line monitor and provides automatic termiration of the release if the setpoint is exceeded. The sample tank discharge is then diluted with water from the Circulating Water Reservoir as it is discharged to the lake. The Circulating Water Reservoir Decant monitor monitors the combined discharge.
As the discharge was proceeding, periodic low flow slarms were indicated in the control room for the decant line monitor sampling pump. At approximately 2015 hours on April 23, the decant line sample pump tripped. This was annunciated in , the control room. An operator was dispatched to vent the sample line and restart the sample pump and the Nuclear Shift Supervisor (NSS) was informed. The NSS consulted Technical Specification 3.3.7.11.b and determined that the discharge could continue for up to 30 days provided that grab samples were taken every 8 hours.
Radwaste The NSS also Effluent monitorcontacted the radwaste control room and verified that the was operable. In discussions with the control room ' , operator the NSS stated that the technical specification would not be a problem l and that the discharge could continue. The control room operator interpreted this ! to mean that the technical specification was not applicable since the Radwaste Effluent monitor was operable. Shortly thereafter the sample pump was successfully
. tarted and thus no grab sample was taken.
Later that shift, the sample pump (General Atomic Model RD-33-12) tripped again.
The control room operator did not consider this a problem because of his earlier misunderstanding of what the NSS had said. Consequently, he did not log the pump trip or attempt to restart the pump nor did he advise the NSS. As a result,
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I the oncoming shift was not made aware of the decant monitor being inoperable and I did not detect the Icw flow alarm window. The discharge continued through the j nicht.
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At about 0730 hours on April 24, 1985, the control room operator noticed the low flow alarm from the decant line monitor and stopped the discharge. It was deter- I mined that the decant line monitor had been inoperable since about 2015 hours on April 23 without a sample being obtained. This eg eg.ded the eloht hrw y le reautrement by 3-1/2 hours.
At about 0010 hours on April 25, the NSS reminded the Chemistry Section that a sample of the decant line discharge had to be taken by 0400 hours that morning as the previous sample had been drawn at 2000 hours on April 24. The Chemistry ,
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Technician assigned to take the grab sample waited until about 0330 hours to i prepare and then experienced unexpected delays in reaching the decent line dis- i charge area. Consequently, the sample was not obtained until 0415 hours vio- ! lating the eight hour requirement.
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Although the NSS attempted to contact the Chemistry Section to determine the status of the sample, the technicians on the shift were engaged in activities away from the telephone. At 0444 hours, the Chemistry Section leader contacted the NSS and advised him of the time the sample was taken. The NSS recognized the violation and documented the event.
, It should be noted that the Lant has not reached initial criticality and thus no radioactive effluents were expected and samples taken confirmed this.
. The e of the M t failure to obtain a sample within the time required by I technical specifications is the miscommunication between the nd control * room operator concerning the annlicability of the.ggf)ni~ cal sgftcifica to the decant line monit6r. The second failure to obtain a sample on time was
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c p gaused by not allowin u ufficient time for continaencies_in reaching the sample
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A.]l @hgpistry Section personnel have read and initiale_d a memo describi_ng the cuant 4,nd n its c0JL5?tS.
A procedura has been written and aonroved tn rnrmally address technical sp_edfication surveillances Ed action rannirements which are
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the responTiT1Tity of the Chemistry Section. The procedure includes adequate cautions concerning the critical nature of the time periods associated with technical specification requirements. A memo addressino the eEADt and the ae.itd to consult technical specifications directly will be placed in the Required Readina Book for Licensed Ooerators.
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\ May 24, 1985 NP-85-535 U. S. Nuclear Regulatory Ccmmission Attention: Document Control Desk j
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Washington, D.C. 20555 Gentlemen:
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Reference: Fermi 2 NRC Operating License No. NPF-33 i l Subject: Transmittal of Licensee Event Report No. 85-007 f
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Please find enclosed LER No. 85-007-00, dated May 24, 1985, for a reportable event which occurred on April 24, 1985. As indicated ! below, a copy of this LER is being sent to the Region III office.
l If you have any questions, please contact us.
