ML20065C888
| ML20065C888 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 03/29/1994 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20065C892 | List: |
| References | |
| GL-90-06, GL-90-6, NUDOCS 9404060095 | |
| Download: ML20065C888 (12) | |
Text
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UNITED STATES
., -[
j NUCLEAR REGULATORY COMMISSION t
WASHINGTON. D.C. M0001
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CONSUMERS POWER COMPANY DOCKET N0. 50-255 4
PALISADES PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.160 License No. DPR-20 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.' The application for amendment by Consumers Power Company (the licensee). dated April 15, 1992, as modified by letters dated December 8, 1992, June 25, 1993, and February 2, 1994, 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 Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) 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 common defense and security or to the health and safety of the public; 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to the license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-20 is hereby amended to read as follows:
9404060095 940329 PDR ADOCK 05000255 p
i Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.160, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of issuance with full implementation within 60 days.
1 FOR T UCLEAR REGULATORY COMMISSION Ser L. B. Marsh, Director 4
Project Directorate III-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical 4
Specifications 1
Date of Issuance: March 29, 1994 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 160' FACILITY OPERATING LICENSE NO, DPR-20 DOCKET N0. 50-255 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by.
amendment number and contain vertical lines indicating the areas of change.
REMOVE INSERT J
3-25a 3-25a
~3-25b 3-25b 3-25d l
3-25e 3-25f 3-25g 3-81a 3-81a 4-le 4-le 4-2 4-2 I
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'3.1.8' OVER PRESSURE PROTECTION SYSTEMS Soecifications i
i 3.1.8.1 Two PORV flow paths, each consisting of an OPERABLE PORV and an OPERABLE block valve, shall be OPERABLE.
Acolicability Specification 3.1.8.1 is applicable when the temperature of all PCS i
' ' l egs i s ;t 430
- F.
Action
- a. With one PORV flow path inoperable:
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- 1. For each inoperable block valve, place the associated PORV control in the "CLOSE" position within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- 2. For each inoperable PORV, close the associated block valve within I hour.
- 3. Restore both PORV flow paths to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
- b. With two PORV flow paths inoperable:
- 1. For each inoperable block valve, place the associated PORV control in the "CLOSE" position within I hour.
- 2. For each inoperable PORV, close the associated block valve within I hour.
3.- Restore one PORV flow path to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- c. If any action required by 3.1.8.1 is not met AND the associated completion time has expired, the reactor shall be placed in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
3-25a Amendment No. M, M, W, W,160
3.1. 8 ' OVER PRESSURE PROTECTION SYSTEMS Soecification r
3.1.8.2 Two PORV flow paths, each consisting of an OPERABLE PORV, with a lift pressure less than specified in Figure 3-4, shall be OPERABLE.
Note: The provisions of Specification 3.0.4 are not applicable.
Acolicability Specification 3.1.8.2 is applicable when the ter.perature of any of the PCS cold legs is < 430*F, unless the reactor vessel head is removed.
Action
- a. With one PORV flow path inoperable, restore both PORV flow paths to OPERABLE status:
- 1. within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with pressurizer water level > 57%, or
- 2. within 7 days with pressurizer water level s 57%.
- b. With two PORY flow paths inoperable, or if action required by 3.1.8.2a is not met and the associated completion time has expired: depressurize and vent the PCS through a vent path capable of relieving 167 gpm at a PCS pressure of 315 psia within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and
- 1. When the pathway is through any valve that is not locked, sealed, or otherwise secured in the open position, verify the vent pathway is open at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or
- 2. Otherwise, verify that the vent pathway is open at least once per 31 days.
3-25b Amendment No. 444, 4M,160
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3.1.8' OVER PRESSURE PROTECTION SYSTEMS I
l Basis 3.1.8 Specification 3.1.8 assures that the PORVs are available as a pressure relief path for the PCS.
Specification 3.1.8.1 applies when the PCS is above 430*F, to assure the PORVs would be available to. reduce PCS pressure in the event of the loss of normal means of PCS pressure control, or to provide an alternate path for removal of decay heat -in the event.of the loss of all normal methods. With the PCS above 430*F automatic PORV operation for Low Temperature Overpressure Protection (LTOP) is'no longer required. Specification 3.1.8.2 applies when the temperature of either PCS cold leg is below 430*F, where excessive addition of either mass or j
energy could result in significant PCS pressure increases.
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i If an inoperable PORV flow path cannot be repaired within the specified completion time, Specification 3.1.8.1 requires the plant to be placed in _
-l HOT SHUTDOWN.
It does not require a cooldown, which would place the plant in a condition where the PORVs provide the required automatic pressure' a
protection.
