ML20203D260

Forwards Min Acceptance Curve for Periodic Surveillance of RHR Pumps & Revised Tech Spec Page Ix,Reflecting Addition of Curve,Per Util 860311 Request to Amend License NPF-37.Curve Identified as Lower Curve on FSAR Figure 6.3-3

ML20203D260
Person / Time
Site:	Byron
Issue date:	04/11/1986
From:	Ainger K COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
1545K, NUDOCS 8604220070
Download: ML20203D260 (4)

Text

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,D Commonwealth Edison O

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) One First Nrtionti Pttia, Chicago. Ilknog C

( O Addr ss Riply to. Post Office Box 767 x

Chicago, Ilknois 60690 April 11, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Byron Station Units 1 and 2 Technical Specifications l

Residual Heat Removal Pumps NRC Docket Mos. 50-454 and 50-455 Reference (a): March 11, 1986 letter from K. A. Ainger to H. R. Denton

Dear Mr. Denton:

I l

Reference (a) requested an amendment to Appendix A Technical Specifications, of Facility Operating License NPF-37.

The amendment involves the acceptance criteria for a periodic surveillance of the residual heat removal (RHR) pumps. The proposed change would allow use of a minimum acceptable performance curve instead of a point on the curve to demonstrate the required performance of the RHR pumps.

It has been requested by the NRC to include the minimum acceptable performance curve for the RHR pumps in the Technical Specifications instead of referring to the curve in the Technical Specifications. Enclosed is the minimum acceptable performance curve which has been assigned Figure No.

4.5-1 and page no. 3/4 5-5a.

A revision to pages II and 3/4 5-5, which reflect the addition of this curve, is also enclosed.

This curve was inadvertently identified in reference (a) as the upper curve on FSAR Figure 6.3-3.

The enclosed mininum acceptable performance curve is the lower curve on FSAR Figure 6.3-3.

One signed original and fifteen copies of this letter and the enclosure are provided for NRC review.

Please direct any questions regarding this matter to this office.

Very truly yours, 8604220070 860411 PDR ADOCK 05000454 PDR K. A. Ainger p

Nuclear Licensing Administrator 1m Enclosure ec: Byron Resident Inspector f

L. N. Olshan - NRR 1545K I

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0 lodo 20do 30$0 4doo 50'00 RHR PUMP FLOW (GPM)

FIGURE 4.5-1 RESIDUAL HEAT REMOVAL PUMP MINIMUM ACCEPTABLE PERFORMANCE CURVE 3/4 5-Sa

.r LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 9

SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS.............................................

3/4 5-1

{

3/4.5.2 ECCS SUBSYSTEMS - T,,g >350*F...........................

3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - T,yg <350*F...........................

3/4 5-7 3/4.5.4 REFUELING WATER STORAGE TANK.............................

3/4 5-9 FIGuitE 3.5-1 RE5ibunt H PE RFoe. EAT REMOVAL. PUMP mlNimVM ACCEPTHGLC mA s /9 5-54 3/4.6 CONTAINMENT SYSTEMS'NCE. c.URVE

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3/4.6.1 PRIMARY CONTAINMENT Containment Integrity....................................

3/4 6-1 Containmen'. Leakage......................................

3/4 6-2 Containment Air Locks....................................

3/4 6-4 Internal Pressure........................................

3/4 6-6 l

Air Temperature..........................................

3/4 6-7 Containment Vessel Structural Integrity..................-

3/4 6-8 Containment Purge Ventilation System.....................

3/4 6-11 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System.................................

3/4 6-13 Spray Additive System....................................

3/4 6-14 Containment Cooling System...............................

3/4 6-15 3/4.6.3 CONTAINMENT ISOLATION VALVES.............................,

3/4 6-16 TABLE 3.6-1 CONTAINMENT ISOLATION VALVES..........................

3/4 6-18 3/4.6.4 COMSUSTIBLE GAS CONTROL Hyd ro ge n Mo n i to rs........................................

3/4 6-25 Electric Hydrogen Recombiners............................

3/4 6-26 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves............................................

3/4 7-1 l

BYRON - UNITS 1 & 2 IX

.9 EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 1)

For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2)

Of the areas affected within containment at the completion of each containment entry when CONTAINMENT INTEGRITY is established.

d.-

At least once per 18 months by:

1)

Verifying automatic isolation and interlock action of the RHR System from the Reactor Coolant System by ensuring that:

i a)

With a simulated or actual Reactor Cool' ant System pressure signal greater than or equal to 360 psig the interlocks prevent the valves from being opened, and b)

With a simulated or actual Reactor Coolant System pressure signal greater than or equal to 662 psig the interlocks will cause the valves to automatically close.

2)

A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or abnormal corrosion.

l e.

At least once per 18 months, during shutdown, by:

1)

Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection test signal and on a RWST Level-Low-Low test signal, and 2)

Verifying that each of the following pumps start automatically upon receipt of a Safety Injection actuation test signal:

a)

Centrifugal charging pump, b)

Safety Injection pump, and c)

RHR pump.

f.

By verifying that each of the following pump' develops the indicated s

differential pressure on recirculation flow when tested pursuant to Specification 4.0.5:

1)

Centrifugal charging pump 1 2396 psid, 2)

Safety Injection pump 1 1412 psid, and 3)

RHR pump 1 191 prie 'In awdonce. sth Fk vre. i.5 -1 3

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BYRON - UNITS 1 & 2 3/4 5-5 a