ML20211K064
| ML20211K064 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/01/1999 |
| From: | BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20211J990 | List: |
| References | |
| NUDOCS 9909070097 | |
| Download: ML20211K064 (17) | |
Text
. _ _
ATTACHMENT (3)
PROPOSED CIIANGES TO TECHNICALSPECIFICATIONS j
i l
1 9909070097 990901 PDR ADOCK 05000317 P
PDR Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant September 1,1999
Definitions 1.1 1.'O -USE AND APPLICATION 1.1 Definitions 1
NOTE-------------------------------------
The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.
Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.
AXIAL SHAPE INDEX (ASI)
ASI shall be the power generated in the lower half of the core less the power generated in the upper half of the core, divided by the sum of the power I
generated in the lower and upper halves of the Core.
lower upper lower + upper AZIMUTHAL POWER TILT (T )
AZQUTHAL POWER TILT shall be the maximum of)t e q
AarMvTHAL Pow e RTv-T 3g differehce between the power generated in try core quadran up(er or lower) (P,4) and average qu be. k po w e a.s3 mme h power of all qlta ants (Pug)in half (upper b*b
- N'""' M or lower) of the co divi by the average j
lo c.a_ f,m,
power of all quadrants hat half (upper or 5 y m e. h, c.
toet lower) of the core P""
P"'
Max
=
CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel moni tors. The CHANNEL CALIBRATION shall encompass the entire channe~i ir,cluding the sensor and alarm and/or trip functions, and shall include the CALVERT CLIFFS - UNIT 1 1.1-1 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201
~
2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs i
2.1.1.1-In MODES 1 and 2, the combination of THERNML POWER, pressurizer pressure, and the highest operating loop cold leg coolant temperature shall not exceed the limits shown in Figure 2.1.1-1.
NOTE-----------_-----------------.
For Unit 2 only, Figure 2.1.1-la shall apply through Cycle 12.
...................___..__.__.__.......__.....____.__........J[
2.1.1.2 In MODES 1 and 2, the peak linear heat rate (LHR) shall i
be54LFr0kW/ft.
11 0
[
4 2.1.2 Reactor Coolant System (RCS) Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained s 2750 psia.
2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2.2.2 If SL 2.1.2 is violated:
2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within I hour.
2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.
l CALVERT CLIFFS - UNIT 1 2.0-1 Amendment No. 228 CALVERT CLIFFS - UNIT 2 Amendment No. 202 I
1
AC Sources-Operating 3.8.1 SURVEILLANCE
- REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY
. e.
SR 3.8.1.8 Verify interval between each sequenced load 31 days block is within ! 10% of design interval for the load sequencer.
NOTE-------------------
All DG starts may be preceded by an engine prelube period.
Verify each DG starts from standby condition 184 d,ays and achieves, in s 10 seconds, voltage 24o63 : 3740 V and frequency > 58.8 Hz, and after steady state conditions are reached, maintains voltage +J740 V and Ng g gyo, frequency of 2 58.8 iz and 5 61.2 Hz.
24 months from the normal offsite circuit to the e
alternate offsite circuit.
.SR 3.8.1.11
NOTE-------------------
Momentary transients outside the load and power factor limits do not invalidate this test.
Verify each DG, operating at a power factor 24 months of s 0.85, operates for 2 60 minutes while loaded to 2 4000 kW for DG 1A and 2 3000 kW for DGs IB, 2A, and 28.
SR 3.8.1.12 Verify each DG rejects a load 2 500 hp 24 months without tripping.
CALVERT CLIFFS. UNIT 1 3.8.1-12 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201
r AC Sources-Operating 3.8.1 l
t
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'SURVEILt.ANCE' REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY
' SR 3.8.1.15
--..---..--NOTE-------------------
All DG starts may be preceded by an engine prelube period.
Verify on an actual or simulated loss of 24 months offsite power signal in conjunction with an actual or simulated Engineered Safety Feature actuation signal:
a.
De-energization of emergency buses; l
b.
