ML20084B326
| ML20084B326 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/24/1995 |
| From: | Broughton T GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20084B328 | List: |
| References | |
| C311-95-2099, NUDOCS 9505310201 | |
| Download: ML20084B326 (8) | |
Text
a GPU Nuclear Corporation
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Route 441 South P.O. Box 480 Middletown, Pennsylvania 17057-0480 (717)944 7621 Writer's Direct Dial Nurnber:
(717) 948-8005 May 24 1995 C3 I l-95,-2099 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555
Dear Sir:
Subject:
Three Mile Island Nuclear Generating Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Facility Operating License Amendment Request No. 250 In accordance with 10 CFR 50.4 (b)(1), enclosed is one (1) original copy of the Facility Operating License Amendment Request No. 250.
Also enclosed is one signed copy of the Certificate of Service for this request which confinns service to the senior officials of the township and county in which the facility is located, as well as the Commonwealth of Pennsylvania, Bureau of Radiation Protection.
The purpose of this license amendment request is to change the surveillance " Test" requirements for the source-range Nuclear Instrumentation. New instmments, manufactured by GAMMA 4fETRICS Inc., and installed during the 7R refueling outage have been found to exhibii very little instmment drift in operation and by tests conducted since installation.
Therefore, this change eliminates the potential for unnecessary testing, which could result if the requirement is not revised.
It is requested that the license amendment be issued prior to the restart from refueling outage llR, presently scheduled for September,1995.
9505310201 950524 PDR ADOCK 05000209 S.incerely, P
' bb T. G. Brohghton Vice President / Din:ctor, TMI t
- I j GPU Nuclear Corporabon is a subsidiary of General Pubhc UtAties Corporation I
,.~ ~ '. 0311-95-2099
Enclosures:
- 1) ~ Facility Operating License Amendment Request No. 250 6
2)
Certincate of Service for the Facility Operating License Request No. 250 cc:
TMI-1 Senior Project Manager l
Region I Administrator TMI Senior Resident Inspector
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I
METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT 1 i
Operating License No. DPR-50 Docket No. 50-289 Facility Operating License Amendment Request No. 250 TIIE STATE OF PENNSYLVANIA
)
) SS:
COUNTY OF DAUPIIIN
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This Facility Operating License Amendment Request is submitted in support of Licensee's request to amend the Operating License No. DPR-50 for Three Mile Island Nuclear Station, Unit 1. As part of this mquest, proposed replacement pages for the Facility Operating License are also included.
GPU NUCLEAR CORPORATION BY:
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Vice President/ Director, TMI Sworn and subscribed before me this 24th' day of May
,1995.
_dtt(Wkl17[N-YbLbf)J Notary Public NatanalSeal Kim
, Notary PLtAc tmn
.Daurtw1 County My Comeori es Aug 21,1997 Me.ca,PumyNwu Asaxrdsn ot Notanos
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN TIIE MATI'ER OF DOCKET NO. 50-289 GPU NUCLEAR CORPORATION LICENSE NO. DPR-50 CERTIFICATE OF SERVICE This is to certify that a copy of the Facility Operating License Amendment Request is submitted in support of Licensee's request to change the Operating License No. DPR-50 for Three Mile Island Nuclear Station, Unit 1, has, on the date given below, been filed with executives of Londonderry Township, Dauphin County Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania Department of Environmental Resources, Bureau of Radiation Protection, by deposit in the United States mail, addressed as follows:
Mr. Jay H. Kopp, Chairman Mr. Russell L. Sheaffer, Chairman Board Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Courthouse Middletown, PA 17057 Harrisburg, PA 17120 Director, Bureau of Radiation Protection PA Dept. of Environmental Resources P.O. Box 2063 IIarrisburg, PA 17120 Att: Mr. Robert Barkanic GPU NUCLEAR CORPORATION BY:
Vice President /birector, TMI DATE:
May 24, 1995
ENCLOSURE Three hiile Island Nuclear Plant, Unit 1 (TA11-1)
Operating License No. DPR-50 Docket No. 50-289 Facility Operating License Amendment Request No. 250 I.
