ML20064C744
| ML20064C744 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 02/24/1994 |
| From: | Broughton T GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C311-94-2026, NUDOCS 9403100194 | |
| Download: ML20064C744 (16) | |
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l GPU Nuclear Corporation Nuclear b .2. an::gr*
Middletown, Pennsylvania 17057-0480 (717) 944-7621 Writer's Direct Dial Number:
(717) 948-8005 February 24, 1994 C311-94-2026 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Dear Sir:
Subject:
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50, i
Docket No. 50-289 l 1993 Technical Specifications Section 6 Annual Report Attached is the 1993 Technical Specifications Section 6 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.2 through 6.9.1.B.5 and 6.17 of the TMI-1 Technical Specifications (T.S.). The attachments to this letter contain the following information:
Attachment I - Aircraft Movement Data from the Harrisburg International Airport for the Calendar Year 1993 (per T.S. Section 6.9.1.B.2).
Attachment II - Leak Reduction Program Test Information for the Calendar Year 1993 (per T.S. 6.9.1.B.3).
Attachment III - Pressurizer Power Operated Relief Valve and Pressurizer Safety Valve Challenges for the Calendar Year 1992 (per '
l T.S. Section 6.9.1.B.4).
Attachment IV - Results of Specific Activity Analysis - Primary Coolant System (per T.S. Section 6.9.1.B.5).
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l 9403100194 940224 PDR ADOCK 05000289 PDR
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R GPU Nuclear Corporation is a subsidiary of General Public Utilities Corporation
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C311-94'-2026 Page 2 Attachment V - Major Changes to Radioactive Waste Treatment Systems (per T.S. Section 6.17).
Sincerely,
. klfw T.G.Brouhon Vice President and Director, TMI DVH/ emf Attachments cc: Region I Administrator TMI-1 Senior Project Manager TMI Senior Resident Inspector l
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C311-94-2026 ATTACHMENT I AIRCRAFT MOVEMENTS AT THE l l HARRISBURG INTERNATIONAL AIRPORT JANUARY 1 THROUGH DECEMBER 31, 1993 1
- 1. Total Aircraft Movements = 85,251 1
- 2. Total number of movements of aircraft larger than 200,000 pounds is ,
estimated to be less than 200. ,
NOTE: For Item 2, the data is based on estimates provided by the Capital City Airport Tower. This facility is responsible for tracking Harrisburg International Airport flights. The tower is not required to (and does not) record flights by weight or plane category.
The total number of movements (200) is 0.2% of the total movements.
This compares to the TMI-1 FSAR assumption of 3%.
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l C311-94-2026 ATTACHMENT II Annual Report Regarding the Periodic Leak Reduction Program Tests (T.S.
6.9.1.B.3).
Table I summarizes the results of the Leak Reduction Program tests and- i inspections, by procedure number, that were performed between January 1 and >
December 31, 1993. Component identification of those components found to be 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 the as found condition to an acceptable level.
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C311-94-2026 ATTACHf!ENT II
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TABLE 1 l 4 1993 LEAK REDUCTION PROGRAM TEST RESULTS FOR TMI l l SURVEILLANCE DATE OF LEAKING LEAK RATE MAINTENANCE PROCEDURES PERFORMANCE COMPONENT l.D. mVmin UNDERTAKEN ASFOUND AS LEFT l 1303-11.16 10-1 93 DH-V158 0.02 0.02 l WR#772978 submitted to l l tighten packing l 1303 11.27 9-1-93 MU-P1B SEAL 1 1 l JO# 70882 submitted to l l repair seal l l 1303-11.28 12 3-92 0 0 l l l 1303 11.29 6-9-93 0 0 l l 1303-11.30 1-16-93 CA-V323 0.13 0.13 JO# 68357 submitted to l
repair seat leakage 1303-11.31 10-11-93 0 0 l l 1303-11.50 1-22-93 BS-V1B 2 2 JO#69762 submitted to tighten packing l
TOTAL LEAKAGE IN 1993 3.15 3.15 TABLE 2 1993 LOCAL LEAKRATE TEST RESULTS FOR TMl SURVEILLANCE DATE OF LEAKING LEAK RATE MAINTENANCE l PROCEDURES PERFORMANCE COMPONENT l.D. seem UNDERTAKEN i
- l AS FOUND AS LEFT maxpath/minpath ' maxpath/minpath 1303-11.18 various see note 1 61379 (max) 61379 (max) see note 1 9650 (min) 9844 (min) 1303-11.16 DECAY HEAT REMOVAL SYCTEM LEAKAGE 1303-11.18 RB LOCAL LEAKRATE TESTING 1303-11.27 MAKEUP AND PURIFICATION LEAKAGE CHECK 1303-11.28 LIQUID WASTE SYSTEM LEAK CHECK 1303-11.29 WASTE GAS DISPOSAL SYSTEM LEAK CHECK i 1303-11.30 REACTOR COOLANT SAMPLING LEAKAGE CHECK l 1303-11.31 HYDROGEN RECOMBINER SYSTEM LEAK CHECK 1303-11.50 REACTOR BUILDING SPRAY SYSTEM LEAKAGE CHECK The two hour site boundary and 30 day low population zone off-site dose conddions were not limiting conditions for acceptable leakage criteria in 1993. All"AS-FOUND" or "AS-LEFT'Isakage recorded did not significantry increase the magnitude of either on-site or o'f-site releases during 1993.
l Per TMI Technical Specification 4.4.1 total leakage less than 104,846 sccm is considered acceptable for as-left leakage l condition. J Note 1:
i Equipment Hatch equalizing valve and inner door seal were replaced. l l
Equipment Hatch and Personnel Hatch door handwheel packing was adjusted.
