ML20135F091
| ML20135F091 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 12/06/1996 |
| From: | Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20135F094 | List: |
| References | |
| NUDOCS 9612120347 | |
| Download: ML20135F091 (7) | |
Text
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ct; tion cupport Department 10CFR50.90 s_
=r PECO NUCLEAR mco m. c -
A Unit of PECO Energy wa[p$NsN***
December 6,1996 I
i Docket No. 50-353 l
i License No. NPF-85 l
l U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Subject:
Umerick Generating Station, Unit 2 Technical Specifications Change Request No. 96-11-2 Gentlemen:
PECO Energy Company is submitting Technical Specifications (TS) Change Request No. 96 -l 2, in accordance with 10CFR 50.90, requesting an amendment to the TS (Appendix A) of Operating Ucense No. NPF-85 for Umerick Generating Station (LGS), Unit 2. This proposed change will revise TS Section 2.1, " Safety Umits," to change the Minimum Critical Power Ratio l
(MCPR) Safety Umit due to the use of GE13 fuel product line and the cycle-specific analysis l
performed by General Electric Co. (GE), for LGS Unit 2 Cycle 5. Information supporting this Change Request is contained in Attachment 1 to this letter, and the marked up pages showing the proposed change to the LGS Unit 2 TS are contained in Attachment 2. This information is being submitted under affirmation, and the required affidavit is enclosed., Letter R. M. Butrovich (GE) to H. J. Diamond (PECO), " Limerick Unit 2 Cycle 5 Safety Umit MCPR ", dated November 11,1996 specifies the new MCPR Safety Umit for LGS Unit 2, Cycle 5.
i We request that, if approved, the amendment to the LGS Unit 2 TS be issued by January 31,1997, and become effective within 30 days of issuance.
I If you have any questions, please do not hesitate to contact us.
i Very truly yours, f
l G. A. Hunger, Jr.,
Director - Licensing f
I l-Enclosure, Attachments f[(jg /
cc:
H.J. Miller, Administrator, Region I, USNRC (w/ enclosure, attachments)
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N. S. Perry, USNRC Senior Resident inspector, LGS (w/ enclosure, attachments)
R. R. Janati, PA Bureau of Radiological Protection (w/ enclosure, attachments) i 9612120347 961206 l
PDR ADOCK 05000353 p
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j COMMONWEALTH OF PENNSYLVANIA l
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ss.
COUNTY OF CHESTER 3
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- D. B. Fetters, being first duly sworn, deposes and says:
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That he is Vice President of PECO Energy Company, the Applicant herein; that he has read the foregoing Application for Amendment of Facility Operating Ucense No. NPF-85 (Technical Specifications Change Request No. 96-11-2), to change the Minimum Critical Power Ratio (MCPR) Safety Umit due to the use of GE13 fuel product line and j
the cycle-specific analysis performed by General Electric Co. for Umerick Generating l
L Station, Unit 2 Cycle 5, and knows the contents thereof; and that the statements and 5
l matters set forth therein are true and correct to the best of his knowledge, information l
1-i and belief.
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Vice President Subscribed and sworn to before me this ay of 1996.
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Notary Public Notaria :al LOU Skrocki, Notary PubRc inn T*p. Che=te. Coun g. y c mrnissic-r May17 hl%rVW/Vegenmoutk60f '
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ATTACHMENT 1 j
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LIMERICK GENERATING STATION l
UNIT 2
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DOCKET NO. 50-353 LICENSE NO. NPF-85 TECHNICAL SPECIFICATIONS CHANGE REQUEST NO. 96-11-2 Supporting Information for Change - 4 Pages
" CHANGE TO THE MINIMUM CRITICAL POWER RATIO (MCPR)
SAFETY LIMIT "
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Docket No. 50-353 License No. NPF-85 I
PECO Energy Company, under Facility Operating Ucense No. NPF-85 for Limerick Generating Station (LGS), Unit 2, requests that the Technical Specifications (TS) contained in Appendix A to the Operating Ucense be amended as proposed herein, to i
revise TS Section 2.1 and its associated TS Basis to reflect the change in the Minimum Critical Power Ratio (MCPR) Safety Limit due to the use of GE13 fuel product line and the cycle-specific analysis performed by General Electric Co. (GE), for LGS Unit 2 Cycle 5. The proposed change to the LGS Unit 2 TS is indicated by markups on TS page 2-1 and TS Bases page B 2-1. The TS page and TS Bases page showing the proposed change are contained in Attachment 2.
!, Letter R. M. Butrovich (GE) to H. J. Diamond (PECO Energy), " Limerick l
Unit 2 Cycle 5 Safety Limit MCPR ", dated November 11,1996 specifies the new MCPR Safety Limit for LGS Unit 2, Cycle 5.
l We request that, if approved, the TS change proposed herein be issued by January l
31,1997, and become effective within 30 days of issuance.
l This TS Change Request provides a discussion and description of the proposed TS change, a safety assessment of the proposed TS change, information supporting a finding of No Significant Hazards Consideration and information supporting an J
Environmental Assessment.
l l
Discussion and Descriotion of the Prooosed Chanoe i
1 The proposed Technical Specifications (TS) Change Request involves the change of Umerick Generating Station (LGS), Unit 2, TS Section 2.1 and its associated TS Basis to revise the Minimum Critical Power Ratio (MCPR) Safety Limit due to the use of -
GE13 fuel product line and the cycle-specific analysis performed by General Electric Co. (GE), for LGS Unit 2 Cycle 5.
l, Letter R. M. Butrovich (GE) to H. J. Diamond (PECO Energy), " Limerick Unit 2 Cycle 5 Safety Umit MCPR " dated November 11,1996, specifies the new MCPR Safety Umit for LGS Unit 2, Cycle 5. The new MCPR Safety Limit is calculated using NRC-accepted methodology described in " General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A-13, and U.S. Supplement, NEDE-24011-P-A US, August 1996 and the Technical Design Procedure (" GETAB Safety Limit ", TDP-0049, Revision 0, July 1996). The Technical Design Procedure includes cycle-specific i
parameters such as: the actual core loading, conservative variations of projected a
control blade patterns, the actual bundle parameters (e.g., local peaking), and the full cycle exposure range. The MCPR Safety Limit is 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 results of the GE analysis for LGS Unit 2 Cycle 5 show a MCPR Safety Limit of 1.11 for two loop operation and 1,1p.for single loop operation.
