ML20134A949
| ML20134A949 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 01/23/1997 |
| From: | Bajwa S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20134A950 | List: |
| References | |
| NUDOCS 9701290190 | |
| Download: ML20134A949 (25) | |
Text
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J6 UNITED STATES j
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20N50001
'+9.....,o BALTIM0RE GAS AND ELECTRIC COMPANY i
DOCKET N0. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 1 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No.218 License No. DPR-53
~
1.
The Nuclear Regulatory Commission (the Cownission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated September 10, 1996, complies with the standards and requirements of the Atomic D ergy 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; I
C.
There is reasonable assurance (i) 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 4
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:
i 4
- 212; ggt ;;gygg, P
2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.218, 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 20 days.
FOR THE NUCLEAR REGULATORY COMMISSION S. Singh Bajwa, Acting Director 1
Project Directorate I-1 l
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications j
Date of Issuance: January 23, 1997
f*%
g 4
UNITED STATES j
j NUCLEAR REGULATORY COMMISSION C
g WASHINGTON. D.C. 20666 0001
- %*****4 BALTIMORE GAS AND ELECTRIC COMPANY DOCKET N0. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE
,i Amendment No.195 License No. DPR-69 J
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated September 10, 1996, 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 (i) 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 amandment is in accordance with 10 CFR Part i
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-69 is hereby amended to read as follows:
4 i
i
2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 195, are hereby incorporated in the 4
license. The licensee shall operate the facility in accordance with i
the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
j FOR THE NUCLEAR REGULATORY COMMISSION S. Singh Bajwa, Acting Director Project Directorate I-1 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation i
I
Attachment:
Changes to the Technical l
Specifications i
4 Date of Issuance: January 23, 1997 4
i i
J W
i 1
d
+
i ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 218 FACILITY OPERATING LICENSE NO. DPR-53 AMENDMENT NO.195 FACILITY OPERATING LICENSE N0. DPR-69 DOCKET N05. 50-317 AND 50-318 Revise Appendix A as follows:
DPR-53 Remove Paaes Insert Paaes 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 l
3/4 5-4 3/4 5-4 3/4 5-5 3/4 5-5 i
3/4 5-6 3/4 5-6 3/4 6-15 3/4 6-15 3/4 6-16 3/4 6-16 B 3/4 3-1 B 3/4 3-1 DPR-69 Remove Paaes Insert Paaes 3/4 3-19 3/4 3-19 3/4 3-20 3/4 3-20 3/4 3-21 3/4 3-21 i
3/4 3-22 3/4 3-22 3/4 5-4 3/4 5-4 3/4 5-5 3/4 5-5 3/4 5-6 3/4 5-6 3/4 6-11 3/4 6-11 4
3/4 6-12 3/4 6-12 B 3/4 3-1 B 3/4 3-1 1
4 I
i.
I g
TABLE 4.3-2 w
G g
EMINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE0UIREMENTS w
b CHAMEL MODES IN WHICH q
CHAMEL CHAMEL FUNCTIONAL SURVEILUUICE g
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED "i
e 1.
SAFETY INJECTION (SIAS) y
=
~
a.
Manual (Trip buttons)
NA NA REFUELIM NA INTERVAL b.
Containment Pressure - High S
REFUELIN Q
1,2,3 INTERVAL c.
Pressurizer Pressure - Low S
REFUELIM Q
1,2,3 INTERVAL d.
Automatic Actuation Logic NA NA Q
1, 2, 3 l
l III(2)(3)
'f 2.
G a.
Manual (Trip buttons)
NA NA REFUELIM NA INTERVAL b.
Containment Pressure - High S
REFUELIN Q
1, 2, 3 INTERVAL c.
Automatic Actuation Logic NA NA Q(1)(6) 1, 2, 3 l
3.
CONTAINMENT ISOLATION (CIS)'
Ng a.
Manual CIS (Trip buttons)
NA NA REFUELIM NA g
INTERVAL g
b.
Containment Pressure - High S
REFUELI M Q
1, 2, 3
(
INTERVAL f
Q )("I 1, 2, 3 l
I1 c.
Automatic Actuation Logic NA NA M
m t
1
\\
l l
l l
g TABLE 4.3-2 (Continued)
R, a
gy EMINEERED SAFETY FEATURE ACTUATION SYSTEM INSTREENTATION SURVEILLANCE REOUIREMENTS U
~
~
b CeANNEL MODES IN WNiCN h
q CNANNEL CNAIN1EL FWCTIONAL SURVEILLANCE FUNCTIONAL UNIT CNECK CALIBRATION TEST RE0UIRED
- m C
5 4.