Load shedding from emergency buses; c.
DG auto-starts from standby condition and:
l 1.
energizes permanently connected l
loads in 5 10 seconds, L
l 2.
energizes auto-connected emergency loads through load sequencer, 3.
maintains steady state voltage 2 3Me y and s 4680- V, l
4 voGo Woo
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4.
maintains steady state frequency of 2 58.8 Hz and s 61.2 Hz, and 5.
supplies permanently connected and auto-connected emergency loads for 2 5' minutes.
CALVERT. CLIFFS - UNIT 1, 3.8.1-14 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201
r DG-LOVS 3.3.6 ACTIONS '(continued)
CONDITION REQUIRED ACTION COMPLETION TIME D.
Required Action and 0.1 Enter applicable Immediately associated Completion Conditions and Time not met.
Required Actions for the associated DG made inoperable by DG-LOVS instrumentation.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.6.1 Perform CHANNEL FUNCTIONAL TEST.
92 days SR 3.3.6.2 Perform CHANNEL CALIBRATION with setpoint 24 months Allowable Values as follows:
1.
ded Voltage function V and s 365 seconds and Time Del
- 5..
seconds at 362 nd 32.
Loss of voltage Function 2 2345 V and 5 2555 V Time Delay: 2 1.8 seconds and 5 2.2 seconds at 2450 V.
- l. Trwaia,b Degrabd \\loU
. Fund lon : ? 3630V ud y
6 3,90 V 2
,,6 seconds ~ N s 8.y seco.nh Timr D e-l s k.k D yry ult /cIfu y FuacEsn.' 2 3 8 L o
\\
d
- 1. s [ee.13 cd s % 9 Bo V Tlm._Dalq. 2 9 7, r s.conda d 'EloY,r seconds CALVERT CLIFFS - UNIT 1 3.3.6-3 Amend' ment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201
p Reporting Rtquirements 5.6 5.6 Reporting Requirements 1
5.6.4 Monthlv Operatina Reports Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.
5.6.5 COREOPERATINGLIMITSREPORT(COLR) a.
Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the, following:
3.1.1 SHUTDOWN MARGIN
,,,,,,, J-3.1.3 Moderator Temperature Coefficient 0
3.1.6 Regulating Control Element Assembly Insertion Limit 3.2.1 Linear Heat Rate 3.2.2 Total Planar Radial Peaking Factor 3.2.3 Total Integrated Radial Peaking Factor h4g 3
.2.5 AXIAL SHAPE INDEX
.9.1 Boron Concentration g,q b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
1.
CENPD-199-P, Latest Approved Revision, "C-E Setpoint Methodology: C-E Local Power Density and DNB LSSS and LC0 Setpoint Methodology for Analbg' Protection Systems,"
January 1986 2.
CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 1: C-E Calculated Local Power Density and Thermal Margin / Low Pressure LSSS for Calvert Cliffs Units I and II," December 1979 3.
CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 2: Combination of System Parameter CALVERT CLIFFS - UNIT 1 5.0-33 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201
SLs 2.0 2.0 SAFETY LIMITS (SLs) 600
=
UNACCEPTABLE OPERATION 580 0.93 1.02 1.09 1.13 FOR PRE-CLAD COLLAPSE OPERATION ONLY UNACCEPTABLE F
w 560 OPERATION g
LIMITS CONTAIN NO ALLOWANCE g
FOR INSTRUMENT ERROR OR FLUCTUATIONS
<> s gg g,
q, I #
g VAL 10 FOR AXIAL SHAPES AND 4 44 4
)(
a R00 RADIAL PEAKING Y.,
ITTUJL UN I luuru. Uc. A ' &
h '
ACCEPTABLE g 500 REACTOR OPERATION LIMITED TO LESS OPERATION 2
THAN 580F BY ACTUATION OF THE SECONDARY SAFETY VALVES 480 I
460 1.671.741.801.8?