PROPOSED TECHNICAL SPECIFICATION CHANGE REOUEST (TSCR)
GPU Nuclear (GPUN) Corporation hereby requests that the following pages of the TMI-l Technical Speci6 cations (Tech. Specs.) be replaced as indicated below:
Eeplace Paces: 1-8 and 4-3.
II.
BACKGROUND AND DESCRIPTION OF CHANGES l
Background:
Nuclear Instrumentation channels include redundant GAMMA-METRICS Inc. analog instnament loops each of which provides source range and wide-range reactor neutron flux monitoring. Each loop consists of: two (2) fission chambers in a neutron detector tube in close pmximity to the reactor vessel; a qualified, low noise triaxial cable; and, pre-amplifier and signal conditioning instnaments. The testing requirements for these instniments are contained in TMI-l Technical Specifications Table 4.1-1, where Item 6 requin:s a " Test" of the Source Range Channel seven (7) days prior to any reactor startup. The same nuclear instnimentation channels also serve as wide-range neutron monitors for Post Accident Monitoring Instrumentation. Technical Specifications Table 4.1-4, Item 6, requires a calibration of these instruments on the basis of a surveillance interval not to exceed 24 months. These nuclear instntmentation channels also provide a control md withdrawal inhibit interlock, control room displays and alarms.
These GAMMA-METRICS Inc. instruments were installed during refueling outage 7R l
and have been found to exhibit very little instrument drift in operation and by tests conducted during refueling outages 8R,9R, and 10R.
Description of Changes 1.
p.1-8 Revision of the Frequency Notation Table 1.2, which is part of Tech. Spec. Definition 1.25, with the incorporation of a new six months prior to staitup requirement.
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4 Three Mile Island Nuclear Plant, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Facility Operating License Amendment Request No. 250 2.
p.4-3 Tech. Spec. Table 4.1-1, "Instniment Surveillance Requirements," has been revised to reflect new Test frequency for the Source Range Channel, Item No. 6 on the table, by deletion of the seven (7) days prior to startup (P S/U) notation and replacement with the requirement to Test within six (6) months prior to each reactor startup.
III.
SAFETY EVALUATION JUSTIFYING CHANGE The safety functions and requirements for Nuclear Instrumentation are specified in the TMI-I Technical Specifications: (a) Section 3.5.1 " Operational Safety Instrumentation"; (b) Section 3.5.5, " Accident Monitoring Instrumentation"; and, (c)
Section 3.8, " Fuel Imading and Refueling."
(a) Tech. Spec. 3.5.1.5 requires that, "During STARTUP when the intermediate range instruments come on scale, the overlap between intennediate range and source range shall not be less than one decade." The Nuclear Instnimentation source-range instniments provide indication of reactor power during reactor startup until reactor power has increased to the point where the intermediate-range nuclear instruments are on scale. This TSCR eliminates the seven-day test of source-range nuclear instmmentation and replaces this requirement with a requirement to test these NI channels within six (6) months prior to each reactor startup. The manufacturer GAMMA-METRICS, Inc. has specified that this equipment exhibits a maximum drift rate of i0.5% of span over six months.
(b) Tech. Spec. 3.5.5 Bases states: "The operability of design basis accident monitoring instnimentation as identified in Table 3.5-3, ensures that sufficient infonnation is available on selected plant parameters to monitor and assess the variables following an accident." The wide-range nuclear instruments channels provide post-accident monitoring of reactor power. The current surveillance reauirements are that a channel check be perfonned weekly and a calibration be performed on an interval not to exceed 24 months. This TSCR does not change surveillance requirements for the wide-range nuclear instrument channels.
(c) Tech. Spec. 3.8 Bases, states that, " Continuous monitoring of radiation levels and neutmn flux provides immediate indication of an unsafe condition during refueling and fuel loading activities." Testing of the source-range channels six (6) months prior to a reactor restart is acceptable based on the 0.5% drift specified by the manufacturer, G AMM A-METRICS, Inc.