Sincerely, ,
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R. S. Lenart Superintendent Nuclear Production Enc!csure: NRC Ferms 365, 300A cc: Mr. P.M. Byron Regional Administrator U5NRC Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137
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' U.S. Nuclear Regulatory Commission i May 24, 1985 !
l NP-85-535 i i
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Page 2 i bcc: Approval Control P. P. Acharya j F. E. Agosti H. O. Arora K. J. Brooks W. F. Colbert l J. T. Coleman 0. K. Earle R. R. Eberhardt C. R. Gelletly E. P. Griffing H. F. Hetfner ; W. H. Jens S. J. Latone l J. D. Leman ' T. J. O'Keefe T. D. Phillips J. H. Plona E. R. Preston
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T. Randazzo R. G. Rateick
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L. J. Simpkin G. M. Trahey A. E. Wegele O. K. Earle (Bethesda .0ffice) OSRO Secretary NSRG Secretary NRR Chron File Secretary's Office (2412 WCB) LER File
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' ; - [hehR)ll e4 l Edison l
Date: May 28, 1985 ! RW-85-026 To: S. Veale General Supervisor - Radwaste From: D. Dumas Radwaste Supervisor . Contamination Control Subject: Impact of CRD Rebuild on Radwaste Group Per your request, the following report documents our experience in supporting the CRD Rebuild job in April 1985. This job covered
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a time span of 17 days and required a total commitment of about
.' 1500 man-hours. This commitment impacted the Radwaste sub-groups / sas follows: " '
Materials 30 m-h
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Shipping (Sorting Trash) 80 m-h
/ , Decon 965 m-h g ,8 , '/ Personnel Protection 419 m-h ,
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70TAL 1494 m-h V s The Materials group provided all consumables to the job. A list
/ of these items and quantities are shown in Attachment 1. Addition- , -
ally, the Materials group spent a considerable amount of time in _-- preparing and tracking "E" type requisitions for a breathing air j comoressor, bubble hoods, and vented rainsults. The breathing air compressor was rentea s7ortly aftcr the job began w;.cr. it become evident that we could not keep up with the demand for _ breathing air by refilling bottles at our Bottle Fill Station.
The bubble hoods and rainsults were needed to replenish rne - -- limited quantity (100 each) that were rapidly being consumed on the job.
The Shipping group was involved with sorting trash. It is ! estimated that about 100, forty four gallon, bags of trash were generated over the course of the job. Even though contamination
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! was not present, radiological controls were in effect. Thus, much of the trash was yellow or had tri-blades and needed to be
' segregated from non-yellow trash for disposal. This task was '
further complicated by the fact that during the first few days
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s of the CRD job, reusable protective clothing was indiscriminate 1y
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mixed with trash at the job site.
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a . S. Vaale May 28, 1985 RW-85-026 [e Page 2 The Decon group and the Personnel Protection group were impacted the most by the CRD rebuild job. It was the responsibility of the Decon group to set up the areas, maintain cleanliness, and restore the areas after job completion. The Personnel Protection troup was responsible for providing breat'hi6g air and protective ~
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clothing to the under vessel workers and to provide protective clothing to the CRD workers on the first and third floors.
Attachment 2 is a list of equipment and supplies provided by the Personnel Protection group to support the CRD rebuild job.
With a staff of 5 people, the Personnel Protection group could not cover all of their responsibilities to the CRD job. Further-more, coverage of their routine responsibilities essentially came to a halt. Thus, the Decon group was given the added responsibility of supporting the Personnel Protection group. Of the 965 man-hours provided by the Decon group, 552 of these were in support of Personnel Protection responsibilities. This included 292 man-hours for CRD related support and 260 man-hours te help the Personnel Protection
. group keep up with their normal routines.
Attachment 3 shows the impact, in man-hours per day, that the CRD job had on both the Personnel Protection group and the Decon group. Three modes of work are displayed for comparison. In the first mode, "Before CRD Job", the man-hours shown are for the routines of each group averaged over a seven day period. The second mode, " Bottle Filling", shows daily man-hours for'Ehe'Tirst
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__3 days of the CRD job when we were filling bottles at termi 1 and exchanging them at the dry well access. The third mode, "C65'pr E s s o r" , ' covers a time span of f rom 12 to 14 ifays and stiows dMy~nisn hdurs
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during the remainder of the CRD joD wnen breathing air was supplied by a rented portable breathing air compressor. -- The following is a list of observations and comments:
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p(1. During the Bottle Filling mode, 165 three hundred cubic foot
/ bottles were filled at Fermi 1. These bottles were depleted s at the rate of one every 10 minutes. It takes 15 minutes to N fill a bottle.