CA-V2 "AS-FOUND" AND "AS-LEFT" seat leakage for 1993 was 38527 scem. In February 0f1994 the valve was replaced and the new seat leakage was zero. This new leakage will be factored in with the 1994 leakrate results.
RB Closed Cooling Water Piping "AS-FOUND" leakage was 19893 seem and will be repaired during next 11 R Outage. l l
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ATTACHMENT III l
Pressurizer Power Operated Relief Valve and Pressurizer Safety Valve Challenges l for Calendar Year 1993. l There were n_o pressurizer power operated relief valve or pressurizer safety valve challenges during 1993 in response to plant transients.
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C311-94-2026 ATTACHMENT IV l
RESULTS OF SPECIFIC ACTIVITY ANALYSIS -
PRIMARY COOLANT SYSTEM
! Technical Specification 6.9.1.B.5 requires certain information regarding the
! results of specific activity analyses in which the primary coolant exceeded 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 radiciodine performed prior to exceeding the limit, results of the analysis while the limit was exceeded, and results of (at least) one analysis after radiciodine activity was reduced to 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 first sample in which the limit was exceeded; and d) the time duration when the specific activity of the primary coolant exceeded the radiciodine limit. Figure 1 contains a graph of the dose equivalent I-131 i
concentration for 1993. Figures 2a through 2f contain graphs of the I-131 l concentration, the I-133 concentration, and the dose equivalent I-131 l concentration as a function of time for the duration of the specific activity l above the steady-state level.
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ATTACHMENT IV TABLE 1 IODINE DATA FOR 1993 ANNUAL REPORT RADIOIODINE CONCENTRATION (pCi/gm) l SAMPLE POWER LETDOWN DOSE Eq*
DATE TIME (%FP) (GPM) I-131 I-132 I-133 I-134 I-135 I-131 03/10/93 820 100.0 53 0.01040 0.0378 0.0342 0.0743 0.0440 0.026 03/12/93 545 0.0 62 2.46000 1.2100 2.2600 0.0932 1.1300 3.210 03/12/93 800 0.0 62 2.44000 1.0400 2.0700 ---
0.8980 3.110 03/12/93 1140 0.0 62 2.27000 0.8540 1.7100 ---
0.5670 2.810 03/12/93 1530 0.0 62 1.91000 0.7420 1.2900 ---
0.3450 2.310 l 1
03/12/93 1930 0.0 62 1.63000 0.6650 0.9200 ---
0.1770 1.910 03/12/93 2330 0.0 62 1.24000 0.5310 0.6680 ---
0.0985 1.450 03/13/93 330 0.0 62 1.05000 0.5090 0.5060 ---
0.0522 1.210 03/13/93 730 0.0 62 0.89500 0.4870 0.3800 ---
0.0316 1.020 03/13/93 1130 0.0 62 0.74400 0.4380 0.2810 ---
0.0196 0.837
- Tin.s tration where 1.0 pCi/ml was exceeded = 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> RADIOIODINE CONCENTRATION (pCi/gm)
SAMPLE POWER LETDOWN DOSE Eq* !
DATE TIME (%FP) (GPM) I-131 I-132 I-133 I-134 I-135 I-131 l
t 09/08/93 730 50.0 FJ 0.04740 0.0397 0.0441 0.0415 0.0382 0.065 l I 09/09/93 725 50.0 53 0.04950 0.0362 0.0395 0.0456 0.0360 0.065 l
l 09/10/93 800 50.0 53 0.05070 0.0384 0.0403 0.0509 0.0350 0.067
{ 09/10/93 1936 0.0 53 1.100 0.561 0.680 0.0976 ---
1.31 09/10/93 2020 0.0 53 1.50000 0.6210 0.9530 0.0750 0.5390 1.83 09/10/63 2206 0.0 53 1.76 0.635 0.987 0.0288 0.557 2.100
! 09/11/93 200 0.0 47 2.27 0.507 1.23 ---
0.482 2.660 09/11/93 530 0.0 43 1.96 0.257 0.959 ---
0.289 2.250
( 09/11/93 900 0.0 70 1.45 0.126 0.651 ---
0.155 1.640 09/11/93 1300 0.0 70 1.35 0.0828 0.506 ---
0.0840 1.490 09/11/93 1700 0.0 60 1.23 0.0862 0.427 ---
0.0557 1.350 09/11/93 2100 0.0 61 0.94200 0.0460 0.2860 ---
0.03490 1.020 09/12/93 100 0.0 66 --- --- --- --- ---
0.816
- Time duration where the 1.0 pC1/ml limit was exceeded = 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> TOTAL TIME = 57 hours6.597222e-4 days <br />0.0158 hours <br />9.424603e-5 weeks <br />2.16885e-5 months <br /> for 1993 l
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[ S C311-94-2026 ATTACHMENT V Technical Specification Section 6.17 requires reporting of " Major Changes to :
Radioactive Waste Treatment Systems." Major changes are interpreted to mean changes that would alter how the system functions or the predicted releases that l were previously analyzed, i
l Based on the above, no major changes were made during 1993.
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