ML20033E318
| ML20033E318 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/31/1989 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C311-90-2017, NUDOCS 9003120279 | |
| Download: ML20033E318 (15) | |
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,To OPU Nucloer Corporation S MJ Nuclear
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Middletown Pennsylvania 170$7 0191 717 944 7621 TELEX 84 2386 Writer's Direct Olal Number:
March 1, 1990 C311-90-2017 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 1989 Annual Report Attached is the 1989 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 attachments to this letter contain the following information:
Attachment I Tabulation of Personnel Exposure Data for the calendar year 1989 (per T.S. Section 6.9.1.B.1).
Attachment II Aircraft Movement Data from the Harrisburg International Airport for the calendar year 1989 (per T.S. Section 6.9.1.B.2).
Attachment III -
Leak Reduction Program Test Information for the calendar year 1989 (per T.S. Section 6.9.1.B.3).
Attachment IV Pressurizer Power Operated Relief Valve and Pressurizer Safety Valve Challenges for the calendar year 1989 (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).
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GPU ' Nuclear Corporation is a subsidiary of the General Public Utilities Corporation I
DR DC 89 R
C311-90-2017 March 1, 1990 l
Attachment VI Major Changes to Radioactive Waste Treatment Systems (per T.S. Section 6.17).
f Sincerely, wW H. D. Hukill Vice President & Director, TMl-1 HDH/DVH/spb:2017 cc:
W. Russell R. Hernan F. Young Attachments I
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l ATTACHMENT II AIRCRAFT MOVEMENTS AT THE HARRISBURG INTERNATIONAL AIRPORT JANUARY 1 THROUGH DECEMBER 31, 1969 1.
Total Aircraft Movements 144,280
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Total Number of Movements of Aircraft Larger Than 200,000 Pounds is Estimated Less Than 220.
NOTE: For Item 2, the data is based on estimates provided by the Capital City Airport Tower who are responsible for Tracking Harrisburg International Airport flights.
The tower is not required to (and do not) record flights by weight or plant category. The increase in number of movements from 1988 to 1989 is attributed to a United Parcel Service Flight which started in October 1989.
The total number of movements (220) is less than.20% of the total movements. This compares to the TMI-1 FSAR assumption of 3%.
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ATTACHMENT 111 Page 1 of 4 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 inspections by procedure number that were performed between January 1 and December 31, 1989.
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 as found.
The two hour site boundary and 30 day low population zone off-site dose considerations were not limiting conditions for acceptable leakage criteria in 1989. All "AS-FOUND" or "AS-LEFT" leakage recorded did not significantly increase the magnitude of either on-site or off-site releases during 1989.
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Page 4 of 4 ATTACHMENT III TABLE 1 (CONTINUED)
NOTE 1:
The Surveillance was last performed in 1988 during the 7R Outage.
Not requited to be performed until 1990 during the SR Outage.
NOTE 2:
Partial performance during 1989.
NOTE 3:
Per the " MIN PATH" method of calculating leakage the As-Found LLRT Leakage was 18483 SCCM. The " MAX PATH" method assumes for two valves in series that the one with lower leakage has failed to close post accident.
" MIN PATH" assumes the opposite.
NOTE 4:
Per TM1-1 Tech. Spec. 4.4.1, total leakage less than 104,846 SCCM is considered acceptable for the as-left leakage condition.
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Page 1 of 4 ATTACHMENT V RESULTS OF SPECIFIC ACTIVITY ANALYSIS -
PRIMARY COOLANT SYSTEM Technical Specification 6.9.1.B.5 requires certain information regarding the results of specific activity analysis in which the primary coolant exceeded limits of Technical Specification 3.1.4.1.
There was only one occurrence in 1989. Table I contains 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; results of the last isotopic analysis for radio-iodine performed prior to exceeding the limit, results of analysis while the limit was exceeded, and results of an analysis after the radio-iodine activity was reduced to less than the limit; cleanup system 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 the tiine duration when the specific activity of the primary coolant exceeded the radio-iodine limit.
Figure 1 contains e graph of the dose equivalent 1-131 concentration for 1989.
Figure 2 contains a graph of the dose equivalent 1-131 concentration, the I-131 concentration, and the 1-133 concentration as a function of time for the duration of the specific activity above the steady-state level.
I Page 2 og 4 NY 2551 TNTW DIL'I1 PGt 1989 *"'MT. m.aum MDIO-IODINE 00N3NIRATIONS (sci /gm)
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1-121 1-122 1-122 I-las I-135 I-131 11/27/89 0600 100 50 a
11/27/89 1800 100 50 11/28/89 0600 100 50 11/28/89 1800 100 50 11/29/89 0035 100 50 0.0931 0.117 0.124 0.119 0.115 0.142 11/29/89 2015 0
50 2.98 1.49 3.17 0.295 1.68 4.04 11/29/89 1340 0
50 2.46 0.669 2.23 0.978 3.37 11/29/89 1740 0
50 2.26 0.484 1.93 0.603 2.85 11/29/89 2140 0
50 1.82 0.403 1.36 0.309 2.23 11/30/89 0140 0
50 1.43 0.283 0.946 0.174 1.71 11/30/89 0535 0
50 1.19 0.260 0.710 0.0933 1.40 11/30/89 0925 0
71 0.976 0.245 0.517 0.0551 1.13 11/30/89 1320 0
72 0.759 0.225 0.358 0.0251 0.866 11/30/89 1500 0
73 0.315 0.173 0.105 0.368 Time Duration when the 1.0 #C1/gm Limit was M = 27.08 Hours s
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t ATTACHMENT VI P
Technical Specification Section 6.17 requires reporting of " Major Changes to Radioactive Waste Treatment Systems." Major changes are interpreted to mean changes that would change how the system functions or changes the predicted releases that were previously analyzed.
Based on the above, no major changes were made during 1989.
However, temporary portable domineralizers were used in the Liquid Waste Disposal System during the last quarter of 1989. The use of these portable domineralizers is described in the UFSAR Sections 11.2.1.1 and 11.2.1.3.
The portable domineralizers have since been removed.
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e o e ATTACHMENT IV Pressurizer Power Operated Relief Valve and Pressurizer Safety Valve Challenges for Calendar Year 1989.
There were n_o pressurizer power operated relief valve or pressurizer safety i
valve challenges which occurred during 1989 in response to any plant transients, I
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