ML20043E613
| ML20043E613 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/05/1990 |
| From: | Suh G Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9006130201 | |
| Download: ML20043E613 (6) | |
Text
c.
- r June 5, 1990 C
Docket Nos.:
50-277/278 LICENSEE:
Philadelphia Electric Company, et. al.
FACILITY:
Peach Bottom Atomic Power Station Unit 2 and Unit 3
SUBJECT:
SUMMARY
OF MAY 21, 1990 MEETING ON FUEL TOPICAL REPORT FMS-0006 l
On May 21, 1990 at the NRC offices in Rockville, Meryland, a meeting was held 1
between the NRC staff and representatives of the Ph iadelphia Electric Company to discuss the review of fuel topical report PEco-FMS-0006, titled " Methods for Performing BWR Reload Safety Evaluations." This topical report is the last of a series of six topical reports submitted by the licensee to support a program of. in-house reload application analyses. provides a list of the meeting participants. Meeting highlights are described in the following.
'The staff asked a series of questions identified in its review of FMS-0006. provides a suninary of the additional information requested by the staff. The staff also requested that the licensee identify those sections of FMS-0006 which addressed the open items identified in the review of a previous topical report, FMS-0004 The licensee agreed to submit the requested information in the near future.
The question of the applicability of the staff's approval of the previous five fuel topical reports, currently approved for the Peach Bottom facility, to the Limerick Generating Station was briefly discussed.
The licensee will contact 4
the Limerick NRC Project Manager to resolve what actions will be required.
/s/
Gene Y. Suh, Project Manager Project Directorate I-2 Division of Reactor Projects - I/II
Enclosures:
As stated cc w/ enclosure:
See next page
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t WASHINGTON, D. C. 20555 I%,.... + p June 5, 1990 l
l Docket Nos.: 50-277/278 LICENSEE:-
Philadelphia Electric Company, et. al.
FACILITY:
Peach Bottom Atomic Power Station, Unit 2 and Unit 3
SUBJECT:
SUMMARY
OF MAY 21, 1990 MEETING ON FUEL TOPICAL REPORT FMS-0006 l
.On May 21, 1990 at the NRC cffices in Rockville, Maryland, a meeting was held between the NRC staff and representatives of the Philadelphia Electric Company to discuss the review of fuel topical report PECo-FMS-0006, titled " Methods for Performing BWR Reload Safety Evaluations." This topical report is the~
last of a series of six topical reports submitted by the licensee to support a program of in-house reload application analyses. provides a list of the meeting participants. Meeting highlights are described in the following.
The staff asked a series of questions identified in its review of FMS-0006. provides a summary of the additional information requested by the-staff. The staff also requested that the licensee identify those sections of I
FMS-0006 which addressed the open items identified in the review of a previous topical report, FMS-0004. The licensee agreed to submit the requested information in the near future.
1' 4
The question of the applicability of the staff's approval of the previous five
\\
fuel topical reports, currently approved for the Peach Bottom facility, to the l
Limerick Generating Station was briefly discussed.
The licensee will contact the Limerick NRC Project Manager to resolve what actions will be required.
M
)
Gene Y.
uh, Project Manager Project Directorate I-2
)
Division of Reactor Projects - I/II
Enclosures:
l-As stated cc w/ enclosure:
See next page 1
l l
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' ' Mr. George A. Hunger, Jr.
Peach Bottom Atomic Power Station, Philadelphia Electric Company Units 2 and 3 L
l cc:
Troy B. Conner, Jr., Esq.
Single Point of Contact i
1747 Pennsylvania Avenue, N.W.
P. O. Box 11880 Washington, D.C.
20006 Harrisburg, Pennsylvania 17108-1880 l.
Philadelphia Electric Company Mr. Thomas M. Gerusky, Director ATTN: Mr. D.B. Miller, Vice President Bureau of Radiation Protection Peach Bottom Atomic Power Station-Pennsylvania Department of Route 1, Box 208 Environmental Resources Delta, Pennsylvania 17314 P. O. Box 2063 Harrisburg, Pennsylvania 17120 Philadelphia Electric Company ATTH:
Regulatory Engineer, A1-25 Mr. Albert R. Steel, Chairman Peach Bottom Atomic Power Station Board of Supervisors Route 1, Box 208 Peach Bottom Township l
Delta, Pennsylvania 17314 R. D. #1 Delta, Pennsylvania 17314 Resident Inspector V.S. Nuclear Regulatory Comission Public Service Comission of Maryland l
Peach Bottom Atomic Power Station Engineering Division P.O. Box 399 ATTN: Chief Engineer Delta, Pennsylvania 17314 231 E. Baltimore Street 4
Baltimore, MD 21202-3486 Regional Administrator, Region 1 L
U.S. Nuclear Regulatory Commission Mr. Tom Magette 475 Allendale Road Power Plant Research Program King of Prussia, Pennsylvania 19406 Department of Natural Resources B-3 L
Mr. Roland Fletcher Tawes State Office Building Department of Environment Annapolis, Maryland 21401 201 West Preston Street Baltimore, Maryland 21201 i
I l
1
pp 1
,t c,
t ENCLOSURE 1 u
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NRC/PEco MEETING ON FUEL TOPICAL REPORT FMS-0006 1
N/.ME ORGAN 11ATION A. M. Olson PEco/ Fuel Management J. P. Waldmen PEco/ Fuel-Management F. D. Lear PEco/ Licensing L. Lois NRC/NRR/ DST i
G. Y. Suh NRC/NRR/DRP 1
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ENCLOSURE 2 QUESTIONS FROM MAY 21, 1990 NRC MEETING WITH PHILADELPHIA ELECTRIC COMPANY 1.
The analytical results presented in the report were determined primarily for the PB3C7 reference cycle.- The report howevcr indicates applicability to future Peach Bottom cycles and to other BWRs. Justify the application of the methods described in the report to future cycles and other BWRs.
1 2.
The void and Doppler verification for the RETRAW point kinetics model was perforred by comparing the equilibrium end result of a slow transient to the 3-D simulator result. Since the limiting licensing events are rapid power increase transients, explain the applicability of this verification to reload licensing.
3.
The qualification and application of the 1-0 kinetics methods are described-at end-of-cycle (E00) and EOC-2000 MWD /T exposure statepoints only.
Since some transient events are more severe at other cycle exposures, explain why.other exposure statepoints were not analyzed.
4.
Provide further justificetion that the uniform fuel pellet radial power distribution is conservative.
5.
Justify PECo's use of the BSAFE code.
4
-6.
Provide further justificatien that the reactivity oscillation described in the analysis of the feedwater centroller failure does not impact licensing results.
7.
Provide further justification that the reactor recirculation controller failure event becomes less severe at higher initial core flows.
8.
Assure that this report is complete with respect to Chapter 15 of the NRC Standard Review Plan.
9.
Clarify the process by which the impact of plant modifications on reload licensing will be evaluated.
- 10. Address the application of NRC approved safety limits for mixed fuel Cores.
- 11. Update the status of the EWR stability issue in the discussion presented in the topical report.
IP. Address the application of cycle operating flexibility options in future reload analyses.
- 13. Section 6 of the PECo Supplemental Reload Licensing Report should be revised to include values for Doppler coefficient and core average fuel temperature. Also, section 9 should be revised to include feedwater heaters out-of-service and section 10 should be revised to indicate the analysis methods employed.
- 14. Revise the listing of topical reports in section 6 " References," to indicate their approval status.
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