ML20100L617

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Tabulation of TMI Worker Exposures by Work & Job Function Jan-Dec 1995
ML20100L617
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 12/31/1995
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20100L599 List:
References
NUDOCS 9603040346
Download: ML20100L617 (16)
v • d • e


Text

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6710-96-2081 TMI-I Annual Repon i

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ATTACHMFNT 1 4

t TABULATION OF TMI WORKER EXPOSURES BY WORK AND JOB FUNCTION i

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JANUARY 1,1995 THROUGH DECEMBER 31,1995 l

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l 9603040346 960228 PDR ADOCK 05000289 R PDR .; .

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I NUMBER OF PERSONNEL AND PERSON REMS SY WORK ANO J05 FUNCTION (INTERNAL

  • EXTERNAL BRD) <

GPU NUCLEAR TM! UNIT 1 l REPORT PERIOD - 01/01/95 TO 12/31/95 l 1

JOS CATEGORY STATION PERSONNEL UTILITY PERSONNEL CONTRACTOR PERSONNEL JOS FUNCTION NUMBER REMS NUMBER REMS NUMBER REMS REACTOR OPERAfl0NS/SURV.

MAINTENANCE PERSONNEL 1D8 1.891 5 .081 90 2.971 OPERATING PERSONNEL 108 11.695 1 .026 0 .000 HEALTH PHYSICS PERSONNEL 70 8.554 4 .356 23 1.658 SUPfRV!30RY PERSONNEL 78 2.566 9 .098 16 .946 ENGtNEERING PERSONNEL 59 1.987 7 .119 7 .178 ADMINSTRATIVE PERSONNEL 89 .961 28 .179 13 .343 ROUTINE MAINTENANCE MAINTENANCE PERSONNEL 139 10.264 14 .255 397 5.182 OPERATING PERSONNEL 59 1.043 3 .001 4 .004 HEALTH PHYSICS PERSONNEL 28 .276 1 .003 6 .033 SUPERVISORY PERSONNEL 79 1.666 4 .002 16 .011 ENGINEERING PERSONNEL 75 .803 13 .059 16 .387 ADMINSTRATIVE PERSONNEL 118 .545 31 .096 21 .059  ;

INSERVICE INSPECTION MAINTENANCE PERSONNEL 31 .883 1 .008 88 2.945 OPERATING PE*SONNEL 6 .101 1 .049 1 .160 NEALTH PHYSICS PERSONNEL 5 .052 0 .000 1 .014

$UPERVISORY PERSONNEL 8 .485 1 .020 1 .013 ENGINEERING PERSONNEL 9 .028 4 .020 1 .104 ADMINSTRATIVE PERSONNEL 11 .614 2 .0 73 2 .012 SPECIAL MAINTENANCE MAINTENANCE PERSONNEL 125 11.874 6 .D89 740 92.543 OPERATING PERSONNEL 59 3.742 0 .000 3 .3 79 HEALTH PHYSICS PERSONNEL 40 3.95 7 1 .327 13 3.855

$UPERVISORY PERSONNEL 47 1.980 2 .084 43 5.557 ENGINEERING PERSONNEL 45 2.263 7 .078 37 5.763 ADMINSTRATIVE PERSONNEL 27 1.599 3 .050 12 .350 WASTE PROCES$!NG MAINTENANCE PERSONNEL 56 1.189 1 .022 61 3.057 OPERATING PERSONNEL 63 8.446 0 .000 1 .127 HEALTH PHYSICS PERSONNEL 34 .624 1 .000 3 .107 30PERVISORY PERSONNEL 25 .960 0 .000 2 .000 ENGINEERING PERSONNEL 8 .010 4 .000 3 .000 ADMINSTRATIVE PERSONNEL 10 .5ET 4 .000 1 .000 REFUELING MAINTENANCE PERSONNEL 91 5.736 1 .004 193 10.478 OPERATING PERSONNEL 85 4.047 0 .000 0 .000 HEALTH PHYSICS PERSONNEL 17 .705 3 .026 5 .232 LOPERVISORY PERSONNEL 25 1.584 2 .020 4 .513 ENGINEERING PERSONNEL 18 .516 4 107 20 2.818 ADMINSTRATIVE PERSONNEL 21 498 3 .122 7 .093

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NUMBER OF PER$0NNEL AND PERSON REMS BY WORK AND JOB FUNCTION i (INTERNAL + EXTERNAL SRD)

