ML20028H096
| ML20028H096 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/25/1990 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | GPU Nuclear Corp, Jersey Central Power & Light Co, Metropolitan Edison Co, Pennsylvania Electric Co |
| Shared Package | |
| ML20028H097 | List: |
| References | |
| DPR-50-A-156 NUDOCS 9010090109 | |
| Download: ML20028H096 (7) | |
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o UNITED STATES-
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NUCLEAR REGULATORY COMMISSION.
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- WASHINGTON, D, C,20555
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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.156 License No. DPR-50.
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-The Nuclear Regulatory Commission (the Commission) hasLfound that:
. A.
The-application for amendment by GPU Nuclear Corporation, et al.
(the licensee) dated July 26, 1989, complies with'the standards and requirements of the Atomic Energy Act of'1954, as~ amended
' t (the Act), and the Commission's rules and regulations set forth
..l in'10 CFR Chapter I; 4
Y B.
The facility will operate in conformity with the application, a
the provisions of the Act, and the rules and regulations of the Commission; q
C.
There is reasonable assurance (i) that the activities authorized i
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; 1
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of tie 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.
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Accordingly the license is amended by chan es to the Technical Specifications as indicated in the attachment to this license amendment, and paragraphs 2.c.(2) of Facility Operating License No.
DPR-50 are hereby amended to read as follows:
(2) Technical Specifi, cations The Technical Specifications contained in~ Appendix A, as revised through Amendment No. 156, are bereby 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 i's date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMISSION i
o Jo n F. Stolz, Director l
V P oject Directorate I-4 ivision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 25, 1990 4
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i-ATTACHMENT TO LICENSE AMENDMENT NO.iS6' FACILITY OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289
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Replace the following pages of the Facility Operating-License and the Appendix-A Technical Specifications with the attachea pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
4 Remo se Insert
-viii viii L* Figure 3.5 - 2K
- Figure 3.5 - 2L 1
4-2 4-2 4-5 4-5 4-Sa 4-Sa t
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- These figures were deleted by Amendment No. 150 i
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I LIST OF FIGURES Figure Title 3.5-2K thru DELETED 3.5-2L 3.5-2M LOCA Limited Maximum Allowable Linear Heat Rate 3.5-1 Incore Instrumentation Specification Axial Imbalance Indication, TMI-1 3.5-2 Incore Instrumentation Specification Radial Flux Tilt Indication, TMI-1 3.5-3 Incore Instrumentation Specification 3.11-1 Transfer Path to and from Cask Loading Pit 4.17-1 Snubber Functional Test - Sample Plan 2 i.
5-Extended Plot Plan TMI 5-2 Site Topography 5 Mile Radius 5-3 Locations of Gaseous Effluent Release Points and Liquid Effluent Outfalls
(
viii Amendment Nos. 72, JJ,179, 3)p, JA2, AA), AAD,156
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i Calibration.
- Calibration shall be performed'to assure the presentation and acquisition of accurate information. The nuclear flux (power range)
- channels amplifiers shall=be checked and calibrated if necessary, g
every shift against-a heat balance standard. The frequency of heat balance checks will assure that the difference between the
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sut-of-core instrumentation and the heat balance remains less than t'
4%.
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 perfer# at the intervals of each refueling period, t
Substantial calibration shifts within a channel (essentially a channe'. failure) will be revealed during routine checking and testing procedures.
Ths, minimum calibration frequencies set forth are considered acceptable.
Testing On-line testing of reactor protection channels is required-monthly on o
a rotational basis.
The rotation scheme is designed to reduce the L
. probability of an undetected failure existing within the system and r
- tp minimize the likelihood of the same systematic test errors being L
introduced into each redundant channel.
The rotation schedule for the reactor protection channels is as follows:
al Channels A, B, C 4.0 Before Startup, when shutdown greater
. than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and in b) Monthly with one channel being tested per week on a centinuous sequential rotation.
- 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 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 De required that actuation was within the limiting safety system setting.
