ML20080Q027
| ML20080Q027 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 10/07/1983 |
| From: | Kemper J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| GOVT-1-1(NRC), NUDOCS 8310120148 | |
| Download: ML20080Q027 (4) | |
Text
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PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 1881 -1981 PHILADELPHlA, PA.19101 JOHN S. KEMPER
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V IC E-PR ESID E N T
.............o..u..'"
October 7, 1983 Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Limerick Generating Station, Units 1 and 2 Core Performance Branch
Reference:
Telecon, W. Brooks (NRC) to R. J. Stipcevich and D. F. Ciarlone (PECO), July 15, 1983 File:
GOVT l-1 (hTC)
Dear Mr. Schwencer:
As requested by the Core Performance Branch Reviewer in the reference telecon, with this letter we are providing additional information on the Misplaced Bundle Accident Analysis presented in FSAR Section 15.4.7.
The first attachment, entitled Requested Additional Information, clarifies the analytical results of this accident presented in FSAR Table 15.4-6.
The second attachment is a draf t replacement for FSAR Table 15.4-6.
This revision is being made to document the clarification discussed in the first attachment.
The attached draf t FSAR revision will be incorporated into the FSAR exactly as it appears on the attachment in the revision scheduled for Novemb.
1983.
Sincerely, SWf/
DFC/gra/J-4 Copy to: See Attached Service List f
s aso/sss i \\
831012014e e31007 DR ADOCK 05000352 j
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cc: Judge Lawrence Brenner (w/o enclosure)
Judge Richard F. Cole (w/o enclosure)
Judge Peter A. Morris (w/o enclosure)
Troy B. Conner, Jr., Esq.
(w/o enclosure)
Ann P. Hodgdon, Esq.
(w/o enclosure)
Mr. Frank R. Romano (w/o enclosure)
Mr. Robert L. Anthony (w/o enclosure)
Mr. Marvin I. Lewis (w/o enclosure)
Judith A. Dorsey, Esq.
(w/o eaclosure)
Charles W. Elliott, Esq.
(w/o enclosure)
Jacqueline I. Ruttenberg (w/o enclosure)
Thomas Y. Au, Esq.
(w/o enclosure)
Mr. Thomas Gerusky (w/o enclosure)
Director, Pennsylvania Emergency Management Agency (w/o enclosure)
Mr. Steven P. Hershey (w/o enclosure)
Angus Love, Esq.
(w/o enclosure)
Mr. Joseph H. White, III (w/o enclosure)
David Wersan, Esq.
(w/o enclosure)
Robert J. Sugarman, Esq.
(w/o enclosure)
Martha W. Bush, Esq.
(w/o enclosure)
Spence W. Perry, Esq.
(w/o enclosure)
Atomic Safety and Licensing Appeal Board (w/o enclosure)
Atomic Safety and Licensing Board Panel (w/o enclosure)
Docket and Service Section (w/o enclosure)
Jay M. Gutierrez, Esq.
(w/o enclosure) i l
l
o REQUESTED' ADDITIONAL INFORMATION CORE PERFORMANCE BRANCH
Subject:
FSAR Subsection 35.4.7, Misplaced Bundle Accident
Reference:
Telecon, W. Brooks (NRC) to R. J. Stipcevich and D. F. Ciarlone (PECO), " Questions on FSAR Table 15.4-6, Initial Conditions and Results of Fuel Bundle Loading Error," July 15, 1983.
' Concern:
In reference telecon the NRC reviewer questioned the the information presented in Table 15.4-6.
Specifically, he questioned the notation used to specify the location of the most severe error (with respect to each of the two criteria used to evaluate this accident), and he questioned the meani..g of the Minimum CPR data as presented in the Rev. 23, 8/83 version of this Table.
Response
The core location notation used in Table 15.4-6 followed the convention of the nodal computer code used in the analysis and was not converted into the core location notation used throughout the balance of the Limerick FSAR.
This concern has been addressed in replacement Table 15.4-6, attached.
The format of the Table has been revised to clarify that the analysis of this accident assumed an initial operating CPR of 1.40, which. is typical of normal operation, and that the accident resulted in a maximum ACPR of 0.11.
When this ACPR is added to the Safety Limit MCPR of 1.06, the Operating Limit MCPR for this accident is 1.17.
Since this is within the OLMCPR of 1.22 already established by the limiting transient (Loss of Feedwater Heater, Manual Flow Control), no further change to the FSAR is required to resolve the above concern.
TABLE 15.4-6 o
INITIAL CONDITIONS AND RESULTS OF FUEL BUNDLE LOADING ERROR (1)
Reactor Power, % rated 100 Core Flow, % rated 100
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For Largest ACPR Core Exposure, MWD /ST 7810 Location of Error (29,32)
Initial Operating CPR 1.40 A CPR with Fuel Loading Error 0.11 For Largest MLHGR Core Exposure, MWD /ST 5000 Location of Error (21,54)
Initial LHGR, KW/FT 13.4 (Assumed at Operating Limit)
LHGR with Fuel Loading Error, 16.97 KW/FT (1) Core conditions are assumed to be normal for a hot, operating core.
DRAFT j
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