ML20147D182

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Personnel Exposure Rept for CY87
ML20147D182
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 12/31/1987
From: Hukill H
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
C311-88-2010, NUDOCS 8803030254
Download: ML20147D182 (12)


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-->_ y REPORT---PERIOD DATE O 2 / ft / S S

,s gy NUMSER OF PERSONNEL AND MAN REMS SY NORK AND JOS TJNCTION OMIT s 01/01/87 - 12/31/87 PAGE 1

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OVJ - CONTRACTOR PERSONNEL O UR JOS CATEGORY STATION PERSONNEL UTILITY PERSONNEL NUMSER REMS NUMBER REMS NUMBER RENS +

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MAINTENANCE. PERSONNEL 2 .004 b- 3 O N) OPERATING-adRSONNEL ES 14 . 7' r 20.954 3 .005 9 C7CK4 NEALYN PNiSICS PERSONNEL 39 5 036 6 .614

- O M od SUPERVISORY PERSONNEL SL 5.171 77 3.osa 13 065 26 . 099 Om LNGINE E N E .4G PENbONNLL 431 9 .006 28 .1?9 4 ADMINSTRATIVE PERSONNEL Bs ROUTINE MAINTEN4NCE MAINTENANCE PERSONNEL 150 L23.572 O 000 111 3.405 29 .124 1 000 3 035

- ' OPERATING PERSONNEL .008 5 048 S.. NEALTH PNVSICS PERSONNEL 33 1.010 1 .

37 1.247 0 .000 6 025

$UPERWISORY PERSONNEL 433 6 .029 24 .679 ENGINEERING PERSONNEL 34 ADMINSTRATIVE PERSONNEL 32 .150 3 .002 15 . 131 INSERw1CE INSPECTION MAINTENANCE PERSONNEL 94 .719 1 .000 46 3.234 s 17 .339 3 010 4 .274 OPERATING PERSONNEL 7 017 0 000 1 .010 NEALYN PNVSICS PERSONNEL 786 2 .012 to .024 SUPERVISORY PERSONNEL 52 ENGINEERING PERSONNEL 55 .867 IS 042 38 2.136 ADMINSTRATIVE PERSONNEL se .479 12 .021 21 .549

- SmECIAL MAINTENANCE MAINTENANCE PERSONNEL 132 S.243 0 .000 413 43.002

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OPERATIN4 JERSONNEL 30 1.500 0 000 2 .006 NEALTH PN)&ICS PERSONNEL 19 472 0 000. 1 .055 41 .854 1 .000 17 .790

$UPERv!$ORf PERSONNEL 43 1.076 12 .142 42 1.204 -_g EMGINEERING PERSONNEL " _ .S.2 0 .000 15 1.613 ADMINSTRATIVE PERSONNEL IS v

NASTE *ROCESSING MAINTENANCE PERSONNEL 81 2.763 O. .000 27 .028 OPERATING PERSONNEL 44 11.024 *O- .000 3 .547 NEALTN PHYSICS PERSONNEL 45 945 0 000 15 .004 .

14 .611 O .000 3 .000 SUPERw1 SORT PERSONNEL 9 .157 1 000 3 .000 M-ENGTNEERING PERSONNEL .007 0 .000 2 .001 1 ADMINSTRATIVE PERSONNEL 9 ,,,

RE5wCLING MAINTENANCE PERSONNEL 47 4.919 0 .000 2 .014 OPERATING PERSONNEL SO 2.474 0 .000 1 .006 NEALTH PNYSICS PERSONNEL 3 .061 0 .000 O "

.000 SUPEpw1SONV P E N S ONNEL - 22 2.386 2 .002 _. O . .000 ENGINEERING PERSONNEL 7 .288 7 .071 2: .075 ADMINSTRATIWC PERSONNEL S .241 1 .002 4

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3f's FUNCTION REPORT---PEDIOD DATE O2/12/88 NU>SER OF PERSONNEL Ala ". MAN REWS SV NORK .*ND UNIT 1 . 91/01/87 .32/31/87 .PAGL,. 2 .

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s STATION PERSONNEL UTILITY FERSONNEL CONTRACTOR PERSONNEL -

' .Y 300 CATEGORY NUNGER REMS MUNSER REMS MUMSER REMS JOS F C'MC T L*JN *

  • TOTAL MV JOS FbMCTION * ,

. <j 196 41.344 1 .040 434 4%.727 -

MAINTENAhCE PERSONNEL 106 29.950 4 -C14 S *-87a t OPERATInt PERSONNEL 95 23.459 4 033 25 ,1-5 HEALTH *MYCICS PER$ONNEL ROS 11.555 9 .05u 22 ' .E03 ,.m SUPERWi&ORY P.250NNEL 94 e.449 ai d 349 's~ a -J.192 . 4 E N G 3 04E L R I Nte PER6UhNEL 2.180 20 .031 50 .2.457

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q ADMINSTRATFYE PERSONNEL 121 720 114.967 82 457 597 58.268 -

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t ATTACHMENT II AIRCRAFT MOVEMENTS AT THE HARRISBURG INTERNATIONAL AIRPORT JANUARY l THROUGH DECEMBER 31, 1987

1. Total Aircraft Movements = .166,622
2. Total Number of Movements of Aircraft Larger Than 200,000 Pounds is Less Than 50 b

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ATTACHMENT III Page 1 of 4 Annual Report Regarding the Periodic Leak Reduction Program Tests (T.S. 6.9.1.B.3)

J Table I summarizes the results of the Leak Reduction Program tests and inspections by procedure number that were performed between January 1 and December 31, 1987. Component identification of those components found to be t leaking and the type of repair (if required) are included in Table I. Leaking components were repaired and retested such that the leakage was reduced from as found.

