ML20236R301

Application for License Change ECR 98-01403,requesting Change to License DPR-44 Revising TS Section 2.0 & non-proprietary & Proprietary Versions of 980609 Addl Info Re 1.10 Cycle Specific Slmcpr.Proprietary Version Withheld

ML20236R301
Person / Time
Site:	Peach Bottom
Issue date:	07/10/1998
From:	Geoffrey Edwards PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20138K425	List: ML20236R301 ML20236R312
References
NUDOCS 9807210353
Download: ML20236R301 (9)

Text

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Et; tion Support DepIrtment 10 CFR 50.90 v

PECO NUCLEAR nce c-A Unit of PECO Energy wa7N1NN59 July 10,1998 Docket No. 50-277 License No. DPR-44 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Subject:

Peach Bottom Atomic Power Station, Unit 2 License Change Application ECR 98-01403

Dear Sir:

PECO Energy Company (PECO Energy) hereby submits License Change Application ECR 98-01403, in accordance with 10 CFR 50.90, requesting a change to the Peach Bottom Atomic Power Station (PBAPS), Unit 2 Facility Operating License. This proposed change will revise Technical Specifications (TS) Section 2.0, " Safety Limits" and Section 5.6.5 (" Core Operating Limits Report"). These Sections will be revised to incorporate revised Safety Limit Minimum Critical Power Ratios (SLMCPRs) due to the use of cycle-specific analysis performed by General Electric Nuclear Energy (GENE) for PBAPS, Unit 2, Cycle 13.

Information supporting this request is contained in Attachment 1 to this letter, I and the marked up pages showing the proposed changes to the PBAPS, Unit 2 I TS are contained in Attachment 2. Attachment 3 (letter from S. B. Shelton (GENE) to K. W. Hunt (PECO Energy)," Peach Bottom Unit 2 Cycle 13 Safety Limit MCPR," dated June 10,1998) specifies the new SLMCPRs for PBAPS, Unit 2. Attachment 3 contains information proprietary to General Electric.

General Electric requests that the document be withheld from public disclosure in .

accordance with 10 CFR 2.790(a)(4). An affidavit supporting this request is I contained in Attachment 3. Attachment 4 contains a non-proprietary version.

We request that the amendment to the PBAPS, Unit 2 TS be approved by September 28,1998, and be made effective prior to the restart from the upcoming PBAPS, Unit 2 refueling outage.

• i 9807210353 980710 PDR ADOCK 05000277 P PDR r C-I .

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, July 10,1998 Page 2 If you have any questions, please do not hesitate to contact us.

Very truly yours, h Garrett D. E ards Director- Licensing

Enclosures:

Affidavit, Attachment 1, Attachment 2, Attachment 3, Attachment 4 cc: H. J. Miller, Administrator, Region I, USNRC A. C. McMutray, USNRC Senior Resident inspector, PBAPG ,

R. R. Janati, Commonwealth of Pennsylvania '

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. COMMONWEALTH OF PENNSYLVANIA:

ss.

COUNTY OF CHESTER  :

J. B. Cotton, being first duly swom, deposes and says:

That he is Vice President of PECO Energy Company; the Applicant herein; that he has read the attached License Change Application ECR 98-01403,' for Peach Bottom Facility Operating License DPR-44, and knows the contents thereof; and that

- the statements and matters set forth therein are true and correct to the best of his knowledge,information and belief.

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Vice President Subscribed and swom to before me this /0 M day of 1998.

