ML20155K097

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Proposed Tech Specs Making Minor Corrections to Table 3.5.5-1, Accident Monitoring Instrumentation,Items 5 & 14 & Table 4.1-1 Items 65 & 92 & Adding Second Note to Table 4.1-1,Item 80
ML20155K097
Person / Time
Site: Rancho Seco
Issue date: 06/14/1988
From:
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20155K066 List:
References
NUDOCS 8806210104
Download: ML20155K097 (13)
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Text

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation The OPERABILITY of the SFAS instrumentation systems and bypasses ensure that

1) the associated SFAS action will be initiated when the parameter monitored by each channel or combination thereof reaches 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 SFAS purposes from diverse parameters.

The OPERABILITY of these systems is required to provide the overall.

reliability, redundancy, and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.

REFERENCE USAR, Subsection 7,1 Proposed Amendment No. 37, 87, 93, 159 3-26b 8806210104 880614 PDR

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RANCHO SECO UNIT 1 .

TECHNICAL SPECIFICATIONS ,

Limiting Conditions for Operation Table 3.5.1-1 (Continued) ~

INSTRUMENTS OPERATING CONDITIONS (C)

(A) (B) Operator Action if Functional Unit Minimum Operable Minimum Degree Conditions of Columns A Channels of Redundancy and B Cannot be Met Safety Features *

4. Reactor Building spray valve
a. Reactor Building pressure instrument channels 2 1 Bring to hot shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
b. Manual pushbutton 2 1 Bring to hot shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Tctal Number Minimum Channels Process Instrumentation of Channels Operabl e
1. Deleted
2. Deleted
3. Deleted
4. Deleted
5. Deleted
6. Deleted
7. Deleted
8. Deleted
  • If minimum conditions are not met within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af ter hot shutdown, the unit shall be placed in cold shutdown condition within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

I Proposed '

Amendment No. 31, 159 3-30

n RANCHO SECO UNIT 1 -

TECHNICAL SPECIFIC /.IIONS -

Table 3.5.1-1 (Continued) Limiting Conditions for Operation INSTRUMENTS OPERATING CONDITIONS .

(C)

(A) (B) Operator Action if Functional Unit Total Number of Minimum Channels Conditions of Columns A Channels Operable and B Canrot be Met

9. Reacto- Lunainy Purge Isolation 2 1 Operation may continue provided the purge on Mgh radiation inlet and outlet valves of the inoperable channel (s) are closed and their respective breakers de-energized or comply with 3.5.1.2. At cold shutdown or refueling, each of the purge inlet and outlet valves will be closed.
10. Deleted Emeroency Feedwater Initiati>n and Control (EFIC) System
1. A N Initiation
a. Manual 2 (Note 1) 2 (Note 1) See Actions 3 and 4.
b. Low Level, SGA or B (Note 2) 4/SG (Note 1) 3/SG See Actions 1, 2 and 3. May be bypassed below 750 psig OTSG pressure.
c. Low Pressure, SGA or B 4/SG (Note 1) 3/SG See Actions 1, 2 and 3. May be bypassed below 750 psig OTSG pressure.
d. Loss of M N Anticipa-tory Reactor Trip 4 (Note 1) 3 See Actions 1, 2 and 3. Loss of MFW Anticipatory Reactor Trip is effectively bypassed in RPS below 20 percent power.
e. Loss of 4 RC Pumps 4 (Note 3 See Actions 1, 2 and 3. May be bypassed below 750 psig OTSG pressure.
f. Automatic Trip Logic 2 (?!ote 1) 2 (Note 1) See Actions 3 and 4. l
2. SG-A Main Feedwater Isolation
a. Manual 2 (Note 1) 2 (Note 1) See Actions 3 and 4.
b. Low SGA Pressure (hote 3) 4 (Note 1) 3 See Actions 1, 2 and 3. May be bypassed below 750 psig OTSG pressure.
c. Automatic Trip Logic 2 (Note 1) 2 (Note 1) See Actions 3 and 4 Note 1 For channel testing, calibration, or maintenance the Total Number of Charnels and/or the Minimum Channels Operable may be reduced by one for a maximum of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> providing the remaining channels are OPERABLE.

Note 2 Low level AFW Initiation has a maximum of a 10.0 second delay.

Note 3 Low pressure AFV Initiation has a maximum of a 3.0 second delay.

Proposed Amendment No. 31, 43, 60, 9J, 97, 159 3-30a _.

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.5.5 ACCIDENT MONITORING IhSTRUMENTATION Accident monitoring instrumentation channels shown in Table 3.5.5-1 shall be OPERABLE.

Acolicability At all times except when reactor coolant Tavg is less than 280*F.

Action As defined in Table 3.5.5-1.

Bases The operability of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, "Instrumenta-tion for Light-Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," and NUREG-0578, "THI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."

