ML20140D161
| ML20140D161 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/10/1984 |
| From: | Musolf D NORTHERN STATES POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, NUDOCS 8412180331 | |
| Download: ML20140D161 (5) | |
Text
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Northem States Power Company 414 Nicollet Mall Minneapohs Minnesota 55401 Telephone (612) 330-5500 December 10, 1984 Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Preliminary Shunt Trip Technical Specifications Our letter of July 6,1984 provided our response to NRC generic questions related to tha Shunt Trip Modification.
In our response to question 13 we stated that a review of existing testing intervals identified no require-ments for Technical Specification changes. Through discussions with the NRC Project Manager for Prairie Island and a review of Generic Letter 83-28, we have concluded that changes to the Technical Specifications are desireable to reflect the Shunt Trip Modification.
This letter is intended to supplement our July 6, 1984 submittal by providing a preliminary draft of Technical Specification changes incorporating the shunt trip and manual reactor trip requirements requested in the NRC Generic Safety Evaluation Report for the Westinghouse Shunt Trip Modification. We believe these proposed changes will provide adequate assurance that the reactor trip system is maintained in a highly reliable state while providing workable operability and surveillance requirements.
These proposed changes are preliminary in nature and minor changes t.) the format or wording may occur when they are submitted formally in a License Amendment Request.
Please contact us if you have any questions related to l
this information.
g d M -i David Musolf Manager-Nuclear Support S rvices
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c: Regional Administrator-III, NRC NRR Project Manager, NRC Resident Inspector, NRC ho 2
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INSTRUMENT OPERATING CONDITIdNS FOR REACTOR TRIP (Page 1 of 2) 1 4
3
.4 MINIMUM MINIMUM PERMISSIBLS OPERATOR ACTION IF OPERABLE DEGREE OF BYPASS CONDITIONS OF COLUMN FUNCTIONAL UNIT CHANNELS REDUNDANCY CONDITIONS III.
1 OR 2 CANNOT BE MET
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i 1.
Manual 2
1 Notes 3, 4 i
2.
Nuclear Flux Power Range
- low setting 3
2 2 of 4 power Maintain hot shutdown i
high setting 3
2 range channels greater than positive rate 3
2 negative rate 3
2 tt n o y 3.
Nuclear Flux Intermediate 2
1 2 of 4 power Maintain hot shutdown l
Range range. channels Note 2 l
greater than 104'F.P.
4.
Nuclear Flux Source Range 2
1 1.of 2 inter-Maintain hot shutdown mediate range Note 2 channels-greater than 10-3' amps 5
Overtemperature AT 3
2 Maintain hot shutdown 3
2 Maintain hot shutdown 6.
Overpower AT
.7.
Low Pressurizer Pressure 3
2 Maintain hot shutdown i
8.
Hi Pressurizer Pressure 2
1 Maintain hot shutdown 9.
Pressurizer-Hi Water Level 2
1 Maintain hot shutdown f
i 10, Low Flow in one loop 2/lo0P l/lo0P Maintain hot shutdown
(> 10% F.P. )
Low Flow both loops 2/ loop 1/ loop
(> 104 F.P. )
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d W U U-J (Page 2 of 2) 1 2
3 4
MINIMUM MINIMUM PERMISSIBLE OPERATOR ACTION IF OPERABLE DEGREE OF BYPASS CONDITIONS OF COLf1MN III FUNCTIONAL UNIT CHANNELS REDUNDANCY CONDITIONS 1 OR 2 CANNOT BE MET 11.
1 Maintain <50% ot' (Overspeed Protection) rated power 12.
Lo-Lo Steam Generator 2/ loop 1/ loop Maintain hot shutdown Mater Level 13.
Underioltage 4KV RCP Bus 1/ bus 1/ bus Maintain hot shutdown 14 Underfrequency 4KV Bus 1/ bus 1/ bus Maintain hot shutdown Control Rod Himalignment Monitor dh a.
Rod position deviation I
b.
