ML18052A166

Application for Amend to License DPR-20,changing Tech Specs to Upgrade Range of Subcooling Margin Monitor & Qualification & Readout Capability of Core Exit Thermocouples to Satisfy Generic Ltr 82-28.Fee Paid

ML18052A166
Person / Time
Site:	Palisades
Issue date:	11/21/1985
From:	Berry K, Dewitt R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Office of Nuclear Reactor Regulation
Shared Package
ML18052A167	List: ML18052A166 ML18052A168
References
GL-82-28, NUDOCS 8511270057
Download: ML18052A166 (4)

Text

consumers Power Kenneth W Berry company Director Nuclear licensing

• General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-1636 November 21, 1985 Directo;:,

Nuclear Reactor Reg*ulation US Nuclear Regulatory Colillllission

. Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -

.TECHNICAL SPECIFICATION CHANGE REQUEST -

CORE EXIT THERMOCOUPLES Attached are three (3) originals and thirty-seven (37) conformed copies of a.

request for change to the Palisade$ Technical Specifications.

The change to the Palisades Technical .Specifications provides requirements that are inore restrictive in some c*ases than those provided in. Generic* J:,etter 83-37 and its enclosed Standard Technical Specifications.

In accordance with our October 19, 1984 comniitment, the Core Exit .Thermo-couples will be upgraded with environmentally qualified thermocouples prior to startup from the 1985/86 refueling outage.

A check in the -amount of $150 .* 00 is enclosed as required by 10CFR170.21.

Kenneth_W Berry Director, Nuclea! Licensing CC Administrator, Region III, USNRC NRC Resident Ins~ector - Palisades Attachment r 8511270057 ~~ba5~55; j* PDR ADOCK . PDR I p 0Cl185-0326-NL04

CONSUMERS POWER COMPANY Docket 50-255 Request for Change to the Technical Specifications 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 Company on October 16, 1972, for the Palisades Plant be changed as described in Section I below:

I. Changes

1. Correct the typographical error in the notation in Table 3.17.4, Item 11, as follows: " .*. vent 6:1.3 sq. in."

2. Add a new item to Table 3.17.4 and* add footnote (i) as follows:

Minimum Minimum Permissible Operable Degree of Bypass No Function Unit Channels Redundanc~ Conditions 22 Core Exit 2/Core  !/Core Not Required Thermocouples Quadrant (i) Quadrant in Cold or Refueling Shutdown (i) The core exit thermocouples in core quadrant locations (H2, G7, J7, JlO), (Q4, R7, RB, Nll), (M13, X14, Q16, R17) and (Bl3, H13, J16, Gl7) are to be used in determining the minimum operable equipment.

3. Add a new item to Table 4.1.3 and add footnote (6) as follows:

Surveillance No Channel Description Function Frequency Surv Method 23 Core Exit a) Check M a) Comparison Thermocouples b) Calibrate R of channels (6). b) Known voltage sub-stituted for thermocouple (6) Only applicable to core exit thermocouples in core locations H2, G7, J7, JlO, Q4, R7, RB, Nll, M13, X14, Q16, R17, B13, H13, J16 and Gl7.

TSOP1185-0003-NL02

2 II. Discussion The above proposed Technical Specifications changes are in response to Generic Letter 82-28 which required licensees to submit their plans for installing instrumentation for the detection of inadequate core cooling.

Palisades has committed to upgrading the range of the subcooling margin monitor, upgrading the qualification and readout capability of the core exit thermocouples and providing a reactor vessel level monitoring system.

Generic Letter 83-37 provided requirements for Technical Specifications for NUREG-0737 items, including instrumentation for detection of inadequate core cooling. These proposed changes to the Technical Specifi-cations incorporate the required changes to the core exit thermocouples portion of, core cooling instrumentation.

The proposed changes are more conservative than with NRC Standard Technical Specifications (STS) provided in Generic Letter 83-37. Section 3.17.2 of the Palisades Technical Specifications requires the reactor be placed in a hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if the number of channels falls below the "minimum operable channels." The STS however would allow the plant to remain in power operation for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> with less than the minimum channels operable or be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Analysis of No Significant Hazards Consideration This change request is the result of a modification to the core exit thermocouples which will be completed during the upcoming 1985-86 refueling outage and is also more conservative than the Standard Technical Specifications, provided in Generic Letter 83-37. The addition of the core exit thermocouple operability and surveillance specifications does not involve an increase in the probability or consequences of an accident previously evaluated. The upgrading of the core exit thermocouples with environmentally qualified thermocouples and increasing the range of control room temperature indicator will significantly increase the operator's ability to monitor core temperatures following an accident condition. The addition of these proposed changes to the Technical Specifications does not create the possibility of a new or different kind of accident nor does it involve a significant reduction in any margin of safety since the only equipment changes are to environmentally qualify existing equipment and to extend the indicator range. As stated above, the modification will enhance the operator's knowledge of core temperatures .in the post-accident condition and these proposed changes serve to ensure the operability of the equipment.

TSOP1185-0003-NL02

3 III. Conclusion The Palisades Plant Review Committee has reviewed this Technical Specif i-cation 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 Specifi-cation Change Request has been sent to the State of Michigan official designated to receive such Amendments to the Operating License.

CONSUMERS POWER COMPANY BvffA1Jhd£ R B DeWitt, Vice President Nuclear Operations Sworn and subscribed to before me this 21st day of November 1985.

elen I Dempski, Nota Jackson County, Michigan My commission expires October 12, 1987.

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