ML20209G848

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Amend 35 to License NPF-35,revising Tech Specs to Permit Raising Main Steam Line Radiation Monitor Tech Spec Setpoint from Three Times Background to Seven Times Background Radiation
ML20209G848
Person / Time
Site: Susquehanna Talen Energy icon.png
Issue date: 04/22/1987
From: Butler W
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20209G815 List:
References
NUDOCS 8705010084
Download: ML20209G848 (8)
v • d • e


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UNITED STATES 8' 3 T n NUCLEAR REGULATORY COMMISSION

{ ' .$ WASHINGTON, D. C. 20$55 t ,f U$

9 ***** ,o' PENNSYLVANIA POWER & LIGHT COMPANY

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ALLEGHENY ELECTRIC COOPERATIVE. INC.

DOCKET NO. 50-388 SUSOUEHANNA STEAM ELECTRIC STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 35 License No. NPF-22

1. The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A. The application for the amendment filed by the Pennsylvania Power & l Light Company (PP&L), dated June 23, 1986, complies with the standards  ;

and requirements of the Atomic Energy Act of 1954, as amended (the Act), i and the Commission's regulations set forth in 10 CFR Chapter I; I B. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endanoerino the health and  ;

safety of the public, and (ii) that such activities will be conducted 1 in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the enclosure to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-22 is hereby amended to read as follows:

(2) _ Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 35 and the Environmental Protection Plan con-tained in Appendix B, are hereby incorporated in the license. PP&L shall operate the facility in accordance with the Technical Specifica-tions and the Environmental Protection Plan.

8705010084 870422 PDR P ADOCK 05000388 PDR

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3. This amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/s/

l Walter R. Butler, Director i Project Directorate No. I-2 i Division of Reactor Projects - I/II

Enclosure:

Changes to the Technical Specifications Date of Issuance: April 22, 1987

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3. This amendment is effective as of the date of issuance. -

d FOR THE NUCLEAR REGULATORY COMMISSION a

i k /!?. k;)hu .lk Walter R. Butler, Director Project Directorate No. I-2 j Division of Reactor Projects - I/II 4

Enclosure:

i Changes to the Technical Specific ilons Date of Issuance: April 22, 1987 l

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1 ENCLOSURE TO LICENSE AMENDMENT h0. 35 FACILITY OPERATING LICENSF NO. NFF-2?

DOCKET NO. 50-388 Peplace the following paces of the Appendix A Technical Specifications with enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE INSERT 2-3 2-3(overleaf) 2-4 2-4 3/4 3-17 3/4 3-17 3/4 3-IP 3/4 3-18(overleaf)

. t SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS l

2.2 LIMITING SAFETY SYSTEM SETTINGS a

REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS 2.2.1 The reactor protection system instrumentation setpoints shall be set consistent with the Trip Setpoint values shown in Table 2.2.1-1.

APPLICABILITY: As shown in Table 3.3.1-1.

ACTION:

l With a reactor protection system instrumentation setpoint less conservative i

than the value shown in the Allowable Values column of Table 2.2.1-1, declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1 until the channel is restored to OPERABLE status with its setpoint adjusted consistent with the Trip Setpoint value.

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SUSQUEHANNA - UNIT 2 1

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TABLE 2.2.1-1 l REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS I E ALLOWABLE l E FUNCTIONAL UNIT TRIP SETPOINT VALUES Ni

! 5 1. Intermediate Range Monitor, Neutron Flux-High < 120/125 divisions < 122/125 divisions j Ef full scale Bf full scale e 2. Average Power Range Monitor:

e a. Neutron Flux-Upscale, Setdown -< 15% of RATED THERMAL POWER < 20% of RATED 5

- THERMAL POWER m b. Flow Biased Simulated Thermal Power-Upscale

1) Flow Biased < 0.58 W+59% , with <0.58W+62d,with a maximum of a maximum of
2) High Flow Clamped < 113.5% of RATED < 115.5% of RATED l THERMAL POWER THERMAL POWER
c. Neutron Flux-Upscale -< 118% of RATED THERMAL POWER < 120% of RATED THERMAL POWER
d. Inoperative NA NA 1 3. Reactor Vessel Steam Dome Pressure - High 5 1037 psig i 1057 psig
4. Reactor Vessel Water Level - Low, Level 3 > 13.0 inches above > 11.5 inches above Instrument zero* Instrument zero l S. Main Steam Line Isolation Valve - Closure i 10% closed i 11% closed
6. Main Steam Line Radiation - High < 7.0 x full power < 8.4 x full power Background Sackground
7. Drywell Pressure - High 1 1.72 psig i 1.88 psig l 8. Scram Discharge Volume Water Level - High i a. Level Transmitter < 88 gallons < 88 gallons i g b. Float Switch 588 gallons {88 gallons l

