ML18046B341
| ML18046B341 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 03/01/1982 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML18046B340 | List: |
| References | |
| NUDOCS 8203080336 | |
| Download: ML18046B341 (6) | |
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I I 020:3000336 020301 1 r PROPOSED TECHNICAL SPECIFICATION CHANGE PALISADES PLANT
'PDR ADOCK 05000255 1, !.,..
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3.16 ENGINEERED SAFETY FEATURES SYSTEM INITIATION INSTRUMENTATION
'SETTINGS r
Applicability This specification applies to the engineered safety feat~es sys~em initia-tion instrumentation settings.
Objective To prov~de for automatic initiation of the engineered safety features in the event that principal process variable.limits are exceeded.
Specifications The engineered safety features system initiation instrumentation setting limits and permissible bypasses shall be as stated in Table 3.16.1.
Basis
- a.
High Containment Pressure - The basis for the 4 psig(+o.40) set
-0.30 point for the high-pressure signal is to establish a setting which would be reached immediately in the event of a DBA, cover a spectrum of break sizes and yet be far enougn above normal operation maximum internal pressure to prevent spurious initiation. (l, 2 )
- b.
Pressurizer Low Pressure - The pressurizer low-pressure safety injection signal is a diverse signal to.the high containment pressure safety in-jection signal.
The settings include an uncertainty of -22 psia and are the* settings used in the Loss of Coolant Accident analysis. ( 3)
- c.
Containment High Radiation - Four area monitors in the containment initiate an isolation signal under high radiation condition.
The setting is based on the following analysis:
A 10 gpm primary coolant leak to the containment atmosphere is used based upon Specification 3.1.5. Primary coolant radioactivity con-centration was assumed to be the maximum allowable by Specification 3.1.4.
Note:
Added to this is the contribution from tr6 whose equilibrium radioactivity in the primary coolant is estimated to be 121
~Ci/cc. Semi-infinite cloud geometry and uniform mixing of radioactivity in the containment atmosphere was assumed.
r 6 equilibrium exists in containment atmosphere due to its short half-life, but all other radioactivity was assumed 3-71 PROPOSED
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- 1.
High Power Level(l)
- 2.
Low Primary (2 Coolant Flow
)
- 3.
High Pressurizer Pressure
- 4.
Thermal Margin/Low PressureC2, 3)
- 5.
Lov Steam Generator Water Level
- 6.
Low Steam Generator Pressure(2)
- 7.
Containment High Pressure TABLE 2.3.1 Reactor Protective System Trip Setting Limits Four Primary Coolant Pumps Operating
< 106.5% of Rated Power
~ 95% of Primary Coolant Flow With Four Pumps Operating
~ 2255 Psia PT ~Applicable Limits To Satisfy Figure 2-3 Not Lower Than the Cen-ter Line of Feed-Water Ring Which Is Located 6'-0" Below Normal Water Level
~ 500 Psia 2.3. 70 Psig Three Primary Coolant Pumps Operating
< 39' of Rated Power(4)
(continuous Operation Not Permitted)
~ 71% of Primary Cool-ant Flow With Four Pumps Operating 2 2255 Psia Replaced by' High Power Level Trip and 1750 Psia Minimum Low-Pressure Setting Not Lower Than the Cen-ter Line of Feed-Water Ring Which Is Located 6'-0" Below Normal Water Level
~ 500 Psia 2 3.70 Psig
(!)Below 5% rated power, the trip setting may be manually reduced by a factor of 10.
Two Primary Coolant Pumps Operating 2 21~ of"\\ Rated Power(4)
(Continuous Operation
- Not Permitted)
~ 46% of Primary Cool-ant Flow With Four Pumps Operating
~ 2255 Psia Replaced by High Power Level Trip and 1750 Psia Minimum Low-Pressure Setting
- Not.Lower Than the Cen-ter Line of Feed-Water Ring Which Is Located 6'-0" Below Nornial Water Level
~ 500 Psia
~ 3.70 Psip; (2 )May be bypassed below l0-4% of rated power proVlded auto bypass removal circuitry is operable.
For low power physics tests, thermal margin/low pressure and low steam generator pressure trips may be bypassed until their react points are reached (approximately 1750 psia and 500 psia, respectively), provided auto-matic bypass removal circuitry at lo-1% rated power is operable.
C3)Th and Tc in °F.
Minim'um trip setting shall be 1750 psia for two-and three-pump combinations.
For four-pump operation, the minimum trip setting shall be 1650 psia for nominal operating pressures less than 1900 psia; and 1750 psia for nominal operating pressures. 1900 psia and greater.
