ML080650121
| ML080650121 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/20/2008 |
| From: | Dougherty T AmerGen Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 5928-08-20024 | |
| Download: ML080650121 (11) | |
Text
AmerGen.
AmerGen Energy Company, LLC Three Mile Island Unit 1 Route 441 South, P.O. Box 48o Middletown, PA 17057 Telephone: 717-948-8ooo An Exelon Company February 20, 2008 5928-08-20024 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 THREE MILE ISLAND UNIT 1 (TMI-1)
OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289
SUBJECT:
2007 ANNUAL REPORT Attached is the 2007 Annual-Report for TMI-1 and TMI-2. This report is being submitted in accordance with TMI-1 Technical Specifications Sections 6.9.1.B.2 through 6.9.1.B.5 and 6.17. The attachments to this letter contain the following information: - - - -
Aircraft movement data from the Harrisburg International Airport (per TMI-1 T.S. section 6.9.1.B.2).
Leak reduction program test information (per TMI-1 T.S.
6.9.1.B.3).
Pressurizer power operated relief valve and pressurizer safety valve challenges (per TMI-1 T.S. section 6.9.11.B.4).
Results of specific activity analysis - primary coolant system (per TMI-1 T.S. section 6.9.1..B.5).
A001/
5928-08-2002,4 Page 2 of 2 -
Major changes to -radioactive waste treatment systems (per TMI-1 T.S. section 6.17)
Sincerely, Thomas Dough~erty Plant Manager TJD/awm Attachments cc:
TMI-1 Senior Resident Inspector Administrator, Region I TMI-1 Project Manager File 08009
5928-08-20024 ATTACHMENT 1 AIRCRAFT MOVEMENTS AT THE HARRISBURG INTERNATIONAL AIRPORT (HIA)
JANUARY 1, 2007 THROUGH DECEMBER 31, 2007
- 1.
Total Aircraft Movements - 71,011.
- 2.
Estimated total number of movements of aircraft larger than 200,000 pounds -
1232.
This estimate is composed of two parts, 1190 movements of civilian aircraft, and 42 movements of military aircraft.
5928-08-20024 ATTACHMENT 2 TECHNICAL SPECIFICATION 6.9.1.B.3 PERIODIC LEAK REDUCTION PROGRAM TEST RESULTS The results of the TMI-1 2007 periodic Leak Reduction Program Tests, which included visual inspections, are summarized in Table 1. These tests were performed in accordance with the referenced procedures. (See Note 1 for procedure titles.)
TABLE 1 2007 LEAK REDUCTION PROGRAM TEST RESULTS FOR TMI-1 SURVEILLANCE DATE OF LEAKING LEAK LEAK RESULTING PROCEDURES PERFORMANCE COMPONENT RATE RATE MAINTENANCE I.D.
UNDERTAKEN AS-FOUND AS-LEFT OP-TM-823-251 OP-TM-823-252 (LLRT performed under Option B provisions, 1303-11.18 series procedures) 10-03-07 11-15-07 10-09-07 10-15-07 10-12-07 10-23-07 10-24-07 10-25-07 10-26-07 AH-V1A/B AH-V1A/B AH-V1C/D AH-V1 C/D Eq. Hatch Fig CA-V-189/443 NI-V-26 NI-V-27 Pen. 221 Pen. 222 HP-V-1 HP-V-6 HM-V-3A HM-V-3B HM-V-4A HM-V-4B IA-V-6/20 HM-V-1A HM-V-1B HM-V-2A HM-V-2B Pen. 417 WDG-V-3/4 IC-V-6 IC-V-16 NS-V-1 1 NS-V-15 2093 sccm 1363 2093 sccm 8287 sccm 24 963 63 63 23 23 168 61 61 61 61 61 22 22 22 22 22 22 1160 63 63 1079 273 2093 sccm 1363 2093 sccm 8287 24 963 63 63 23 23 168 61 61 61 61 61 22 22 22 22 22 22 1160 63 63 1079 273 None None None None None None None None None None None None None None None None None None None None Retest None None None None
(LLRT performed under Option B provisions, 1303-11.18 series procedures -
continued) 10-27-07 10-30-07 11-01-07 11-03-07 11-04-07 11-05-07 11-07-07 11-10-07 11-11-07 11-12-07 11-13-07 CF-V-2B CF-V-20B CF-V-46B WDG-V-3/4 CA-V-4A CA-V-5A CA-V-449 CA-V-2/446 CA-V-13 MU-V-20 MU-V-116 MU-V-3/238 DH-V-64 DH-V-69 WDL-V-534/535 CF-V-12A CF-V-19A WDL-V-303 WDL-V-304/727 CF-V-2A CF-V-20A/46A IC-V-4 IC-V-18 NS-V-35 NS-V-4/211 IC-V-2 IC-V-3 IC-V-102 CF-V-2B CF-V-20B/46B CF-V-1i2B Pen. 106 Pen. 211 Pen. 104 Pen. 210 SF-V-22 SF-V-23 MU-V-25 63 571 77 980 63 63 23 63 63 174 88 77 77 88 96 151 1070 616 63 64 209 63 63 991 991 736 255 77 127 63 63 23 23 23 23 107 16 63 63 571 77 980 63 63 23 63 63 174 88 77 77 88 96 151 1070 616 63 64 209 63 63 991 991 736 255 77 127 63 63 23 23 23 23 107 16 63 None None None WDG-V-3 replacement scheduled None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None None
