ML18051A919
| ML18051A919 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 06/07/1984 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18051A920 | List: |
| References | |
| NUDOCS 8406130103 | |
| Download: ML18051A919 (7) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 CONSUMERS POWER COMPANY DOCKET NO. 50-255 PALISADES Pl.LI.NT AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 82 License No. DPR-20
- l. The Nuclear Regulatory Commission (the Commission) has found that:
A.
The_:;;i.application for amendment by Consumers Power Company (the licensee) dated September 29, 1983, 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 confonnity 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 ~uch 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; 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.
(*.*
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B of Provisional Operating License No.
DPR-20 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications tontained in Appendices A and B, (Environmental Protection Plan) as revised through Amendment No. 82, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance.
~.
Attachment:
Changes to the Technical Speci fi cations Date of Issuance: June 7, 1984 FOR THE NUCLEAR REGULATORY COMM I SS ION t1) a.f_,I;_'\\, /./
- Pcuv~,
i!r, / Dennis M. Crutchfield, Chief n,- Operating Reactors Branch #5 ~
Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NO. 82 PROVISIONAL OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 Revise Technical Specifications by removing the following pages and by inserting the enclosed pages.
The revised pages contain the captioned amendment number and margtr.ial lines *indicating the area of change.
Remove Pages 2-8 2-10 3-104 3-106 Insert Pages 2-8 2-10 3-104 3-106
- 2. 3 LIMITING SAFETY SYSTEM SETTINGS -
REACTOR PROTECTIVE SYSTEM (Cont'd)
Basis (Cont'd)
(TM/LP) trip will occur before these limits are reached.
Refer-ence 13 forms the basis for Figure 2-3 for 4-pump operation.
For 2-and 3-pump operation the flow instability criterion is more limiting than the }IDNBR criterion.
Reference 7 forms the basis for Figures 2-1 and 2-2.
The trip is initiated whenever the pressurizer pressure drops below the minimum value given on Table 2.3.1, or a value computed as described below, whichever is higher.
The computed val~e is a function of reactor inlet temperature and reactor outlet temperature, and takes the form PT. * = ATH -
BTC - C where A, B and C are ccnstants np and TH and TC are the hct and cold leg toolant temperatures, respec-tively.
The ~ihimum value of reactor coolant flo..., anci the mc.ximum expected values of axial and radial peaking factors are assumed in generating t-Ois trip function.
The TM/LP trip set points are derived from the 4-pump operation core thermal limits (Figure 2-3) through application of appropriate
- allowances for measurement uncertainties and processing errors.
A maximum error of 165. psi is assumed to account for expected instru-ment drift and repeatability errors, process measurement uncertain-ties, flow stratification effects, and calibration errors.
As ~uch,-
a maximum error in the calculated set point of -165 psi has been d.
h
. d 1
- 02) assume ln t e accl ent ana ysls.
An analysis has been perf~rmed(l 4
) which verifies that th.e TM/LP
.trip for 4-pump operation provides adequate thermal margin -when*}TD time delays and conservative assumptions regarding part power radial peaking factors are compensated for by an improved pressurizer model, a primary coolant flo" update and the XNB DNB correlation for control rod withdrawal transients.
The ~B DKB correlation has been sho'lo."!l to be applicable to the Palisades Plant in Reference 15.
. For two-and three-puwp coolant pump operation, po'Wer is limited to 21% and 39% of rated power, respectively, for a maxi~um of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
During either of these modes of operation, the high power level trip
. in conjunction -with the TM/LP trip (minimum set point = 1750 psia) and the secondary system safety valves (set at 1000 psia) assure that the lioits shown on Figures 2-1 and 2-2 -will not be violated.
- 5.
Low Steam Generator Water Level - The low steam generator -water level reactor trip protects against the loss of feed-water flo~
accidents and assures that the design pressure of the primar~' coolant system will not be exceeded.
The specified set point assures that there will be sufficient water inventory in the.steam generator at the time of trip to provide a 15-minute margin before the auxiliary feedwater is required.< 9) 2-8
~,.*.
2.3 LIMITING SAFETY SYSTE:M SETTINGS - REACTOR PROTECTIVE SYSTEM (Cont'd)
References (Cont'd).
(8)
XN-NF-77-18, Section 3.8.
(9)
XN-N'F-77-18, Section 3.7.
(10)
FSAR, Amendment No 17' Item 4.0.
(11)
XN-NF-77-18, Section 3. 6.
(12)
XN-NF-77-18, Section 3.1.
(13)
XN-NF-77-22, Section 3.4.
(14)
XN-NF-83-57.
(15)
XN-NF-709.
2-10 Amendment/ 82
POWER DISTRIBUTION LIMITS 3.23.1 LINEAR HE.AT RATE (LHR)
LIMITING CONDITION FOR OPERATION ACTION 3:
If the incore alarm system is inoperable and the excore monitoring syste~
is not being used, operation at less than or equal to 85% of rated power may continue provided that incore readings are recorded manually.
Readings shall be taken on a minimum.of 10 individual detectprs per quadrant (to include 50% of the total number of detectors in a 10-hour
~erio~) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and at least every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> thereafter.
If readings indicate a local power level equal to or greater than the alan:i setpoints, the action specified in ACTION 1 above shall be taken.
Basis The limitation on LHR ensures that, in the event of a LOCA, the peak temperature of the cladding will not exceed 2200°F. (l)
In addition, the limitation on LHR for the highest power fuel rod,-narrow ~ater gap fuel rod and interior fuel rod ensures that the minimum DNBR will be maintained above 1. 30 for the W-3 correlation or above 1. 17 for the XNB correlation during anticipated transients; and, that fuel damage during Condition IV
~vents.such as locked rotor will not excee~ acceptable limits.< 2)C3>C5)
The inclusion of the axial po-wer distribution term ensures that the.*~.
operating power distribution is enveloped by the design power distri-butions.
Either of the two core power distribution monitoring systems (the incore
~larm syster. or the excore monitorir.g system) provides adequate monitoring of the core power distribution and is capable of verifying that the LHR does not exceed its limits.
The incore alarm system performs this 3-104
PO\\.."IR DISTRIBUTION LIMITS 3.23.l LINEAR HEAT KATES (LHR LIMITIN.G CONDITIONS OF OPERATION Basis (Cont'd) uncertainty.factor of 1. 03, a thenr.al power measurement uncertainty factor of 1.02 and allo~ance for quadrant tilt.
References (l)
XK-NF..:,77-24
.(2)
XN'"'.'NF-77-18 (3)
XN-NF-78-16 (4)
Xl\\-NF-80-47 (5)
~-KF-83-57 3-106
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