ML20112C879

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Proposed Tech Specs Re Pages for App A.Certificate of Svc Encl
ML20112C879
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 05/24/1996
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20112C872 List:
References
NUDOCS 9606030102
Download: ML20112C879 (7)
v • d • e


Text

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% TABLE 4.1-1 ,

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z o INSTRUMENT SURVEII1ANCE REQUIREMENTS jn -

13 J' CHANNEL DESCRIFFION CHECK TEST CALIBRATE REMARKS

5 2" '
1. Pmtection Channel NA M NA j$ Coincidence Imgic j$ 2. Control Rod Drive Trip NA M NA (1) Includes independent te-sting of shunt Breaker and Regulating trip and 3 undervoltage trip features. Rod Power SCRs r
3. Power Range Amplifier D(1) N (2) (1) When reactor power is greater than 15 %.

e (2) When above 15% reactor power mn a heat

'd balance check once per shift. Heat balance calibration shall be performed whenever heat balance exceeds indicated neutmn power by more than two percent.

4. Power Range Channel S M M(1)(2) (1) When reactor power is greater than 60%

verify imbalance using incore instmmentation.

(2) When above 15% reactor power calculate axial offset upper and lower chambers after each startup if not done within the previous seven days.

5. Intermediate Range Channel S(l) PS/U NA (1) When in service.
6. Source Range Channel S(l) PS/U NA (1) When in service.
7. Reactor Coolant Temperature S M R Channel 9606030102 960524 PDR ADOCK 05000289 p PDR

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E TABLE 4.1-1 (Continued) a

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@ CHANNEL DESCRIPTION CHECK TEST CALIBRATE REMARKS ,

-i y 19. Reactor Building Emergency o Cooling and Isolation '

C System Analog Channels Ja y a. Reactor Building S(l) M(1) R (1) When CONTAINMENT INTEGRITY is required.

n 4 psig Channels j b. RCS Pressure 1600 psig S(l) M(1) NA (1) When RCS Pressure > 1800 psig.

3 c. Deleted '

2

d. Reactor Bldg. 30 psig S(l) M(1) R (1) When CONTAINMENT INTEGRITY is required.

G pressure switches f, e. Reactor Bldg. Purge W(1) M(1) F (1) When CONTAINMENT INTEGRITY is required.

g Line High Radiation (AH-V-1 A/D)
f. Line Break Isolation W(1) M(1) R (1) When CONTAINMENT INTEGRITY is required.

Signal (ICCW & NSCCW)

20. Reactor Building Spray NA Q NA y System Logic Channel
21. Reactor Building Spray NA M R 30 psig pressure switches
22. Pressurizer Temperature S NA R Channels
23. Control Rod Absolute Position S(l) NA R (1) Check with Relative Position Indicator.
24. Control Rod Relative Position S(l) NA R (1) Check with Absolute Position Indicator.
25. Core Flooding Tanks
a. Pressure Channels S(l) NA R (1) When Reactor Coolant system pressure is greater than 700 psig.
b. Level Channels S(l) NA R
26. Pressuri1.er Level Channels S NA R

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I TABLE 4.1-1 (Continued) -

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$ CHANNEL DESCRIFFION CHECK TEST CALIBRATE REMARKS '

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30. Borated Water Storage W NA R Tank Level Indicator
31. Boric Acid Mix Tank: DELETED
32. Reclaimed Boric Acid Storage Tank: DELETED
33. Containment Temperature NA NA F
34. Incore Neutmn Detectors M(1) NA NA (1) Check functioning; including functioning of computer readout or mcorder madout u when reactor power is grater than 151
35. Emergency Plant Radiation M(1) NA F -(1) Battery check.

Instmments

36. Strong Motion Accelerometer Q(1) NA Q (1) Batteg check.
37. Reactor Building Sump NA NA R Level

. _ _ _ _ _ . _ _ _ - - - _ _ _ _ . - - - _- -_ _ _ _ _ _ - - _ = - _ _ _ - _ - . _ _ _ . _ _ - _ _ . - _ _ . __ .-_ -_

I m .

$ TABLE 4.1-1 (Continued)

?

l CHANNEL DESCRIPTION CHECK TEST _ CALIBRATE REMARKS .