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ATTACHMENT III Page 2 of'4 TABLE NO. 1 3310-88-0027 1987 LE M REDUCTION PROGRAM TEST RESULTS FOR TMI-1 ,

l l DATE OF l LEMING l LE M RATE l l .

lSURVEILLMCE PROCEDURE l PERf00NWGCE l COMPONENT I.D. l AS FOLND l AS LEFT l NAINTEMMCE tseERTMEN l I I I I I I I l1303-11.16 Decay Heat l 01/28/87 l DH-V-15A i 120 ml/Hr l 12 ml/Hr l Packing Tightening l l Removal System Leakage l 1 l 1 I l l l l l l l l l130F11.18R.B. Local l See Note 1 l See Note 1 l >162105 SC01 1 29906 SCCM lSeeNote1 l lRateTesting l l 1 l l l l 1 1 I I I I l1303-11.27 Nakeup and l l E P-1A l351ml/hr l 351 al/hr l Expected to be Worked Durir:q l l Purification System l See Note 3 l Inboard Seal i I l 7R Outage l lLeakageCheck l l l l l l l l l M V-688 l 75 ml/hr l 75 ml/hr l Expected to be Worked During l l 1 1 I I I7ROutage l l l 1 l l 1 I l l l PS)-P-1 A l222al/hr l Zero lRepairedFlange l l I 1 Discharge I i i I l l 1 Orain Flange l l l l 1 1 I I I I I l l l PtJ-P-1A l 6 ml/hr l 6 al/hr lNoRepair,SeeNote4 l l l l Outboard Seal i I l l l l l l 1 I I l l l M P-1C l51al/hr l 51 ml/hr lNoRepair,SeeNote4 l l l 1 Inboard Seal l l l l 1 I I I I I I l l l M P-1C l24al/hr l 24 ml/hr lNoRepair,SeeNote4 l l l 1 Outboard Seal i I I I l l l l l l 1 l l 1 h v-898 1 12 ml/hr l Zero lReplacedPipePlugon l l l l l l l sonnet / Repacked I l l 1 1 I I I l l l M V-196A l6ml/hr l Zero lRepackedValve 1 l l l l l l 1 l l l MU-V-1978 l3ml/hr l Zero lRepackedValve l l l 1 1 1 1 I l l l MU-V-2298 l 12 ml/hr l Zero l Installed Pipe Cap on l l 1 ', l l lteakoffNipple l l 1 1 I I I I er

ATTAClif1 Erit III Page 3 of- 4 TABLE ND. 1 (Continued) 3313-88-0027 1987 LEAK REDUCTION PROGAAM TEST RfSULTS FOR TMI-1 l l DATE OF l LEAKING l LEAK RATE l l .

lSURVEILtMcCE PROCEDURE l PERFOInteCE ICOMPONENT I.D. l AS F0tDe l AS 1 EFT l MAINTENANCE tmDERTAKEN l 1 1 I I I l l l 1303-11.28 Liquid W ete l 04/30/87 l N/A lZero l Zero lN/A l lSystemteakCheck I I I I I I I I l l l I 1 l1303-11.29 m ete Gas 1 01/24/07 l Delay Tank l 142 Scot i Zero l Tightened Manway l l Disposal System Leak l l Manmay I l l l I mak I i l I I I l l l tef5T Tube l 99 SCOT l Zero l Tightened rittituj l l 1 I ritting I l l l l l l 1 l i I l 1303-11.30 Reactor Cool- l 04/21/87 l Ca-V-25C l96al/Hr l 36 ml/Hr lReplacedStemand l l ant S g ling Leakage l l l l l Packing l l Check l l l l l l l l l CA-Y-31A l20ml/Hr l 10 ml/Hr lAdjustedPacking l l 1 I l l 1 l l l l CA-PI-5 l120ml/Hr l Zero l Replaced Packing l 1 1 I I I I I l l l fitt bg Hear l10ml/Hr l 10 ml/Hr lAdjustedPacking l l 1 i Ca-v-31A/s i I I I I I I I I I i l1303-11.31 Hydrogen l See Note 2 l l l l l 1 Recominer Sy.te. teak l l l 1 l 1 1 0-ck i i i i l I l l i i i I l l 130.1-11.50 Reactor l 05/04/87 l N/A lZero l Zero lM/A l l Building Spray System l l l l l l lteaka,eCheck I l 1 I I I

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The tmG "AS-LETT" Systems gaseous leakage was O SCOT. As-Found esas 241 Scot. .

