ML20211N879
| ML20211N879 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 02/19/1987 |
| From: | Mcneil S Office of Nuclear Reactor Regulation |
| To: | Tiernan J BALTIMORE GAS & ELECTRIC CO. |
| References | |
| NUDOCS 8703020243 | |
| Download: ML20211N879 (3) | |
Text
-,
bHB ok February 19, 1987 4.
Dockef Nos. 50-317 DISTRIBUTION and 50-318 (Docket FiTg EJordan NKU Vurs BGrimes L PDR JPartlow Mr. J. A. Tiernan PBD#8 Rdg NThompson Vice President-Nuclear Energy FMiraglia PKreutzer Baltimore Gas & Electric Company OGC-Beth SMcNeil P. O. Box 1475 ACRS-10 Gray File Baltimore,.MD 21203 CThomas-TMarsh
Dear Mr. Tiernan:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - MODERATOR TEMPERATURE COEFFICIENT' AMENDMENT AND UNIT 2 CYCLE 8 RELOAD REQUESTS The Commission-has completed its review of your request to modify the Units 1 and 2 Technical Specification-(TS) Limiting Condition for Operation 3.1.1.4 by raising the upper limit of the moderator temperature coefficient (MTC) above 70% Rated Thermal Power from the current limit of less positive than
+ 0.2 E-4 delta k/k/ F to a proposed limit of less positive'than +(1.16.66P)
E-4 delta k/k/ F where P is the Fraction of Rated Power.
This TS amendment request was submitted in your letter of July 31, 1986 and was supplemented by your submittals dated August 20, 1986, October 22, 1986, October 27, 1986, November 4, 1986 (signed November 13, 1986) and February 3, 1987.
The Commission has determined that further information concerning feedline break (FLB) events and the peak reactor coolant system pressure permissible for FLBs is necessary to justify this TS amendment request.
The request for additional information is enclosed.
In addition, contrary to your letter of February 3,1987, the Commission has determined that resolution of the issues involving FLB is essential to the determination of the acceptability of the upcoming Unit 2 Cycle 8 reload license 4
submittal.
Please provide the information as requested within 30 days following the receipt of this letter.
This request for information affects fewer than 10 respondents; therefore OMB clearance is not required under P.L.96-511.
Sincerely, f
870302O243 870219
/S/
i PDR ADOCK 05000317 Scott Alexander McNeil, Project Manager P
PDR PWR Project Directorate #8 Division of PWR Licensing-B
Enclosure:
Request for Additional Information 7
cc w/ enclosure:
See next page PB PB RSB: PWR-B -
EB: PWR-6 PBD#8 PKr zer S
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.o 9
Mr. J. A. Tiernan Baltimore Gas & Electric Company Calvert Cliffs Nuclear P.ower Plant cc:
Mr. William T. Bowen, President Regional Administrator, Region I Calvert County Board of U.S. Nuclear Regulatory Commission Commissioners Office of Executive Director Prince Frederick, Maryland 20768 for Operations 631 Park Avenue D. A. Brune, Esq.
King of Prussia, Pennysivania 19406 General Counsel Baltimore Gas and Electric Company P. O. Box 1475 Baltimore, Maryland 21203 Jay E. Silberg Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.W.
H Washington, DC 20037 Mr. M. E. Bowman, General Supervisor Technical Services Engineering Calvert Cliffs Nuclear Power Plant MD Rts 2 & 4, P. O. Box 1535 Lusby, Maryland 20657-0073 Resident Inspector c/o U.S. Nuclear Regulatory Commission P. O. Box 437 t'
Lusby, Maryland 20657-0073 Bechtel Power Corporation i'
ATTN:
Mr. D. E. Stewart Calvert Cliffs Project Engineer 15740 Shady Grove Road L
Gaithersburg, Maryland 20760 Combustion Engineering, Inc.
ATTN: Mr. W. R. Horlacher, III Project Manager P. O. Box 500 1000 Prospect Hill Road Windsor, Connecticut 06095-0500 Department of Natural Resources Energy Administration, Power Plant Siting Program l
ATTN:
Mr. T. Magette l
Tawes State Office Building l
Annapolis, Maryland 21204 1
L
l REQUEST FOR ADDITIONAL INFORMATION BALTIMORE GAS AND ELECTRIC COMPANY MTC AHENDMENT AND UNIT 2 CYCLE 8 RELOAD REQUESTS 1.
Provide your justification for permitting the peak reactor coolant system (RCS) pressure to exceed 110% of the design RCS pressure as described in your July 31, 1986 safety analysis for the feedline break (FLB) event with a loss of AC power on reactor trip.
Please note that a justification based solely upon your belief that FLB is not a design basis event (DBE) would be considered by the Commission to be inadequate.
2.
The Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Updated Final Safety Analysis Report states that "...Feedline Break Events have been subsequently added to the Design Bases Events required by the operating license." In addition, your submittals of November 5 and 17, 1982, which you provided to demonstrate that the Unit 2 auxiliary feedwater actuation system (AFAS) was safety grade and met the requirements of Item II.E.1.2 of NUREG-0737, stated that the FLB is a DBE.
Your submittals of August 22, September 1 and September 16, 1983 stated that FLB was a transient that was required to be analyzed to accommodate installation of a safety grade AFAS on Unit 1.
a.
Please justify your assertion as provided in your submittals of January 20 and July 31, 1986 that the FLB is not a DBE.
b.
If the FLB is not a DBE, justify how the Units 1 and 2 AFAS's would continue to meet Criteria 13, 20 and 34 of 10 CFR Part 50, Appendix A, as required by Sections 2.1.7.a & b of NUREG-0578 when the FLB peak RCS pressure exceeds 110% of the design RCS pressure.
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