O 0.2 0.4 0.6 0.8 1
1.2 1.4 1.6 1.8 2
FRACTION OF RATED THERMAL POWER l
Figure 2.1.1-1 (page 1 of 1)
Unit 1 and Unit 2 Reactor Core Thermal Margin Safety Limit CALVERT CLIFFS - UNIT 1 2.0-2 Amendment No'. 228 CALVERT CLIFFS - UNIT 2 Amendment No. 202
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1' In MODES 1 and 2, the combination of THERMAL POWER, pressurizer pressure, and the highest operating loop cold leg coolant temperature shall not exceed the limits shown in Figure 2.1.1-1.
NOTE------------
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2.1.1.2 In MODES 1 and 2, the peak linear heat rate (LHR) shall bes21.0kW/ft.
2.1.2 Reactor Coolant System (RCS) Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained s 2750 psia.
2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within I hour.
2.2.2 If SL 2.1.2 is violated:
2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.
CALVERT CLIFFS - UNIT 1 2.0-1 Amendment No. 228 CALVERT CLIFFS - UNIT 2 Amendment No. 202
r-e e
t.
4 SLs 2.0
\\
2.0 SAFETY LIMITS (SLs) 60C i
i i
i l
l l
l UNACCEPTA LE OPERATION 8S $y UN CEPTABLE 580-----------------------
ERATION i
FOR PRE-CLAD COL PSE OPERATION ONLY u.
56C.
'b
+k
~
>, 4 i
LIMITS CONTAIN NO ALLO NCE e
l FOR INSTRUMENT ERROR O 4,
- g g 540.
FLUCTUATIONS VALID FOR AXIAL SHAPES AND ROD RADIAL PEAKING 52C.
FACTORS WITHIN LIMITS REACTOR OPERATION LIMITE OLESS
- 50C, THAN 580 F BY ACTUATION O THE g
SECONDARY SAFETY VALV S ACCEPT E
4sd.
OPERATIO
% oA %
46C i
O o.2
.4 o.6 o.8 1.o 1.2 1.4 1.6 1.8 2.0 FRACTION OF RATED THERMAL POWER
__----_-------.--NOTE---------.------..-_---_--
For Uni 2 only, Figure 2.1.1-la shall apply through Cycle 12.
P Figure 2.1.1-la (page 1 of 1)
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Unit 1 and Unit 2 Reactor Core Thermal Margin Safety Limit CALVERT CLIFFS - UNIT 1 2.0-3 AmendrI1ent NO. 228 CALVERT CLIFFS -. UNIT 2 Amendment No. 202
O RPS Instrumentation-Operating 3.3.1 Table 3.3.1-1 (page 1 of 3)
Reactor Protective System Instrumentation SURVEILLANCE i
FUNCTION MODES REQUIREMENTS ALLOWABLE VALUE 1.
Power Level-High 1, 2 SR 3.3.1.1 s 10% RTP above SR 3.3.1.2 current THERMAL POWER SR 3.3.1.3 but not < 30% RTP nor
)
> 107% RTP SR 3.3.1.5 SR 3.3.1.8 SR 3.3.1.9 2.
Rate of Change of 1, 2 SR 3.3.1.1(U s 2.6 dpm Power-High(*)
SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.8 (I
M 3.
Reactor Coolant 1, 2 SR 3.3.1.1 2 92% of Design Flow Flow-Low (O SR 3.3.1.4 SR 3.3.1.7 SR 3.3.1.8 SR 3.3.1.9 4.
Pressurizer 1, 2 SR 3.3.1.1 s 2400 psia Pressure-High SR 3.3.1.4 SR 3.3.1.8 SR 3.3.1.9 5.
Containment 1, 2 SR 3.3.1.1 s 4.0 psig Pressure-High SR 3.3.1.4 SR 3.3.1.8 SR 3.3.1.9 1
CALVERT CLIFFS - UNIT 1 3.3.1-9 Amend' ment No. 228 CALVERT CLIFFS - UNIT 2 Amendment No. 202 1
L
'., ', io RPS Instrumentation-Operating 3.3.1 Table 3.3.1-1 (page 3 of 3)
L Reactor Protective System Instrumentation SURVEILLANCE l
FUNCTION MOD'ES REQUIREMENTS ALLOWABLE VALUE 9b. Asymetric Steam 1, 2 SR 3.3.1.1 5 135 id SR 3.3.1.4 Gene'ragrTransient SR 3.3.1.7 (AbON SR 3.3.1.8 SR 3.3.1.9 NI SR 3.3.1.6 NA
- 10. Loss of Load".)
