ML20006A582
| ML20006A582 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 01/22/1990 |
| From: | Mcdonald D Office of Nuclear Reactor Regulation |
| To: | Creel G BALTIMORE GAS & ELECTRIC CO. |
| References | |
| TAC-75562, TAC-75563, NUDOCS 9001290150 | |
| Download: ML20006A582 (3) | |
Text
.
Janu:ry 22, 1990 l
Docket Nos. 50 317 Distribution:
and 50-318
!800ketJilf PDI-1 Rdg NRC/ Local PORs SVarga BBoger Mr. G. C. Creel RCapra Vice President Nuclear Energy CVogan Baltimore Gas & Electric Company OGC Calvert Cliffs Nuclear Power Plant EJordan MD Rtes 2 & 4 ACRS(10)
P. O. Box 1535 JLinville Lusby, Maryland 20667 Plant File DMcDonald
Dear Mr. Creel:
SUBJECT:
PROPOSED TECHNICAL SPECIFICATION AMENDMENT RELATING TO HIGH PRESSURE SAFETY INJECTION PUMP OPERABILITY IN MODE 3 REQUEST FOR ADDITIONAL INFORMATION Re:
CalvertCliffs, Unit 1(TacNo.75562)andUnit2(TacNo.75563)
By letter dated December 20, 1989, you proposed the subject changes to the Calvert Cliffs, Units 1 and 2, Technical Specifications. The staff is currently reviewing your request and has identified the need for additional information. The requested information has been discussed with your staff and is provided in the enclosure to this letter.
We request a prompt response to support our review schedule.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents, therefore, OMB clearance is not required under P. L. 96 511.
Sincerely.
Original signed by Daniel G. Mcdonald, Senior Project Manager Project Directorate 1 1 L
Division of Reactor Projects I/II Office of Nuclear Reactor Regulation L
cc:
See next page l
Enclosure:
As stated n
.n l-
~
......f $
.f
..l............f............f............l.........
l - NAMb gan
- DMcDonald:rc/
pra
............:............t c:[2%O : otggo:g gg:
DATE :
i il l
OFFICIAL RECORD COPY Document Name: MEMO TO CREEL TAC 75562 g
9001290150-900122 PDR ADOCK 05000317 l
P PDC Ik I
L Mr. G. C. Creel Baltimore Gas & Electric Company calvert Cliffs Nuclear Power Plant cc:
Mr. William T. Bowen, President Mr. Joseph H. Walter Calvert County Board of Engineering Division Cerrissioners Public Service Commission of Maryland Prince Frederick, Maryland 20678 American Building 231 E. Baltimore Street D. A. Brune, Esq.
B61timore, Maryland 21202-3486 General Counsel Baltimore Gas and Electric Company Ms. Kirsten A. Burger, Esq.
P. O. Box 147f Maryland People's Counsel Baltimore, Maryland 71?O3 American Building 9th Floor 231 E. Baltimore Street Mr. Jay E. Silberg, Esq.
Raltimore, Maryland 21202 Shaw, Pittman, Potts and Trowbridge 2300 N Street, NW Ms. Patricia Birnie Washington, CC ?0037 Co-Cirector Mr. W. J. Lippold, General Supervisor Maryland $6fe Energy Coalition P. O. Rox 902 Technical Services Ergineering Columbia, Maryland M044 Calvert Cliffs Nuclear Power Plant MD Rts 2 ?. 4, P. O. Box 1535 Lusby, Maryland 20657 Pesident Inspector c/o U.S. Nuclear Degulatory Consnissien P. C. Box 437 Lusby, Maryland IO657 Mr. Thomas Magette Administrator - Nuclear Evaluations Department of Natural Resources 580 Taylor Avenue Tawes State Office Building PPCR D?
Annacolis, Maryland 21401 Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 4
o ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION CONCERNING TECHNICAL SPECIFICATION CHANGE ON HIGH PRESSURE SAFETY INJECTION PUMP OPERABILITY IN MODE 3 FOR CALVERT CLIFFS UNIT 1 AND 2 DOCKET NO. 50-317 1.
In your LOCA evaluation during Mode 3 with reactor coolant temperature below 350*F, you have assumed that the fission product decay heat is based on 110 percent of 1971 ANS proposed standard.
It is the staff's position that the fission product decay heat following a LOCA shall be based on 120 percent of 1971 ANS proposed standard per the requirements of 10 CFR 50, Appendix K.
Provide the results of your evaluation using this corrected assumption.
2.
Provide a discussion of the consequences of a SBLOCA during Mode 3 with reactor temperature below 350'F ano the HPSI pumps placed in PULL-TO-LOCK.
Include the following:
a.
The time available for operator action to initiate HPSI pumps following identification of an SBLOCA. Describe the actions needed to manually initiate HPSI pumps.
b.
Describe the procedures available to operators for the above postulated SBLOCA. Discuss the time assumed between the initiation of the event and positive event identification.
3.
Discuss the consequences of manual startup of HPSI pumps during Mode 3 relative to LTOP concerns.
t