Time is allowed for repair of the valve, if possible, or to plan a cooldown witn limited overpressure protection available.
If a l
cooldown must be made to repair an inoperable valve, the specified completion times ~of 3.1.8.2 allow a slow, controlled evolution to occur, i
Each completion time starts when it is discovered that the particular action statement applies. The specified actions and completion times are based on those in the model' Technical Specifications provided in Generic Letter 90-06.
I 3.1.8.1 4
When PCS temperature is at or above 430*F, the maximum allowable PCS pressure is the Safety Limit of 2750 psia.
The pressurizer safety valves, required by Specification 3.1.7, prevent exceeding this pressure.
The t
PORVs are required to be OPERABLE above 430'F to support Emergency
- 4 Procedure. operation in case of the need for reducing PCS pressure or for Once-Through-Cooling. The PORVs are not assumed to function by the plant t
safety analyses.
Since the pressurizer safety valves provide the necessary automatic l
protection against excessive pressure when the PCS is above 430*F, automatic actuation of the PORVs is not required to be OPERABLE.
The PORVs and their block valves must provide two safety functions; maintenance of PCS integrity and PCS pressure control capability.
If either of these safety functions is unavailable, corrective action must be taken.
3-25d Amendment No. +14, m, 160
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3.1. 8 ' OVER PRESSURE PROTECTION SYSTEMS Basis 3.1.8.1 (continued)
Normally, during operation at HOT STANDBY and above, the PORV controls are in the CLOSE position, and the block valves are closed.
The PORVs, block i
valves, and the associated manual controls must be operable.
If either valve in a PORV flow path is inoperable, the other valve in the flow path must provide PCS integrity assurance. When a'PORV is inoperable, the block valve must be closed; when a block valve is inoperable, the PORV must have its control in the "CLOSE" position.
If the inoperable valves cannot be restored to OPERABLE status within the specified completion time, the plant must be placed in HOT SHUTDOWN.
The completion times allow the required action to be accomplished without undue haste, yet allow less time when more equipment is inoperable.
3.1.8.2 When PCS is below 430*F with the reactor vessel head installed, two PORVs are required to be operable to avoid pressures which might lead to failure of the reactor vessel.
Pressure increases could be caused by sudden additions (or imbalances) of either mass or energy.
The allowable pressure limits are determined in accordance with 10 CFR 50, Appendix G, and are referred to as " Low Temperature Overpressure Protection" (LTOP) limits.
The variable setpoint of the.LTOP system is programmed and calibrated to ensure opening of the pressurizer PORVs when the PCS pressure is above the limit in Figure.3-4.
The pressure limit for each temperature is developed from the heating or cooling limits for the PCS.
The limit in Figure 3-4 includes an allow nce for pressure overshoot during the interval between the time pressurizer pressure reaches the limit, and the time a PORV opens enough to terminate the pressure rise.
LTOP is provided by two independent channels each consisting of measurement, control, actuation, and valves.
Either channel is capable of providing full protection.
The actual setpoint of PORV actuation for LTOP will be below the limit in Figure 3-4 to allow for potential instrument inaccuracies, and drift. This will ensure that at no time between l
calibration intervals will the PCS pressure exceed the limit of Figure 3-4 without PORV actuation.
Mass additions could come from the starting of pumps or from opening a Safety Injection Tank isolation valve. Only the charging pumps or high l
pressure safety injection pumps could cause the PCS pressure to exceed its limits. Neither the shutoff head of the low pressure safety injection nor the operating pressure of the safety injection tanks is above the cold PCS pressure limit.
Specification 3.3.2 9 places limits on HPSI pump operability when the PCS is below 260*F to assure inadvertent starting does not cause overpressurization of the PCS.
3-25e Amendment No. W, m,160
3.1.8 OVER PRESSURE PROTECTION SYSTEMS Basis 3.1.8.2 (continued)
Energy additions could come from either the steam generators or from the reactor core.
Small energy addition could come from operation of the pressurizer heaters. Energy addition from the steam generatces could occur if a primary coolant pump was started when the steam generator secondary temperature was significantly above the PCS temperature.
Specification 3.1.1.h places limits on the starting of primary coolant pumps to avoid i
undesired energy additions from the steam generators.
Energy addition from the reactor core could occur due to an inadvertent criticality or to an imbalance in decay heat removal.
Specification 3.10.1 places limits on j
shutdown margin to avoid a rod withdrawal event causing a criticality and j
to provide sufficient time for operator action to terminate a dilution event prior to criticality.