MAIN STEAM LINE ISOLATION (SGIS) d E
~
a.
Manual SGIS (MSIV Hand Switches NA NA REFUELIM NA and Feed Head Isolation Hand INTERVAL I
Switches) b.
Steam Generator Pressure - Low S
REFUELIM Q
1,2,3 INTERVAL UM5) c.
Automatic Actuation Logic NA NA Q
1, 2, 3 l
w 5.
CONTAINMENT SUMP RECIRCULATION (RAS) h a.
Manual RAS (Trip Buttons)
NA NA REFUELIM NA INTERVAL b.
Refueling Wster Tank - Low NA REFUELIM Q
1,2,3 INTERVAL UI c.
Automatic Actuation Logic NA NA Q
1, 2, 3 l
6.
CONTAINMENT PURGE VALVES ISOLATION k
a.
Wnual (Purge Valve Control NA NA REFUELIM NA Switches)
INTERVAL
=>
k b.
Centainment Radiation - High Area S
REFUELIM Q
6**
g Monitor INTERVAL E.
co L
g TA8LE 4.3-2 (Continued)
R G
- l g
EMINEEitED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE0UIREMENTS i
i b
CHANNEL MODES IN WHICH q
CHAMEL CHAMEL FUNCTIONAL SURVEILLANCE k
FUNCTIONAL UNIT CHECK CALIBRATION TEST RE0UIRED g
e c
5 7.
LOSS OF POWER d
E a.
4.16 kv Emergency Bus Undervoltage NA REFUELIM Q
1, 2, 3 i
~
(Loss of Voltage)
INTERVAL b.
4.16 kv Emergency Bus Undervoltage NA REFUELIM Q
1, 2, 3 (Degraded Voltage)
INTERVAL
[
8.
CVCS ISOLATION R
West Penetration Room / Letdown NA REFUELIM Q
1,2,3,4 Heat Exchanger Room Pressure - High INTERVAL
[
~
9.
a.
Manual (Trip Buttons)
NA NA REFUELIM NA INTERVAL b.
Steam Generator Level - Low S
REFUELIM Q
1,2,3 INTERVAL f
c.
Steam Generator AP - High S
REFUELIM Q
1, 2, 3 INTERVAL i
N k
d.
Automatic Actuation Logic NA NA Q
1,2,3 l
f 5
i
=
1
3/4 3 INSTRUMENTATION 0
l 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.
(I)
The logic circuits shall be tested manually at least once per 92 days.
l (2)
SIAS logic circuits A-10 and B-10 shall be tested quarterly with the l
exception of the Safety Injection Tank isolation valves. The SIAS logic circuits for these valves are exempted from testing during operation; however, these logic circuits shall be tested at least once per REFUELING INTERVAL during shutdown.
(3)
SIAS logic circuits A-5, and B-5 are exempted from testing during operation; however, these logic circuits shall be tested at least onc? per REFUELING INTERVAL during shutdown.
(4)
CIS logic circuits A-5 and B-5 are exempted from testing during operation; however, these logic circuits shall be tested at least once per REFUELING INTERVAL during shutdown.
(5)
SGIS logic circuits A-1 and B-1 are exempted from testing during operation; however, these logic circuits shall be tested at least once per REFUELING INTERVAL during shutdown.
(6)
CSAS logic circuits A-3 and B-3 are exempted from testing during operation; however, these logic circuits shall be tested at least once per REFUELING INTERVAL during shutdown.
CALVERT CLIFFS - UNIT 1 3/4 3-22 Amendment No. 218
3/4.5 EMERGENCY C0RE C0OLING SYSTEMS (ECCS)
SURVEILUUICE REQUIREMENTS l
4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE *:
i a.
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 following valves are in the indicated positions with power to the valve operators 2
removed:
Valve Number Valve Function Valve Position 1.
MOV-659 Mini-flow Isolation Open j
2.
MOV-660 Mini-flow Isolation Open j
j 3.
CV-306 Low Pressure SI Open Flow Control b.
At least once per 31 days by:
i Verifying)that each valve (manual, power-operated or l
1.
automatic in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
1 c.
At least once per 92 days by:
l y
1.
Verifying that upon a Recirculation Actuation Test Signal, j
the containment sump isolation valves open.
d.
By a visual inspection which verifies that no loose debris (rags, l
trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of
)
the pump suctions during LOCA conditions. This visual inspection shall be performed:
1.
