ML18003B215
| ML18003B215 | |
| Person / Time | |
|---|---|
| Site: | Harris |
| Issue date: | 04/22/1986 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NLS-86-125, NUDOCS 8604280115 | |
| Download: ML18003B215 (6) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDB>
ACCESSION NBR: 8604280115 DOC. DATE: 86/04/22 NOTARIZED:
NO DOCKET 0 FAC IL:50-400 Shearon Harr is Nuc lear Power P Ianti Unit 1 i Car olina 05000400 AUTH. NAME AUTHOR AFFILIATION ZIMMERMANiS. R.
Carolina Power 5 Light Co.
RECIP. NAME REC IP IENT AFFILIATION DENTONi H. R.
Office of Nuclear Reactor Regulationi Director (post 851125
SUBJECT:
Forwards correction to Table
- 15. 4-6-ii " "Time Sequence of Events for Chemical 8c Vol Control Sgs Malfunction That Results in Decrease in Boron Concentrations...
~" for Amend 25 to FSAR. Table will be in AMend 27.
DISTRIBUTION CODE:
SOCIO COPIES RECEIVED: LTR J ENCL J SIZE:
TITLE: Licensing Submittal:
PSAR/FBAR Amdts 0 Related Correspondence NOTES:Application for permit renewal filed.
05000400 RECIPIENT ID CODE/NAME PWR-A ADTB PWR-A EICBB PWR-A PD2 LA BUCKLEYiB 01 PWR-A RBB INTERNAL ADM/LFMB IE FILE IE/DGAVT/GAB 21 NRR PWR-A ADTB NRR ROE> M. L NRR/DHFT/MTB RCN2 EXTERNAL: 24X DMB/DSS (AMDTS)
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AMI/MIB BNL(AMDTS ONLY)
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I SECS Carolina Power & Light Company APR 33 1986 SERIAL: NLS-86-125 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO.
1 DOCKET NO.50-000 CORRECTION TO AMENDMENTNO. 25 TO THE FINALSAFETY ANALYSISREPORT
Dear Mr. Denton:
In Amendment No. 25 to the Shearon Harris Nuclear Power Plant (SHNPP) Final Safety Analysis Report (FSAR) submitted March 12, 1986, a value in Table 15.0.6-1, Time Sequence of Events for CVCS Malfunction that Results in a Decrease in the Boron Concentration in the Reactor Coolant Incidents contained a typographical error. For dilution during cold shutdown, the minimum time r equired for the shutdown margin to be lost and the reactor to become critical is greater than 900 seconds (15 minutes) not 209 seconds as the Amendment No. 25 page shows.
Note that FSAR Section 15.0.6.3 b) correctly shows a value of 15 minutes.
Table 15.0.6-1 willbe corrected in Amendment No. 27. Both above referenced pages are included for your reference, as well as the marked-up Table 15.0.6-1 which willbe included in Amendment No. 27.
If you have any questions concerning this matter, please contact Mr. Jim Kloosterman at (919) 836-8055.
Yours very truly,
~
~
~4~
S.. Zi merman anager Nuclear Licensing Section SR Z/BAT/ccc (3677BAT)
Enclosure Cct Mr. B. C. Buckley (NRC)
Mr. G. F. Maxwell (NRC-SHNPP)
Dr. J. Nelson 'Grace (NRC-RII)
Mr. Travis Payne (KUDZU)
Mr. Daniel F. Read (CHANGE/ELP)
Wake County Public Library Mr. Wells Eddleman Mr. John D. Runkle Dr. Richard D. Wilson Mr. G. O. Bright (ASLB)
Dr. J. H. Carpenter (ASLB)
Mr. J. L. Kelley (ASLB)
~'60iZeotXS BSoem PDR ADOCK 05000400 A
PDR i,
411 Fayettevilte Street o P. O. Box 1551
~ Raleigh, N. C. 27602 Son lt()
SHNPP FSAR d)
Dilution During Hot Standby Conditions at hot standby require the reactor to have availabLe at least 1.77 percent Ak shutdown margin.
The maximum boron concentration required to meet this shutdown margin is very conservatively estimated to be 1515 ppm.
