ML20101F314
| ML20101F314 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/21/1996 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp |
| Shared Package | |
| ML20101F317 | List: |
| References | |
| DPR-50-A-200 NUDOCS 9603250450 | |
| Download: ML20101F314 (8) | |
Text
.
1 UNITED STATES y
j NUCLEAR REGULATORY COMMISSION
%,.....[#
WASHINGTON. D.C. M1 METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION. UNIT N0. 1 AMENDMENT TO FACILITY QPERATING LICENSE Amendment No. 200 License No. DPR-50 1.
The Nuclear Regulatory Commission (the Comission or NRC) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.
(the licensee) dated August 10, 1995, as supplemented on December 21, 1995 and February 22, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR 'hapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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.
9603250450 960321 PDR ADOCK 05000289 P
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.c.(2) of Facility Operating License No.
DPR-50 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 200, are hereby incorporated in the license.
.GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
)
J n F. Stolz, Dired;or oject Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 21, 1996
4 ATTACHNENT TO LICENSE AMENDMENT NO. 200 FACILITY OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289
' Replace the following pages of the Appendix A, Technical Specifications, with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Insert 3-32 3-32 4-2a 4-2a 4-5 4-5 4-10 4-10 4-46 4-46 l
I
~.
TABLE 3.5-1 (Cont'd)
INSTRUMENTS OPERATING CONDITIONS t
g Functional Unit (A)
(B)
(C) m Minimum Operable Minimum Degree Operator Action if Conditions Channels of Redundancy of Column A and B Cannot Be Met K
{
C. Eneineered Safety Fesitures (cant'd)
- 3. Reactor Building Isolation and
,3 Cooling System w
a.
Reactor Bldg. 4 psig Instrument Channel 2
1(b)
.(a) b.
Manual Pushbuttons 3
- i. 4 psig feature 2
N/A (g) i m
,9 ii. 30 psig feature 2
N/A (g) c.
Deleted
- d. Reactor Building 30 psig pressure switches 2
1 (c) c.
RCS Pressure less than 1600 psig 2
1(b)
(a) f.
Reactor Building Purge Line Isolation 1
0 (f)
(AH-VIA and AH-VID) High Radiation 4.
Reactor Building Spray System a.
Reactor Building 30 psig pressure switches 2
1 (d) l
- b. Spray Pump Manual Switches 2
N/A (g)
- 5. 4.16KV ES Bus Undervoltage Relays a.
Degraded Grid Voltage Relays 2
1 (e)
- b. Loss of Voltage Relay 2
1 (e)
bees (Cont'd.)
i Channels subject only to " drift" errors induced within the instrumentation itself can tolerate longer intervals between calibrations. Process system instrumentation errors induced by drift can be expected to remain within acceptance tolerances if recalibration is performed at the mtervals of each refueling period, i
J Substantial calibration shifts within a channel (essentially a channel failure) will be revealed j
during routine checking and testing procedures.
1 Thus, minimum calibration frequencies set forth are considered acceptable.
3 1
Testing On-line testing of reactor protection channels is required monthly on a rotational basis. The J
rotation scheme is designed to reduce the probability of an undetected failure existing within the system and to minimize the likelihood of the same systematic test errors being introduced into each redundant channel (Reference 1).
3 The rotation schedule for the reactor protection channels is as follows:
a) Deleted l
l b) Monthly with one channel being tested per week on a continuous sequential rotation.
l The reactor protection system instrumentation test cycle is continued with one channel's instrumentation tested each week. Upon detection of a failure that prevents trip action in a i
channel, the instrumentation associated with the protection parameter failure will be tested in the remaining channels. If actuation of a safety channel occurs, assurance will be required that 4
actuation was within the limiting safety system setting, j
The protection channels coincidence logic, the control rod drive trip breakers and the regulating control rod power SCRs electronic trips, are trip tested monthly. The trip test checks all logic combinations and is to be performed on a rotational basis.
I i
Discovery of a failure that prevents trip action requires the testing of the instrumentation associated with the protection parameter failure in the remaining channels.
i For purposes of surveillance, reactor trip on loss of feedwater and reactor trip on turbine trip are considered reactor protection system channels.
1 i
4 e
i I
k 4-2a 1
Amendment No. 78,157, lei, 200
b b
TABLE 4.1-1 (Continued)
Ey CHANNEL DESCRIPTION CHECK TEST CALIBRATE REMARKS m
- 19. Reactor Building E.m.uay 2
Cooling and Isolation O
System Analog Channels M.*
=
a.
