ML20041F421

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Proposed Changes to Tech Specs 3/4 3-28 & B 3/4 3-6 to Reflect Common Water Level Ref Setpoints,Per NUREG-0737 Item II.K.3.27
ML20041F421
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 03/10/1982
From:
GEORGIA POWER CO.
To:
Shared Package
ML20041F414 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.27, TASK-TM TAC-49512, TAC-49513, NUDOCS 8203160483
Download: ML20041F421 (7)


Text

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ATTACHMENT 2 NRC DOCKET 50-366 CPERATING LICENSE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 PROPOSED CHANCES TO TECHNICAL SPECIFICATI0t6 The proposed change to Technical Specifications (Appendix A to Operating License fFF-5) would be incorporated as follows:

Remove Page Insert Page 3/4 3-28 3/4 3-28 0 3/4 3-6 8 3/4 3-6 O483 820310 p gj3gOCK05000321 PDR

TABLE 3.3.3-2 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUENTATION SETPOINTS ALLOWABLE TRIP FUNCTION TRIP SETPOINT VALUE

1. CORE SPRAY SYSTEM
a. Reactor Vessel Water Level - Low Low Low 2 -146.5 inches
  • 2-146.5 inches *
b. Drywell Pressure - High 12 psig 12 psig
c. Reactor Steam Dome Pressure - Low 1500 psig 1500 psig
d. Logic Power Monitor NA NA
2. LOW PRESSURE COOLANT IN.JECTION MODE OF RlR SYSTEM
a. Drywell Pressure - High 12 psig 12 psig u b. Reactor Vessel Water Level - Low Low Low 2.-146.5 inches
  • 1-146.5 inches
  • D c. Reactor Vessel Shroud Level - High > -203.5 inches >-203.5 inches w d. Reactor Steam Dome Pressure-Low 5500psig 3500psig g e. Reacter Steam Dome Pressure-Low <

__335 psig 1335 psig

f. RHR Pump Start - Time Delay Relay
1) Pulips A, B and D 10 + 1 seconds 10 + 1 seconds
2) Pump C 0.5 1 0.5 seconds 0.5 1 0.5 seconds-l g. Logic Power Monitor NA NA
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ATTACFNENT 3 WC DOCKET 50-321 OPERATING LICENSE OPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS The proposed change to Technical Specifications (Appendix A to Operating License DPR-57) would be incorporated as follows:

Remove Page Insert Page 3.2-11 '3.2-11 3.2-22 3.2-22 3.2-61 3.2-61

7 TABLE 3.2-5 -

INSTRUENTATION WHICH INITIATES OR CONTROL THE LPCI HODE of R$

Required Operable-Ref. Trip- Channels No. Condition Per Trip (a) Instrument Nomenclature System (b) Trip Setting Remarks 1 Reactor Water Level (Yarway)

Low Low 2 -> - 146.5 inches Initiates LPCI mode of Rm Low (LL3) 2 Drywell High 2 2 psig Initiates LPCI mode of R$

1 3 Reactor Pressure High (Shutdown 1 i 135 psig With primary containment isola-w Cooling Mode) tion signal, closes Rm (LPCI)

,L inboard motor operated injection r valves Low 2 1 335 psig Permissive to close Recirculation-Discharge Valve and Bypass Valve Low 2 1 500 psig Permissive to open LPCI injection valves 4 Reactor Water Level 1 > - 203.5 inches Acts as permissive to divert (Shroud Level Indicator) some LPCI flow to containment l spray 5 LPCI Cross Connect N/A 1 Valve not closed Initites annunciator when valve is 1

Valve Open Annunciator not closed

TABLE 3.2-11 -

Required Ref. Operable .

No. Instrument Instrument Type and (a) (b) Channels Range Action Remarks 1 Reactor Water Level (GE/MAC 1 Recorder (c) (d) 2 Indicator 0 to 60" (c) (d) 2 Shroud Water Level 1 Recoider (c) (d) 1 Indicator -317" to -17" (c) (d) 3 Reactor Pressure 1 Recorder (c) (d) 2 Indicator 0 to 1200 psig (c) (d) 4 Drywell Pressure 2 Recorder -5 to +80 psig (c) (d) 5 Drywell Temperature 2 Recorder 0 to 5000F (c) (d) y 6 Suppression Chamber Air Temperature 2 Recorder 0 to 5000F (c) (d)

/> 7 Suppression Chamber Water Temperature 2 Recorder O to 2500F (c) (d) 8 Suppression Chamber Water Level 2 Indicator 0 to 300" (c) (d) 2 Recorder 0 to 30" (c)(e) (d) 9 Suppression Chamber Pressure 2 Recorder -5 to +80 psig (c) (d) 10 Rod Position Information System (RPIS) 1 28 Volt Indicating Lights (c) (d) 11 Hydrogen and Oxygen Analyzer 1 Recorder 0 to 52 (c) (d) 12 Post LOCA Radiation Monitoring System 1 Recorder (c) (d)

Indicator 1 to 106 R/hr (c) (d) 13 Drywell/ Suppression Chamber Differential Pressure 2 Recorder -0.5 to + 2.5 psid (c)(e) (d) 14 a) Safety / Relief Valve Position Primary 1 Pressure Switch 4-100 psig (f)

Indicator b) Safety / Relief Valve Position Secondary 1 Temperature element 0-6000F (f)

Indicator

3.2.E.3. Reactor Pressure Lcw (Continued) jection valves. The valves do not open, however, until reactor pressure falls below the discharge head of LPCI.

4. Reactor Water Level (Shroud Level Indicator)

A reactor water level > 203.5 inches below instrument zero is ~

indicative that LPCI has made progress in reflooding the core. A simultaneous high drywell pressure trip indicates the need for containment cooling. The > 203.5 inch setpoint acts as a permissive for manual diversion for some of the LPCI flow to containment spray.

7. LPCI Cross Valve Open Annunciator With the modified LPCI arrangement, the cross connect valve status was changed from nomally open to nomally closed. Inadvertent opening of this valve could negate the LPCI system injection when needed. The annunciator will alarm when the LPCI cross connect valve is not fully closed.
6. RHR (LPCI) Pump Discharge Pressure Interlocks A pressure > 100 psig on the RHR pump discharge indicates that the pump has started successfully. The setpoint provides a permissive signal to ADS which allows ADS initiation if other requirements are met.
7. RHR (LPCI) Pump Flow (op Switch) Low A flow switch is provided downstream of each RHR pump to indicate the condition of each pump. To protect the pumps from overheating at low flow rates a minimum flow bypass line, which routes water from the pump discharge to the suppression chamber, is provided for each pair of pumps. A single motor-operated valve controls the condition of each bypass line. The minimum flow bypass valve automatically opens upon sensing low flow in the discharge lines from both pumps of the associated pump pair. The valve automatically closes whenever the flow from either of the associated main system pumps is above the low flow setting.
8. RFR (LPCI) Pump Start Timers If normal AC power is available, four pumps automatically start without delay. If normal AC power is not available, one pump starts without delay as soon as power becomes available from the standby sources. The other three pumps start after a 10-second delay. The timer provides correct sequencing of the loads to the diesel generator.

3.2-61

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