ML20236X781

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Application for Amend to License DPR-59,proposing Rev to Note Which Will Allow TS Section 1.1.A Re SLMCPR to Be Applicable During Cycle 14
ML20236X781
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 08/03/1998
From: James Knubel
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20138K589 List:
References
NUDOCS 9808100253
Download: ML20236X781 (7)
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BEFORE THE UNITED STATES l NUCLEAR REGULATORY COMMISSION l in the Matter of )

NEW YORK POWER AUTHORITY ) Docket No. 50-333 James A. FitzPatrick Nuclear Power Plant )

APPLICATION FOR AMENDMENT TO OPERATING LICENSE The New York Power Authority requests an amendment to the Technical Specifications l (TS) contained in Appendix A to Facility Operating License DPR-59 for the James A.

FitzPatrick Nuclear Power Plant. This application is filed in accordance with Section 10 CFR 50.00 of the Nuclear Regulatory Commission's regulations.

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This application for an amendment to the James A. FitzPatrick TS proposes a revision to a note which will allow TS Section 1.1.A, regarding the Safety Limit Minimum Critical Power Ratio (SLMCPR), to be applicable during Cycle 14. TS Section 1.1.A is currently only applicable for Cycle 13.

The signed original of the Application for Amendment to the Operating License is enclosed for filing. Attachment I contains the proposed new TS page ano Attachment 11is the Safety Evaluation for the proposed change. A markup of the affected TS page is included as Attachment lli.

A General Electric letter (Reference) specifies that the SLMCPR limits for FitzPatrick, Cycle 14 remain unchanged. This letter is included in this submittal as Attachment IV.

Information in Attachment IV is considered General Electric (GE) proprietary information and should be withheld from public disclosure in accordance with 10 CFR 9.17(a)(4) and 10 CFR 2.790(a)(4). An Affidavit, prepared in accordance with 10 CFR 2.790(b)(1),

supporting this request is provided with Attachment IV. Attachment V contains the non-proprietary version of Attachment IV.

New York Power Authority STATE OF NEW YORK COUNTY OF WESTCHESTER Subscri ed and s orn t before me this day of 998.

J. Idnubel . ,b - mM Senior Vice President and Notary Pu%c V Chief Nuclear Officer EE.EEN E. O'CONNOft Y No Oueilliedinwoeschester l

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9808100253 980803 T PDR ADOCK 05000333 P PDR .

Attachmant I to JPN-98-036

, REVISED TECHNICAL SPECIFICATION PAGES I SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (JPTS-98 002) i, l

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l New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT l Docket No. 50-333 DPR-59

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e Att: chm:nt ll to JPN-98-036 SAFETY EVALUATION SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (JPTS-98-OO2)

New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59

Attachment il to JPN-98-036 SAFETY EVALUATION

! Page 1 of 3

1. DESCRIPTION The following change revises a note which will allow TS Section 1.1.A, regarding the Safety Limit Minimum Critical Power Ratio (SLMCPR), to be applicable during Cycle 14. TS Section 1.1.A is currently only applicable for Cycle 13.

Paae 7 Change the note at the bottom of the page to read:

" NOTE: TS 1.1.A is applicable for Cycle 14 only."

ll. PURPOSE OF THE PROPOSED CHANGE A cycle specific evaluation has been performed by General Electric (GE). The results of this evaluation show that the current SLMCPR is conservative and remains applicable through Cycle 14.

lil. SAFETY IMPLICATIONS OF THE PROPOSED CHANGE in 1996, GE informed utilitiet. that under some conditions the generically calculated SLMCPR can be non-conservative. Based upon a discussion with the NRC on this issue, the Authority added a note to TS Section 1.1.A (JAFP-96-0449, Reference 1) to support the issuance of Amendment 238 (Reference 2). As a result of this note being added, a validation or re-calculation of the SLMCPR is required each cycle. Reference 3 is a 10 CFR 21 notification made by GE identifying the problem with the generic method of the SLMCPR calculation.

In Reference 4, GE reports a generic calculation of the SLMCPR for GE 12 fuel. This value was found to be applicable for Cycle 13 (Reference 5). The Cycle 13 SLMCPR was determined using the analysis basis documented in GESTAR (Reference 6) with the following exceptions: (1) the planned core loading pattern was analyzed; (2) the actual bundle parameters (e.g., local peaking) were used; (3) the full cycle exposure range was analyzed.

