ML080650121

2007 Annual Report

ML080650121
Person / Time
Site:	Three Mile Island
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 Telephone: 717-948-8ooo An Exelon Company Three Mile Island Unit 1 Route 441 South, P.O. Box 48o Middletown, PA 17057 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:

Attachment 1 - Aircraft movement data from the Harrisburg International Airport (per TMI-1 T.S. section 6.9.1.B.2).

Attachment 2 - Leak reduction program test information (per TMI-1 T.S.

6.9.1.B.3).

Attachment 3 - Pressurizer power operated relief valve and pressurizer safety valve challenges (per TMI-1 T.S. section 6.9.11.B.4).

Attachment 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 Attachment 5 - 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 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 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- 10-03-07 AH-V1A/B 2093 sccm 2093 sccm None 251 1363 1363 11-15-07 AH-V1A/B 2093 sccm 2093 sccm OP-TM-823- 10-09-07 AH-V1C/D 8287 sccm 8287 None 252 10-15-07 AH-V1 C/D None (LLRT 10-12-07 Eq. Hatch Fig 24 24 None performed 10-23-07 CA-V- 189/443 963 963 None under NI-V-26 63 63 None Option B NI-V-27 63 63 None provisions, 10-24-07 Pen. 221 23 23 None 1303-11.18 Pen. 222 23 23 None series HP-V-1 168 168 None procedures) HP-V-6 61 61 None 10-25-07 HM-V-3A 61 61 None HM-V-3B 61 61 None HM-V-4A 61 61 None HM-V-4B 61 61 None IA-V-6/20 22 22 None HM-V-1A 22 22 None HM-V-1B 22 22 None HM-V-2A 22 22 None HM-V-2B 22 22 None Pen. 417 22 22 WDG-V-3/4 1160 1160 Retest 10-26-07 IC-V-6 63 63 None IC-V-16 63 63 None NS-V-1 1 1079 1079 None NS-V-15 273 273 None

(LLRT 10-27-07 CF-V-2B 63 63 None performed CF-V-20B 571 571 None under CF-V-46B 77 77 None Option B provisions, 10-30-07 WDG-V-3/4 980 980 WDG-V-3 1303-11.18 replacement series scheduled procedures - CA-V-4A 63 63 None continued) CA-V-5A 63 63 None CA-V-449 23 23 None 11-01-07 CA-V-2/446 63 63 None CA-V- 13 63 63 None 11-03-07 MU-V-20 174 174 None MU-V-116 88 88 None MU-V-3/238 77 77 None 11-04-07 DH-V-64 77 77 None DH-V-69 88 88 None WDL-V-534/535 96 96 None CF-V-12A 151 151 None CF-V-19A 1070 1070 None 11-05-07 WDL-V-303 616 616 None WDL-V-304/727 63 63 None 11-07-07 CF-V-2A 64 64 None CF-V-20A/46A 209 209 None IC-V-4 63 63 None IC-V-18 63 63 None 11-10-07 NS-V-35 991 991 None NS-V-4/211 991 991 None IC-V-2 736 736 None IC-V-3 255 255 None IC-V-102 77 77 None 11-11-07 CF-V-2B 127 127 None CF-V-20B/46B 63 63 None CF-V-1i2B 63 63 None 11-12-07 Pen. 106 23 23 None 11-13-07 Pen. 211 23 23 None Pen. 104 23 23 None Pen. 210 23 23 None SF-V-22 107 107 None SF-V-23 16 16 None MU-V-25 63 63 None

MU-V-26 63 63 None 11-14-07 FTT West 63 63 None FTT East 63 63 None Pen. 105 23 23 None 11-15-07 Pen. 414 23 23 None Eq. Hatch Flange 23 23 None FS-V-401 0 0 None HR-V-22A/B 63 63 None HR-V-2A/B 63 63 None MINPATH MINPATH AS- AS-LEFT FOUND =

8,460 10,088 SCCM SCCM MAXPATH MAXPATH AS- AS-LEFT FOUND =

21,531 22,106 SCCM 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)

OP-TM-211 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 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 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 Attachment 4 TM I-1 Dose Equivalent Iodine (DEI) in 2007 I .OOE+00 1.00E-01 OE

• DEI a., 1.OOE-02

_-TS Limit C

1.OOE-03 1.00E-04 I-1-Jan 31-Jan 2-Mar 1-Apr 1-May 31-May 30-Jun 30-Jul 29-Aug 28-Sep 28-Oct 27-Nov 27-Dec Date

5928-08-20024 Attachment 5 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.