{2 9. Turbine Stop Valve - Closure

10. Turbine Control Valve Fast Closure,

< 5.5% closed < 7% closed 3 Trip Oil Pressure - Low > 500 psig > 460 psig f 11. Reactor Mode Switch Shutdown Position NA NA 4 g 12. Manual Scram NA NA l "See Bases Figure B 3/4 3-1. ..

l #See Specification 3.4.1.1.2.a for single loop operation requirements.

TABLE 3.3.2-2 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS 1E E ALLOWABLE

$ TRIP FUNCTION TRIP SETPOINT VALUE 2"

1. PRIMARY CONTAINMENT ISOLATION e a. Reactor Vessel Water Level

! i'E 1) Low, Level 3 >13.0 inches * > 11.5 inches

  • i -45.0 inches
2) Low Low, Level 2 . i -38.0 inches *

" Low Low Low, Level 1 5 -129 inches

  • I -136 inches 3)
b. Drywell Pressure - High 7 1.72 psig i 1.88 psig
c. Manual Initiation HA NA i d. SGTS Exhaust Radiation - High < 23.0 mR/hr < 31.0 mR/hr l
e. Main Stean Line Radiation - High 37.0Xfullpowerbackground?8.4Xfullpowerbackground 1 2. SECONDARY CONTAINMENT ISOLATION w a. Reactor Vessel Water Level -

A Low Low, Level 2 1 -38.0 inches * > -45.0 inches Y b. Drywell Pressure - High 5 1.72 psig 5 1.88 psig

" Refuel Floor High Exhaust Duct c.

Radiation - High 5 2.5 mR/hr** $ 4.0 mR/hr**

Railroad Access Shaft Exhaust d.

Duct Radiation - High 1 2.5 mR/hr** i 4.0 mR/hr**

e. Refuel Floor Wall Exhaust Duct Radiation - High 1 2.5 mR/hr** 5 4.0 mR/hr**
f. Manual Initiation NA NA g 3. MAIN STEAM LINE ISOLATION

$ a. Reactor Vessel Water

,& Level - Low Low Low, Level 1 > -129 inches * > -136 inches 5 b. Main Steam Line Radiation - High 5 7.0 X full power background 5 8.4 X full power background

,F c. Main Steam Line Pressure,- Low > 861 psig > 841 psig 11

d. Main Steam Line Flow - High 5 107 psid 5 110 psid

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l TABLE 3.3.2-2 (Continued)

I h ISOLATION ACTUATION INSTRUNENTATION SETPOINTS E

l g ALLOWA8LE

3 TRIP FUNCTION TRIP SETPOINT VALUE

! 5 MAIN STEAM LINE ISOLATION (Continued)

I E e. Condenser Vacuum - Low 1 9.0 inches Hg vacuum 2 8.8 inches Hg vacuum U f. Reactor Building Main Steam Line N

i Tunnel Temperature - High 1 177*F $ 184*F

g. Reactor Building Main Steam Line j Tunnel A Temperature - High 5 99'F $ 108'F i

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h. Manual Initiation NA NA i
1. Turbine Building Main Steam Line Tunnel Temperature - High 1 177'F $ 184*F i

g 4. REACTOR WATER CLEANUP SYSTEM ISOLATION ,

j w a. RWCU A Flow - High $ 60 gpm i 80 gpm l h b. RWCU Area Temperature - High 5 147*F or 118.3*F# $ 154*F or 125.3*F#

c. RWCU/ Area Ventilation A

, . Temperature - High ~ $ 69*F or 35.3*F# $ 78*F or 44.3*F#

d. SLCS Initiation MA NA
e. Reactor Vessel Water Level -

tow Low, Level 2 1 -38 inches

  • 1 -45 inches
f. RWCU Flow - High 5 426 gpa 5 436 gym l

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! g. Manual Initiation MA NA ,

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5. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION N

) g a. RCIC Steam Line A Pressure - High $ 153" H2 0** 1 165" H2 0** l l I b. RCIC Steam Supply Pressure - Low 1 60 psig 1 53 psig

! E c. RCIC Turbine Exhaust Diaphragm y Pressure - High 5 10.0 psig 5 20.0 psig '8 L

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