GPU NUCLEAR TN! UNIT *1 ,

I REPORT PERIOD - 01/01/95 TO 12/31/95 f

1 JOS CATEGORY STATION PERSONNEL. UTILITY PERSONNEL CONTRA 1 TOR PERSONNEL I JOB FUNCTIDW NUMBER REMS NUMBER REMS NUF3ER REMS

  • TOTAL BY JOS FUNCT!DN
  • MAINTENANCE PERSONNEL 150 31.R37 19 459 835 117.176 i OPERATING PERSONNEL 116 29.074 3 .076 4 .670 i HEALTH PHYSICS PERSONNEL 71 14.168 6 .712 26 5.899 l I

SUPERVISORY PERSONNEL 101 9.241 12 .224 50 7.040 ENGINEERING PERSONNEL 102 5.607 26 .583 57 9.250 i i

ADMINSTRATIVE PERSONNEL 138 4.799 60 .520 29 . 85 7
    • GRAND TOTAL ** 678 94.726 126 2.374 1,001 140.892 i

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NUMBER OF PERSONNEL AND PERSON REMS SY WORK AND JOB FUNCTION (INTERNAL + EXTERNAL SRD)

GPU NUCLEAR TMI UNIT 2 REPORT PERIOD - 01/01/95 TO 12/31/95 JOS CATEGORY STAT!DN PERSONNEL UTILITY PERSONNEL Jos FUNCTION CONTRACTOR PERSONNEL NUMBER REMF NUMBER REMS MUMBER REACTOR OPERATIONS /SURV. REMS MAINTENANCE PERSONNEL 28 .232 OPERATING PERSONNEL 1 .000 15 .002 91 .255 0 .000 0 HEALTH. PHYSICS PERSONNEL 37 .000 466 1 .000 5 .009 SUPERVISORY PERSONNEL 19 .212 0 .000 4 .000 ENGINEERING PERSONNEL 8 .004 1 .000 0 .000 ADMINSTRATIVE PERSONNEL 10 .000 3 .001 2 .000 ROUTINE KAINTENANCE MAINTENANCE PERSONNEL 57 .008 0 .000 5 .000 DPERATING PERSONNEL 6 .000 0 .000 0 .000 HEALTH PHYSICS PERSONNEL 9 .005 0 .000 0 .000 SUPERVISORY PERSONNEL 3 .000 0 .000 0 .000 ENGINEERING PERSONNEL 2 .001 0 .000 0 .000 ADMINSTRATIVE PERSONNEL 1 .000 0 .000 0 .000 INSERVICE INSPECT!DN MAINTENANCE PERSONNEL 4 .343 0 .000 0 .000 OPERATING PERSONNEL 1 .000 0 .000 0 .000 HEALTH PHYSICS PERSONNEL 3 .293 0 .000 0 .000 SUPERVISORY PERSONNEL 2 .093 0 .000 0 .000 SPECIAL MAINTENANCE MAINTENANCE PERSONNEL 8 .000 0 .000 0 .000 OPERATING PERSONNEL 5 .000 0 .000 0 .000 HEALTH PHYSICS PERSONNEL 3 .000 0 .000 0 .000 WASTE PROCES$1NG

. MAINTENANCE PERSONNEL 1 .017 0 .000 1 .000 I OPERATING PERSONNEL 7 .080 0 .000 0 .000 a

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WUMBER OF PERSONNEL AND PERSON RENS SY WORK AND JOS FUNCTION i (INTERNAL

  • EXTERNAL SRD) i:

GPU NUCLEAR TMl UNIT-2 REPORT PERIOD - 01/01/95 To 12/31/95 t

UTILITY PERSONNEL CONTRACTOR PERSONNEL  !

JOS CATEGORY STATION PERSONNEL JOB FUNCTION NUMBER REMS NUMSER REMS NUMBER REMS

  • TOTAL SY JOS FUNCTION
  • MAINTENANCE PERSONNEL 71 .600 1 .000 20 .002 OPERATING PERSONNEL 95 .335 0 .000 0 .000 NEALTN PHYSICS PERSONNEL 39 764 1 .000 5 .009

$UPERVISORT PERSONNEL 22 .305 0 .000 4 .000 ENGINEERING PERSONNEL 10 .005 1 .000 0 .000 ADMINSTRATIVE PERSONNEL 11 .000 3 .001 2 .000

    • GRAND TOTAL ** 268 2.009 6 .001 31 .011 i t

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6710-96-2081

. TMI-l Annual Report. <

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i ATTACHMENT II j i

AIRCRAFT MOVEMENTS AT  !

