ML20095L748
| ML20095L748 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 12/28/1995 |
| From: | Marsh L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20095L752 | List: |
| References | |
| NUDOCS 9601040008 | |
| Download: ML20095L748 (17) | |
Text
-. -..
p ato uq UNITED STATES y
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20684-4001
'+4.....,o BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317
~
CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 209 License No. DPR-53 1.
The Nuclear Regulatory Commission (the Commission) has found that:
j A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated October 20, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2. of Facility Operating License No. DPR-53 is hereby amended to read as follows:
9601040008 951228 PDR ADOCK 05000317 p
PDR o
. 2.
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 209, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY C0ptilSSION
$f L.
<1/
Ledyard B. Marsh, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 28, 1995
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 200 FACILITY OPERATING LICENSE NO. DPR-53 DOCKET NO. 50-317 Revise Appendix A as follows:
l Remove Paaes Insert Paaes 3/4 3-1 3/4 3-1 3/4 3-6 3/4 3-6 3/4 3-8 3/4 3-8 l
3/4 3-9 3/4 3-9 3/4 3-19 3/4 3-19 3/4 3-20 3/4 3-20 3/4 3-21 3/4 3-21 3/4 3-22 3/4 3-22 3/4 3-26 3/4 3-26 3/4 3-32 3/4 3-32 3/4 3-36 3/4 3-36 3/4 4-8 3/4 4-8 3/4 4-18 3/4 4-18 3/4 4-35 3/4 4-35 I
3/4.3 INSTRUNENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION LIMITIM COMI' LION FOR OPERATION 3.3.1.1 As a minimum, the reactor protective instrumentation channels and bypasses of Table 3.3-1 shall be OPERABLE.
APPLICABILITY: As shown in Table 3.3-1.
ACTION: As shown in Table 3.3-1.
SURVEILLANCE REQUIREMENTS 4.3.1.1.1 Each reactor protective instrumentation channel shall be demonstrated 0PERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CNkNNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-1.
4.3.1.1.2 The logic for the bypasses shall be demonstrated 0PERABLE prior to each reactor STARTUP unless perfonned during the preceding 92 days. The total byptss function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by l
bypass operation.
4.3.1.1.} hall be demonstrated to be within its limit at least once per The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function s 18 months.
Each test shall include at least one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the " Total No. of Channels" column of Table 3.3-1.
I For Cycle 12, the Steam Generator Low Pressure Trip Bypass surveillance shall be due by March 31, 1996, after which time this amendment will be superseded by Amendment No. 208.
Neutron detectors are exempt from response time testing.
CALVERT CLIFFS - UNIT 1 3/4 3-1 Amendment No. 209 i
g TABLE 4.3-1 R
G g
REACTOR PROTECTIVE INSTRUMENTATION SURVEILUUICE RE0UIREMENTS w
b CIUUNIEL N00ES IN WilICM 7
CNAl#1EL CIUUlllEL FUllCTIONAL SURVEILUUICE E
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED h
1.
Manual Reactor Trip NA NA S/UIII NA g
g 2.
Power Level - High j
a.
Nuclear Power S
D(2) M(3) Q(8)
Q 1, 2 l
D '), R ')
Q 1
l i
I I
b.
AT Power S
3.
Reactor Coolant Flow - Low S
R(8)
Q 1, 2 l
l I
R ')
Q 1, 2 l
g 4.
Pressurizer Pressure - High S
w 5.
Containment Pressure - High S
R Q
1, 2 6.
Steam Generator Pressure - Low S
R(8)
Q 1, 2 l
7.
Steam Generator Water Level -
S R(8)
Q 1, 2 l
Low B.
Axial Flux Offset S
R Q
1 R ')
Q 1, 2 l
I 9.
a.
Thennal Margin / Low Pressure S b.
Steam Generator Pressure S
R(8)
Q 1, 2 l
g Difference - High il a
- 10. Loss of Load NA NA S/U )
NA
.E
3/4.3 INSTRUMENTATION TABLE 4.3-1 (Continued)
TABLE NOTATION With reactor trip breakers in the closed position and the CEA drive system capable of CEA withdrawal.
(1)
If not perfonned in previous 7 days.
(2)
Heat balance only, above 15% of RATED THERMAL POWER; adjust " Nuclear Power Calibrate" potentiometers to make the nuclear power signals agree with calorimetric calculation if absolute difference is > 1.5%.
