ML19336A677
| ML19336A677 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/20/1980 |
| From: | Hukill H METROPOLITAN EDISON CO. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| TLL-472, NUDOCS 8010300457 | |
| Download: ML19336A677 (12) | |
Text
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Metropolitan Edison Company
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Post Office Box 480 1jI ' C 'J # 2
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- Middletown, Pennsytvania 17057 717 9444 041 Writer's Direct Dial Nunter October 20, 1980 TLL 472 Office of Inspection and Enforcement Attn:
B. H. Grier, Director Region I U. S. Nuclear Regulatory Com=ission 631 Park Avenue King of Prussia, PA 19406
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (DiI-1)
Operating License No. DPR-50 Docket No. 50-289 10CFR 50.59 Report In accordance with the requirements of 10CFR 50.59, enclosed please find two copies of changes to systems in niI-1 from May 26, 1977 to the present as described in the FSAR.
Additionally, enclosed are 2 items not listed in our predous report of May 26, 1977 (GOL 0714).
There were neither any changas to procedures requiring a change to the FSAR, nor test or experiments performed not described in the FSAR.
Sincerely, Signed R.D. Hukill H. D. Hukill Director, TMI-l HDE:DGM: hah Enclosures cc: Director, Office of Inspection and Enforcement (40 copies)
U. S. Nuclear Regulatorv Co=ission Washington, D.C.
20555 Director, Office of Management Information &
Program Control (1 copy)
U. S. Nuclear Regulatorv Commission Washington, D.C.
20555 R. W. Reid B. J. Snyder
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J. T. Collins D. DiIanni k
8010800 t/e: recon:an E::so. Com::anf is a fle e c'ine Genera.;oc: U:mt es System
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Chance Mx3 #439: AH-F-2 Install Shutoff Dampers 2.
Cmpletion Date:
5/10/76 3.
Description of Change:
Installation of shutoff dampers in the plentans of filter banks AH-F-2A, 2B, 2C and 2D, allow DOP and freon testing of individual filter banks within the Auxiliary and Fuel Handlina Building INAC systen rather than as an entire unit.
4.
Safety Evaluation Str:trarv:
1.
The dampers will be stored hanging down, and since gravity will keep the daw down, there is no possibility of an inadvertant closing which would perturbate the operation of the aux and fuel handling building HVAC systen.
2.
The dampers do not change the desian or function of the AH-F-2 filters in the aux. and fuel handling building INAC systen.
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Change Mod #465: Add a Spool Piece and Vent Line to the top of the B ET 2.
Canpletion Date: 7/18/77 4
3.
Description of Change:
The existing overflow line on the BWST exits the tank and rises several feet before turning down. The nonral water level covers the line where it exits the tank. During increases in tank level, air trapped in the derne causes erroneous level roMings and unnecessary overflows. A vent line was added between the top of the tank and the top of the overflow line.
4.
Safety Evaluation Sumarv:
Addition of the vent line will not result in any degradation of the original requirenents, and will not prevent the tank from delivering borated water as designed.
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Change Mod #489:
Pressurizer Relief Valve Discharge Piping, Pipe Hanger PR-31 2.
Completion Date:
7/13/76 3.
Description of Change:
Itxiify guide type pipe hanger PR-31, add restraint type hangers PR-20A, 21A & 22A. These modifications prevent further darrage to RC-W-2 discharge line and preclude the possibility of damaging RC-W-1A & B discharge lines.
4.
Safety Evaluation Sunrary:
This change modification does not constitute an unreviewed safety question for the following reasons:
a.
bbdifying the hangers for the discharge pipes of PC-W-1A, RC-W-1B and RC-W-2 will limit discharge pipe rrevenent &
will rerove an obstacle which has previously dented these pipes. Therefore, the pr*bility of a pipe denting occurrence is decreased. Fbdifying the discharge pipe restraints will provide the same supoort as previously was supplied.
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Change Mod #589: Keyphasor Notch for Reactor Coolant Pumps 2.
Ccmpletion Date: 4/7/78 1
3.
Description of Change:
A notch was cut into each Reactor Coolant Pune coupling to provide a shaft position reference for the keyphasor probe of the shaft vibration monitoring system. The resulting keyphasor signal will aid in halancing the pumps.
4.
Safety Evaluation Sumary:
Westinghouse, Gilbert Associates and Met-Ed Generation Engineering reviewed the design of the keyphasor notch and concluded that all stresses and deflection fall within accepted engineering tensile, shear and fatigue limits. The material of the RC Pump Coupling is A235 Class F which has mechanical properties of 40 KSI yield and 80 KSI ultimate tensile stress. The absolute maximum erress on the coupling due to the rotch has been calculated to 30.5 KSI.