THE HARRISBURG INTERNATIONAL AIRPORT l i

- JANUARY 1,1995 THROUGH DECEMBER 31,.1995 )

. 1. Total Aircraft Movements - 80,846 l

2. Total number of movements of aircraft larger than 200,000 pounds is estimated to be .

equal to or less than 200. l

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1 NOTE: ' For item 2, this data is based on discussion with the Harrisburg International Airport Tower. The number of movements of aimraft larger than 200,000 pounds is not tracked and -

the number given in this report is consistent with the estimates of prior years. The Harrisburg International Airport Tower is not required to (and does not) record aircraft movements by weight or, plane category.

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6710-96-2081 ~

TMI-I Annual Report' l ATTACHMENT III TECIINICAL' SPECIFICATION 6.9.1.B.3 PERIODIC LEAK REDUCTION PROGRAM TEST RESULTS The results of the TMI-l 1995 periodic leak Reduction Program Tests which included visual inspections are summarized in Table 1. The results of the TMI-1 1995 local leakrate tests are summarized in Table 2.

These tests were performed in accordance with the referenced procedures.

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TABLE 1 1995 LEAK REDUCTION PROGRAM TEST RESULTS FOR TMI I

LEAK RATE SURVEILLANCE DATE OF LEAKING (ml/ min) MAINTENANCE PROCEDURES PERFORMANCE COMPONENT UNDERTAKFN I.D. AS AS (see Note 1)

FOUND LEFT 1303-11.16 10-1-95 None 0 0 l None l 1303-11.27 9 1-95 None 0 0 l None l 1303-11.28 11-20-95 None 0 0 l None l 1303-11.29  !!-14-95 None 0 0 l None l 1303-11.30 11-30-95 PI-I103 20 0 l Tightened fitting l 1303-11.31 10-8-95' FT-1 2 2 l None l 1303-11.32 7 1-95 None 0 0 l None l 1303-11.50 11-8-85 None 0 0 None TOTAL LEAKAGE IN 1995 22 2 e

L 6710-96-2081 lIMI-l Annual Repott ATT'ACHMENT III (continued)

TABLE 2 1995 LOCAL LEAK RATE TEST RESULTS FOR TMI-1 SURVEILLANCE DATE OF LEAKING LEAK RATE MAINTENANCE PROCEDURES PERFORMANCE COMPONENT (scem) UNDERTAKEN (see Note 1) 1.D.

AS AS FOUND LEFT 1303-11.18 Various see Note 2 36934 (max) 30426 (max) see Note 2 16993 (min) 16986 (min)

Note 1: 1303-11.16, " Decay Heat Removal System leakage" 1303-11.18, "RB Local leakrate Testing" 1303-11.27, " Makeup and Purification Ieakage Check" 1303-11.28, " Liquid Waste System Leak Check" 1303-11.29, " Waste Gas Disposal System I.eak Check" 1303-11.30, " Reactor Coolant Sampling Leakage Check" 1303-11.31, " Hydrogen Recombiner System leak Check" 1303-11.32, "MU Pump Discharge and Ietdown Ieak Check" 1303-11.50, " Reactor Building Spray System Ieakage Check"

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Note 2: CA-V5A/5B Cleaned and capped valve disk CF-V20A Replaced packing CF-V20B Replaced valve body CM V4 Adjusted operator

6710-96-2081 TMI-l Annual Report ATTACHMENT IV PRESSURIZER POWER OPERATED RELIEF VALVE AND PRESSURIZER SAFETY .

VALVE CHAY.IRNGES IN 1995 Them were no pressurizer power operated relief valve or pressurizer safety valve challenges during 1995 in response to plant transients.

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6710-96-2081 l

.TMI-l Annual Report  ;

ATTACHMENT V RESULTS OF SPECIFIC ACTIVITY ANALYSIS-PRIMARY COOLANT SYSTEM ,

l Technical Specification 6.9.1.B.5 requires certain information regarxiing the results of specific activity analyses in which the primary coolant exceeded the limits of Technical ,

Specification 3.1.4.1. Table 1 contains: a) the reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; b) the results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of the analysis while the limit 1 was exceeded, and results of (at least) one analysis after radioiodine activity was reduced to i less than the limit; c) the cleanup system (letdown) flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the j first sample in which the limit was exceeded; and d) the time duration when the specific j activity of the primary coolant exceeded the radioiodine limit. Figure 1 contains a graph of l 1

the dose equivalent I-131 concentration for 1995. Figures 2a through 2c contain graphs of the I-131 concentration, the I-133 concentration, and the dose equivalent I-131 concentration as a function of time for the duration of the specific activity above the steady-state level.

