ML20117P994

Forwards Request for Addl Info Re 891210 Request for Tech Spec Change on HPSI Pump Operability in Mode 3

ML20117P994
Person / Time
Site:	Calvert Cliffs
Issue date:	01/16/1990
From:	Rosalyn Jones Office of Nuclear Reactor Regulation
To:	Capra R Office of Nuclear Reactor Regulation
Shared Package
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References
FOIA-96-237 NUDOCS 9001220113
Download: ML20117P994 (2)

Text

1 l

o January 16, 1990 l

MEMORANDUM FOR: Robert A. Capra, Project Director (148-2)

Project Directorate I-I Division of Reactor Projects - I/II FROM:

Robert C. Jones, Chief Reactor Systems Branch Division of Systems Technology

SUBJECT:

CALVERT CLIFFS UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION CONCERNING TECHNICAL SPECIFICATION CHANGE ON HIGH PRESSURE SAFETY INJECTION PUMP OPERABILITY IN N0DE 3 In order to complete our review of the ifcensee proposed Technical Specification change submitted in its letter dated December 10, 1989, we require additional information. The enclosure identifies the information which we need. We request prompt response from the licensee to support the target date of the subject review.

Robert C. Jones, Chief Rcactor Systems Branch Division of Systems Technology

Enclosure:

As stated cc w/ enclosure:

A. Thadani S. McNeil (14B-2)

DISTRIBUTION Docket File SRXB R/F RJones TCollins CLiang Cliang R/F e.

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Contact:

C. Liang, SRXB/ DST Ext. 23233 C :SRXB:DS

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REQUEST FOR ADDITIONAL INFORMATION CONCERNING TECHNICAL SPECIFICATION CHANGE ON HIGH PRESSURE SAFETY INJECTION PUMP OPERABILITY IN MODE 3 FOR CALVERT CLIFFS UNIT I DOCKET NO. 50-317 1.

In your LOCA evaluation during Mode 3 with reactor coolant temperature below 350*F, you have assumed that the fissica zduct 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 tempet eture below 350 F and the HPSI pumps placed in PULL-TO-LOCK.

Include the following:

The time available for operator action to initiate HPSI pumps 6.

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.

Discuss the consequences of manual startup of HPSI pumps during Mode 3 3.

relative to LTOP concerns.

l

.