2. The Personnel Protection group could have covered all of their responsibilities, both routine and CRD related, with a minimum complement of 10 people working 12 hour shifts. This assumes the use of a compressor as opposed to filling bottles. We can expect the work load, both routine and speciality jobs, of the Personnel Protection group to increase as we move into commercial operation.
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May 28, 1985 y RW-85-026 Page 3 3. Respirator Fit Testing, a responsibility of the Personnel Protection group, requires 2 operators. During the Bottle Filling mode, only 1 operator was available. Thus, John Hale, the Respiratory Protection Specialist, stepped in and assisted. Newer fit test equipment is available that requires only 1 operator and doubles the rate at which people can be tested. Both the Personnel Protection group and the people being tested would benefit by this new equipment.
4. The breathing air compressor required 100 amp service. This
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was only available at a temporary power box on the 1st floor.
Without the availability of station air, a portable compressor is a must for all bubble hood jobs. Without adequate power, a portable compressor will be useless. As the plant warms up, it is likely that bubble hoods will be needed more and
. more to combat heat stress.
N - 5. The Decon Work Force was already working 12 hour shifts before the CRD job began. Thus, their hours were not increased.
As can be seen on Attachment 3, the CRD job significantly impacted Decon routines. Various written comments accurately reported that overall plant cleanliness deteriorated.
DWD/pmc cc: R. Eberhardt J. Bobba R. Andersen H. Higgins Attachments _ _ __.
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Attachmint 1 {
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Meterial Used On CRD J:b - Csneum:bleo
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Item Quantity Duct Tape 31 Rolls, 3" x 60 yards Masking Tape 24 Rolls, 1%" x 60 yards Blank Manila Tags 12 each Yellow Herculite Heavy Duty 1 Roll, 100 yards / roll Yellow Herculite 2 Rolls, 100 yards / roll Masslinn Tool 1 each Masslinn Cloth 16" x 24" 3 Packages, 50 sheets Clear Sleeving 3" w/ Lanyard 4 Rolls, 100' per roll Yellow Sleeving 3" w/ Lanyard 14 Rolls, 100' per roll Rad Rope 2 Rolls, 600' per spool Step Off Pad 4 each Sm. Tool Bag w/ Magenta Strip 10 each Sm. Yellow Bags 20 each Lg. Yellow Bags 1 Roll, 200 each Sm. Clear Bags 6 Rolls, 200 each Lg. Clear Bags 2 Rolls, 200 each Rad Tape: 2" Striped 1 Roll, 60 yards Teri Wipes 1000 each Poly Bottles 2 each, 5 gallon each Filter Assm. for Poly Bottles 2 each ,
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Attochment 2
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Matertair Used on CRD Job - Personnel Protection Group 3 . .:. 600 Feet of Air Hose Line 400 Feet of Communication Line 4 Head Sets - Communicate'
3 Dual 300 Ft Cylinder Push Carts
2 Single 300 Ft Cylinder Push Carts
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10 Scott Air Line check valves 4 - 200-4000 PSI 2 Stage Regulators (3 Tagged Unaafe) 2 Manifold with 5 Hansen Female Quick Disconnects 1 Schrader Male and Female Quick Disconnect 1 Hansen Male Connection 1 Calibrated 0-200 PSI Ashcroft Gauge 11 Scott Pigtails (Used to Interconnect 300 Ft Cylinders) 1 - 100 Ft High Pressure Air Line 37 - 300 Ft Breathing Air Cylinders 1 Eagle Air Systems Air Compressor w/ Purification System 1) Oil Change 3 Gals of Tellus 100 Shell Lubricating Oil 2) Purification Filter Change-Out
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7 - 50ML-03 Filters 3 - 50ML-01 Filters 1 - 50MM-01 Filter 1 Bottle Filling Station - Air Compressor 1 Filter Chenge-Out i i 143 Bubble Hoods 150 Vented Rainsuits 70 X-Large Suits 55 Large Suits 1 25 Small Suits i i .
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Befcre Bottle Work Group Responsibility Job CRD Job Filling Compressor Routines 22.4 4.7 16.9 Respirators Fersonnel CRD 0 56.7 20.7 l l Protection 1 Routines 19.0 0.7 6.0 Laundry CRD 0 0 0
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Routines 0 0 0 . Respirators , Decon CRD 0 48.0 4.3 Routines 0 14.0 16.8
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i t,aundry ' CRD 0 0 7.4 > l . Routines 312.0 210.0 262.6 % l Decon i i CRD 0 40.0 20.9 @ e.
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