For all accessible areas of the containment prior to establishing CONTAIBMENT INTEGRITY, and i
i 2.
Of the areas affected within containment at the completion of containment entry when CONTAINMENT INTEGRITY is established.
1 i
l e.
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to increasing the RCS pressure above l
1750 psia by verifying, via local indication at the valve, that CV-306 is open.
i 1
j 4
e i
i Whenever flow testing into the RCS is required at RCS temperatures of 365 F and less, the high pressure safety injection pump shall recirculate RCS water (suction from RWT isolated) or the controls of f
Technical Specification 3.4.9.3 shall apply.
CALVERT CLIFFS - UNIT 1 3/4 5-4 Amendment No. 218 1
q 3/4.5 M RGENCY CORE COOLING SYSTEMS (ECCS) l SURVEILLANCE REQUIREMENTS (Continued) f.
At least once per REFUELING INTERVAL by:
l 1.
Verifying the Shutdown Cooling System open-pemissive interlock prevents the Shutdown Cooling System suction isolation valves from being opened with a simulated or actual j
RCS pressure signal of 1309 psia.
2.
A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by 1
debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.
3.
Verifying that a minimum total of 289.3 cubic feet of solid granular trisodium phosphate dodecahydrate (TSP) is contained within the TSP storage baskets.
4.
Verifying that a sample from the TSP baskets provides adequate pH adjustment of water borated to be representative of the post-LOCA sump condition.
g.
At least once per REFUELING INTERVAL, during shutdown, by:
l 1.
Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection Actuation test signal.
2.
Verifying that each of the following pumps start automatically upon receipt of a Safety Injection Actuation Test Signal:
a.
High-Pressure Safety Injection Pump.
1 b.
Low-Pressure Safety Injection Pump.
s CALVERT CLIFFS - UNIT 1 3/4 5-5 Amendment No. 218 l
i
3/4.5 EMERGENCY CORE C0OLING SYSTEMS (ECCS)
SURVEILLANCE REQUIREMENTS (Continued) h.
By performing a flow balance test during shutdown following l
completion of HPSI System modifications that alter system flow characteristics and verjfying the following flow rates for a single HPSI Pump System :
1.
The,, sum of the three lowest flow legs shall be greater than 470 gpm.
- i. By verifying that the HPSI pumps develop a total head of 2900 ft.
l on recirculation flow to the refueling water tank when tested pursuant to Specification 4.0.5.
l A HPSI Pump System is a HPSI pump and one of two safety injection headers.
These limits contain allowances for instrument error, drift or fluctuation.
i CALVERT CLIFFS - UNIT 1 3/4 5-6 Amendment No. 218
3/4.6 CONTAll#4ENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 4
Containment Soray System LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent Containment Spray Systems shall be OPERABLE with each spray system capable of taking suction from the RWT on a Containment Spray Actuation Signal and Safety Injection Actuation Signal and automatically transferring suction to the containment sump on a Recirculation Actuation Signal.
Each spray system flow path from the containment sump shall be via an OPERABLE shutdown cooling heat exchanger.
APPLICABILITY: MODES 1, 2, and 3*.
ACTION: With one Containment Spray System ino)erable, restore the inoperable spray system to 0PERABLE status wit11n 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least NOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the 2
following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.1 Each Containment Spray System shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
Verifying)that each valve (manual, power-operated, or i
1.
automatic in the flow path that is not locked, sealed or otherwise secured in position is positioned to take suction from the RWT on a Containment Pressure-High test signal.
b.
At least once per 92 days by:
l 1.
Verifying that upon a Recirculation Actuation Test Signal, the containment sump isolation valves open and that a recirculation mode flow path via an OPERABLE shutdown cooling heat exchanger is established.
c.
At least once per REFUELING INTERVAL, during shutdown, by:
l 1.
Verifying tht.t each automatic valve in the flow path actuates to its correct position on the appropriate ESFAS test signal.
2.
Verifying that each spray pump starts automatically on the appropriate ESFAS test signal.
With pressurizer pressure 1 1750 psia.
(
CALVERT CLIFFS - UNIT 1 3/4 6-15 Amendment No. 218
3/4.6 CMTAllMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.
At least once per 5 years by perfonning an air or smoke flow test l
through each spray header and verifying each spray nozzle is unobstructed.
f
?
