ML20080Q185

1994 TS Section 6 Annual Rept, Including Aircraft Movement Data & Leak Reduction Program Test Info

ML20080Q185
Person / Time
Site:	Three Mile Island
Issue date:	12/31/1994
From:	Broughton T GENERAL PUBLIC UTILITIES CORP.
To:
References
C311-95-2113, NUDOCS 9503080276
Download: ML20080Q185 (9)

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GPU Nuclear Corporation Nuclear m:nte Middletown, Pennsylvania 17057-0480 (717)944 7621 Writer's Direct Dial Number:

(717) 948-8005 February 28, 1995 C311-95-2113 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Subject:

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

Operating License No. DPR-50 Docket No. 50-289 l 1994 Technical Specifications Section 6 Annual Report 1

Attached is the 1994 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 1 Technical Specifications (T.S.). The attachments to this letter contain the l following information: l Attachment I - Aircraft Movement Data from the Harrisburg International Airport for the Calendar Year 1994 (per T.S. Section .

6.9.1.B.2). l Attachment II - Leak Reduction Program Test Information for the Calendar Year 1994 (per T.S. 6.9.1.B.3).

Attachment III - Pressurizer Power Operated Relief Valve and Pressurizer Safety Valve Challenges for the Calendar Year 1994 (per  ;

T.S. Section 6.9.1.B.4).

l Attachment IV - Results of Specific Activity Analysis - Primary Coolant System (per T.S. Section 6.9.1.B.5).

0700G9 95030830276 941231 PDR AJ.JCK 05000289 /I R PDR ;l GPU Nuclear Corporation is a subsidiary of General Public Utilities Corporation I

l C311-95-2113 Page 2 Attachment V - Major Changes to Radioactive Waste Treatment Systems (per l T.S. Section 6.17). ,

l 1

Sincerely, l

,W i T. G.-Bro hton l

.Vice President and Director,-TMI l

JSS/ emf Attachments cc: Region I Administrator TMI-1 Senior Project Manager TMI Senior Resident Inspector l

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C311-95-2113 ATTACHMENT I l AIRCRAFT MOVEMENTS AT THE l HARRISBURG INTERNATIONAL AIRPORT JANUARY 1 THROUGH DECEMBER 31, 1994 i

l 1. Total Aircraft Movements - 83,004 i

2. Total number of movements of aircraft larger than 200,000 pounds is  ;

estimated to be less than 200. I I NOTE: For Item 2, the data is based' on estimates provided by the Harrisburg l 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. l

l C311-95-2113 l

ATTACHMENT II l

Technical Specification 6.9.1.3.b periodic ' Leak Reduction- Program Test Results The results of the THI-l 1994 periodic Leak Reduction Program Tests which jncluded visual inspections are summarized in Table'l. The_ results of the TMI-l 1994 Local Leakrate Tests are summarized in Table 2. These tests were performed in accordance with the referenced procedures.

l TABLE 1 ,

1994 LEAK REDUCTION PROGRAM TEST-RESULTS FOR TMI SURVEILLANCE LEAK RATE PROCEDURES DATE OF LEAKING. ml/ min MAINTENANCE (See Note 1) PERFORMANCE . COMPONENT I.D. AS FOUND AS LEFT UNDERTAKEN 1303-11.16 See Note 2 .None 1303-11.27 See Note 2 None 1303-11.28 05/18/94 None 0 0 None 1303-11.29 See Note 2 None 1303-11.30 10/11/94 None 0 0 -None 1303-11.31 See Note 2 0 0 None 1303-11.50 06/10/94 None 0 0 None TOTAL LEAKAGE IN 1994 0 0 MJ d-Mdj r?2-

l C311-95,-2113 ATTACHMENT II l 1

i TABLE 2 .

-i 1994 LOCAL LEAKRATE TEST RESULTS FOR TMI 1303-11.18 (See Note 1)

DATE COMPONENT REASON FOR 1994 1993 LEAKAGE PERFORMED I.D. TEST. LEAKAGE LEAKAGE SAVINGS.

(sccm) (sccm) (sccm) 06/07/94 PENET 104 Opened during CRDM Outage 88- 56 +32 1 09/16/94 AH-VIC/1D Last Quarterly Test 1794- 1794 0 l

11/26/94 AH-VIA/1B Last Quarterly. Test 858 1248- -390 l 11/02/94 Equipment Last Biannual Test 3763 1634 +2129 l Hatch  !

11/07/94 Personnel. Last Biannual Test 1156 463 +693 Hatch l 12/21/93 CA-V2 Replaced per Modification 61 18634 -18573 l (See Note 3) TMM-412626-229 i

MAXPATH MINPATH

(sccm) (sccm) l l 1993 As-Left 61379 9844 l 1994 Total Leakage Savings -16109 0

! 1994 Running Total 45270 9844 I

Note 1: 1303-11.16 Decay Heat Removal System Leakage '

1303-11.18 RB Local Leakrate Testing 1303-11.27 Makeup and Purification Leakage Check l 1303-11.28 Liquid Waste System Leak Check 1303-11.29 Waste Gas Disposal System Leak Check. .

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 i

Note 2: Not performed in 1994.

Note 3: CA-V2 replacement valve leakrate was not included in the 1993 report. I i

The two hour site boundary and 30 day low population zone off-site dose conditions were not

limiting conditions for acceptable leakage criteria in .1994. All "AS-FOUND" or ' " AS-LEFT"

!- leakage recorded did not significantly increase the magnitude of either on-site or off-site releases during 1994.

Per TMI Technical Specification 4.4.1 total leakage less than 104,846 sccm is considered acceptable for as-left leakage condition.

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• C,311-95-2113 ATTACHMENT III Pressurizer Power Operated Relief Valve and Pressurizer Safety Valve Challenges-for Calendar Year 1994.

There were n_o pressurizer power operated relief valve or pressurizer safety valve challenges during 1994 in response to plant transients.

C.311-95-2113 ATTACHMENT IV 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. The limits of Technical Specification-3.1.4.1 were not' exceeded during 1994. Figure 1 contains a graph of the dose equivalent iodine concentration for 1994.

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i C311-95-2113 ATTACHMENT V i

l Technical Specification Section 6.17 requires reporting of " Major Changes to  ;

l Radioactive Waste Treatment Systems." Major changes are interpreted to mean '

l changes that would alter how the system functions or the predicted releases that l were previously analyzed.

In 1994 there were no major physical changes to the Radioactive Waste Treatment Systems. However, TMI-1 has changed the method by which waste concentrates are solidified. The following explanation of the change is provided for information.

However, the change does not alter how the system functions or the predicted ,

i releases. j l

Previously liners were partially filled with evaporator concentrates and i solidified with concrete. At that point the liners were shipped to the disposal l facility. Currently liners are filled to'a predetermined free board level and l l lifted into a secondary container and readied for shipment to a processor l facility. At the processor's. facility the liquid portion of the waste is driven l off leaving behind a solid in the form of a powder. This powder is then packaged for disposal with an overall volume reduction of 8 to 1 when compared to the i previous method. Due to the current lack of access to disposal facilities, the  !'

packages are returned to TMI-1 for interim storage.

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