ML18051A622
| ML18051A622 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 09/29/1983 |
| From: | Vandewalle D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML18051A621 | List: |
| References | |
| NUDOCS 8310050465 | |
| Download: ML18051A622 (3) | |
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-*coNSUMERS- -POWER-COMPANY - ----- -- - -
DOCKET 50-255 - LICENSE DPR PALISADES PLANT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS 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 Company on October 16, 1972, for the Palisades Plant be changed as described in Section I below:
I.
CHANGES Change Section 2.3 to include the following:
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_ 2.3 Limiting Safety System Settings - Reactor Protective System Basis
- As such, a maximum error in the calculated set point of
_ -165 psi. has been assumed-in the accident analysis. (1 2)
An analysis has been performed(l4) which verifies that the TM/LP_ -trip for 4-pump operation provides adequate thermal margin when,RTD time delays and conservative assumptions-regarding part power radial peaking factors are compensated for by an improved pressurizer modei, a primary coolant flow update and the XNB DNB correlation for control rod withdrawal transients.
The XNB DNB correlation has been shown to be applicable to the Palisades Plant in Reference 15.
For two-and three-pump coolant pump operation, power is limited to 21% and 39% of rated power, respectively, for a maximum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ****
Change Section 2.3 ~eferences to include the ~ollowing:
(14) XN-NF-83-57 (15) XN-NF-709 8310050465 830929 I PDR ADOCK 050002551 P
PDR' MI0883-0001A-NL02
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~-- -- - Change--Secdon-3.23~1-Basis-to-include--the*following:---.
- In addition, the limitation on LHR for the highest power fuel rod, narrow water gap fuel rod and interior fuel rod ensures that the minimum DNBR will be maintained above
- 1. 30 for the W3 correlation or ab_ove 1.17 for the _XNB correlation during anticipated transients; and that fuel damage during Condition IV events such as locked rotor will not exceed acceptable limits. <2)(3)(5)
Change Section 3.23.1 References to include the following:
(5) XN-NF-83-57
.The revised Technical Specifications pages are attached.
Proposed changes are shown by a vertical line in the right~hand margin.
II.
DISCUS~ION The Licensee Event Report (LER) 83-20 (RTD Response Time) was submitted to the NRC on April 5, 1983.
The LER reported that Consumers Power Company discovered that the safety analysis contained in XN-NF-77-18, "Plant Transient Analysis of the Palisades Reactor for Operations at 2530 Mwt," dated July 1977,.
did not account for the response times of the RTDs in the primary coolant system.
The purpose of this Technical Specif i-cation Change is to complete the corrective actions required by the LER.
The 1977 analysis was performed with the PTSPAL version of the PTSPWRs transient code and with the W-3 DNB correlation.
Calculations for the most limiting tran~ient, the rod withdrawal transient initiated from 52% of rated power, resulted in an MDNBR of 1.32, compared to the W-3 limit of 1.30.
The current rod withdrawal analysis is performed in a more conservative manner than the previous analysis in 1977.
The current analysis accounts for the effect of the RTD response time on the TM/LP trip.
To further add conservatism, radial peaking values are held constant during rod withdrawal tran-sients and not allowed to decrease as reactor power increases.
The analysis was performed at the current Palisades Technical Specificati~n part power peaking limits.
To provide acceptable DNB limits, some of the excess conservatisms were removed from the 1977 analysis.
This included the use of the ENC XNB corre-lation to calculate DNB, and an update to the algorithm for MI0883-0001A-NL02
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calculating--rea-ctor-coolant n-ow.-- -In addition--to--the above - ------ -- ---
changes, the UFEB82 version of thePTSPWR2 code which has been used in licensing analyses of other CE reactors was adopted.
The new version of the code include a pressurizer model which more accurately calculates the pressure increase in the pressur-izer during rod withdrawal transients.
The use of an improved basis for DNBR analysis of the rod withdrawal transient does not compromise the previous 1977 analysis of the other limiting transients which is based upon models and a DNB correlation containing excess conservatisms.
III.
CONCLUSION The Palisades Plant Review Committee has reviewed this Technical Specification Change Request and'has determined that this change does not involve an unreviewed safety question and therefore involves no significant hazards consideration.
This change has also been reviewed under the cognizance of the Nuclear Safety Board.
A copy of this Technical Specification Change Reque_st has been sent to the State of Michi~an off~cial designated to receive such Amendments to the Operating License.
CONSUMERS POWER Com> ANY
- By Ji2t5'bdtluz>
R B DeWitt, Vice President Nuclear Operatiorts Sworn and subscribed to before me this 29th day o.f September 1983.
rfey, Notary County, Michigan My commission expires November 5, 1986.
SHERRY LYNN DURFEY N,otary Pu~li~, Jackson County, Miclt.
~. Y r omrr.1ss1on Exoire~ Nov. 5. I98S MI0883-0001A-NL02