I l
l t
CALVERT CLIFFS - UNIT 1 3/4 6-16 Amendment No. 218 i
=- - -
l 3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF)
INSTRUMENTATION The OPERABILITY of the protective and ESF instrumentation systems and bypassesensurethat1)theassociatedESFactionand/orreactortripwill be initiated when the parameter monitored by each channel or combination thereof exceeds its setpoint, 2) the specified coincidence logic is maintained, 3) sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance, and 4) sufficient system functional capability is available for protective and ESF purposes from diverse parameters.
The OPERABILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility design for the protection and mitigation of accident and transient I
conditions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.
I The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests perfonned at the minimum frequencies are sufficient to demonstrate this capability. The i
quarterly frequency for the channel functional tests for these systems is based on the analysis presented in the NRC-approved Topical Reports CEN-327, "RPS/ESFAS Extended Test Interval Evaluation," as supplemented, and CEN-403, "ESFAS Subgroup Relay Test Interval Extension."
The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident j
analyses. No credit was taken in the analyses for those channels with response times indicated as not applicable.
j 4
Response time may be demonstrated by any series of sequential, overlapping
~i or total channel test measurements provided that such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either 1) in place, onsite or offsite test measurements or 2) utilizing replacement sensors with certified response times. The response time limits are contained in UFSAR Chapter 7, and updatedinaccordancewith10CFR50.71(e).
3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 Radiation Monitorino Instrumentation The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
CALVERT CLIFFS - UNIT 1 B 3/4 3-1 Amendment No. 218
~ __
t I
g TABLE 4.3-2 g
{
G s
g EMINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS
[
w n
a t
C CHAMEL MODES IN MICH M
i y
CHANNEL CHAMEL FUNCTIONAL SURVEILLANCE i
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED "i
i e
5 1.
SAFETY INJECTION (SIAS) d E
a.
Manual (Trip buttons)
NA NA REFUELIM NA INTERVAL 1
b.
Containment Pressure - High S
REFUELIM Q
1,2,3 INTERVAL c.
Pressurizer Pressure - Low S
REFUELIM Q
1,2,3 INTERVAL d.
Automatic Actuation Logic NA NA Q(1)(2)(3) 1, 2, 3 l
[
2.
G i
a.
Manual (Trip buttons)
NA NA REFUELIM MA INTERVAL b.
Containment Pressure - High S
REFUELIN Q
1, 2, 3 INTERVAL c.
Automatic Actuation Logic NA NA Q(1)(8) 1, 2, 3 l
l 3.
CONTAIMENT ISOLATION (CIS)'
$g a.
Manual CIS (Trip buttons)
NA NA REFUELIN NA g
INTERVAL g
b.
Containment Pressure - High S
REFUELIN Q
1,2,3 INTERVAL f
III(*)
c.
Automatic Actuation Logic NA NA Q
1, 2, 3 l
i
g TABLE 4.3-2 (Continued) w G
EMINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE0UIREMENTS w
g b
CHANNEL MODES IN W ICN q
CHAIN 1EL CHAlNIEL FINICTIONAL SURVEILLANCE E"
L FUNCTIONAL UllIT CHECK CALIBRATION TEST REQUIRED 3I c
5 4.
MAIN STEAM LINE ISOLATION (SGIS) d E
~
a.
Manual SGIS (MSIV Hand Switches NA NA REFUELIM NA and Feed Head Isolation Hand INTERVAL Switches) b.
Steam Generator Pressure - Low S
REFUELIM Q
1,2,3 INTERVAL WN c.
Automatic Actuation Logic NA NA Q
1, 2, 3 l
w S.
CONTAINMENT SUMP RECIRCULATION (RAS) b a.
Manual RAS (Trip Buttons)
NA NA REFUELIM NA INTERVAL b.
Refueling Water Tank - Low NA REFUELIM Q
1, 2, 3 INTERVAL W
c.
Automatic Actuation Logic NA NA Q
1, 2, 3 l
6.
CONTAINMENT PURGE VALVES ISOLATION k
a.
Manual (Purge Valve Control NA NA REFUELING NA Switches)
INTERVAL
=
[
b.
Contain:nent Radiation - High S
REFUELIM Q
6**
g Area Monitor INTERVAL 5
~.
g TABLE 4.3-2 (Continued)
R
=
r-EMINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILUUlCE REQUIREMENTS U
b CNANNEL MODES IN WNICH q
CHANNEL CNANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED ka C
7.
LOSS OF POWER y
=
a.
4.16 kv Emergency Bus Undervoltage NA REFUELIM Q
1,2,3
~
(Loss of Voltage)
INTERVAL b.