During PNYSICS TESTS, these daily calibrations of nuclear power and AT power may be suspended provided these calibrations are perfonned upon reaching each major test power plateau and prior to proceeding to the next major test power plateau.
(3)
Above 15% of RATED THERMAL POWER, recalibrate the excore detectors which monitor the AXIAL SHAPE INDEX by using the incore detectors or restrict THERMAL POWER during subsequent operations to < 90% of the maximum allowed THERMAL POWER level with tha existing Reactor Coolant Pump combination.
(4)
Above 15% of RATED THERMAL POWER, adjust "AT Pwr Calibrate" potentiometers to null " Nuclear Pwr - AT Pwr." During PHYSICS TESTS, these daily calibrations of nuclear power and AT power may be suspended provided these calibrations are perfonned upon reaching each major test power plateau and prior to proceeding to the next major test power plateau.
i (5)
Neutron detectors may be excluded from CHAlelEL CALIBRATION.
(6)
For Cycle 12, the surveillance shall be due by March 31, 1996, after which time this amendment will be superseded by Amendment No. 208.
l CALVERT CLIFFS - UNIT 1 3/4 3-8 Amendment No. 209
3/4.3 INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION I
LINITING CONDITION FOR OPERATION 3.3.2.1 The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and bypasses shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4.
APPLICABILITY: As shown in Table 3.3-3.
ACTION:
a.
With an ESFAS instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.
b.
With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.
SURVEILLANCE REQUIREMENTS 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated 0PERABLE by the perfonnance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-2.
4.3.2.1.2 The logic for the bypasses shall be demonstrated 0PERABLE during the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation.
The total bypass function shall be demonstrated OPERABLE at least once per 18 months
- during CHANNEL CALIBRATION testing of each l
channel affected by bypass operation.
4.3.2.1.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months *.
Each test shall include at least one channel per function I
such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" Column of Table 3.3-3.
For Cycle 12, the surveillance shall be due by March 31, 1996, after which time this amendment will be superseded by Amendment No. 208.
CALVERT CLIFFS - UNIT 1 3/4 3-9 Amendment No. 209
I r
t g
TABLE 4.3-2 R
[
G
?
y
< ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS l
w i
n
=
t C
CHANNEL MODES IN W ICH i
7 CNAMEL CNAMEL FMCTIONAL SURVEILLANCE g
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 5
c 5
1.
SAFETY INJECTION (SIAS) d
~
E R)
NA l
I7 a.
Manual (Trip buttons)
NA NA b.
Containment Pressure - High S
f7 Q
1,2,3 R)
M)g)(3) 1, 2, 3 l
l c.
Pressurizer Pressure - Low S
ll d.
Automatic Actuation Logic NA NA 1, 2, 3 2.
CONTAINMENT SPRAY (CSAS) l w5 a.
Manual (Trip buttons)
NA NA R(7)
NA l
l b.
Containment Pressure - High S
R Mg(8) 1, 2, 3 il 1, 2, 3 l
G c.
Automatic Actuation Logic NA NA 3.
CONTAIMENT ISOLATION (CIS)'
i a.
Manual CIS (Trip buttons)
NA NA R(7)
NA l
l M(1g(*)
1, 2, 3 i
b.
Containment Pressure - High S
R c.
Automatic Actuation Logic NA NA 1, 2, 3
$a ita 5
a I
I I
I ew g
TABLE 4.3-2 (Continued)
R G
g ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS w
b CHANNEL MODES IN WNICH q
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE k"'
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED
- i C
5 4.
MAIN STEAM LINE ISOLATION (SGIS) d 2
I R ')
NA l
~
a.
Manual SGIS (MSIV Hand Switches NA NA and Feed Head Isolation Hand Switches)
R ')
I b.
Steam Generator Pressure - Low S
Mg(5) 1,2,3 l
D c.
Automatic Actuation Logic NA NA 1, 2, 3 g
5.
CONTAINMENT SUMP RECIRCULATION (RAS)
I R ')
NA l
a.
Manual RAS (Trip Buttons)
NA NA 8
b.
Refueling Water Tank - Low NA R
MgI 1,2,3 c.
Automatic Actuation Logic NA NA 1, 2, 3 6.
CONTAINMENT PURGE VALVES ISOLATION a.
Manual (Purge Valve Control NA NA R
NA Switches) b.
