ML20045A737
| ML20045A737 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 06/08/1993 |
| From: | Mcdonald D Office of Nuclear Reactor Regulation |
| To: | Denton R BALTIMORE GAS & ELECTRIC CO. |
| References | |
| TAC-M83999, TAC-M84000, NUDOCS 9306110321 | |
| Download: ML20045A737 (5) | |
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WASHINGTON, D. C. 20555 k..... p June 8, 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:
REQUEST FOR ADDITIONAL INFORMATION CONCERNING RELIEF REQUEST FROM THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) CODE, SECTION III, ARTICLE 9, FOR CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 1 (TAC N0. M83999) AND UNIT NO. 2 (TAC NO. M84000)
By letter dated June 30, 1992, Baltimore Gas and Electric Company (BG&E) requested permanent relief from the ASME Boiler and Pressure Vessel Code,Section III (1968 Edition), Article 9.
The request is to allow a stop valve to remain installed downstream of thermal overpressure relief devices for the regenerative heat exchangers of each unit.
The NRC staff reviewed the initial submittal and requested additional information by letter dated September 16, 1992.
BG&E provided the requested information by letter dated November 10, 1992. However, based on the staff's review it has determined that additional information is needed to complete its review of the subject relief request.
Enclosed is the staff's request for additional information (RAI).
This request affects one respondent and, therefore, is not subject to the Office of Management and Budget review under P.L.96-511.
Sincerely, Iok
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m Daniel 'G. Mcdonald, Senior Proje t Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation h
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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 i
Jay E. Silberg, Esquire Baltimore, Maryland 21202 Shaw, Pittman, Potts and Trowbridge 2300 N Street, NW Patricia T. Birnie, Esquire Washington, DC 20037 Co-Director Maryland Safe 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 j
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 i
B3 Annapolis, Maryland 21401 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 4
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1 ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST FROM ASME III, ARTICLE 9 - STOP VALVE DOWNSTREAM THERMAL RELIEF IN THE CHEMICAL AND VOLUME CON CALVERT CLIFFS UNITS I AND 2 1.
If the Regenerative Heat Exchanger loss of auxiliary pressurizer spray (RHX) fails, this will result in the (APS).
The November 10, 1992, coolant accident. submittal states that the APS is not required to mitigate a loss-of-However, the Generic letter (GL) 90-06 response, dated December 20, 1990, m
states that the APS system is safety-related and is used to depressurize the primary system during normal cooldown and for a steam generator tube rupture (SGTR) event.
Therefore, describe the accident event, such as for depressurizing the primary SGTR event.
2.
a result, are the letdown isolation control valves capa against the resulting RCS flow and pressure loading?
included within the scope of the GL 89-10 program?
Are these valves 3.
flow and differential pressure load on manual valve CVC-18 would any condition prevent an operator from closing it for the local If not, environmental conditions or for the flow and pressure loading on the valve disk?
4.
The licensee stated that CVC-435 is to be modified to control AP Does this modification involve adding an additional actuating mechanism to the valve, and could it prevent the valve from accomplishing its thermal pressure relieving function?
Describe this modification.
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5.
The licensee stated that there should be no major damage to reactor j
coolant pumps, steam generators, or letdown isolation control valves as a result of RHX failure.
equipment is in close proximity to the RHX.However, the licensee indicated that thi If the RHX ruptures and major damage could occur. fragments of sufficient energy or broken pipe ends which would prevent damage to any safety components. Describe the configura
q Docket Nos. 50-317 L
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 I
Dear Mr. Denton:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION CONCERNING RELIEF REQUEST FROM THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) CODE, SECTION III, ARTICLE 9, FOR CALVERT CLIFFS NUCLEAR. POWER PLANT, UNIT NO. 1 (TAC.N0. M83999) AND UNIT NO. 2 (TAC NO. M84000)
By letter dated June 30, 1992, Baltimore Gas and Electric Company (BG&E) requested permanent relief from the ASME Boiler and Pressure Vessel Code,Section III (1968 Edition), Article 9.
The request is to allow a stop valve to remain installed downstream of thermal overpressure relief devices for the regenerative heat exchangers of each unit.
The NRC staff reviewed the initial submittal and requested additional information by letter dated September 16, 1992.
BG&E provided the requested information by letter dated November 10, 1992. However, based on the staff's review it has determined that additional information is needed to complete its review of the subject reliaf request.
Enclosed is the staff's request for additional information (RAI).
This request affects one respondent and, therefore, is not subject to the Office of Management and Budget review under P.L.96-511.
Sincerely, Original signed by:
Daniel G. Mcdonald, Senior Project Manager Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
RAI i
cc w/ enclosure:
l See next page l
Distribution:
See attached sheet n
LA:PDI-l PM:PDI-h h D:PDI-l CVogan 6d DMcDon3'io voi RACapra F f S 93 d b 0 ',b 3 e6 /cb/93
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0FFICIAL RECORD COPY FILENAME: CC83999.LTR l
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DATE: June 8, 1993
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION CONCERNING RELIEF REQUEST FROM THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) CODE, SECTION III, ARTICLE 9, FOR CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. I (TAC NO. M83999) AND UNIT NO. 2 (TAC NO. M84000)
Distribution:
Docket File NRC & Local PDRs PDI-1 Reading SVarga JCalvo RAcapra CVogan DMcDonald OGC ACRS (10)
CCowglil, RGN-I JNorberg, 7/E/23 GHammer, 7/E/23 10001u