ML20217R125
| ML20217R125 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 08/28/1997 |
| From: | Dromerick A NRC (Affiliation Not Assigned) |
| To: | Cruse C BALTIMORE GAS & ELECTRIC CO. |
| References | |
| TAC-M99013, TAC-M99014, NUDOCS 9709040227 | |
| Download: ML20217R125 (4) | |
Text
._
o* C88g p+
t UNITE] STATES s
}
NUCLEAR REGULATORY COMMISSloN
't WASHINGTON, D.C. 30MH001 August 28, 1997 Mr. Charles H. Cruse Vice President - Nuclear Energy Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702
SUBJECT:
EXTENSION OF CONTROL ROOM HABITABILITY ANALYSIS SUBMITTAL DATE FOR CALVERT CLIFFS NUCLEAR POWER PLANT (TAC N05. M99013 AND M99014)
Dear Mr. Cruse:
In a letter to the staff dated June 10, 1997 Baltimore Gas and Electric Company (BGE) requested an extension until December 31, 1998, for their submittal of the Calvert Cliffs' control room thyroid dose analysis.
In a letter dated June 7,1995, BGE committed to making such a submittal by July 31, 1996.
In a letter dated June 18, 1996, BGE requested a 1 year extension.
This extension was granted by the staff, in the June 1997 letter, BGE explained that they are making the request for the extension until the end of calendar year 1998 because they intend to incorporate into their control room thyroid dose analysis some of the timing aspects associated with the revised accident source terms of NUREG-1465. As noted in the June 1997 letter, both the industry and the Nuclear Energy Institute are pursuing an initiative involving the licensing implications and accident methodology associated with the adoption of the revised accident source terms. While BGE is not participating in the industry initiative, they indicated that they are following the development of the initiatives and are basing the thyroid dose analysis on the generic methodology being developed through the initiative.
The staff has requested that non-participatory licensees not submit analyses using the information from NUREG-1465 untti the pilot plant submittals have been approved by the staff and the staff has issued guidance on the use of the new source terms, BGE proposed the December 1998 schedule expecting the staff to complete the review of the pilot plant submittals by mid-1998.
The staff has reviewed this request and has determined that the request be denied. The basis for the denial follows:
1.
It is imperative that BGE have on their docket an analysis which indicates the status of Calvert Cliffs to meet General Design Criterion (GDC) 19 not only for the whole body but for other organs.
This analysis needs to be based upon the licensing framework as it exists today cnd to the same framework under which all licensees are presently licensed.
2.
The BGE letter seems to imply that the requirement to meet GDC 19 is limited only for a loss-of-coolant accident (LOCA),
lhat is incorrect.
It is a requirement to meet GDC 19 for all postulated l
accidents.
While the timing issue of NUREG-1465 may imp D
1
'U na.. a it in,i lu.t.II.il.
m b
b 7
{
b
Mr. C. Cruse i it will have no impact on a steam generator tube rupture or a main steam line break event nor is it likely to impact a control rod ejectionoralockedrotorevent.
3.
The implementation of the revised accident source terms is proceeding on a schedule which is too indeterminate to allow a postponement in the BGE submittal of 18 months or. longer.
4.
Without such a submittal, the staff cannot make an assessment of the ability of Calvert Citffs to meet GDC 19.
Based upon the above, the licensee should provide a dose analysis which reflects the current operational conditions for the Calvert Cliffs control All pertinent assumptions associated with the analysis should be room.
provided.
The submittal of the habitability analysis is necessary in order for the staff to assess the ability of the plant to meet GDC 19.
If the plant does not meet l
GDC-19, the habitability analysis will assist the staff in determining whether the problem is associated with envelope integrity, inadequate-control room ESF ventilation system capability, or inadequate mitigation of release paths for the various accidents.
Your res)onse to this request for the dose analysis is requested by March 1 1998.
$1ould you have any questions, please do not hesitate to contact me at (301) 415-3473.