Quadrant power tilt I
TS 3.10 I and TS 3. 10 J 16 RCP Breakers Open 2
1 Safety Injection Maintain hot shutdown 17.
Actuation Signal 2
1 Maintain hot shutdown j
18 Lo Feedwater Flow 1/ loop 1/ loop Maintain h'at shutdown 19.
Reactor Trip Breakers **
2 1
Notes 3, 4 20.
Automatic Trip Logic **
2 1
Notes 3, 4 Note 1: Automatic permissives not listed Note 2: When bypass condition exists, maintain normal operation h
Note 3: With the number of operable channels one less than the minimum operable channels requirement, be in at least hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to
. [jl 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.1, provided the other channel is operable.
.h Note 4: When in the hot shutdown condition with the' number of operable channels one less than the minimum
,Y" operable channels requirement, restore the inoperable channel to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> l
or open the reactor trip breakers within the next hour.
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F.P. = Full Power One additional channel may be taken out of service for low power. physics testing I
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Includes both undervoltage and shunt trip circuits
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TABLE TS.4.1-1 "I{l@[fil;n't,f[!l.. k h! !!9
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Channel Functional Response Description Check Calibrate Test Test Remarks lj 16.
Refueling Water W
R H(1)
NA
- 1) Functional test can be performed Storage Tank Level by bleeding transmitter i
17.
Volume Control Tank 8
R NA
. NA l
18a. Containment Pressure 8
R N(1)
NA Wide Range Containment Pressure SI Signal
- 1) Isolation Valve Signal ISb. Containment Pressure 8
A H
NA Narrow Range Containment Pressure Steam Line Isolation l
18c. Containment Pressure 8
R H
NA Containment Spray i
184. Annulus Pressure NA R
R NA (Vacuum Breaker)
- 19. Auto Load Sequencers NA NA M
NA *
- 20. Boric Acid Hake-up Flow NA R
NA NA g *8 Channel M
- 21. Containment Sump Level NA R
R NA Includes Sumps A, R, and C-g i b
- 22. Accumulator Level 8
R R
NA and Pressure
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- 23. Steam Generator Pressure 8
R H
NA
- 24. Turbine First Stage Pressure S R
H NA E
- 25. Emer8ency Plan Radiation
- H R
H NA Includes those named in the emergency 3
l Instruments procedure (referenced in Spec. 6.5 A.6.)
26a. Protect ton Systema NA NA H
NA Includes reactor trip logic for both the Logic channel Testing undervoltage and shunt trips 26b. Reactor Trip Breakers NA NA M
NA Includes testing of both undervoltage and shunt trips 26c. Manual Reactor Trip NA NA R
NA Includes testing of both undervoltage and dhunt trip circuits
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TABLE TS.4.1-2A
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I d l D '_i" 2 ' f 4U MINIMUM FREOUENCIES FOR EOUIPMENT TESTS FSAR Section Test Frequency-Reference
- 1. Control Rod Assemblies Rod drop times All rods during each 7
of full length refueling shutdown rods or following each removal of the reac-tot vessel head; affected rods follow-ing maintenance on or modification to the control rod drive system which could affect performance of those specific rods
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- 2. Control Rod Assemblies Partial move-Every 2 weeks 7
ment of all rods
- 3. Pressurizer Safety Set point Per ASME Code,Section II -
Valves Inservice Testing Program
- 4. Main Steam Safety Set point Per ASME Code,Section XI -
Valves Inservice Testing Program
- 5. Reactor Cavity Water level Prior to moving fuel assemblies or control rods and at least once every day while the esvity is flooded.
- 6. Pressurizer PORV Functional Quarterly Block Valves
- 7. Pressurizar PORV's Functional Every 18 months
- 8. Deleted
- 9. Primary System Leakage Evaluate Daily 4
- 10. Deleted Monthly (l)
- 11. Turbine stop valves, Functional 10 governor valves, and intercept valves. (Part of turbine overspeed protection.)
- 12. Deleted (1) This test may be waived for and of cycle operations when boron concentrations are less than 150 ppa provided more than 60 days do not elapse following the last test.
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