Reactor Building S(l)
M(1)
F (1) When CONTAINMENT INTEGRITY is l
L 4 psig Channels required.
K b.
RCS Pressure 1600 psig S(l)
M(1)
NA (1) When RCS Pressure > 1800 psig.
~
c.
Deleted i
5
- d. Reactor Bldg. 30 psig S(l)
M(1)
F (1) When CONTAINMENT INTEGRITY is
- s pressure switches required.
e.
Reactor Bldg. Purge W(1)
M(1)(2)
F (1) When CONTAINMENT INTEGRITY is 1
-g Line High Radiation required.
(AH-VIA/D) f.
Line Break Isolation W(1)
M(1)
R (1) When CONTAINMENT INTEGRITY is i
Signal (ICCW & NSCCW) required.
- 20. Reactor Building Spray NA Q
NA System Igic Channel
- 21. Reactor Building Spray NA M
F 30 psig pressure switches
- 22. Pressurizer Temperature S
NA R
t 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 F
(1) When Reactor Coolant system pressure is greater than 700 psig.
i
- b. level Channels S(l)
NA F
- 26. Pressurizer level Channels S
NA R
..c.
..-s
TABLE 4.1-3 Cont'd.
m Ilcm Check Frei m 3:
~
{
4.
Spent Fuel Pool Boron concentration greater than Monthly and after each makeup.
Water Sample or equal to 600 ppmb 2o gn 5.
Secondary Coolant 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 c>3 System Activity EQUIVALENT I-131 concentration reactor coolant s stem pressure 3
is greater than psig or Tav 3
is greater than 200*F.
5 6.
Boric Acid Mix Tank or Boron concentration Twice weekly ***
Reclaimed Boric Acid Tank g
7.
Deleted 8.
Deleted o
9.
Deleted
- 10. Sodium Hydroxide Tank Concentration Semi-Annually and after each makeup.
- 11. Deleted
- 12. Deleted Until the specific activity of the primary coolaat 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 6 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.
- Deleted
- The surveillance of either the Boric Acid Mix Tank or the Reclaimed Boric Acid Tank is not necessary when that respective tank is empty.
l-4.6 EMERGENCY POWER SYSTEM PERIODIC TESTS Applicability: Applies to periodic testing and survrillance requirement of the emergency power system.
i l
l Obiective:
To verify that the emergency power system will respond promptly and properly when required.
2 Snecifwinn:
l The following tests and surveillance shall be rerformed as stated:
4.6.1 Diesel Generators i
a.
Manually-initiate start of the diesel generator, followed by manual synchronintian
' with other power sources and assumption of load by the diesel generator up to the i
name-plate rating (3000 kw). This test will be conducted every month on each diesel generator. Normal plant operation will not be effected.
b.
Automatically start and loading the s. My diesel generator in accordance with Specification 4.5.1.1.b/c including the folowag. Ilus test will be conducted every l
refueling interval on 'ench diesel generator.
(1) Verify that the diesel generator starts from ambient condition upon receipt of the ES signal and is ready to load in s 10 seconds.
I 1
(2) Verify that the diesel block loads upon simulated loss of offsite power in s30 seconds.
1 (3) The diesel operates with the permanently connected and auto c+vatM load 4
for 25 minutes.
1 (4) The diesel engine does not trip when the generator breaker is opened while 1
carrymg emergency loads.
i 1
(5) The diesel generator block loads and operates for 25 minutes upon reclosure of the diesel generator breaker.
Each diesel gmEcr shall be given an inspection at least annually in accordance l
c.
j with the manufacturer's recommendations for this class of stand-by service.
i 4.6.2 Station Batteries I
The voltage, specific gravity, and liquid level of each cell will be measured and a.
i recorded:
(1) every 92 days (2) once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after a battery discharge < 105 V 4
(3) once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after a battery overcharge > 150 V (4) If any cell parameters are not met, measure and record the parameters-on each connected cell every 7 days thereafter until all battery parameters are met, b.
The voltage' and specific gravity of a pilot cell will be measured and recorded weekly. If any pdot cell parameters are not met, perform surveillance 4.6.2.a on each coamM cell within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and every 7 days thereafter until all battery parameters are met, Each time data is recorded, new data shall be compamd with old to detect signs of c.
abuse or deterioration.
4-46 Amendment No. 70, 149, 157 200