ML18093B560

Forwards Nonproprietary Info Used from C-E Rept NPSD-151, C-E Safety Analysis Method for Calvert Cliffs,Units 1 & 2, Per SA Mcneil 880224 Ltr to Ja Tiernan Requesting Addl Info in Response to Generic Ltr 86-06

ML18093B560
Person / Time
Site:	Calvert Cliffs
Issue date:	05/12/1988
From:	Tiernan J BALTIMORE GAS & ELECTRIC CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
TASK-2.K.3.05, TASK-TM GL-86-06, GL-86-6, TAC-49674, TAC-49675, NUDOCS 8805200335
Download: ML18093B560 (4)

Text

• BALTIMORE GAS AND ELECTRIC CHARLES CENTER

• P. 0. BOX 1475 *BALTIMORE, MARYLAND 21203 JOSEPH A. TIERNAN VJCE PRESIDENT NUCLEAR ENERGY May 12, 1988 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2; Docket Nos. 50-317 & 50-318 Response to Request for Additional Information - Generic Letter 86-06 (TACS 49674 and 49675)

REFERENCES:

(a) Letter from Mr. S. A. McNeil (NRC) to Mr. J. A. Tiernan (BG&E),

dated February 24, 1988, Request for Additional Information -

Generic Letter 86-06, "Implementation of TMI Action Item 11.K.3.5, Automatic Trip of Reactor Coolant Pumps" Gentlemen:

As requested in Reference (a), we are providing the non-proprietary information used from the CE report, NPSD-151, "CE Safety Analysis Method for Calvert Cliffs Units 1 and 2." There is no non-proprietary version of the complete report available, therefore, we have extracted the non-proprietary portion of the trending tables that were used in our evaluation.

Should you have any questions on this matter, we will be pleased to discuss them with you.

JA T /PSF /WPM/ dlm cc: D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC S. A. McNeil, NRC W. T. Russell, NRC D. C. Trimble, NRC

(

88os200335 e:::os:t~

PPDR ADOCK 05000317 DCD

TABLE 8-1 KEY INPUT P/\llAMETERS Atm TllE IR IMPACT ON TllE LOSS OF LOAD EVENT Par;meter Sense of Chanqe Physical Impact Impact on Analytical Results Power Level lligher 1.. /\ higher initial power 1. No impact on transient results ex-level ~1ill initiate the cept that higher powers lower the initial ONBR and thus result in

\

event from conditions closer to SAFDLs. a lower transient minimum ONBR.

. i l

/\higher power will maximize *2. /\ higher power to steam space 2.

the power to pressurizer ratio will maximize the peak steam space ratio. pressure during the event.

lligher A bighe~ Tinlet will initiate* No impact on transient results except the event from conditions that a higher Tinlet lowers the initial co closer to SAFOLs. DNBR and thus results in a *lower tran- I

\.0 sient minimum ONBR.

RCS Pressure Lower 1. A lower initial pressure 1. No impact on minimum ONBR during will initiate the event the event since no credit is taken from conditions closer for the pressure increase.

to SAFDLs.

2. A lower initial pressure 2. Lower initial pressure delays delays the time of high time of trip. This maxi~izes pressurizer pressure trip the rate of change of pressure and thus maximizes the.rate at time of trip and t~~s res~]ts of pressure change at time in higher peak RCS pressures~

of trip.

---

*- *---~...=*=~-=*"~--*-=-*=**-~~--~ .. *--*-------------*--*---**-*--.

i TABLE B-1 (continued)

Par;*r.1eter Sense of Change Phys1cal Impact Impact on Analyt1cal Results MTC More Positive A more positive MTC in combina- 1. Increasing core average heat flux (i.e., BOC) tion with increasing coolant and coolant temperature result in tempera tu res wi 11 add greater lower. transient orrnn values.

positive reactivity. This in-creases the core power, heat 2. Maximizes the peak RCS pressure flux, coolant system pressure during the event.

and temperatures.

Doppler Less Negative A less negative Doppler 1. Results in higher core heat flux Coefficient (i.e., BOC) coe'fficient in combination and coolant temperatures and thus with increasing fuel minimizes the transient DNBR. ~

temperatures, adds less I negative reactivity 2. Maximizes the peak RCS pressure. 0 ThiS maximizes the increase in power, heat flux, coolant temperature and pressure.

Ii Mi~her Allows the heat flux to follow 1. Results in higher core average the power more closely. Also, heat flux and coo 1ant tempera tu res ilicreases the rate at \'1hich the and thus minimizes the transient heat generated within the fuel ONBR.

gets into the coolant and there-by increases the coolant 2. Maximizes the peak RCS pressure.

tempera lures and l~CS pressure.

1 I

0

\

0

• T/\OLE 8-1 (continued}

Parm1eter Sense of Chanqe Physical Impact Impact on Analytical Results Initial Steam Lower A lower initial steam Maximizes the peak RCS pressure.

Generator . generator pressure delays Pressure the time when main steam safety

. valves open. The delay in opening the MSSVs increases the heatup of both the primary and secondary systems.

Axial Power Top Peaked A top peaked shape results in Minimizes transient DNBR.

Distribution higher enthalpy rise in the hot channel.

Sera~ Positive Scram reactivity insertion l. Maximizes core average heat flux, neactivity associated with a positive and coolant temperatures.

• Insertion ASI 1 minimizes the scram Minimizes the transient DNBR.

Curve (i.e. 1 reactivity inserted after ASI) a reactor trip. This maxi- 2. Maximizes RCS pressure.

rni zes the power, heat flux, coolant temperature and pressure overshoot.

Pressurizer Inoperable (i.e., More pronounced transient *

• Maximizes peak RCS pressure.

Pressure no sprays or PROVs) variations in primary Control pressure.

System