M
' e protection channels coincidence logic, the control rod drive trip
..eakers Ad the regulating control rod power SCRs electronic trips, are trip.sted monthly.
The trip test checks all logic combinations g
and is to be performed on a rotational basis.
The logic and breakers e
of the four protection channels and.the regulating control rod power J1 SCRs shall be trip tested prior to startup when the reactor has been i
shutdown for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Discovery of a failure that prevents trip action requires the testing of the-instrumentation associated with the protection parameter failure in the remaining channels.
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- Amendment No. '/d, fif, igd,156 h
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TABLE 4.1-1 (Continued)
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'5 CHANNEL DESCRIPTION.
CHECK TEST CALIBRATE REMARKS
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- 19. Reactor Building. Emergency.
Cooling and Isolation M
System Analog' Channels M
- a. Reactor Building
~S(1)
M(1)
R (1) When CONTAllplENT INTEGRITY is required 4 psig Channels G
- b. RCS Pressure 1600 psig S(1)
M(1)
NA (1) When RCS Pressure > 1800 psig.
- c. RPS Trip S(1)
.M(1)
' NA (1) When CONTAlle9ENT INTEGRITY is required
- d. Reactor Bldg. 30 psig S(1)
M(1)
R
.(1) When CONTAll#9ENT INTEGRITY.is required
- e. Reactor Bldg. Purge W(1)
M(1)
R (1) When CONTAINMENT INTEGRITY is required Line High Radiation (AH-V-IA/D)
- f. Line Break Isolation W(1)
M(1)
R (1) When CONTAll#9ENT INTEGRITY is required Signal (ICCW & NSCCW)
- 20. Reactor Building Spray NA
'Q NA System Logic Channel e
21.
Reactor Building Spray in System Analog Channels a.
Reacter Building NA M
R 30 psig Channels 22.
Pressurizer Temperature 5
NA R
Channels
- 23. Control Rod Absolute Position S(1)
NA R
(1) Check with Relative Position Indicator 24.
Control Rod Relative Position S(1)
NA R
(1) Check'with Absolute Position Indicator
- 25. Core Flooding Tanks a.
Pressure Channels S(1)
NA R
(1) When Reactor Coolant system pressure.1s greater than 700 psig b.
Level Channels S(1)
NA R
- 26. Pressurizer Level Channels
.S NA R
- 27. Makeup Tank Level Channels D(1)
NA R
(1) When Makeup and Purification System.is-in operation b
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TABLE 4.1-1 (Continued).
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CHANNEL DESCRIPTION CHECK TEST CALIBRATE REMARKS
- 28. Radiation Monitoring Systems
- W(1)(3)
M(3)
Q(2):
-(1) Using the installed check source when
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background is less than twice the
~ Ed expected increase in cpu which would result fran the check source alone.
' ?2 Background readings greater than'this value are sufficient in thems61ves.to show that the monitor is' functioning.
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Et (2) Except area gamma radiation monitors G;
RM-GS, RM-G6, RM-G7, RM-68, and RM-G21, which are located in the Reactor i
Building. When purging is permitted per T.S. 3.6, RM-G5 and RM-G21 will be calibrated quarterly.
If purging is not permitted per T.S. 3.6, RM-GS and IM-G21 shall be calibrated at the next i
scheduled reactor shutdown following the quarter in which calibration would a
Si normally be due. RM-G6, RM-G7, and RM-G8 which are in high radiation areas shall be calibrated at the next i
scheduled reactor shutdown following the quarter in which' calibration is due, if a shutdown during the quarter does not occur.
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(3) Surveillances are required to be performed only when containment integrity is required. This applies to 4
monitors which initiate containment isolation only.
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High and Low Pressure NA-NA R
Injection. Systems:
Flow Channels i
- Does not include the monitors covered under Specifications 3.5.5.2 and 4.1.3 or Specifications 3.21.1, 3.21.2 and 4.21.1, 4.21.2.
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