I SR 3.3.1.7 Bistable trip unit may be bypassed when NUCLEAR INSTRUMENT POWER "I
1E-4% RTP or > 12% RTP. Bypass shall be automatically removed when 4
NUCLEAR INSTRUMENT POWER is 21E-4% RTP and < 12% RTP Bistable trip unit may be bypassed when NUCLEAR INSTRUMENT POWER
(, <
D)
Bypass shall be automatically removed when NUCLEAR INSTRUM 1E-4%.
During testing pursuant to LCO 3.4.16, trips may POWER is 2'1E-4% RTP.
be bypassed below 5% RTP.
Bistable' trip unf t may be bypassed when steam generator pressure is "I
Bypass shall be automatically removed when steam generator
< 785 psig.
pressure is 2 785 psig, i
Bistable trip unit may be bypassed when NUCLEAR INSTRUMENT POWE yl N)
Bypass shall be automatically removed when NUCLEAR INSTR 15% RTP.
POWER is 2 15% RTP.
d Trip is only applicable in MODE 1 NUCLEAR INSTRUMENT POWE b)
CHANNEL CHECK only applies to Wide Range Logarithmic Neutron Flux U)
Monitor.
The Reactor Cuvient Flemtew allowable value_shall Ja-2 1
(
Amendment No. 229 3.3.1-11 CALVERT CLIFFS - UNIT 1 Amendment No. 204 CALVERT CLIFFS - UNIT 2 l
p o
t e
l RCS Pressure, Temperature, and Flew DNB Limits 3.4.1
\\
3.4 REACTOR COOLANT SYSTEM (RCS) 4 I
3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits j
i LC0 3.4.1 RCS DNB parameters for pressurizer pressure, cold leg temperature, and RCS total flow rate shall be within the limits specified below:
a.
Pressurizer pressure 2 2200 psia; b.
RCS cold leg temperature (Tc) s 548*F; and j
i c.
RCS total flow rate 2 340,000 gpm.
~---=----------------------NOTE---------------------------
The RCS total shall b or Unit 2 APPLICABILITY:
MODE 1.
NOTE----------------------------
Pressurizer pressure limit does not apply during:
a.
THERMAL POWER ramp > 5' RTP per minute; or 4
b.
THERMAL POWER step > 10' RTP.
4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
A.1 Restore parameter (s) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> not within limits.
to within limit.
CALVERT CLIFFS - UNIT 1 3.4.1-1 Amendment No. 228 CALVERT CLIFFS - UNIT 2 Amendment No. 202
1
,o RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B.
Required Action and 8.1 Be in MODE 2.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion j
Time not met.
I
. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure 2 2200 psia.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.4.1.2 Verify RCS cold leg temperature 5 548'F.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.4.1.3 NOTE-----------------
For Unit he RCS ow rate shall be 2 3 ro 12.
Verify RCS total flow rate 2 340,000 gpm.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> q;
SR 3.4.1.4 Verify measured RCS total flow rate is 24 months within limits.
i CALVERT CLIFFS - UNIT 1 3.4.1-2 Amendment No. 228 CALVERT CLIFFS - UNIT 2 Amendment No. 202
f=
e MSSVs 3.7.1 Table 3.7.1-2 j
l Main Steam Safety Valve Lift Settings l
VALVE NUMBER LIFT SETTINGm Steam Generator #1 Steam Generator #2 (psig)
RV-3992 RV-4000 935-995 RV-3993 RV-4001 935-995 RV-3994 RV-4002 935-1035 RV-3995 RV-4003 935-1035 RV-3996 RV-4004 935-1050 RV-3997 RV-4005 935-1050 p
RV-3998 RV-4006 935-1050 RV-3999 RV-4007 935-1050 m
Lift settings for a given steam line are also acceptable if any two valves lift between 935 and 995 psig, any two other valves lift between 935 and 1035 psig, and the four remaining valves lift between 935 and 1050 psig.