8 38. OTSG Full Range Level W NA R

s -

]g 39. Turbine Overspeed Trip NA R NA 3 40. BWST/NaOH Differential NA NA F g Pressure Indicator ji 41. Sodium Hydroxide Tank NA NA F 1 Level Indicator is

42. Diesel Generator Protective NA NA R Relaying
43. 4 KV ES Bus Undervoltage Relays (Diesel Start)

$ a. Degraded Grid NA M(1) R (1) Relay operation will be checked by local test pushbuttons.

b. Loss of Voltage NA M(1) R (1) Relay operation will be checked by local test pushbuttons.
44. Reactor Coolant Pressum S(l) M R (1) When reactor coolant system is DH Valve Interlock Bistable pressurized above 300 psig or T,y, is greater than 200 F.
45. Imss of Feedwater Reactor Trip S(l) M(1) R (1) When mactor power exceeds 7% power.
46. Tuitine Trip / Reactor Trip S(l) M(1) F (1) When reactor power exceeds 45 %

power.

47. a. Pressurizer Code Safety Valve S(l) NA R (1) ~Vhen T,y, is greater than 525 F.

and PORV Tailpipe Flow Monitors

b. PORV - Acoustic / Flow NA M(1) R (1) When T oy , is greater than 525*F.
48. PORV Setpoints NA M(1) R (1) Per Specification 3.1.12 excluding valve operation.

- . .. . . . _ . . . _ - . . ~ . - _ . . . .. . .- .. . . _.- . . .- - . - .. . .

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.E TABLE 4.1-3 Cont'd ,

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p Item Check Freauency .

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]g 4. Spent Fuel Pool Water Sample Boron concentration gmater than Monthly and after each makeup.

j; or equal to 600 ppmb Jc ij 5. Seconday Coolant System Isotopic analysis for DOSE At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when  !

h Activity EQUIVALENT I-131 concentration mactor coolant system pressure ja is greater than 300 psig or Tav is y greater than 200*F.

6. Deleted
7. Deleted

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8. Deleted
9. Deleted
10. Sodium Hydroxide Tank Concentration Semi-Annually and after each makeup.
11. Deleted
12. Deleted
  1. Until the specific activity of the primary coolant system is restored within its limits.
  • Sample to be taken after a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since the reactor was last subcritical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.

h

_ . _ . _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ . __.________.___m_ _ _ _ _ _ - _ _ <. . _ _ _ - - , . _ _ _ _ _ _.___mm ._ .

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3:

S TABLE 4.1-4 .

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E POST ACCIDENT MONITORING INSTRUMENTATION ii L FUNCTION INSTRUMENTS CHECK TEST CALIBRATE REMARKS

t j 1. Noble Gas Effluent
a. Condenser Vacuum Pump Exhaust W M F (1) Using the installed check source when background is (RM-A5-Hi) less than twice the expected incmase in cpm which would result from the check source alene. Background madings greater than this value are sufficient in themselves to show that this monitor is functioning.
b. Condenser Vacuum Pump Exhaust W(1) M F i ,

(RM-G25)

E c. Auxiliary and Fuel Handling W M F Building Exhaust (RM-A8-Hi)

d. Reactor Building Purge Exhaust W M F (RM-A9-Hi)
e. Reactor Building Purge Exhaust W(1) M F (RM-G24)
f. Main Steam Lines Radiation W(1) M F (RM-G26/RM-G27)
2. Containment High Range Radiation W M R (RM-G22/G23)
3. Containment Pressure W N/A R
4. Containment Water Level W N/A R
5. Containment Hydrogen W M F
6. Wide Range Neutmn Flux W N/A F ,

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1

- - UNITED STATES OF AMERICA

- NUCLEAR REGULATORY COMMISSION i

CERTIFICATE OF SERVICE IN THE MA' ITER OF DOCKET NO. 50-289 j GPU NUCLEAR CORPORATION LICENSE NO. DPR 50 1

This is to certify that a copy of Technical Specification Change Request No. 243 to Appendix A of the Operating License 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 l; Envisunmental Resources, Bureau of Radiation Protection, by deposit in the United States

. mail, addressed as follows:

Mr. Darryl 12 Hew, Chairman Mr. Russell L. Sheaffer, Chairman j Board of 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 i l

Director, Bureau of Radiation Protection  !
PA. Dept of Environmental Resources l Rachael Carson State Office Building,13th Floor
P.O. Box 8469
Harrisburg, PA 17105-8469

} Att: Mr. Stanley P. Maingi l

4 4

GPU NUCLEAR CORPORATION s

BY:

Vice PWisident and Direct 6r, TMI DATE: [ , ,d,' FA I i

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