4.16 kv Emergency Bus Undervoltage NA REFUELING Q
1,2,3 (Degraded Voltage)
INTERVAL 8.
CVCS ISOLATION R
West Penetration Room / Letdown NA REFUELIM Q
1,2,3,4 Y
Heat Exchanger Room Pressure - High INTERVAL 9.
Manual (Trip Buttons)
NA NA REFUELI M NA INTERVAL b.
Steam Generator Level - Low S
REFUELIM Q
1,2,3 INTERVAL c.
Steam Generator AP - High S
REFUELIM Q
1,2,3 INTERVAL k
d.
Automatic Actuation Logic NA NA QN 1,2,3 l
A E
3/4.3 INSTRUMENTATION TABLE 4.3-2 (Continued)
TABLE NOTATION I
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.
UI The logic circuits shall be tested manually at least once per 92 days.
l (2)
SIAS logic circuits A-10 and B-10 shall be tested quarterly with the l
exception of the Safety Injection Tank isolation valves. The SIAS logic circuits for these valves are exempted from testing during operation; however, these logic circuits shall be tested at least once per REFUELING INTERVAL during shutdown.
1 (3) 2 SIAS logic circuits A-5 and B-5 are exempted from testing during operation; however, these logic circuits shall be tested at least once per REFUELING INTERVAL during shutdown.
(4)
CIS logic circuits A-5 and B-5 are exempted from testing during operation; however, these logic circuits shall be tested at least l
once per REFUELING INTERVAL during shutdown.
(5)
SGIS logic circuits A-1 and B-1 are exempted from testing during operation; however, these logic circuits shall be tested at least once per REFUELING INTERVAL during shutdown.
l (6)
CSAS logic circuits A-3 and B-3 are exempted from testing during 4
operation; however, these logic circuits shall be tested at least once per REFUELING INTERVAL during shutdown.
4 4
j 4
1 4
CALVERT CLIFFS - UNIT 2 3/4 3-22 Amendment No. 195
3/4.5 EMERGENCY CORE C0OLING SYSTEMS (ECCS) i SURVEILLANCE REQUIREMENTS r
4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE *:
i a.
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 following valves are in the indicated positions with power to the valve operators removed:
Velve Number Valve Functi_on Valve Position i
1.
MOV-659 Mini-flow Isolation Open 2.
MOV-660 Mini-flow Isolation Open 3.
CV-306 Low Pressure SI Open Flow Control b.
At least once per 31 days by:
1.
Verifying that each valve (manual, power-operated or l
automatic) in the flow path that is not locked, sealed, or j
otherwise secured in position, is in its correct position.
c.
At least once per 92 days by:
j 1.
Verifying that upon a Recirculation Actuation Test Signal, l
the containment sump isolation valves open.
d.
By a visual inspection which verifies that no loose debris (rags, l
l trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:
i 1.
For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and i
2.
Of the areas affected within containment at the completion 1
of containment entry when CONTAIIMENT INTEGRITY is established.
e.
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to increasing the RCS pressure above l
1750 psia by verifying, via local indication at the valve, that j
CV-306 is open.
N Whenever flow testing into the RCS is required at RCS temperatures of 301 F and less, the high pressure safety injection pump shall recirculate RCS water (suction from RWT isolated) or the controls of Technical Specification 3.4.9.3 shall apply.
CALVERT CLIFFS - UNIT 2 3/4 5-4 Amendment No. 195
i 3/4.5 EMERGENCY C0RE COOLING SYSTEMS (ECCS)
SURVEILLANCEREQUIREMENTS(Continued) f.
At least once per REFUELING INTERVAL by:
l 1.
Verifying the Shutdown Cooling System open-pennissive interlock prevents the Shutdown Cooling System suction isolation valves from being opened with a simulated or actual RCS pressure signal of 1 309 psia.
2.
A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.
3.
Verifying that a minimum total of 289.3 cubic feet of solid granular trisodium phosphate dodecahydrate (TSP) is contained within the TSP storage baskets.
4.
Verifying that a sample from the TSP baskets provides adequate pH adjustment of water borated to be representative of the post-LOCA sump condition.
g.
At least once per REFUELING INTERVAL, during shutdown, by:
l 1.
Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection Actuation test signal.
2.
Verifying that each of the following pumps start automatically upon receipt of a Safety Injection Actuation Test Signal:
a.
High-Pressure Safety Injection Pump.
b.
Low-Pressure Safety Injection Pump.
CALVERT CLIFFS - UNIT 2 3/4 5-5 Amendment No. 195
3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)
SURVEILLANCE REQUIREMENTS (Continued) h.