Containment Radiation - High Area S
R Q
6**
k Monitor a
F.
g TABLE 4.3-2 (Continued)
Q y
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS w
E n
C CHANNEL MODES IN WHICH M
7 CHAl#1EL CHANNEL FUNCTIONAL SURVEILLANCE E"
{
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 3
e
- n 7.
LOSS OF POWER a.
4.16 kv Emergency Bus Undervoltage NA R(')
Q 1, 2, 3 l
(Loss of Voltage) b.
4.16 kv Emergency Bus Undervoltage NA R(7)
Q 1,2,3 l
(Degraded Voltage) 8.
CVCS ISOLATION West Penetration Room / Letdown NA R
Q 1,2,3,4 Heat Exchanger Room Pressure - High DI 9.
[
a.
Manual (Trip Buttons)
NA R
NA Rg Q
1,2,3 l
l b.
Steam Generator Level - Low S
c.
Steam Generator AP - High S
R Mg) 1, 2, 3 l
d.
Automatic Actuation Logic NA NA 1, 2, 3 k
i a
it a
?
=
i I
e
3/403 INSTRUMENTATION TABLE 4.3-2 (Continued)
TABLE NOTATION Containment isolation of non-essential penetrations is also initiated by SIAS (functional units 1.a and 1.c).
Must be OPERABLE only in MODE 6 when the valves are required OPERABLE and they are open.
(1)
The logic circuits shall be tested manually at least once per 31 days.
(2)
SIAS logic circuits A-10 and B-10 shall be tested monthly with the exception of the Safety Injection Tank isolation valves. The SIAS logic circuits for these valves are exempted from testing during operation; however, during shutdown.
these logic circuits shall be tested at least once per 18 months l
(3)
SIAS logic circuits A-5, and B-5 are exempted from testing during operation; however, during shutdown.
these logic circuits shall be tested at least once per 18 months (4)
CIS logic circuits A-5 and B-5 are exempted from testing during operation; however, during shutdown.
these logic circuits shall be tested at least once per 18 months (5)
SGIS logic circuits A-1 and B-1 are exempted from testing during operation; however, during shutdown.
these logic circuits shall be tested at least once per 18 months (6)
CSAS logic circuits A-3 and B-3 are exempted from testing during operation; however, during shutdown.
these logic circuits shall be tested at least once per 18 months (7)
For Cycle 12, the surveillance shall be due by March 31, 1996, after which time this amendment will be superseded by Amendment No. 208.
For Cycle 12, the surveillance shall be du? by March 31, 1996, after which time this amendment will be supersedeo by Amendment No. 208.
CALVERT CLIFFS - UNIT 1 3/4 3-22 Amendment No. 7.09
I g
TABLE 4.3-3 R
G g
RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS w
t CNANNEL MODES IN WNICN E
n C
CNANNEL CNANNEL FUNCTIONAL SURVEILLANCE
'Q
]
INSTRUMENT CNECK CALIBRATION TEST REQUIRED E
i 1.
AREA MONITORS E
Y c
a.
Containment y
=
i.
Purge & Exhaust Isolatico S
R M
6 b.
Containment Area High Range S
R*
M 1, 2, 3, & 4 l
2.
PROCESS MONITORS R
a.
Containment a
- i. Gaseous Activity E$
a)
RCS Leakage Detection S
R M
1, 2, 3, & 4 l
ii. Particulate Activity a)
RCS Leakage Detection S
R M
1, 2, 3, & 4 b.
Noble Gas Effluent Monitors y
- i. Main Vent Wide Range S
R M
1, 2, 3, & 4 m
t A
- 11. Main Steam Header S
R M
1, 2, 3, & 4 l
2 I
For Cycle 12, the surveillance shall be due by March 31, 1996, after which time this amendment will be m8 superseded by Amendment No. 208.
. - -.. -. _ ~ - -. - - -
3/4.3 INSTRUMENTATION i
TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION 1.
Wide Range Neutron Flux M
NA 2.
Reactor Trip Breaker Indication M
NA 3.
Reactor Coolant Cold Leg Temperature M
R*
l 4.
Pressurizer Pressure M
R*
l 5.
Pressurizer Level M
R*
l 6.
Steam Generator Level (Wide Range)
M R*
l 7.
Steam Generator Pressure M
R*
l For Cycle 12, the surveillance shall be due by March 31, 1996, after which time this amendment will be superseded by Amendment No. 208.
CALVERT CLIFFS - UNIT 1 3/4 3-32 Amendment No. 209
g TABLE 4.3-10 w
G g
POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS w
N CNANNEL CNANNEL G
C INSTRUMENT
- CNECK, CALIBRATION n
=
?
