ML20101R157

Proposed Tech Specs,Revising Addl Group of Surveillances in Which Justification Has Been Completed

ML20101R157
Person / Time
Site:	Three Mile Island
Issue date:	04/10/1996
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20101R139	List: ML20101R136 ML20101R157
References
NUDOCS 9604160076
Download: ML20101R157 (7)

Text

.

I E .

c -

TABLE 4.1-1 h

~4 z .

O INSTRUMENT SURVEILLANCE REQUIREMENTS l CHANNEL DESCRIPTION CHECK TEST CALIBRATE REMARKS n

F 1. Pmtection Channel NA M NA j3 Coincidence logic j! 2. Control Rod Drive Trip NA M NA (1) Includes independent testing of shunt

- Bmaker and Regulating trip and S undervoltage trip features. Rod Power i SCRs

3. Power Range Amplifier D(1) N (2) (1) When reactor power is greater than 15%.  :

1 e (2) When above 15% mactor power run a heat

" balance check once per shift. Heat balance calibration shall be performed whenever heat balance exceeds indicated neutron 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 instrumentation.

(2) When above 15% reactor power calculate i 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 9604160076 960410 PDR ADOCK 05000289 P PDR

3:

h TABLE 4.1-1 (Continued) 3: '

CHANNEL DESCRIlrTION CHECK TEST CALIBRATE REMARKS -

y 19. Reactor Building Emergency -

o Cooling and Isolation -

C System Analog Channels -

J j a. Reactor Building S(l) M(1) R (1) When CONTAINMENT INTEGRITY is required.

L 4 psig Channels j3 b. RCS Pressure 1600 psig S(l) M(1) NA (1) When RCS Pressure > 1800 psig.

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

M pressure switches

{ e. Reactor Bldg. Purge W(1) M(1)(2) F (1) When CONTAINMENT INTEGRITY is required.

lg Line High Radiation (AH-V-1A/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 Tarls

a. Pressure Channels S(l) NA R (1) When Reactor Coolant system pressure is greater j than 700 psig.

b. Level Channels S(l) NA R

26. Pressurizer Level Channels S NA R

K E

o -

K TABLE 4.1-1 (Continued) .

k '

o CHANNEL DESCRIIYrION CHECK TEST CALIBRATE REMAR_KS -

b -

30. Borated Water Storage W NA R Tank I.evel Indicator

31. Boric Acid Mix Tank: DELETED

32. Reclaimed Boric Acid Storage Tank: DELETED ,

33. Containment Temperature NA NA F

34. Incore Neutron Detectors M(1) NA NA (1) Check functioning; including functioning of computer readout or recorder readout

. when reactor power is grater than 15%. '

6

35. Emergency Plant Radiation M(1) NA F (1) Battery check.

Instmments

36. Strong Motion Accelerometer Q(1) NA Q (1) Battery check.

37. Reactor Building Sump NA NA R Ixvel 6

_n - -.- . . .-_ . _ . __- -_ .__.__.- ____----. __-_ _ - - _ _ _ . -. _ . _ . - - - - - - . . - _ - - - - _ . _ _ - - . _ ,- -.

m

$ TABLE 4.1-1 (Continued) -

K l

CHANNEL DESCRIPTION CHECK TEST CAllBRATE REMARKS 8 38. OTSG Full Range Ievel W NA R ,'

is '

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

-ij 41.

. Ievel Indicator a

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 Pressure 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. Loss of Feedwater Reactor Trip S(l) M(1) R (1) When reactor power exceeds 7% power.

46. Turbine 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) When T,y, is greater than 525 F. l -

and PORV Tailpipe Flow Monitors

b. PORV - Acoustic / Flow NA M(1) R (1) When T,y, is greater than 525 F.

48. PORV Setpoints NA M(1) R (1) Per Specification 3.1.12 excluding valve operation.

1

3:

E o -

g -

{z TABLE 4.1-3 Cont'd

• o ,.

ja Item Check Fmquency ,'  ;

l8 '

jg 4. Spent Fuel Pool Water Sample Boron concentration greater than Monthly and after each makeup.

jg or equal to 600 ppmb _

Jo t ij 5. Secondary 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 j . Activity EQUIVALENT I-131 concentration reactor coolant system pmssure ,

Ja is gmater than 300 psig or Tav is ll gmater than 200*F.

6. Deleted

7. Deleted t

8. Deleted  ;

9. Deleted  !

i

10. Sodium Hydroxide Tank Concentration Semi-Annually and after each  ;

makeup.

11. Deleted i l

12. Deleted '

t

1. Until the specific activity of the primary coolant system is mstored within its limits.

i Sample to be taken after a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since the reactor was last ,

subcritical fcr 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.

f 1.--. - - . - .. _ - .- - - - _ - _ . . . _ -

k s

a -

3:

@ TABLE 4.1-4 .

H ~

~

o POST ACCIDENT MONITORING INSTRUMENTATION

~

FUNCTION INSTRUMENTS CHECK _TE_ST CALIBRATE REMARKS

t hm 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 increase in cpm which would msult from the check source alone. Background readings greater than this value are sufficient in themselves to show that this monitor is functioning.

b. Condenser Vacuum Pump Exhaust W(1) M F

, (RM-G25) 9 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 Pmssure W N/A R

4. Containment Water Level W N/A R 5.. Containment Hydrogen W M F

6. Wide Range Neutron Flux W N/A F

! . UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION l

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

This is to certify that a copy of Technical Specification Change Request No. 243 to Appendix 1 A of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date l given below, been filed with executives of Londonderry Township, Dauphin County, Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania Department of Environmental Resources, Bureau of Radiation Protection, by deposit in the United States mail, addmssed as follows:

I l Mr. Darryl LeHew, Chairman Mr. Russell L. Sheaffer, Chairman  ;

Board of Supervisors of Board of County Commissioners j Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Courthouse  ;

Middletown, PA 17057 Harrisburg, PA 17120 l

l Director, Bureau of Radiation Protection PA. Dept of Environmental Resources Rachael Carson State Office Building,13th Floor ,

P.O. Box 8469 Harrisburg, PA 17105-8469 >

l Att: Mr. Stanley P. Maingi i

I GPU NUCLEAR CORPORATION j BY:

ice President and Director, TMI DATE: d M,/f b a

i