The LtRT "AS LEfI" gaseous leakage was 29906 S000. As-Found was > 162105 SC09 - See Note 5. '

{ The total "AS LEFT" 1 squid leakage esas 575 al/Hr. As-Fourut was 1128 al/hr.

I The two hour site boundary and 30 day low population zone offsite dose considerations were not limiting ccnditions for acceptable leakage criteria in 1987 All "AS Fonse" or "AS LEFT" leakage recorded did not significantly increase the magnitude of either on or off-site releases during 1987.

MIL 1: The valve leak testing occurred on various dates during 1967 Repairs were performed on the following components due to higher than desirable leakage:

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1. IC-V-3 new type valve installed.
2. IC-V-4 new type valve installed.
3. PP-V-101/102/133/134 seat repaire done.
4. fel-V-2A stem packing leakage repair.
5. MS-V-35 rebuilt valwe.
6. CA-V-SA lapped seats.
7. C& V-58 rebuilt valve.

S. MFV-15 seats ti$tened due to leakage during fourth spaarter.

9. MFV-19 seats tightened due to leakage during fourth apaarter.

Per TMI-1 T.S. 4.4.1, total local leakage less than 104,846 SC01 is considered acceptable for the AS-LEFT condition.

PEHE 2: Surveillance was last performed in 1996 during the 6R outage. Not required to be perfogued until 1988 during /R Outage pe)TE 3: "As Found" data was perfogued and reported in the 1986 annual report. Neuever "As Lef t" data esas not completed until 1987, because plant conditions during the 6R outage in 1906 did not permit aligning the makeup and purification system, solely for the' purpsee of completing the test prior to 1987. This report contains the "As Lef t" data and maintenance undertaken ediich was not '

included in the 1986 annual report.

MDTE 4: Considered relatively minor leakage. An attempt to repair this leakage is not justifiable in tetus of manpower needed. Other more critical outage esork emas resguired to be completed on plant componente during 6R outage. The minimal potential for significant ieprovement in M system leakage did not emarrant the replacement of peep eeals at this time.

M IE 5: Per the "MIM PATH" method of calculating leakage the As-found LLRT Leakage esas 67426 SCOT. The "MAX PATH" method assumes for two walves in series that the one with lower leakage has failed to close post accident. "MIM PATH" asmanes the opposite.

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ATTACHMENT IV -

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l Pressurizer Power Operated Relief Yalve and Pressurizer Safety Valve i Challenges for Calendar Year 1987.  :

There were no pressurizer power operated relief valve or pressurizer safety valve challiiiges which occurred during 1987.

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1 ATTACHMENT y Page 1 of 2 ,

RESULTS OF SPECIFIC ACT!YITY ANALYSIS -

PRIMARY COOLANT SYSTEM c

i Technical Specification 6.9.1.B.5 requires certain information regarding the 4

results of specific activity analysis in which the primary coolant exceeded

! limits of Technical Specification 3.1.4.1. These limits were not exceeded in 1 987. The following page is a graph of the 1987 Dose Equivalent Iodine which shows the values to be less than 1 taci/ml.

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1987 DOSE E001VAIINE ICDINE -

1/ 1/87 TO 12/31/87 o - 00SEI N

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s l ATTACHMENT VI Technical Specification Section 6.17 requires reporting of "Major Changes to Radioactive Waste Treatment Systems." Major changes are interpreted to mean changes that would :hange how the system functions or changes the predicted releases that were previously analyzed.

Based on the above, no major changes were made during 1987.

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r G a Nuolear Cn"n"a:rar" Route 441 South Middle wn, Pennsylvania 17057 0191 TELEX 84 2386 February 29, iger's Dirnt Olal Nurnber:

C311-88-2019 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Dear Sir:

Three Mile Island Nuclear Station, Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 1987 Annual Report Attached is the 1987 Annual Report for Three Mile Island Nuclear Station, Unit 1 (TMI-1). This report is being submitted in accordance with Section 6.9.1.B and 6.17 of the TMI-1 Technical Specifications (T.S.). The attachmnts to this letter contain the following information:

Attachment I - Tabulation of Personnel Exposure Data for the calendar year 1987 (per T.S. Section 6.9.1.B.1).

Attachment II - Aircraf t Movement Data from the Harrisburg International Airport for the calendar year 1987 (per T.S. Section 6.9.1.B.2).

Attachmnt III - Leak Reduction Program Test Information for the calendar year 1987 (per T.S. Section 6.9.1.B.3).

Attachment IV - Pressurizer Power Operated Relief Yalve and Pressurizer Safety Valve Challenges for the calendar year 1987 (per T.S. Section 6.9.1.B.4).

Attachment V - Results of Specific Activity Analysis -

Primary Coolant System (per T.S. Section 6.9.1.B 5).

Attachment VI - Major Changes to Radioactive Waste Treatment Systems (per T.S. Section 6.17).

Sincerely, f hk &

H. D. Hudill Vice President & Director, THI-1 HDH/DVH/spb:1113A cc: W. Russell R. Conte gP Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

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