Sincerely,
/
WM Alexand r W. Dromerick, Acting Director Project Directorate I-1 Division of Reactor Projects - I/11 Office of Nuclear Reactor Regulation cc: See next page
L y
I i
Mr. Charles H. Cruse Calvert Cliffs Nuclear Power Plant Baltimore Gas & Electric Company Unit Nos. I and 2 l
CCi l
President Mr. Joseph H. Walter, Chief Engineer Calvert County Board of Public Service Comission of i
Comissioners Maryland 175 Main Street Engineering Division Prince Frederick, MD 20678 6 St. Paul Centre Baltimore, MD 21202-6806 James P. Bennett, Esquire Counsel Kristen A. Burger, Esquire Baltimore Gas and Electric Company Maryland People's Counsel P.O. Box 1475 6 St. Paul Centre Baltimore, MD 21'. )3 Suite 2102 Baltimore, MD 21202-1631 Jay E. Silberg, Esquire Shaw, Pittman, Potts and Trowbridge Patricia T. Birnie, Esquire 2300 N Street, NW Co-Director Washington, DC 20037 Maryland Safe Energy Coalition P.O. Box 33111 Mr. Thomas N. Prichett, Director Baltimore, MD 21218 NRM Calvert Cliffs Nuclear Power Plant Mr. Loren F. Donate 11 1650 Calvert Cliffs Parkway NRC Technical Training Center Lusby, MD 20657-4702 5700 Brainerd Road Resident Inspector
-U.S. Nuclear Regulatory Comission P.O. Box 287 St. Leonard, MD 20685 Mr. Richard I. McLean Administrator - Radioecology Department of Natural Resou'ces 580 Taylor Avenue Tawes State Office Building, B3 Annapolis, MD 21401 Regional Administrator, Region !
U.S. Nuclear Regulatory Comission 475 Allendale Road King of Prussia, PA 19406
Mr. C. Cruse
-2 August 28, 1997 it will have no impact on a-steam steam line break event nor is it ikenerator tube rupture or a main kely to impact a control rod ejection or a locked rotor event.
3.
The implementation of the re"ised accident source terms 1 is proceeding on a schedule which is too indeterminate to allow a l
postponement in the BGE submittal of 18 months or longer.
4.
Without such a submittal, the staff cannot make an assessment of the ability of Calvert Cliffs to meet GDC 19.
i Based upon the above, the licensee should provide a dose analysis which reflects the current operational conditions for the Calvert Cliffs control room. All pertinent assumptions associated with the analysis should be i
provided.
The submittal of the habitability analysis is necessary in order for the staff to assess the ability of the lant to meet GDC 19.
If the plant does not meet GDC 19, the habitability anal sis will assist the staff in determining whether the problem is associated wit envelope integrity, inadequate control room ESF ventilation system capability, or inadequate mitigation of release _ paths-for the various accidents.
Your res)onse to this request for the_ dose analysis is requested by March 1, 1998.
$1ould you have any questions, please do not hesitate to contact me at (301) 415-3473, i
Sincerely, ORIGINAL SIGNED BY:
Alexander W. Dromerick, Acting Director Project Directorate _1-l' Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation cc:
See next page QlSTRIBilTLON:
Docketfi'e PUBLIC PDI-l R/F B. Boger A. Dromerick S. Little-OGC ACRS
- L._ Doerflein, RI DOCUMENT NAME: G:\\CCl-2\\CCM99013.LTR To receive a copy of this document, indicate in the box:
"C" - Copy withput attachment / enclosure "E"
Copy with attachment / enclosure "N" - No cgpy orricE
$<nosf y >
1E LA PDI 1,n Q l
DJQlyli 1/
I bDt BRPEd/
I I
l nur w ade s /r.i stittie r Waderiet 3 -1 i. /i ri _
i onte os/ w /97 os/, tit 97 os/ w /97 2/'/ SM f /
Of fic' al Record Copy
'