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TABLE 1 4

.1991NE DATA FOR 1995 ANNUAL REPORT I RADIOIODINE CONCENTRATION (uCi/am) j SAMPLE POWER LETDOWN DOSE EQ 1

DATE IlME 11EP.1 1.9EMI hill E112 1.111 hild 1-111 I-f31*

4 09/06/95 0730 100 52 0.0380 0.1010 0.0993 0.1200 0.1110 0.0798 4

09/07/95 0730 100 52 0.0351 0.0943 0.0904 0.1170 0.1040 0.0736 i

l 09/08/95 0800 100 52 0.0432 0.1140 0.1130 0.1350 0.1280 0.0909 09/04/95 2330 0 52 2.1500 0.8770' 1.7400 0.0400 0.8010 2.7200 09/09/95 0330 0 52 1.8000 0.4860 1.3100 - 0.4410 2.2100

, 09/09/95 ~ 0700 0 54 1.3700 0.3050 0.9100 - 0.2290 1.6400 09/09/95 1100 0 70 - - - - - 1.3700 f 09/09/95 1500 0 66 0.9550 0.1210 0.8100 - 0.0803 1.1000 l

1 09/09/95 1900 0 68 0.M90 0.0897 0.4130 - 0.0448 0.9880 09/09/95 2300 0 68 0.8030 0.0715 0.3330 - 0.0313 0.8980 f

09/10/95 0715 0 75 0.4230 0.0344 0.1420 - 0.0047 0.4630

  • Time duration where the 1.0 uCilgm limit was exceeded = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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l_ 6710-96-2081 l TMI-1 Annual Repon i

ATTACHMENT 6 MAJOR CHANGES TO RAD WASTE TREATMENT SYSTEMS

} In 1995, GPU Nuclear completed the majority of the modifications of the TMI-l liquid waste disposal system that will enhance the system capability to reduce the amount of radioactivity released into the envimnment by improving the capability to polish effluent from the TMI-l Miscellaneous Waste Evaporator. Additional tank stoage and pmcessing capability are available 4 utilizing a newly modified liquid rad waste processing system installed in the Chemical Cleaning Building. Attached for your information are the safety evaluation of this plant modification l (Attachment 1, GPU Nuclear Safety Evaluation SE 115302-052) and the modification design document (MDD-TI-232-B DIV1/2, Rev. 2, dated May 25,1995) l The evaluation that determined the modification of the TMI-1 liquid rad waste disposal system did not pose an unreviewed safety question and was consistent with existing Technical

Specifications is contained in Attachment 1. In summary, the change is acceptable because the use of the Chemical Cleaning Building does not increase the pmbability or consequences of a leak of liquid radwaste into the environment and, with the exception of the release point, does i not interface with any other safety related portions of the plant.

1 Attachment 2 pmvides sufficient detailed information to totally support the reason for the change.

4 Attachment 1, Sections 2 and 3 and Attachment 2, in its entirety, provide a detailed description of the equipment, components and processes involved and the interfaces with other plant

systems.

As stated in Attachment 1, Section 3.5, the modification will provide the ability to decrease the releases of radioactive materials in liquid effluents. 'Iherefore, the amount of radioactive materials released via liquid effluents will continue to meet the limits of NPDES permit and Technical Specifications.

Attachment 1, Sections 3.5, 3.6, 3.8 and 3.10 conclusively demonstate that the expected

. maximum exposures to individuals in the unrestricted area and to the general population will not differ from those previously estimated in the license application and amendments thereto.

l 4 Attachment 1, Sections 3.5, 3.6, 3.8 and 3.10 discusses piedicted releases of radioactive  !

materials resulting from the change. As previously stated, the modification will not result in any l l increase in liquid effluents to be released to the environment. Actual quantitative data is not available at this time because there has not been an annual radiological effluent report since the completion of the modification and there can be varying levels of effluent reduction depending on the system configuration.  :

An estimate of the exposures of plant operating personnel as a result of the modification has determined that there'will be no significant change in the total annual exposure to operating personnel. (Reference TMI-l Radiological Controls memorandum 6610-96-0051)

Attachment 1 is documentation of the fact that the change was reviewed and approved in accordance with Section 6.5.1 of the TMI-1 Technical Specifications.

6710-96-2081 TMI-1 Annual Repod [

ATTACHMENT 1 TO ATTACHMENT 6  !

i SAFETY EVALUATION SE-115302-052 i l

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