The potential causes of a sudden PCS pressure increase which the LTOP system must be able to mitigate are imbalance in charging and letdown flow, starting of the HPSI pumps when above 260*F, and in an imbalance in decay heat (and pressurizer heat) addition and removal. A Safety Injection Signal (SIS) could both initiate flow from two HPSI pumps (when above 260'F) and three charging pumps, and iso? ate letdown. The PCS heatup from a loss of shutdown cooling event occurring 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after shutdown from a continuous full power run would generate sess additional coolant volume than the starting of three charging pumps Beference 5). The limiting event for the LTOP system would be an inaourtent SIS occurring during an established PCS heatup.
Analysis (Reference 1) has conclud'ed that an SIS occurring, during a PCS and pressurizer heatup at the maximum allowable rates, either between i
260*F and 430*F with the HPSI pumps, or below 260*F without the HPSI pumps, would not cause PCS pressure to exceed the Appendix G limit if
-cither PORV opens when the set pressure is reached. With the PCS above 430*F, the pressurizer safety valves, required by Specification 3.1.7, provide adequate overpressure protection.
Both PORVs are required to be operable to allow for a single failure.
If a PORV becomes inoperable when it is required for LTOP, it must be restored to operable status, or the plant must be cooled down, depressurized, and vented through a vent path with sufficient capacity to provide the necessary protection.
Since the pressure response to a transient is greater if the pressurizer steam space is small or if PCS is solid, the allowed outage time for a PORV flow path out of service is shorter. The maximum pressurizer level at which credit can be taken for having a bubble (57%, which provides about 700 cubic feet of steam space) is based on judgement rather than on analyses.
This level provides the same steam volume to dampen pressure transients as would be available at full power.
This steam volume provides time for operator action, if the PORVs failed to operate, between an inadvertent SIS and PCS pressure reaching the 10 CFR 50 Appendix G pressure limit.
The time available for action would depend upon the existing pressure and temperature when the inadvertent SIS occurred.
3-25f Amendment W, W,160
3.1. 8' OVER PRESSURE PROTECTION SYSTEMS Basis 3.1.8.2 (continued)
Reference I has determined that any vent path capable of relieving 167 gpm at a PCS pressure of 315 psia is acceptable.
The 167 gpm flow rate is based on an assumed charging imbalance due to interruption of letdown flow with three charging pumps operating, a 40*F per hour PCS heatup rate, a 60*F per hour pressurizer heatup rate, and an initially depressurized and vented PCS.
The PCS heatup rate is limited to 40*F per hour by Specification 3.1.2a; the pressurizer heatup rate is limited to 60*F per hour by Specification 3.1.2c.
Neither HPSI pump nor PCP starts need to be assumed with the PCS initially depressurized, because Specification 3.3.2g requires both HPSI pumps to be inoperable and operating procedures prohibit PCP operation.
The pressure relieving ability of a vent path depends not only upon the area of the vent opening, but also upon the configuration of the piping connecting the vent opening to the PCS.
A long, or restrictive piping connection may prevent a larger vent opening from providing adequate flow, while a smaller opening immediately adjacent to the PCS would be adequate.
The areas of multiple vent paths cannot simply be added to determine the necessary vent area.
The following vent path examples are acceptable:
1.
Removal of the reactor vessel head, 2.
Removal of a steam generator primary manway, 3.
Removal of the pressurizer manway, 4.
Removal of a PORV or pressurizer safety valve, 5.
Both PORVs and associated block valves open, 6.
Opening of both PCS vent valves PC-514 and PC-515.
Reference 2 determined that venting the PCS through PC-514 and PC-515 provided adequate flow area. The other listed examples provide greater flow areas with less piping restriction and are therefore acceptable.
Other vent paths shown to provide adequate capacity could also be used.
One open PORV provides sufficient flow area to prevent excessive PCS pressure. However, if the PORVs are elected as the vent path, both valves must be used to meet the single failure criterion, since the PORVs are held open against spring pressure by energizing the operating solenoid.
When the shutdown cooling system is in service with M0-3015 and M0-3016 open, additional overpressure protection is provided by the relief valves on the shutdown cooling system.
References 3 and 4 show that this relief capacity will prevent the PCS pressure from exceeding its pressure limits during any of the above mentioned events.
References 1.
Consumers Power Company Engineering Analysis, EA-FC-809-13, Rev 1 2.
Consumers Power Company Engineering Analysis, EA-TCD-91-01-01.
3.
Consumers Power Company Engineering Analysis, EA-PAL-89-040-1 4.
Consumers Power Company Corrective Action Document, A-PAL-91-011 5.
Consumers Power Company Engineering Analysis, EA-AG-93-02 3-25g Amendment No. W, m, 160
Table 3.17.4 (Cont'd)
Minimum Minimum Permissible 0)erable Dec ree of Bypass No Functional Unit C lannels Rec undancy Conditions 8.