j<
NOTE------------_------__--_--------
For Unit 2 on y, owable lift s our highest set valves for a given s e
SS prtA cle 12.
l l
'CALVERT CLIFFS. UNIT 1 3.7.1-4 Amendment No. 228 CALVERT CLIFFS _ UNIT 2 Amendment No. 202
o i
MSSVs B 3.7.1 BASES.
{
of accidents that could result in a challenge to the reactor y
coolant pressure boundary.
- -The-four-remening valves lif t betmen -035 -and--1065Wg far Uni &2-only, thrcugh Cycle 12.
APPLICABILITY In MODES 1, 2, and 3, a minimum of five MSSVs per steam generator are required to be OPERABLE, according to Table 3.7.1-1 in the accompanying LCO, which is limiting and i
bounds all lower MODES.
- {
{
In MODES 4 and 5, there are no credible transients requiring 4 the MSSVs.
The steam generators are not normally used for heat remaval in MODES 5 and 6, and thus cannot be overpressurized; there %
.is no requirement for the MSSVs to be OPERABLE in these MODES.
g ACTIONS The ACTIONS table is modified by a Note indicating that separate Condition entry is allowed for each MSSV.
A.1 and A.2 An alternative to restoring the inoperable MSSV(s) to OPERABLE status is to reduce power so that the available MSSV relieving capacity meets Code requirements for the power level. The number of inoperable MSSVs will determine the necessary level of reduction in secondary system steam flow and THERMAL POWER required by the reduced reactor trip settings of the power level-high channels. The reactor trip setpoint reductions are derived on the following basis:
p, (X)-(r)(v) x 5
X where:
reduced reactor trip setpoint in percent of RATED SP
=
h THERMAL POWER maximum number of inoperable safety valves per V
=
steam line 106.5 = Power Level-High Trip Setpoint Total relieving capacity of all safety valves per X
=
steam line in 1bs/ hour CALVERT CLIFFS - UNITS 1 & 2 B 3.7.1-3 Revision 2
~
o Reporting Requirements 5.6 l
5.6 Reporting Requirements l
- 41. The power distribution monitoring system referenced in l
various specifications and the BASES, is described in the following documents:
1.
CENPD-153-P, Latest Approved Revision, " Evaluation of Uncertainty in the Nuclear Power Peaking Measured by the Self-Powered, Fixed Incore Detector System" lli
- 11. CEN-199(B)-P, "BASSS, Use of the Incore Detector l
l System to Monitor the DNB-LC0 on Calvert Cliffs Unit I and Unit 2," November 1979 iii. Letter from Mr. G. C. Creel (BG&E) to NRC Document Control Desk, dated February 7,1989, "Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket 50-318, Request for Amendment, Unit 2 Ninth Cycle License Application" l
iv. Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. G. C. Creel (BG&E), dated January 10, 1990, l
" Safety Evaluation Report Approving Unit 2 Cycle 9 l
License Application"
- 42. Letter from Mr. D. G. Mcdonald, Jr. (NRC) to Mr. R. E. Denton (BGE), dated May 11, 1995. " Approval to Use Convolution Technique in Main Steam Line Break Analysis - Calvert Cliffs Nuclear Power Plant, Unit l
Nos. I and 2 (TAC Nos. M90897 and M90898)-
1 l
c.
The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core
}
thermal hydraulic limits, ECCS limits, nuclear limits such as SDM,transientanalysislimits,andaccidentanalysislimits) of the safety analysis are met.
d.
The COLR, including any mid cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the 1
NRC.
i I
CALVERT CLIFFS - UNIT 1 5.0-38 Amendment-Eo 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201 e