The following conditions are assumed for a continuous boron dilution during hot standby'.
Jl 1)
Dilution flow is assumed to be the combined capacity of the two reactor makeup water pumps with the RCS at 135 psia and 350F (321 gpm).
2)
A minimum water volume (7450 Et.
) in the RCS is'sed.
Tnis volume corresponds to the active volume of the
- RCS, minus the pressurizer volume.
e)
Dilution During Startup Conditions at startup are identical to the hot standby case with the exception of the dilution Elow.
The.dilution flow is assumed to be a conservatively high charging flow rate (285 gpm) consistent with Reactox'ooLant System operation at 2250 psia and 557F.
E)
Dilution During Full Power Operation With the Unit at power and the RCS at pressure, the dilution rate is limited by the capacity of the charging pumps (analysis is. performed assuming all charging pumps axe in operation although only one is normaLly in operation).
The effective reactivity addition rate is a function of the reactor coolant temperature and boron concentration.
The reactivity insertion rate calculated is based on a conservatively high value for the expected boron concentration at power (1500 ppm) as well as a conservatively high charging flow rate capacity (285 gpm).
The RCS volume assumed (7450 ft.
) corresponds to the active volume of the RCS evcluding the pressurizer, for one reactor coolant pump in operation.
15.4.6.3 Results and Conclusions Dilution During Refueling Dilution during refueling cannot occur due to administrative controls (see Section 15.4.6.2).
b)
Dilution During Cold Shutdown For dilution during cold shutdown, the minimum time required fox the shutdown margin to be Lost and the reactor to become critical is greater than 15 minutes.
c)
Dilution During Hot Standby For dilution, during hot standby, the minimum time requixed Eox the shutdown margin to be lost and the reactor to become critical is 19.61 minutes.
15.4.6-4 Amendment No.
25
~
e
~
SHNPP FSAR TABLE 15.4.6-1 TIME SE UENCE OF EVENTS FOR CVCS MALFUNCTION THAT RESULTS IN A DECREASE IN THE BORON CONCENTRATION IN THE REACTOR COOLANT INCIDENTS Accident Dilution during refueling Events Dilution begins Operator isolates source of dilution; minimum margin to criticality occurs Time""
(Seconds) 2851 Dilution during cold shutdown Dilution begins
~
I Operator isolates source of dilution', minimum margin to criticality occurs 249 25 Dilution during hot standby Dilution during Startup Dilution during full power oper-ation Dilution begins Operator isolates source of dilution', minimum margin to criticality occurs Dilution begins Operator isolates source of dilution'minimum margin to criticality occurs 1176 1106 25
- a. Automatic reactor control
- b. Manual reactor control Dilution begins Shutdown margin lost Dilution begins Reactor trip setpoint reached for overtemperature hT 2212 Rods begin to fall into core 44 Shutdown is lost (if dilution continues after trip) 2170 The clock starts when the dilution is started.
15.4.6-5 Amendment No.
25
SHNPP FSAR TABLE 15.4.6-1 TIME SE UENCE OF EVENTS FOR CVCS MALFUNCTION THAT RESULTS IN A DECREASE IN THE BORON CONCENTRATION IN THE REACTOR COOLANT INCIDENTS Accident Events Time'-"
(Seconds)
Dilution during refueling Dilution begins Operator isolates source of dilution; minimum margin to criticality occurs 2851 Dilution during cold shutdown Dilution during hot standby Dilution begins Operator isol.ates source of dilution', minimum margin to criticality occurs Dilution begins Operator isolates source of dilution; minimum margin to criticality occurs
)900 1176 25 Dilution during Startup Dilution begins Operator isolates source of dilution'minimum margin to criticality occurs 1106 Dilution during full power oper-ation
- a. Automatic reactor
- control.
Dilution begins I
Shutdown margin lost 2212 b.
Manual.
reactor control Dilution begins Reactor trip setpoint reached for overtemperature AT Rods begin to fall into core 44 Shutdown is lost (if dilution continues after trip) 2170
- The cl.ock starts when the dilution is started.
15.4.6-5 Amendment No.
25