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/ Notary Public gualAL SEAL carol A. WALTON. Notary Putes j?? en L

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l ATTACHMENT 1 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 -

Docket No. 50-277 License No. OPR-44 LICENSE CHANGE APPLICATION-ECR 98-01403

" Revision of SLMCPRs" Supporting information - 4 Pages l

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Docket No. 50-278 i License No. DPR-56 Introduction PECO Energy Company, Licensee under Facility Operating License DPR-44 for the Peach Bottom Atomic Power Station (PBAPS), Unit 2, requests that the Technical Specifications (TS) contained in Appendix A to the Operating License be amended to revise TS 2.1.1.2 and TS 5.6.5.b.1 to reflect changes in the Safety Limit Minimum Critical Power Ratios (SLMCPRs) due to the use of cycle-specific analysis performed by showing the proposed changes a(re contained in Attachment 2.

from S. B. Shelton (GENE) to K. W. Hunt (PECO Energy), " Peach Bottom Unit 2 Cycle 13 Safety Limit MCPR," dated June 10,1998) specifies the new SLMCPRs for PBAPS, Unit 2, Cycle 13. This License Change A description of the proposed TS changes, a safetypplication assessmentprovides of the proposed a discussion TS and changes, information supporting a finding of No Significant Hazards Consideration and informa'.:on supporting an Environmental Assessment.

Discussion and Description of the Proposed Chanae The proposed changes involve: 1) revising the SLMCPRs contained in TS 2.1.1.2,2) revising the footnote associated with TS 2.1.1.2 to reflect the use of cycle-specific SLMCPRs for Cycle 13, and 3) adding a footnote to TS 5.6.5.b.1.

The calculations of the cycle-specific, two-loop and single-loop operation SLMCPR values for PBAPS, Unit 2, Cycle 13, are based upon USNRC-approved methodology described in " General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A-13, and U.S. Supplement, NEDE-24011-P-A-13-US, August,1996, and the  ;

" Proposed Amendment 25 to GE Licensing Topical Report NEDE-24011-P-A (GESTAR 1 II) on Cycle Specific Safety Limit MCPR." Proposed Amendment 25 was submitted by )

GENE to the U. S. Nuclear Regulatory Commission (USNRC) on December 13,1996.  ;

Revision 13 of GESTAR 11 requires that the SLMCPR be reconfirmed each cycle. This reconfirmation was performed using the procedures contained in the proposed Amendment 25 to GESTAR which include utilization of cycle-specific parameters such as: 1) the actual core loading (GE11 and GE13 fuel),2) conservative variations of and 4) the full cycle exposure rang)e. projected control blade pattems,3 the ac The SLMCPR is selected such that 99.9% of the rods in the core are expected to avoid transition boiling. The results of the GENE analysis for PBAPS, Unit 2 Cycle 13 show a MCPR Safety Limit of 1.10 for two-loop operation and 1.12 for single-loop operation.

Additional information regarding the 1.10 and 1.12 cycle-specific SLMCPR for PBAPS, Unit 2 Cycle 13 is discussed in the Attachment 3 letter. ,

Due to the use of the proposed Amendment 25, the current footnote to TS 2.1.1.2 is being updated to ensure that the SLMCPR value is reconfirmed for the cycle l subsequent to PBAPS, Unit 2, Cycle 13. The current footnote applies to PBAPS, Unit 2, Cycle 12. This footnote was originally added to TS 2.1.1.2 to ensure that the TS clearly articulated that the TS values are applicable only to PBAPS, Unit 2, Cycle 12.

This issue was discussed in the USNRC Safety Evaluation dated September 27,1996, for PBAPS, Unit 2, Cycle 12.

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Docket No. 50-278 License No. DPR-56 Additionally, TS 5.6.5.b provides the analytical methods used to determine the core operating limits. TS 5.6.5.b.1 references the latest approved General Electric Standard Application for Reactor Fuel identified in the Core Operating Limits Report. Due to the use of the proposed Amendment 25, and the use of a proposed R-factor calculation methodology ("R-Factor Calculation Method for GE11, GE12, ano GE13 Fuel,"

NEDC-32505P, Revision 1, June 1997), which has not yet been approved for generic use by the USNRC, a footnote is being added on page 5.0-21 to TS 5.6.5.b.1 which states that for Cycle 13, specific documents will be approved in the USNRC Safety Evaluation that support the License Amendment to revise the SLMCPRs. This footnote was also added to the PBAPS, Unit 3 TS as discussed in the USNRC Safety Evaluation dated October 9,1997, for PBAPS, Unit 3, Cycle 12.