1 Docket No. 50-353 License No. NPF-85 l
l Therefore, we propose that LGS Unit 2 TS Section 2.1 and TS Bases 2.1 be revised to reflect the change in the Minimum Critical Power Ratio (MCPR) Safety Umit, for LGS Unit 2, Cycle 5.
Safety Assessment The proposed TS change will revise TS Section 2.1 and its associated TS Basis to l
reflect the change in the Minimum Critical Power Ratio (MCPR) Safety Limit, due to the l
use of GE13 fuel product line and the cycle-specific analysis performed by General l
Electric Co, (GE), for LGS Unit 2 Cycle 5.
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The new MCPR Safety Limit is calculated using NRC-accepted 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 Technical Design l
l Procedure (" GETAB Safety Limit ", TDP-0049, Revision 0, July 1996). The Technical Design Procedure includes cycle-specific parameters such as: the actual core loading, conservative variations of projected control blade patterns, the actual bundle parameters (e.g., local peaking), and the full cycle exposure range. The MCPR Safety I
Umit is set high enough to ensure that greater than 99.9% of all fuel rods in the core l
avoid transition boiling if the limit is not violated. The new MCPR Safety Limit at LGS Unit 2 is 1.11 for operation with two recirculation loops and 1.12 for single loop l
operation.
Information Succortina a Finding of No Significant Hazards Consideration l
We have concluded that the proposed change to the Limerick Geneating Station (LGS), Unit 2 Technical Specifications (TS) which will revise TS Section 2.1, " Safety Limits," and its associated TS Basis to change the Minimum Critical Power Ratio (MCPR) Safety Umit due to the use of GE13 fuel product line and the cycle-specific analysis performed by General Electric Co. (GE), for LGS Unit 2 Cycle 5, does 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.
l 1.
The orocosed Technical Soecifications (TS) change does not involve a j
significant increase in the orobability or consecuences of an accident oreviously evaluated.
The derivation of the revised Minimum Critical Power Ratio (MCPR) Safety Limit for LGS Unit 2 Technical Specifications, and its use to determine cycle-specific I.
Docket No. 50-353 l
Ucense No. NPF-85 l
l thermal limits have been performed using NRC-accepted methodology l
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 Technical Design Procedure (" GETAB Safety Limit ", TDP-0049, Revision 0, July 1996).This change in the MCPR Safety Umit cannot increase the probability or severity of an accident.
The basis of the MCPR Safety Umit 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 MCPR Safety Umit preserves the existing margin to transition i
boiling and fuel damage in the event of a postulated accident. The fuel licensing acceptance criteria for the calculation of the MCPR Safety Umit apply to Umerick Generating Station (LGS), Unit 2, Cycle 5 in the same manner as they have applied previously. The probability of fuel damage is not increased.
Therefore, the proposed TS change does not involve an increase in the probability or consequences of an accident previously evaluated.
2.
The orocosed TS chance does not create the oossibility of a new or different kind of accident from any accident oreviousiv evaluated.
The MCPR Safety Umit is a TS numerical value, designed to ensure that fuel damage from transition boiling does not occur as a result of the limiting postulated accident. It cannot create the possibility of any new type of accident. The new Minimum Critical Power Ratio (MCPR) Safety Umit is calculated using NRC-accepted 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 199S and the Technical Design Procedure (" GETAB Safety Umit ", TDP-0049, Revision 0, July 1996).
Therefore, the proposed TS change does not create the possibility of a new or different kind of accident, from any accident previously evaluated.
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l Docket No. 50-353 License No. NPF-85 3.
The orocosed TS change does not involve a significant reduction in a margin of safety.
The margin of safety as defined in the TS Bases will remain the same. The new l
Minimum Critical Power Ratio (MCPR) Safety Umit is calculated using NRC-accepted methodology described in ' General Electric Standard Application for l
Reactor Fuel," NEDE-24011-P-A-13, and U.S. Supplement, NEDE-24011-P-A-13-US, August 1996 and the Technical Design Procedure ("GETAB Safety Limit", TDP-0049, Revision 0, July 1996). The fuel licensing acceptance criteria j
for the calculation of the MCPR Safety Umit apply to LGS Unit 2, Cycle 5 in the l
same manner as they have applied previously. The MCPR Safety Limit is 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, thereby preserving the fuel cladding l
integrity.
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Therefore, the proposed TS change does not involve a reduction in a margin of l
safety.
Information Sucoortina an Environmental Assessment An environmental assessment is not required for the change proposed by this TS Change Request because the requested change to the Limerick Generating Station l
(LGS), Unit 2, TS conforms to the criteria for " actions eligible for categorical exclusion" as specified in 10 CFR51.22(c)(9). The requested change will have no impact on the environment. The proposed change does not involve a significant hazards consideration as discussed in the preceding section. The proposed change does not i
I 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 change does not l
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 Umerick Generating Station (LGS), Unit 2, TS and have concluded that it does not involve an unreviewed safety question, and will not j
endanger the health and safety of the public.
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