ML20059N942
| ML20059N942 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 10/12/1990 |
| From: | Mcdonald D Office of Nuclear Reactor Regulation |
| To: | Creel G BALTIMORE GAS & ELECTRIC CO. |
| References | |
| NUDOCS 9010240139 | |
| Download: ML20059N942 (4) | |
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' NUCLEAR REGULATORY COMMISSION i
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-October 12, 1990 j
Docket Nos. 50-317 j
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r Mr~..G. C. Creel
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.Vice President. Nuclear Energy 1
Baltimore Gas and Electric Company 4
'Calvert Cliffs Nuclear Power Plant MD:Rts. 2 & 4-P.-0.-Box 1535 0
.Lusby, Maryland 20657
Dear Mr. Creel:
J 4
SUBJECT:
AUXILIARY FEEDWATER DESIGN COMMITMENTS - CALVERT CLIFFS NUCLEAR l
-POWER PLANT, UNITS 1 AND 2 4
3 By letter dated September 18, 1990, you informed the Nuclear Regulatory i
'Comission (NRC).that while you were reviewing the technical adequacy and licensing-basis;of your Auxiliary Feedwater (AFW) systems for Calvert Cliffs
~
~ Units 1.and 2, you determined that the documentation of a certain issue was c
w sunclear. The purpose of your letter was to inform the NRC of your resolution of the issue.;
The' issue concerns the ability of the AFW systems to provide flow to'the steam generators-following a pipe break anywhere in the. discharge piping of the AFW
. pumps concurrent with a single active failure.-
- Following.the-accident _at Three Mile Island,LUnit 2 (TMI-2), you were requested to evaluate the design of Standard Review Plan = (SRP)your AFW systems-_in-accordance with the criteria in -
Section 10.4'.9'and Branch Technical Position (BTP) 10-1.
Your March 9. -1981,Lresponse to this-request appeared to indicate that, y
'withithe' proposed design and procedural changes that would be implemented, the d
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' AFW systems would meet the criteria of!the SRP and'BTP. This was-found l
acceptable by the NRC' staff in its Safety Evaluation = dated May_8,1981.
Your September 18,;1990, letter clarifies that your. current AFW systems do not.
meet:all 'of the criteria of the' SRP and BTP. Specifically, when one unit is operating and the other unit is shut down with its motor-driven pump g
-ino urable, the operatinf unit's AFW system does not have the ability to cope.
witU a' pipe break everywiere in the discharge piping of the AFW pumps-concurrent with a single-active failure. You have noted.in your letter that the AFW~ systems,- asl modified following the-accident at TMI-2, are designed.to-function' following a break in -the high energy portion of the discharge line
- concurrent:with a single active failure.
For your AFW systems, you have-defined the.high energy portion of Lthe discharge piping as being only that
' portion of the systems-from the check-valves inside containment to the steam generators._ The staff agrees with this definition when the units.are at_ power 90102401'39 90101*
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with the AFW systems secured.: However, during startup and shutdown of a unit when an AFW system-is operating, the entire AFW system is considered high
-energy.,If credit is given to the presence of the cross-connect between the discharge lines of the motor-driven AFW pumps and the motor-driven AFW pump.
from the alternate unit is operable, the systems have the capability to provide flow to the steam generators following a-break anywhere in the discharge piping i
..V of the AFW pumps. Such a break would only be postulated during startup or shutdown when an AFW system was operating.
.l On September 19, 1990, a conference call was held between the NRC and Baltimore Gas & Electric Company -(BG&E) to discuss the issue. ' As a result of the call, the staff concluded that the Units 1 and 2 AFW systems are not in ~
-total conformance with the criteria of the SRP and BTP under certain l
conditions; nevertheless, the staff concluded that your current design is.
