ML20237B309
| ML20237B309 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/11/1998 |
| From: | Geoffrey Edwards PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9808180167 | |
| Download: ML20237B309 (5) | |
Text
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lECO NUCLEAR escm. c-ev A UN:t of PECO Euxcy
$5 c"he Y$ey?rd l
Wayne, PA 19087 5691 August 11,1998 l
Docket Nos. 50-277 50-278 License Nos. DPR-44 DPR-56 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Subject:
Peach Bottom Atomic Power Station, Units 2 and 3 Response to the Request for Additional Information Concerning License Change Application ECR 97-02809 I
Reference:
Letter from G. D. Edwards (PECO Energy Company (PECO Energy)), to U. S. Nuclear Regulatory Commission (USNRC),
dated March 20,1998
Dear Sir / Madam:
In the Referenced letter, PECO Energy Company (PECO Energy) submitted License Change Application ECR 97-02809, in accordance with 10 CFR 50.90, requesting a change to the Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3 Facility Operating Licenses. This proposed change will revise the Technical Specifications (TS) to incorporate an End-of-Cycle Recirculation Pump Trip (EOC-RPT) System at PBAPS, Units 2 and 3.
Based on additional conversations between the U. S. Nuclear Regulatory Commission staff and PECO Energy, attached is a discussion which describes the need to include the Average Planar Linear Heat Generation Rate (APLHGR) in the PBAPS, Units 2 and 3 Technical Specifications.
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l If you have any questions, please do not hesitate to contact us.
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9808190167 980811 PDR ADOCK 05000277 P
August 11,1998
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Very truly yours, h 8 NA$ lc g s
Garrett D. Edwards Director - Licensing l
Attachment i
i cc:
H. J. Miller, Administrator, Region I, USNRC A. C. McMurtray, USNRC Senior Resident inspector, PBAPS i
R. R.~Janati, Commonwealth of Pennsylvania
l COMMONWEALTH OF PENNSYLVANIA:
4 ss.
' COUNTY OF YORK l
l J. Doering, Jr., being first duly sworn, deposes and says:
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That he is Vice President of PECO Energy Company; the Applicant i
1 herein; that he has read the attached response to the request for additional j
information concerning License Change Application ECR 97-02809, for Peach Bottom Facility Operating Licenses DPR-44 and DPR-56, 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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M --. (
y Vice President l-Subscribed and sworn to before me this //A day ofh
- 1998, 0 971 I Y
e r
Notary Public JANET L WILEY, NOTARY PUBUC PEACHBOTTOMTWP YORKCOUNTY,PA WYCOMMISSION EXPIRES JUNE 17,2002
c ATTACHMENT Average Planar Linear Heat Generation Rate (APLHGR) in the PBAPS, Units 2 and 3 Technical Specifications
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BACKGROUND The Average Planar Linear Heat Generation Rate (APLHGR) is a measure of the
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average LHGR of all the fuel rods in a fuel assembly at any axial Incation. Limits on the APLHGR are specified to ensure that the fuel design limits identified in Reference i
1(GESTAR) are not exceeded during abnormal operational transients and that the peak cladding temperature (PCT) during the postulated design basis Loss of Coolant Accident (LOCA) does not exceed the limits specified in 10 CFR 50.46.
Fuel design evaluations are performed to demonstrate that the 1% limit on the fuel cladding plastic strain and other fuel design limits described in Reference 1 are not i
exceeded during abnormal operational transients for operation with LHGRs up to the
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operating limit LHGR. APLHGR limits are equivalent to the LHGR limit for each fuel rod
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divided by the local peaking factor of the fuel assembly. APLHGR limits are developed
'j as a function of exposure and the various operating core flow and power states to ensure adherence to fuel design limits during the limiting abnormal operational transients (Refs. 2 and 3).
LOCA analyses are then performed to ensure that the above determined APLHGR limits are adequate to meet the PCT and maximum oxidation limits of 10 CFR 50.46.
The analysis is performed using calculational models that are consistent with the requirements of 10 CFR 50, Appendix K. A complete discussion of the LOCA analysis code is provided in Reference 4.
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The EOC-RPT system helps to reduce the severity of pressurization transients resulting from a turbine trip or load rejection. These transient events establish in part the operating limits for MCPR and APLHGR. When the RPT system is not operable the consequences of these limiting events are more severe and more restrictive limits must be enforced to ensure the fuel design limits are mat for all postulated events. The thermal limits for both conditions, RPT in service and RPT out of' service, are specified I
in the Cycle Operating Limits Report ( COLR), referred to in Technical Specificaticca LCO 3.3.4.2.
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REFERENCES
- 1. NEDO-24011-P-A-10, " Standard Application for Reactor Fuel," February 1991.
- 2. NEDC-32162P," Maximum Extended Load Line for Peach Bottom Atom:c Power Station Units 2 and 3," Revision 1, February 1993.
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- 3. NEDC-32183P, " Power Rerate Safety Analysis Report for Peach Bottom 2 & 3,"
May 1993.
- 4. NEDC-32163P, " Peach Bottom Atomic Power Station Units 2 and 3 j
SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis," January 1993.
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