1.
Containment Pressure M
R l
2.
Wide Range Logarithmic Neutron Flux Monitor M
NA y
3 3.
Reactor Coolant Outlet Temperature M
R**
l $
4.
Pressurizer Pressure M
R l
~
5.
Pressurizer Level M
R l
f 6.
Steam Generator Pressure M
R**
l 7.
Steam Generator Level (Wide Range)
M R*
l 8.
Auxiliary Feedwater Flow Rate M
R
{
9.
RCS Subcooled Margin Monitor M
R l
- 10. PORV/ Safety Valve Acoustic Monitor NA R
l
- 11. PORV Solenoid Power Indication NA NA
- 12. Feedwater Flow M
R**
l
- 13. Containment Water Level (Wide Range)
M R
l g
NA aR
- 15. Core Exit Thennocouple System M
R.
il t
A The perfonnance of a CNANNEL CALIBRATION operation exempts the Core Exit Thennocouple but includes all electronic components. The Core Exit Thennocouple shall be calibrated prior to
- z installation in the reactor core.
For Cycle 12, the surveillance shall be due by March 31, 1996, after which time this amendment will be superseded by Amendment No. 208.
l
. =.
i j
3/4.4 REACTOR COOLANT SYSTEN 1
SURVEILLANCE REQUIRENENTS 4.4.3.1 Each PORY shall be demonstrated OPERABLE:
a.
At least once per 31 days by performance of a CHANNEL FUNCTIONAL TEST, in accordance with Table 4.3-1 Item 4.
b.
At least once per 18 months
- by performance of a CHANNEL l
CALIBRATION.
4.4.3.2 Each block valve shall be demonstrated 0PERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed to meet the requirements of Action a, b, or c in Specification 3.4.3.
i l
i For Cycle 12, the surveillance shall be due by March 31, 1996, after which time this amendment will be superseded by Amendment No. 208.
CALVERT CLIFFS - UNIT 1 3/4 4-8 Amendment No. 209
...=
3/4.4 REACTOR C0OLANT SYSTEM SURVEILLANCE REQUIRENENTS 4.4.6.1 The Leakage Detection Systems shall be demonstrated OPERABLE by:
a.
Containment Atmosphere Gaseous and Particulate Monitoring Systems-performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3, and b.
ContainmentSumpLevelAlarmSystem-performanceofCHANNEL CALIBRATION at least once per 18 months.
l l
For Cycle 12, the surveillance shall be due by March 31, 1996, after which time this amendment will be superseded by Amendment No. 208.
CALVERT CLIFFS - UNIT 1 3/4 4-18 Amendment No. 209
3/4.4 REACTOR C00UUIT SYSTEM LIMITIl1G CONDITION F0N OPERATION (Continued) i 2.
Verify the excessive flow condition did not raise pressure above the maximum allowable pressure for the given RCS temperature on Figure 3.4.9-1 or Figure 3.4.9-2.
3.
If a pressure limit was exceeded, take action in accordance with Specification 3.4.9.1.
h.
The provisions'of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:
a.
Performance of a CHAlNIEL FUNCTIONAL TEST on the PORY actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORV is required OPERABLE and at least once per 31 days thereafter when the PORV is required OPERABLE.
b.
Performance of a CHAIN 1EL CALIBRATION on the PORV actuation channel at least once per 18 months **.
l c.
Verifying the PORV block valve is open at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the PORY is being used for overpressure protection.
d.
Testing in accordance with the inservice test requirements pursuant to Specification 4.0.5.
4.4.9.3.) hen the vent (s) is being used for overpressure protection.The RCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> w 4.4.9.3.3 All high pressure safety injection pumps, except the above OPERABLE pump, shall be demonstrated inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the motor circuit breakers have been removed from their electrical power supply circuits or by verifying their discharge valves are locked shut. The automatic opening feature of the high pressure safety injection loop MOVs shall be verified disabled at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The above OPERABLE pump shall be verified to have its handswitch in pull-to-lock at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
For Cycle 12, the surveillance shall be due by March 31, 1996, after which time this amendment will be superseded by Amendment No. 208.
Except when the vent pathway is locked, sealed, or otherwise secured in the open position, then verify these vent pathways open at least once per 31 days.
CALVERT CLIFFS - UNIT 1 3/4 4-35 Amendment No. 209
. -