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Three Mile Island Nuclear PI:nt, Unit 1 (TAH-1)
Operating License No. DPR-50 Docket No. 50-289 Facility Operating License Amendment Request No. 250 IV.
b[O SIGNIFICANT HAZARDS CONSIDERATIONS GPUN has determined that this Facility Operating License Amendment Request for TMI-l involves no significant hazards consideration as defined by NRC in 10 CFR 50.92.
1.
Operation of the facility in accordance with the proposed TSCR would not involve a significant increase in the probability of occurrence or the consequences of an accident previously evaluated.
The proposed revision to the Technical Specifications does not involve any physical changes to the plant, and it does not impact the safety analysis with respect to design basis events and assumptions. The only change proposed is in the " Test" frequency for source-range Nuclear Instmmentation by revision of the appropriate Tech. Spec. tables. The revised testing requirement has no impact upon the probability of occurrence or the consequences of any accident previously evaluated, because no credit is taken in the accident analyses for the source range monitors nor are there any inputs to the Reactor Protection System. Tech. Spec.
3.1.9.2 requires that the control rod withdraw inhibit be operable at all times; however, it is not affected by this change request. Additionally, no nuclear safety equipment or systems interface with source-range nuclear instrumentation, and operator ability to monitor and trend post-accident neutron level is not affected by the proposed change. Therefore, this change request will not increase the probability of occurrence or the consequences of any previously analyzed accidents as described in the Updated FSAR (UFSAR).
2.
Operation of the facility in accordance with the proposed TSCR would not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed revision to the TMI-I Technical Specifications does not involve any physical changes to the plant, and does not impact on the safety analysis with respect to design basis events and assumptions. The only change proposed is in the " Test" frequency for Nuclear Instrumentation by revision of the appropriate Tech. Spec. tables. No nuclear safety equipment or systems interface with the source-range nuclear instrumentation, and operator ability to monitor and trend post-accident neutron levels is not adversely affected by the proposed change. In addition, the source-range nuclear instrument channels provide indication to the control room, plant computer and one of two channels provides input to Remote Shutdown Panel B.
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Three Mile Isl:nd Nuclear Plant, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Facility Operating License Amendment Request No. 250 The 0.5% instrument drift over a six (6) month period will not affect the ability to operate other safety equipment; nor, will it increase the probability of failure of the rod withdrawal inhibit. The inhibit function is triggered by a stanup rate, and a 0.5% drift over six (6) months will not affect the instrument's ability to perfonn the inhibit function. Therefore, this change has no impact upon the possibility of creating a new or different kind of accident from any previously evaluated in the UFSAR.
3.
Operation of the facility in accordance with the proposed TSCR would not involve a significant reduction in a margin of safety.
The proposed revision to the TMI-l Technical Specifications does not involve any physical changes to the plant, and does not impact on the safety analysis with respect to design basis events and assumptions. The only change proposed is in the surveillance frequency for Nuclear Instrumentation by revision of the appropriate Tech. Spec. tables. Startup rate instmmentation is not included in Technical Specifications 2.0, " Safety Limits"; and, hence, all system Limiting Conditions for Operation (s) remain unchanged. Testing of the source-range nuclear instmment channels within six (6) months prior to a reactor startup will not decrease the margin of safety. Hence, the margin of safety for the plant is not diminished by this change request, The Commission has provided guidelines on the application of the three standards above, by listing specific examples in 48 FR 14870. The proposed amendment is considered to be in the same category as example (i) of amendments that are considered not likely to involve significant hazards considerations in that the proposed change is, in effect, of an administrative nature which involves the changing a surveillance interval maintained by plant procedure and does not involve any physical changes to the plant or materials, nor are any changes to normal plant operations.
Therefore, operation of TMI-l in accordance with the proposed TSCR involves no significant hazards considerations.
V.
IMPImEMENTATION It is requested that this license amendment bxome effective prior to the restart from refueling outage 11R. presently scheduled for September,1995.
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