Therefore, this change does not constitute an unreview T safety p tion.
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Change Mod #639: Modify % L6 Flushing System 2.
Ccarpletion Date: 1/8/79 3.
Description of Change:
Permanent piping and control valves were installed to allow flushing of radiation monitor % L6 following a discharge of the Waste Evaporator Condensate Storage Tank. The change was made to allcw background reduction in the sampler and to prevent contamination frcm becx2ning fixed.
4.
Safetv Evaluation Sumary:
Since the monitor is flushed with non-radioactive water, and the discharge is nonitored by %L6 itself, no unmonitored or unplanned releases will occur. There is no detrinental effect on any safety-related equiptent.
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Change Mod #845:
Make up Puup Lube Oil Aip 2.
Otrnpletion Date:
3/23/78 3.
Description of Gance:
'Ihe non-seismically qualified lube oil pressure switches on the Make up Pump (MU P 1A, B and C) were replaced with seismimlly qualified switches. 'Ihe engineered Safeguards signal interlock that defeated the lube oil trip signal during an ES was then renoved.
4.
Safetv Evaluation Sunmary:
This change enhances the reliability of the rake up pump during testing, the switches are qualified for the service, and the revised circuit wi.ll prevent pump damage in the event of low lube oil pressure, and does not create the possibility of a different type of accident in that the separation criteria is met.
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Change Mod #849: }bdification of Feedwater Block Systen 2.
Ccrupletion Date: 6/28/79 3.
Descriotion of Gancre:
te main feedwate-tsalation systen for stean line break was modified to close the motor operated block valves in addition to the feedwater control valves. We rrotor operator for the train feedwater block valve was modir'ad so that it would close in 30 seconds or less to provide rap'
.salation.
4.
Safetv Evaluation Su:rarv:
This change enhances the safety of the train feechster isolation systen by providing rapid isolation durirg steamline break as discussed in the DII-l Restart Report.
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Change Mod #865: DP Gauges on River Water Pur:ps Lube Water 2.
Cmpletion Date:
3/15/78 3.
Description of Change:
bbunted differential pressure gauges in parallel with existing lube water differential pressure switches on all river water purrps.
4.
Safety Evaluation Sunrarv:
The differential pressure 7auces were installed to assist operators when investigating an alanti 0.a Iow Lube A P on river water pumps.
The gauges will help detemine if there is a purtp problem, clogged strainer or erratic switch indication.
It was detemined that this change does not involve an unreviewed safety question, since the gauges will not affect operation of any l
safety-related ptrps.
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Change Mod #963: Rmove PT-427 fran Main Steam Systen 2.
Cmpletion Date: March 1978 3.
Description of Change:
A steam leak developed at FI-427 which damaged the transmitter. Since PT-427 was not functional prior to being damaged and not utilized for any ccritrol or indication of pressure, it was decided to remove the transmitter frcrn the systan.
4.
Safety Evaluation Sunmary:
Originally, PT-427 was to measure the initial stean pressure to the turbine DiC system, however, FT-427 output signal was disconnected.
Since the transmitter provides no control or indication, renoval had no effect on any safety-related equignent.
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Change Mod #976: Remove DH-P-1A/lB Recirc Orifice 2.
Ccxnpleticm Date: 2/7/78 3.
Description of Change:
The DH-P-1A/lB recirc orifice was renoved and replaced with a flex-itallic gasket. Recire flow rate increased which inproved pump reliability. LPI flow rates decreased, but are still greater than what is specified in the 'IMI-1 IDCA aralysis.
4.
Safety Evaluation Sunrnarv:
Although the description of pump operation in the FSAR is slightly l
changed by the orifice removal, the change is conservativa taxi tends to inprove punp reliability. Therefore, the potential for the accident and its corseces as described in the FSAR are not increased by this change. Also, in view of the concern for pump reliability at minutun recire flow rates, the reduction in operational flow neasurement capability which results from this change (as described in the FSAR) is acceptable.
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Qunge Fod #1030: Add Redundant Sanpling Channel i
2.
Cmpletion Date:
11/7/78 3.
Description of C unae:
Add a redundant sanpling channel for CE-6, SDI Gen. Inlet Conductivity.
Channel consists of a conductivity cell & Monitor, with a control rocm indicator and alam. Existing sanpling piping was used.
4.
Safety Evaluation Sunmary:
The installation of additional sanpling instrunentation will not affect the operation of any safety-related equipment. There are no equipTent interlocks associated with the conductivity bbnitor.
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