Safety Assessment The proposed TS changes will revise TS 2.1.1.2 and TS 5.6.5.b.1 to reflect the changes in the SLMCPRs due to the cycle-specific analysis performed by GENE for PBAPS, Unit 2, Cycle 13. The new SLMCPRs are calculated using USNRC-approved methodology described in " General Electric Standard Application for Reactor Fuel,"

NEDE-24011-P-A-13, and U.S. Supplement, NEDE-24011-P-A-13-US, August,1996, and the " Proposed Amendment 25 to GE Licensing Topical Report NEDE-24011-P-A (GESTAR 11) on Cycle Specific Safety Limit MCPR." Amendment 25 was submitted by GENE to the USNRC on December 13,1996. The SLMCPRs are set high enough to ensure that greater than 99.9% of all fuel rods in the core avoid transition boiling if the limit is not violated. The MCPRs are calculated to include cycle-specific parameters which include: 1) the actual core loading (GE11 and GE13 fuel),2) conservative variations of projected control blade pattems,3 the actual bundle parameters (e.g.,

local peaking), and 4) the full cycle expocure ra)nge. The new SLMCPRs at PB Unit 2, Cycle 13 are 1.10 (two-loop operation) and 1.12 (single-loop operation).

The footnote associated with TS 2.1.1.2 is being revised to ensure that the SLMCPR value is reconfirmed for the cycle subsequent to PBAPS, Unit 2, Cycle 13. Additionally, a footnote is being added to TS 5.6.5.b.1 due to the use of the proposed Amendment 25, and the use of a proposed R-factor calculation methodology ("R-Factor Calculation Method for GE11, GE12, and GE13 Fuel," NEDC-32505P, Revision 1, June 1997),

which has not yet been approved for generic use by the USNRC.

Information Supportina a Findina of No Significant Hazards Consideration We have concluded that the proposed changes to the PBAPS, Unit 2 TS, which will revise TS 2.1.1.2 and TS 5.6.5.b.1, do not involve a Significant Hazards Consideration.

in support of this determination, an evaluation of each of the three (3) standards set forth in 10 CFR 50.92 is provided below.

1. The proposed TS chanaes do not involve a significant increase in the probability or consequences of an accident previousiv evaluated.

The derivation of the cycle-specific SLMCPRs for incorporation into the TS, and I

its use to determine cycte-specific thermal limits, have been performed using the i methodology discussed in " General Electric Standard Application for Reactor l Fuel," NEDE-24011-P-A-13, and U.S. Supplement, NEDE-24011-P-A-13-US, l~

l August,1996, and the " Proposed Amendment 25 to GE Licensing Topical Report NEDE-24011-P-A (GESTAR ll) on Cycle Specific Safety Limit MCPR."

Amendment 25 was submitted by GENE to the U. S. Nuclear Regulatory 2

Docket No. 50-278 License No. DPR-56 Commission (USNRC) on December 13,1996. This change in SLMCPRs

.cannot increase the probability or severity of an accident.

The basis of the SLMCPR calculation is to ensure that greater than 99.9% of all fuel rods in the core avoid transition boiling if the limit is not violated. The new SLMCPRs preserve the existing margin to transition boiling and fuel damage in the event of a postulated accident. The fuellicensing acceptance criteria for the SLMCPR calculation apply to PBAPS, Unit 2, Cycle 13 in the same manner as they have applied prevously. The probability of fuel damage is not increased.

Therefore, the proposed TS changes do not involve an increase in the probability or consequences of an accident previously evaluated.

In addition to the change to the SLMCPR, the footnote to TS 2.1.1.2 is being revised, and a footnote is being added to TS 5.6.5.b.1. The revision to the footnote associated with TS 2.1.1.2 will ensure that the SLMCPR :;alue is reconfirmed for the cycle subsequent to PBAPS, Unit 2, Cycle 13, and the footnote to TS 5.6.5.b.1 is being added due to the use of the proposed Amendment 25 and the use of a proposed R-factor calculation methodology

("R-Factor Calculation Method for GE11, GE12, and GE13 Fuel,"

NEDC-32505P, Revision 1, June 1997), which has not yet been approved for generic use by the USNRC. The revision to the footnote associated with TS 2.1.1.2 and the addition of the footnote to TS 5.6.5.b.1 are administrative changes that do not involve an increase in the probability or consequences of an

. accident previously evaluated.