GE has performed an evaluation (Reference 7) of the SLMCPR for Cycle 14 and found that the cycle specific value, based on current reload plans, is bounded by the generic value calculated for GE 12 fuel. The methodology utilized in the Cycle 14 evaluation is identical to that used for Cycle 13. The proposed change maintains the same value for Cycle 14. As such, the SLMCPR values in TS Section 1.1.A remain unchanged.

Based on the above, this proposed change has no effect on nuclear safety.

IV. EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION Operation of the FitzPatrick plant in accordance with the proposed amendment would not involve a significant hazards consideration as defined in 10 CFR 50.92, since it would not:

1. involve a significant increase in the probability or consequences of an accident previously evaluated.
A change to a note stating that the SLMCPR remains applicable through Cycle 14 does not 1 affect the initiation of any accident. Operation in accordance with the current SLMCPR ensures the consequences of previously analyzed accidents are not changed. Therefore, this proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

Att:chmsnt 11 to JPN-98-036 SAFETY EVALUATION Page 2 of 3

2. create the possibility of a new or different kind of accident from any accident previously evaluated.

The SLMCPR establishes a performance limit for the fuel. This limit remains unchanged.

Changing a note to reflect this is an administrative change and will not initiate any accident.

Therefore, this proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. involve a significant reduction in a margin of safety.

GE has performed an evaluation of the SLMCPR for Cycle 14 and found that the cycle specific value, based on current reload plans, is bounded by the generic value calculated for GE 12 fuel.

The existing SLMCPR remains unchanged for Cycle 14 and the margin of safety for the prevention of onset of transition boiling is unchanged. Therefore, this proposed change does not involve a significant reduction in a margin of safety.

V. IMPLEMENTATION OF THE PROPOSED CHANGE This amendment request meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) as follows: {

(i) the amendment involves no significant hazards consideration.

As described in Section IV of this evaluation, the proposed change involves no significant hazards consideration.

(ii) there is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite.

The proposed change does not alter the margin of safety which is presently assumed for fuel cladding integrity with respect to onset of transition boiling. Therefore, there is no change in the amounts of effluents which may be released offsite.

(iii) there is no significant increase in individual or cumulative occupational radiation exposure.

The proposed change does not alter the margin of safety which is presently assumed for fuel cladding integrity with respect to onset of transition boiling. The current SLMCPR remains applicable through Cycle 14. Therefore, there will be no change in individual or cumulative radiation exposure.

Based on the above, the Authority concludes that the proposed changes meet the criteria specified in 10 CFR 51.22 for a categorical exclusion from the requirements of 10 CFR 51.21 relative to requiring a j specihc environmental assessment by the Commission.

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~ SAFETY EVALUATION l' Page 3 of 3 VI. CONCLUSION Based on the discussions above, changing a note to allow the current SLMCPR to be applicable during Cycle 14 does not involve a significant hazards consideration, or an unreviewed safety question, and will not endanger the health and safety of the public. The Plant Operating Review Committee (PORC) and Safety Review Committee (SRC) have reviewed this proposed change to the TS and agree with this conclusion.

The proposed TS changes are not applicable for Cycle 13. The Authority requests the Amendment specify that the changes may be implemented any time after the upcoming Refueling Outage 13 begins (Currently scheduled to begin on October 16, 1998), but must be implemented prior to startup for Cycle 14.

Vll. REFERENCES

1. NYPA Letter, M. J. Colomb to the NRC, " Proposed Changes to the Technical Specifications Regarding Minimum Critical Power Ratio Safety Limit," (JAFP-96-0449), dated November 8, 1996
2. NRC Letter to W. J. Cahill, Jr., " Issuance of Amendment for James A. FitzPatrick Nuclear Power Plant (TAC NO. M95522)," dated November 14,1996

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3. General Electric Letter, M. A. Smith to the NRC,10 CFR Part 21, Reportable condition, Safety Limit MCPR Evaluation, dated May 24,1996
4. GE12 Compliance with Amendment 22 of NEDE-24011-P-A (GESTAR ll), NEDE-32417P, December 1994 l

l 5. General Electric Report, Supplemental Reload Licensing Report for James A. FitzPatrick Reload 12 Cycle 13, J11-02914SRL, Rev. O, dated August,1996

! 6. General Electric Standard Application for Reactor Fuel, NEDE-24011-P-A-13, dated August,

1996 l 7. General Electric Letter, J. A. Baumgartner to P. Lemberg, " Cycle Specific SLMCPR for FitzPatrick Cycle 14," dated July 17,1998 l

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