By performing a flow balance test during shutdown following I
completion of HPSI System modifications that alter system flow characteristics and verifying the following flow rates for a single HPSI Pump System :
1.
The,, sum of the three lowest flow legs shall be greater than 470 gpm.
1.
By verifying that the HPSI pumps develop a total head of 2900 ft l
on recirculation flow to the refueling water tank when tested l
pursuant to Specification 4.0.5.
l 1
A HPSI Pump System is a HPSI pump and one of two safety injection headers.
These limits contain allowances for instrument error, drift or j
fluctuation.
CALVERT CLIFFS - UNIT 2 3/4 5-6 Amendment No. 195 l
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4 3/4.6 CONTAIMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS j
Containment Soray System LIMITING CONDITION FOR OPERATION l
3.6.2.1 Two independent Containment Spray Systems shall be OPERABLE with each spray system capable of taking suction from the RWT on a Containment Spray Actuation Signal and Safety Injection Actuation Signal and automatically transferring suction to the containment sump on a Recirculation Actuation Signal.
Each spray system flow path from the containment sump shall be via an 0PERABLE shutdown cooling heat exchanger.
APPLICABILITY: MODES 1, 2, and 3*.
ACTION: With one Containment Spray System inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least NOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the 4
following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.1 Each Containment Spray System shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
Verifying)that each valve (manual, power-operated, or l
1.
automatic in the flow path that is not locked, sealed or otherwise secured in position is positioned to take suction from the RWT on a Containment Pressure-High test signal.
b.
At least once per 92 days by:
1.
Verifying that upon a Recirculation Actuation Test Signal, the containment sump isolation valves open and that a recirculation mode flow path via an OPERABLE shutdown cooling heat exchanger is established.
c.
At least once per REFUELING INTERVAL, during shutdown, by:
l 1.
Verifying that each automatic valve in the flow path actuates to its correct position on the appropriate ESFAS test signal.
2.
Verifying that each spray pump starts automatically on the appropriate ESFAS test signal.
With pressurizer pressure 1 1750 psia.
CALVERT CLIFFS - UNIT 2 3/4 6-11 Amendment No. 195
3/4.6 CONTAIMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.
At least once per 5 years by perfoming an air or smoke flow test l
through each spray header and verifying each spray nozzle is unobstructed.
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2 I
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CALVERT CLIFFS - UNIT 2 3/4 6-12 Amendment No. 195
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i 3/4.3 INSTRUMENTATION j
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BASES T
i 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF) j INSTRUMENTATION l
The OPERABILITY of the protective and ESF instrumentation systems and l
bypasses ensure that 1) the associated ESF action and/or reactor trip will.
be initiated when the parameter monitored by each channel or combination j
thereof exceeds its setpoint, 2) the specified coincidence logic is maintained, 3) sufficient redundancy is maintained to pennit a channel to f
be out of service for testing or maintenance, and 4) sufficient system l
functional capability is available for protective and ESF purposes from j
diverse parameters.
1 i
The OPERABILITY of these systems is required to provide the overall l
reliability, redundance and diversity assumed available in the facility i
design for the protection and mitigation of accident and transient 4
conditions. The integrated operation of each of these systems is j
consistent with the assumptions used in the accident analyses.
i The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability. The l
quarterly frequency for the channel functional tests for these systems is based on the analysis presented in the NRC-approved Topical Reports j
CEN-327, "RPS/ESFAS Extended Test Interval Evaluation," as supplemented, j
and CEN-403, "ESFAS Subgroup Relay Test Interval Extension."
The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident i
analyses. No credit was taken in the analyses for those channels with response times indicated as not applicable.
Response time may be demonstrated by any series of sequential, overlapping l
or total channel test measurements provided that such tests demonstrate the total channel response time as defined.
Sensor response time verification
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may be demonstrated by either 1) in place, onsite or offsite test measurements or 2) utilizing replacement sensors with certified response i
i times. The response time limits are contained in UFSAR Chapter 7, and l
updatedinaccordancewith10CFR50.71(e).
3/4.3.3 MONITORING INSTRUMENTATION i
3/4.3.3.1 Radiation Monitorino Instrumentation The OPERABILITY of the radiation monitoring channels ensures that 1) the i
radiation levels are continually measured in the areas served by the individual channels and 2) the alann or automatic action is initiated when i
the radiation level trip setpoint is exceeded.
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CALVERT CLIFFS - UNIT 2 B 3/4 3-1 Amendment No. 195
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