ML20024G441

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Application for Amend to License DPR-22,changing Tech Specs to Reflect Adoption of Getab/Gexl Heat Flux Correlation in Place of Current Hench-Levy Correlation
ML20024G441
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 03/12/1975
From: Wachter L
NORTHERN STATES POWER CO.
To:
Shared Package
ML20024G439 List:
References
A00L-750312, AL-750312, NUDOCS 9102120467
Download: ML20024G441 (5)


Text

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UNITED STATES NUCLEAR REGUIATORY COMMISSION NORTRERN STATES POWER COMPANY Monticcilo Nuclear Generating Plant Docket No. 50 263 REQUEST FOR AMENIt4ENT TO OPERATING LICENSE NO DPR42 (License Amendment Request Dated March 12, 1975)

Northern States Power Company, a Minnesota corporation, requests authorization for changes to the Technical Specifications as shown on the attachments labeled Exhibit A and Exhibit B. Exhibit A describes the proposed changes along with reasons for the change. Exhibit B is e set of Technical Specification pages incorporating the proposed changes.

This request contains no restricts ar other defense information.

NORTHERN STATES POWER COMPANY By Y 0 $$Yk)

% J Wachter Vice President, Power Production 6 System Operation On this 12th day of March , 1975 , before me a notary public in and for said County, personally appeared L J Wachter, Vice President, Power Production & System Operation, and first being duly sworn acknowledged that he is authorized to 2xecute this document in behalf of Northern States Power Company, that he knows the contents thereof and that to the best of his knowledge, infornat _en and belief, the statements made in it are true and that it is not interp sned for delay.

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EKHIBIT A MONTICELLO NUCLEAR GENERATING P1 ANT l

DOCKET No. 50-263 I LICENSE AMENDMENT REQUEST DATED MARCH 12, 1975 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS ,

APPENDIX A 0F PROVISION /iL OPERATING 1 LICENSE NO. DPR -22 Pursuant to 10CFR50.59 the holders of Provisional Opera'ing c License DPR-22 hereby propose the following changes to Appendix A, Technical Specifications.

The reason for most changes is the adoption of the GCIAB/GEXL thermal 1 analysis as a new basis for safety limita. This new, improved correlation replaces the Hench-Levy heat flux correlation which presently serves as the basis for safety limits. The reason for change stated below as " Adoption of GETAB/GEXL" implies this fact. Additional supporting analysis is presented in the following references:

i) General Electric 5."R 1hermal Analysis Basis (GETAB):

Dats, Correlation and Design Application; NEDO-10958

11) General Electric UWR Generic Reload Application for 8x8 Fuel, NEDO-20360, Revision 1 iii) Monticello Nuclear Generating Plant, Third Reload Submittal, December 11, 1974
1. SPECIFICATION 1.0.I (page 2) 1 PROPOSED CHANGE Delete the definition of NCilFR and insert .he definition of FEPR as indicated.

PIASON FOR CHANGE Adoption of GEIAB/CEXL Note: Our License Amendment Request Dated August 20, 1974, proposed to change this Specification in response to 10CFR50 Appendix K. The change proposed above supercedes both the existing and the August 20, 1974, proposed versions.

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..  ; F ECIrICATICC' 2,1 cnd 2.3 and BASEF 2.1 and 2.3 (pages 6-8, 10 and 13-22A)

PROPOSED CHANCES Revise the pages to conform tc the corrected pages included as Exhibit B.

Changes are indicated by sidelines. Page 10 (previously Figure 2.1.1) has been deleted due to the change to Specification 2.1.A.

REASON FOR CHANGE Adoption of GETAB/GEXL

3. BASES 2.1 (page 17)

PROPOSED CHANGE Delete the Inst paragraph of this section, found on page 17 of existing Bases.

REASON FOR CHANGE This section has become obsolete. It served as the Bases for a reporting recuirerient on the " Summary Status of Fuel" which has been proposed to be eliminated in License Amendment Request Dated December 16, 1974.

4. IR5Eb 3.2/4.2 (pane 67)

PROPOSED CRANCE Chagge the third sentence on this page to read, "The trip settings of 200 F and 150% of HPCI and 300% of RCIC design flows and valve closure times are such that the core will not be uncovered and fission product release will not exceed 10CFR100 guidelines."

REASON FOR CRANCF This change corrects an erroneous statemer. concerning the RCIC high steam flow setpoint. The trip setting for RCIC High Steam Flow listed on page 51 is less than or equal to 45,000 lb/hr.

Design flow is 16,500 lb/hr maximum.

f 5. EiSE9 3.2/4.2 (pnRe 67) i PROPOSED CHANCES In odditf or to the change in item 4 above, make the remaining changes cc

( Indicated in the modified page in Exhibit B. Changes are indicated by l

sidelines.

REASON FOR CHANGER Adoption of GEIAB/GEXL

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l. 6. 2/4T d ?!4.' (pan f 5)

. ;m m a :r Revise the page. to conform to the corrected page included in Exhibit B.

Changes are indicated by sidelines.

REASON FOR CHANGE Adoption of GEIAB/CEXL.

Note: Our Change Request Dated Ibrch 1, 1974, proposed to change the same subject matter on page 85 as discussed above. Since that request has not been acted on, we request that the attached changes to page 85 supersede the earlier request and that page 85 be considered withdrawn from Change Request Dated March 1, 1974.

7. SPECIFICATIONS 3.11 AND 4.11 (pages 189B thru 189D and 189K) AND BASES 3.11 AED 4.11 (pages 189E thru 189G)

PROPOSED Cl!ANGES Revise the pages to conform to the corrected pages included in Exhibit B.

Changes are indicated by sidelines. Page 189K (Figure 3.11.2) has been added due to the change in Specification 3.11.C.

REASON FOP CHANCES Adoption of CETAB/GEXL. The Operating MCPR proposed for Specification 3.11.C is based on the analysis of abnormal operational transients. It is more restrictive than that proposed previously which was the initial condition of LOCA calculations. The required Operating MCPR Limit for 8xS fuel was erroneously reported in Reference 111 to be 1.36. The pro-posed LCO correctly states the limit to be MCPR of 1.41.

The surveillance requirements have been increased to acknowledge the more restrictive limit. The same surveillance requirements have been applied to c11 fuel ILmits addressed in sections 3.11 and 4.11. The increase in curveillance frequency requires that the daily surveillance be augmented by a program specified by the plant technical staff. The necessity for such a program and the frequency at which surveillance should be done is a function of the power level, amount and rate of power change, the associated xenon transient, the control rod sequence and pattern, the core exporure and the margin between operating conditions and limiting values. Because of the interrelationship of all these parameters, a reasonable augmented surveillance can only be determined on a case-by-case basis by the plant technical staff.

.;ote: bpecifications 3.11 and 4.11 were formed by our License Amendment Request Dated August 20, 1974. By order of 10 CFR Part 50.46 the more restrictive of the existing Technical Specifications and those proposed on August 20, 1974, are in effect. The present changes, upon issuance, will supercede the respective portions of the August 20, 1974, submittal. Ilow-evtt, sincc the present changes are not the result of further ECCS evalua-tions, they are not covered by 10 CFR Pact 50.46 and therefore will not be c ota effcetive until issued by the Nuclear Regulatory Coanission.

1 EX111 BIT B LICENSE AMENDMENT REQUEST DATED MARC 11 12,1975 Exhibit B, attached, consists of newly prepared pages for the Appendix A Technical Specifications as listed below. These pages incerporate the propeced changes.

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10 13 14 15 16 17 lb 19 20 21 22 22a 67 85 189B 189C 189D 189E 189F 189G 189K