ML20035H653
| ML20035H653 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/04/1993 |
| From: | Mcdonald D Office of Nuclear Reactor Regulation |
| To: | Denton R BALTIMORE GAS & ELECTRIC CO. |
| References | |
| TAC-M86136, TAC-M86137, NUDOCS 9305060161 | |
| Download: ML20035H653 (4) | |
Text
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.e May 4, 1993 j
' Docket Nos. 50-317 and 50-318 Mr. Robert E.. Denton
'Vice President - Nuclear Energy Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power. Plant 1650 Calvert Cliffs Parkway Lusby, Maryland 20657-4702
Dear Mr. Denton:
SUBJECT:
CORRECTION TO TECHNICAL SPECIFICATION BASES CHANGES FOR CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT 1 (TAC NO. M86136) AND UNIT 2 (TAC N0. M86137)
By letter dated April 26, 1993, the NRC issued revision instructions and revised Technical Specification Bases pages for the Calvert Cliffs Nuclear Power Plant, Unit Hos. I and 2, Technical Specifications (TSs).
However, due.
to an administrative error, Unit 2 TS Bases Page B3/4 7-1 was not included.
We have enclosed the revised TS Bases Page B3/4 7-1 to be included in the Unit 2 TS Bases Section.
We apologize for any inconvenience this error may have caused.
Sincerely, Original signed by:
Daniel G. Mcdonald, Senior Project Manager Project Directorate I-l i
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Revised TS Bases Page cc w/ enclosure:
See next page Distribution:
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May 4, 1993 Docket Nos. 50-317 and 50-318 Mr. Robert E. Denton Vice President - Nuclear Energy Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, Maryland 20657-4702
Dear Mr. Denton:
SUBJECT:
CORRECTION TO TECHNICAL SPECIFICATION BASES CHANGES FOR CALVERT CLIFFS NVCLEAR POWER PLANT, UNIT I (TAC NO. M86136) AND UNIT 2 (TAC NO. M86137)
By letter dated April 26, 1993, the NRC issued revision instructions and revised Technical Specification Bases pages for the Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2, Technical Specifications (TSs). However, due to an administrative error, Unit 2 TS Bases Page B3/4 7-1 was not included.
We have enclosed the revised TS Bases Page B3/4 7-1 to be included in the Unit 2 TS Bases Section.
We apologize for any inconvenience this error may have caused.
Sincerely, Daniel G. Mcdonald, Senior Project Manager Project Directorate I-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Revised TS Bases Page cc w/ enclosure:
See next page
Mr. Robert E. Denton Calvert Cliffs Nuclear Power Plant Baltimore Gas & Electric Company Unit Nos. I and 2 cc:
Mr. Michael Moore, President Mr. Joseph H. Walter Calvert County Board of Engineering Division Commissioners Public Service Commission of 175 Main Street Maryland Prince Frederick, Maryland 20678 American Building 231 E. Baltimore Street D. A. Brune, Esquire Baltimore, Maryland 21202-3486 General Counsel Baltimore Gas and Electric Company Kristen A. Burger, Esquire P. O. Box 1475 Maryland People's Counsel Baltimore, Maryland 21203 American Building, 9th Floor 231 E. Baltimore Street Jay E. Silberg, Esquire Baltimore, Maryland 21202 Shaw, Pittman, Potts and Trowbridge 2300 N Street, NW Patricia T. Birnie, Esquire Washington, DC 20037 Co-Directer Marylana Cafe Energy Coalition Mr. G. L. Detter, Director, NRM P. O. Box 33111 Calvert Cliffs Nuclear Power Plant Baltimore, Maryland 21218 1650 Calvert Cliffs Parkway Lusby, Maryland 20657-47027 Resident Inspector c/o U.S. Nuclear Regulatory Commission P. O. Box 287 St. Leonard, Maryland 20685 Mr. Richard I. McLean Administrator - Radioecology Department of Natural Resources 580 Taylor Avenue Tawes State Office Building B3 Annapolis, Maryland 21401 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406
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3/4.7 PLANT' SYSTEMS BASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 Safety Valves j
The OPERABILITY of the main steam line code safety valves ensures that the-Secondary System pressure will be limited to within 110% of its design pressure of 1000 psia during the most severe anticipated system operational l
transient. The total relieving capacity for all valves on all of the steam lines is 12.18 x 10' lbs/hr'at 100% RATED THERMAL POWER. The maximum relieving capacity is associated with a turbine trip from 100% RATED THERMAL POWER coincident with an assumed loss of condenser heat sink (i.e., no steam bypass to the condenser). The main steam line code safety valves are tested and maintained in accordance with the requirements of Section XI of the ASME Boiler and Pressure Vessel Code.
In MODE 3, two main steam safety valves are required OPERABLE per steam generator. These valves will provide adequate relieving capacity for removal of both decay heat and reactor coolant pump heat from the Reactor Coolant System via either of the two steam generators. This requirement is provided to facilitate the post-overhaul setting and OPERABILITY testing of the safety valves which can only be conducted when the RCS is at-or above 500*F.
It allows entry into MODE 3 with a minimum number of main steam-safety valves OPERABLE so that the set pressure for the remaining valves can be adjusted in the plant. This is the most accurate means-for.
adjusting safety valve set pressures since the valves will be in thermal equilibrium with the operating environment.
STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in Secondary System steam flow and THERMAL POWER required by the reducad reactor trip settings of the Power Level-High channels. The reactor trip setpoint reductions are derived on the following bases:
For two loop operation SP =
x 106.5 X
For single loop operation (two reactor coolant pumps operating in the same loop)'
3p, (X) - (Y)(U) x 46.8 X
Changed by NRC letter dated April 26.1993 l
CALVERT CLIFFS - UNIT 2 B 3/4 7-1
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