2. The orooosed TS chanaes do not create the possibility of a new or different kind of accident from any accident oreviousiv evaluated.

The SLMCPR is a TS numerical value, designed to ensure that transition boiling does not occur in 99.9% of all fuel rods in the core during the limiting postulated accident. It cannot create the possibility of any new type of accident. The new l SLMCPRs are calculated using methodology discussed in " General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A-13, and U.S.

Supplement, NEDE-24011-P-A-13-US, August,1996, and the " Proposed Amendment 25 to GE Licensing Topical Report NEDE-24011-P-A (GESTAR 11) on Cycle Specific Safety Limit MCPR." Amendment 25 was submitted by GENE to the USNRC on Decembe.- 13,1996. Therefore, the revision to the SLMCPR t

will not create the possibility of a new or different kind of accident from any accident previously evaluated.

Additionally, this proposed change will revise the footnote to TS 2.1.1.2, and add i a footnote to TS 5.6.5.b.1. The revision to the footnote associated with TS

2.1.1.2, and the addition of the footnote to TS 5.6.5.b.1, are administrative changes that do not create the possibility of a new or different kind of accident

from any previously evaluated.

3. The proposed TS chanoes do not involve a significant reduction in a maroin of safety.

There is no significant reduction in the margin of safety previously approved by the USNRO as a result of the proposed change to the SLMCPR, and the proposed change that will revise the footnote to TS 2.1.1.2, and add a footnote to TS 5.6.5.b.1. The new SLMCPRs are calculated using methodology 3

Docket No. 50-278 License No. DPR-56

' discussed in " General Electric Standard Application for Reactor Fuel," NEDE-

- 24011-P-A-13, and U.S. Supplement, NEDE-24011-P-A-13-US, August,1996, and the " Proposed Amendment 25 to GE Licensing Topical Report NEDE-

. 24011-P-A (GESTAR 11) on Cycle Specific Safety Limit MCPR." Amendment 25 was submitted by GENE to the USNRC on December 13,1996. The fuel licensing acceptance criteria for the calculation of the SLMCPR applv to PBAPS, Unit 2 Cycle 13 in the same manner as they have applied previously'. The SLMCPRs ensure that greater than 99.9% of all fuel rods in the core will avoid transition boiling if the limit is not violated, thereby preserving the fuel cladding integrity. Therefore, the proposed TS changes will not significantly reduce the margin of safety previously approved by the USNRC.

Additionally, the proposed change that will revise the footnote to TS 2.1.1.2, and add a footnote to TS 5.6.5.b.1 is an administrative change that will not significantly reduce the margin of safety previously approved by the USNRC.

Information Suooortina an Environmental Assessment An environmental assessment is not required for the proposed changes since the proposed changes conform to the criteria for " actions eligible for categorical exclusion" as specified in 10 CFR 51.22(c)(9). The proposed changes will have no impact on the environment. The proposed changes do not involve a significant hazards consideration as discussed in the preceding section. The proposed changes do not involve a significant change in the types or significant increase in the amounts of any effluents that may be released offsite.- In addition, the proposed changes do not involve a significant increase in individual or cumulative occupational radiation exposure.

Conclusion The Plant Operations Review Committee and the Nuclear Review Board have reviewed this proposed change to the PBAPS, Unit 2 TS and have concluded that it does not involve an unreviewed safety question, and will not endanger the health and safety of the public.

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ATTACHMENT 2 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 I

Docket No. 50-277 l License No. DPR-44 i

( TECHNICAL SPECIFICATIONS CHANGES I Attached Pages i

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( TS Page 2.0-1 TS Page 5.0-21 i

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