(4)operation with two or three pumps is permitted to provide a limited time for repair/pump restart, to provide for an orderly shutdown or to provide for the condu\\'.!t of reactor internals noise monitoring test measurements
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TABLE 3.16.1 Engineered Safety :Features System Initiation Instrument Setting Limits Functional Unit
- 1.
High Containment Pressure
- 2. Pressurizer Low Pressure
- 3.
Containment High Radiation
- 4.
Low Steam Generator Pressure
- 5.
SIRW Low-Level Switches
- 6.
Engineered Safeguards Pump Room Vent - Radiation Monitors (l)May be byp~ssed below l600 psi a (2)May be bypassed below 1700 psia and
.and Channel
- a.
Safety Injection
- b.
Containment Spray is is
- c.
Containment Isolation
- d.
Containment Air Cooler DBA Mode Safety Inject ion Containment Isolation Steam Line Isolation Recirculation Actuation Engineered Safeguards Pump Room Isolat:l..on automatically reinstated automatically reinstated
<3>May be bypassed below 550 psia and is automatically reinstated setting Linli t 3.70 - 4.40 Psig
~ 1550 Psia(l) for Nominal Opera.ting
.Pressures < 1900 Psia
~ 1593 Psia.(2} for Nominal Operating Pressures ~ 1900 Psia
~ ~O R/h
~ 500 Psia.( 3)
- ~ 27-Inch ~~~ Above Tank Bottom;
< 2.2 x 105 CPM above 1600 psia.
above 1700 psia.
above-550 pi;iia.
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consumers Power company General Offices: 1945 West Pernell Road, Jackson, Ml 49201 * (517) 788-0550 March 1, 1982 Dennis M Crutchfield, Chief Operation Reactor Branch No 5 Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR
- Da_vid J VandeWalle Nuclear Licensing Administrator PALISADES PLANT - PROPOSED TECHNICAL SPECIFICATIONS CHANGE REQUEST -
CONTAIN ISOLATION PRESSURE SET POINT Attached are three (3) originals and thirty seven (37) conformed copies of a request for change to the Palisades Technical Specifications.
Tpe requested change improves containment isolation dependability and meets the intent of NUREG-0737, Item II.E.4.2.
The bases for arriving at the appropriate minimum pressure set point for initiating containment isolation included containment pressure history and instrument performance.
The containment isolation pressure set point established is the result for an agreement reached between the NRC and Consumers Power Company.
The proposed change involves a single safety issue.
Therefore, a check in the amount of $4,000.00 is attached pursuant to 10 CFR 170.22, Class III change.
David J VandeWalle Nuclear Licensing Administrator CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades ATTACHMENTS
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Request Ir CONSUMERS POWER COMPANY Docket 50-255 if Change to the Technical Speci-..:*ications.
License DPR-20 For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Provisional Operating License DPR-20, Docket 50-255, issued to *consumers Power Coinpany on October 16, 1972, *for the Palisades.
Plant be changed as described in Section I below:
I. Changes A.
Chahge Section 2.3, Table 2.3.1 (7) to read:
" 7.
Containment High Pressure
< 3. 70 Psig
- S 3. 70 Psig
- S 3. 70 Psig "
B.
Change Section 3.16 to read:
"Basis a;* High Containment Pressure - The basis for the 4 ps~g (~8:~8) set point for. the high-pressure signal is to establish a setting which would be reached immediately in the event of a DBA, cover a_ spectrum of break sizes and.yet be far enough above normal operation maximum internal pressure to prevent spurious initiation. (1, 2)
C.
Change Section 3.16, Table 3.16.1 (1) to read:
"l.
High Containment Pressure
- a.
Safety Injection 3.70 - 4.40 Psig"
- b.
- c.
Containment Isolatiqn
- d.
Containment Air Cooler DBA Mode NOTE:
Revised Technical Specifications pages are attached.
Proposed changes are shown by a vertica.J. line in the right-hand margin.
IL Discussion The Technical Specifications change provides for improved containment isolation dependability.
The pres!>ure set point is based upon the maximum observed
- pressure inside containment during normal operation of.99 Psig and 'allowances for instrument dri~ and fluctuation due to the accuracy of the pressure sensor.
In addition, the revised pressure set point was deemed appropriate when reviewed against ISA draft s67.04.
This change was requested by the NRC and.meets the intent of NUREG-0737, Item II.E.4.2, position 5.
III. Conclusion Based on the foregoing, both the Palisades Plant Review Committee and the Safety and Audit Review Board h~ve reviewed these changes and find them acceptable.
CONSUMERS POWER COMPANY BY
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J W Reynolds, Executive Vice President Energy Supply Sworn and subscribed to before me this lst day of March 1982.
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Helen I Dem~blic Jackson County, Michigan My commission expires December 14, 1983