Pressurizer Wide 2 '" "
- No n e Not required in Range Water Level Cold or Refueling Indication Shutdown 9.
Pressurizer Code 1 per None Not Required Safety Relief Valves Valve below 325'F Position Indication (Acoustic Monitor or Temperature Indication) 10.
Power Operated Relief 1 per None Not required when Valves (Acoustic Valve PORV isolation Monitor or Temperature valve is closed Indication) and its indication system is operable 11.
PORV Block Valve 1 per None Not required when Position Indication Valve reactor is depressurized and vented in accordance with Specification 3.1.8 12.
Subcooling Margin 1
None Not required Monitor below 325'F 13.
Auxiliary Feed Flow 1 peg' None Not required Rate Indication flow below 325'F Control Valve 14.
Auxiliary Feedwater 2 per 1
Not required Actuation System steam below 325'F 4
Sensor Channels generator *'
15.
Auxiliary Feedwater 2 "'
1 Not required Actuation S stem below 325'F Actuation C annels 16.
Excore Detector l
None Not Required Deviation Alarms Below 25% of Rated Power 17.
Axial Shape Index 2 "'
1 Not Required Alarm Below 25% of Rated Power 2 *' "*
None Not Required 0
18.
Reactor Vessel Water Level Below 325'F 19.
Core Exit 4/ core None Not required Thermocouples gup, rant below 300*F 3-81a Amendment No. 67, 68, %, M6, HB, M9, W, 160
4.1 INSTRUMENTATION AND CONTROL Acolicability Applies to the reactor protective system and other critical instrumentation and controls.
Ob.iective l
l To specify the minimum frequency and type of surveillance to be applied to critical plant instrumentation and controls.
Soecifications l
l Calibration, testing, and checking of instrument channels, reactor protective l
system and engineered safeguards system logic channels and miscellaneous instrument l
systems and controls shall be performed as specified in 4.1.1 and in Tables 4.1.1 l
to 4.1.3.
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4.1.1 PORVs and Overoressure Protection System Tests l
In addition to the requirements of Specification 4.0.5, each PORV flow path shall l
be demonstrated OPERABLE by:
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- 1. Testing the PORVs in accordance with the inservice inspection requirements for ASME Boiler and Pressure Vessel Code,Section XI, Section IWV, Category B valves.
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- 2. Performance of a CHANNEL CALIBRATION on the PORV actuation channel at least once per 18 months.
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(a)
Performing a complete cycle of the PORV with the plant above COLD SHUTDOWN at least once per 18 months.
(b)
Performing a complete cycle of the block valve prior to heatup from COLD SHUTDOWN, if not cycled within 92 days.
(a)
Performance of a CHANNEL FUNCTIONAL TEST on the PORV actuation channel, but excluding valve operation, at least once per 31 days.
(b)
Verifying the associated block valve is open at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
4-le Amendment No. 130, 449,160 l
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Basis 4.1 l
Failures such as blown instrument fuses, defective indicators, and faulted 1
l amplifiers which result in " upscale" or "downscale" indication can be easily l
recognized by simple observation of the functioning of an instrument or' system.
Furthermore, such failures are, in many cases, revealed by alarm or annunciator action and a check supplements this type of built-in surveillance.
Based on experience in operation of both conventional and nuclear plant systems when the plant is in operation, a checking frequency of once-per-shift is deemed adequate for reactor and steam system instrumentation.
Calibrations are performed to insure the presentation and acquisition of accurate information.
The power range safety channels and AT power channels are calibrated daily against a heat balance standard to account for errors induced by changing rod patterns and core physics parameters.
Other channels are subject only to the " drift" errors induced within the instrumentation itself and, consequently, can tolerate longer intervals between calibration.
Process system instrumentation errors induced by drift can be expected to remain within acceptable tolerances if recalibration is performed at l
each refueling shutdown interval.
l Substantial calibration shifts within a channel (essentially a channel failure) will be revealed during routine checking and testing procedures. Thus, minimum l
calibration frequencies of one-per-day for the power range safety channels, and once each refueling shutdown for the process system channels, are considered adequate.
The minimum testing frequency for those instrument channels connected to the reactor protective system is based on an estimated average unsafe failure rate of I
4 1.14 x 10 failure / hour per channel. This estimation is based on limited operating experience at conventional and nuclear plants. An " unsafe failure" is defined as one which negates channel operability and which, due to its nature, is revealed only when the channel is tested or attempts to respond to a bonafide l
signal.
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I 4-2 Amendment No. M, M, W. MB, W,160 i
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