MU-V-26 11-14-07 11-15-07 FTT West FTT East Pen. 105 Pen. 414 Eq. Hatch Flange FS-V-401 HR-V-22A/B HR-V-2A/B 63 63 63 23 23 23 0
63 63 63 63 63 23 23 23 0
63 63 None None None None None None None None None MINPATH AS-FOUND =
8,460 SCCM MAXPATH AS-FOUND =
21,531 SCCM MINPATH AS-LEFT 10,088 SCCM MAXPATH AS-LEFT 22,106 SCCM OP-TM-214-07-19-07 None 0 GPH None required 254 OP-TM-214-08-10-07 None 0 GPH 253 None required 1303-11.30 08-27-07 None 0 ml/
min None required OP-TM-21 1-09-03-07 None N/A None required 251 (7.2)
OP-TM-21 1-09-06-07 None N/A None required 251 (7.3)
09-17-07 MU-V-16A N/A Tightened 251 (7.1) packing, MU-packing glands, V-6A packing, replaced MU12-MU-V-90 FT gasket and
- packing, torqued bolts MU12-FT flange OP-TM-21 1-10-22-07 None N/A None required 251 OP-TM-212-10-24-07 DH-V-12B 0 GPH Tightened plug, 215 leakoff plug, cleaned boron, BS-V-3B tightened packing packing, DH-glands, minor V-15B seal leakage packing, DH-P-i1B mechanical seal OP-TM-212-11-04-07 DH-V-6A 0 GPH Tightened -
217 packing packing gland OP-TM-212-11-05-07 None 0 GPH None required 218 1
Note 1:
OP-TM-823-251, "LLRT of Purge Exhaust Penetration Valves" OP-TM-823-252, "LLRT of Purge Supply Penetration Valves" OP-TM-214-254, "BS Leakage Exam Train B" OP-TM-214-253, "BS Leakage Exam Train A" 1303-11.30, "Reactor Coolant Sampling Leakage Check" OP-TM-211-251, "Leakage Exam of Make-up System" OP-TM-212-215, "DHR Train A/B Leakage Exam" OP-TM-212-217, "DH-V-6A to RB Sump Leak Check" OP-TM-212-218, "DH-V-6B to RB Sump Leak Check" OP-TM-211-261, "MUP Suction Leak Check"
5928-08-20024 ATTACHMENT 3 PRESSURIZER POWER OPERATED RELIEF VALVE AND PRESSURIZER SAFETY VALVE CHALLENGES IN 2007 There were no challenges to the pressurizer power operated relief valve (PORV) or either of the two pressurizer (PZR) safety valves during the entire calendar year of 2007.
A review of the Reactor Coolant System (RCS) pressure indication trend data resulted in a maximum pressure indication of 2177 psig during the calendar year of 2007. The maximum indicated operating pressure of 2177 psig is well below the PORV set point of 2450 psig, and both PZR safety valve set points of 2500 psig. Therefore no challenges to the PORV or PZR safety valves occurred during 2007.
5928-08-20024 ATTACHMENT 4 RESULTS OF SPECIFIC ACTIVITY ANALYSIS-PRIMARY COOLANT SYSTEM Technical Specification 6.9.1..B.5 requires annual reporting of certain information regarding the results-of specific activity analyses in which the primary coolant exceeded the limits of Technical Specification (TS) 3.1.4.1. The limits of TS 3.1.4.1 were not exceeded at TMI-1 at any time during the year 2007. The figure of RCS activity for 2007 shows that the limit of 0.35 microcurie/gram dose equivalent 1-131 was not exceeded in 2007.
5928-08-20024 TM I-1 Dose Equivalent Iodine (DEI) in 2007 I.OOE+00 1.00E-01 OE a.,
C 1.OOE-02 DEI
_-TS Limit 1.OOE-03 1.00E-04 I-1-Jan 31-Jan 2-Mar 1-Apr 1-May 31-May 30-Jun Date 30-Jul 29-Aug 28-Sep 28-Oct 27-Nov 27-Dec
5928-08-20024 ATTACHMENT 5 MAJOR CHANGES TO RAD WASTE TREATMENT SYSTEMS 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 changes that would affect operational exposures, offsite dose rates or integrated doses. There were no major changes to the liquid, gaseous, or solid radioactive waste treatment systems at TMI-1 during the year of 2007.