ML18052A349

Application for Amend to License DPR-20,revising Tech Specs to Reflect New Reactor Vessel pressure-temp Limits for Heatup & Cooldown to Account for Effects of Irradiation on Vessel Matls.Fee Paid

ML18052A349
Person / Time
Site:	Palisades
Issue date:	03/17/1986
From:	Reynolds J CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Office of Nuclear Reactor Regulation
Shared Package
ML18052A350	List: ML18052A349 ML18052A351
References
NUDOCS 8603200199
Download: ML18052A349 (4)

Text

consumers

~Mr . ~~w~

--Company --------- ---- ---------- --- - --. ----------------------Director---------- - --- -- -------- -

Nuclear licensing General Offices: 1945 West Parnall Road, Jack~n *.Ml 49201 * (517) 788-1636 March 17, 1986 Director, .,

Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 ~ ' ' t'*

DOCKET 50~255 - LICENSE DPR PALISADES PLANT -

TECHNICAL SPECIFICATION CHANGE REQUEST - REACTOR VESSEL PRE.S~VRE/TEMPERATURE LIMITS Attached are three (3) originals and thirty-seven (37) conformed copies of a request for .change to the P_alisades Technical Specifications. The attached changes provide new reactor vessel pressure-temperature ;limits for heat-up and cooldown and hydrostatic test to account for the effects of .irradiation on the vessel mat~_rials.

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This 'change request wfll provide new, more* restrictive pressure-temperature

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limits .that extend the present limits from 6.6 effective full power years (EFPY) to approximately 9.0 EFPY. The current limits are projected to expire (based on 100% power operation from the end of .the refueling outage) approximately mid August 1986.

A check'in the amount of $150.00 is enclosed as required by 10CFR170.21.

Kenneth W Berry * .

Director,'.Nuclear Licensing CC Administrator, Region III, USNRC NRC Resfden:t inspector.- Palisades Attachment OC0386-0043-NL04

3 III. Conclusion The Palisades Plant Review Committee has reviewed this Technical

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--speciTica-fion -cnange- Request-and has determined that--fhis 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 Request has been sent to the State of Michigan official designated to receive such Amendments to the Operating License.

CONSUMERS POWER COMPANY ~

ByJ~ Energy Supply Sworn and subscribed to before me this 17th day of March 1986.

Elaine E Buehrer, Notary Public Jackson County, Michigan My commission expires.October 31, 1989 TSOP0386-0043-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 A. ~pecification 3.l.2.e(2), delete the last 3 sentences and replace with the following:

"Such a conversion shall be(1f21e consistent with the dosimetry evaluation of Capsule W-290 ."

B. Specificatiog)3.l.2.e(3), add reference footnote 8 after 60°F, to read, "60°Ft . "

C. Specification 3.1.2 Basis, fourth paragraph, delete the following sentence. "The maximum integrated ... 80% load factor." and change footnote reference "(6)" to "(10)" in following sentence.

D. Specification 3.1.2 Basis, ninth P.aragraph, change the following numbers:

From To "19 19

1. 3 x 10 nvt 1.8 x lo nvt 223°F . 241°F 170°F 183°F 352°F 371°F 352°F 371°F E. Specification 3.1.2 Basis, last paragraph, delete the fourth and fifth sentences that begin and end as; "For heatup rates less than

... thus a composite curve is drawn."

F. Specification 3.1.2, Figure 3-1 is completely revised to reflect new heatup limits.

G. Specification 3.1.2, Figure 3-2 is completely revised to reflect new cooldown limits.

TSOP0386-0043-NL04

2 H. Specification 3.1.2, Figure 3-3 is completely revised to reflect new inservice hydrostatic test limits.

"Analysis of Capsules T-330 and W-290 fr_om the Consumers Power Company Palisades Reactor Vessel Radiation Surveillance Program,"

WCAP-10637, September, 1984.

J. Specification 3.l.3(b), change 352°F to 371°F.

K. Specification 3.1.3 Basis, in the third paragraph change 286°F to 371°F.

II. Discussion Changes A and C more clearly identify the data origiti, and deletes information contained in reference and evaluation documents.

Change B provides a reference for t~e 60°F value.

Changes D, F, G, H, I and J reflect new values or figures due to data derived in Attachment I, Engineering Analysis, EA-WJA-85-38, Palisades Reactor Pressure Vessel Temperature Limits Determination.

Change E deletes information no longer consistent with Figures 3-1 and*

3-2.

Change K provides the reference to the Capsule W-290 analysis.

Refer to Attachment I, Engineer,~ng Analysis, EA-WJA,-85-38, for determination of the pressure-temperature limits.

Analysis of No Significant Hazards Consideration The revised pressure-temperature limits are required to meet the reactor vessel fracture toughness requirements in 10CFR50 Appendix G. In order to operate safely, the reactor pressure vessel (RPV) must be kept in the

~uctile region. Therefore, pressure-temperature limits are defined to ensure the RPV will not be stressed under conditions which promote b~ittle failure. Higher temperature and corresponding higher pressuie limits are required to compensate for the effects of neutron exposure on the RPV material. The higher operating limits account for the irradiation effects and maintain the RPV within its nil-ductility transition temperature. Therefore, the proposed change does not involve an increase in the probability or consequences of a previously evaluated ac~ident and~ new o~ differ~nt kind of accident is not. created.

Operation of the RPV within the nil-ductility temperature, as determined by the methodology in Regulatory Guide 1.99, revision 2, will ensure the margin of safety is maintained.

TSOP0386-0043-NL04