'I acceptable and is consistent with what the staff has accepted on similar plants licer.s&d prior to the issuance of the SRP and'BfP. However, it is our
. understanding that BG&E is in the process of implementing procedural changes H
and administrative controls to assure that the operability status of the cross-connected motor-driven AFW pumps will be known by the control room operators of both units.
l We appreciate your bringing this issue to our attention and providing the-detailed information in your. September 18, 1990, letter to resolve any uncertainties in the connitments made to and approved' by the NRC staff. We consider this-issue resolved.
p Sincerely.
~
Daniel G. Mcdonald,' Senior Project Manager Project Directorate I-1 1
Division of Reactor Projects - I/II Office of Nuc_ lear Reactor Regulation s
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e 3-, Mr; G. C. Creel' J
Baltimore Gas &' Electric Company-Calvert Cliffs Nuclear Power Plant 4
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Mr. William. T.'_ Bowen, President _
Mr. Joseph H. Walter
- )
.Calvert County Board of Engineering Division 1
. Commissioners Public Service-Commission _of Maryland' Prince Frederick, Maryland ' 20678 American Building.
231 E. Baltimore Street Baltimore, Maryland 2120E-34B6 1
D..A. Brune, Esq..
n General Counsel. '. -
Baltimore Gas and Electric Company Ms. Kirsten A. Burger, Esq.
P. 0.. Box 1475 1
. Baltimore, Meryla6d 21203 _
Maryland-People's Counsel Americar Building, 9th Floor 231 E. Baltimore. Street Mr. Jay E. ' Silberg, Esq.
Galtimore, Maryland 21202 Shaw, Pittman, Potts: and-Trowbridge i
'2300'N. Street, NW Ms. Patricia Birnie-
, Washington,~DC. 20037 Co-Director Maryland Safe Energy Coalition P. O. Box-902'
0.. Box'1535 j
lLusby, Maryland 20657 '
j' Resident-Inspector--
c/o U.S. Nuclear Regulatory Commission -
P' O. Box 437-
- Lusby, Maryland 20657 l
Mr.: Richard McLean.
i
' Administrator - Radioecology
- i
, Department of: Natural; Resources i
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580; Taylor-Avenue a
.Tawes State.0ffice Building PPER 83 l(
Annapolis ~, _ Maryland = 21401 t
p Regional Administrator, Region I U.S. Nuclear Regulatory Connission-475 Allendale Road' p
' King of Prussia, Pennsylvania 19406 i
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Mr. G. C. Creel e with.the AFW systems secured. However, during.startup and. shutdown of a unit
- when an AFW system is. operating the entire AFW system is consisdered high --
i energy.
If credit is.given to the presence of the cross-connect between the t
discharge lines: of the motor-driven AFW pumps and the motor-driven AFWL pump from the alternate unit is operable, the systems have the capability to provide flow to the~ steam generators following a break anywhere in the discharge piping
'of the AFW' pumps. Such a' break would only be postulated during startup or j
shutdown when an'AFW system was operating.
On-September 19, 1990, a conference call was' held between.the NRC and 7
L Baltimore Gas & Electric Company (BG&E) to discuss the issue. As a result of s
'the call', the staff concluded that the Units 1 and 2 AFW systems are not in-total. confonnance with the criteria of the SRP and BTP under certain.
a conditions; nevertheless, the staff concluded that your current design is.
O acceptable and is consistent with what the staff has accepted on similar p
plants licensed prior to the issuance of the SRP and BTP.
However, it is' our l
understanding that BG&E is in the process of implementing procedural changes -
and administrative controls to assure that the operability status of the cross-connected motor-driven AFW pumps will be known by the control room operators of.both units.
We appreciate your bringing this issue to'our attention and providing the h
detailed--information in your September 18,1990, letter to resolve any
' uncertainties in the commitments made to and approved by the NRC staff. We consider this issue resolved.
Sincerely,.
ORIGINAL slGNED BY Daniel G. Mcdonald, Senior Project Manager Project Directorate I-1
~
Division of Reactor Projects - I/II
-t Office of Nuclear Reactor Regulation cc:
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