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Proposed Amendment No. 80, 93, 159 3-38d 1

a RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation TABLE 3.5.5-1 ACCIDENT MONITORING INSTRUNENTATION OPERABILITY REQUIREMENTS Total Number Minimum Number of Channels of Channels Action Instrument Ooerable Radiation Monitorina Instrumentation

1. Containment Area 2 2 I High Range Radiation Monitor (7)
2. High Range Noble (6)

Gas Effluent Monitors a) RB Exhaust Stack (3) 1 1 I b) Aux Building Stack 1 1 I c) Aux Building Grade Level Vent (4) 1 1 I

3. Main Steam Lines 2 2 I Radiation Monitors 4 Accident Monitorina Instrumentation
1. Hide Range Con- 2 1 II tainment Water Level (5)
2. Containment 2 1 II Hydrogen Analyzer (5)
3. Emergency Sump 2 1 III Level narrow range (2)
4. Containment Hide 2 1 II Range Pressure (5)
5. Subcooling Margin 2 1 II Monitor
6. Incore Thermocouples(5) 4/ core 2/ core III quadrant quadrant Proposed Amendment No. 80, 93, 159 3-38e

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RANCHO SECO UNIT 1 -l' TECHNICAL SPECIFICATIONS Limiting Conditions for Operation l TABLE 3.5.5-1 (continued) i ACCIDENT HONITORING INSTRUMENTATION OPERABILITY REQUIREMENTS i

l Total Number Minimum Number of Channels of Channels Action  !

Instrument Ooerable  !

7. Reactor Cool nt Hot leg 2 1 II Temperature 7)
8. Reactor Coolant System 2 1 II Pressure - Hide Range (5)
9. Steam Generator Water 2/0TSG 1/0TSG II Level High Range (7)
10. Hot Leg Level (5)(8) 2/ LOOP 1/ LOOP III I
11. Steam Generator 2/0TSG 1/0TSG II i Pressure (7) l
12. Condensate Storage 2 1 IV I Tank Level (5) i
13. Pressurizer Water 3 1 IV Level (5) 14.Auxil{aryFeedwater 2/0TSG 1/0TSG IV Flow SJ
15. EH0V Pressurizer 2 1 IV Relief Valve Position Indicator (Acoustic Flow Monitor)
16. EHOV Block Valve 1 1 IV Position Indicator (2)
17. Safety Valve Position 2/ valve 1/ valve IV Indicator (Acoustic Flow Monitor)
18. Borated Water Storage 2 1 IV Tank Level (2) ,

Proposed Amendment No. 80, 93, 159 3-38ee

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.5.5-1 (Continued)

(1) Deleted (2) Not displayed on SPDS.

(3) Monitoring of the RB Exhaust Stack is not required when the purge and equalizing valves are closed.

(4) Monitoring of the Auxiliary Building Grade Level Vent is not requirri when the unit is not operating.

(5) If SPDS display channel (s) is inoperable, then that instrument channel (s) is considered inoperable.

(6) These monitors are also considered effluent monitors and must be operable during releases per Technical Specification 3.16. See Table 3.16-1 for compensatory action in the event of an inoperable effluent monitor.

(7) SPDS Display channel (s) only. See Table 3.5.1-1 for instrument channel (s) operability.

(8) Reactor Coolant Hot Leg Level portion of the Reactor Coolant Inventory Tracking System.

Action I. Hith the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, either restore the inoperable Channel (s) 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 perform both of the following:

1) Initiate the pre-planned alternate method of monitoring
2) Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.5.0, within 30 days following the event, outlining the action taken, the cause of the inoperability, and the corrective action and schedule for implementation.

II. a. With the number of OPERABLE accident monitoring instrumentation channels less than the Total Number of Channels, restore the inoperable channel (s) to OPERABLE status within 30 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

b. Hith the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Number of Channels Operable, restore the inoperable channel (s) to OPERABLE status within 7 days or be in at least HOT SHUTDOHN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

III. With the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Number of Channels Operable, restore the inoperable channel (s) to OPERABLE status within 30 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Proposed Amendment No. 80, 93, 159 3-38f i

1 RANCHO SECO UNIT 1

- TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 4

Table 3.5.5-1, (Continued)

Action (Continued) .

IV. a. With the number of OPERABLE accident monitoring instrumentation channels less than the Total Number of Channel (s), restore the inoperable channels to OPERABLE status within 7 days, or be in

- at least HOT SHUTD0HN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b. Hith the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Number of Channels Operable, either restore the inoperable channel (s) to OPERABLE within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOHN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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Proposed Amendment No. 159 3-38ff f

RANCHO SFC0 UNIT 1 .

TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.1-1 (Continued) -

INSTRUMENT SURVEILLANCE REQUIREMENTS ,,

Channel Descriotion Check Test Calibrate Remarks

42. Reactor Building drain NA NA R accumulation tank level
43. Incore neutron detectors M(1) NA NA (1) Check functioning, including functioning of computer readout and/or recorder l

readout.

44. a. Process radiation monitoring system W Q R l b. Area radiation monitoring syster.

W M Q l

l c. Chlorine Detector W(1) M(1) R(1) (1) Only required if the total Quantity of gaseous chlorine l

in the RESTRICTED AREA exceeds 100 pounds.

d. Containment Area Monitors W NA R
45. Emergency plant radiation Instruments M(1) NA R (1) Battery check
46. Environmental air monitors M(1) NA R (1) Check functioning
47. Strong motion accelerometer Q(1) NA R (1) Battery check
48. Deleted
49. Pressurizer Water Level M(1) NA R(1) (1) Includes SPDS
50. Auxiliary Feedwater Flow Rate M(1) NA R(1) (1) Includes SPDS and Control Room Indicators
51. Spent Fuel Pool Level W(1) NA R (1) Daily during refueling when moving fuel or control rods.
52. EMOV Pressurizer Relief Valve Position Indicator (Acoustic Flow Monitor) M NA R
53. Deleted
54. EMOV 81ock Valve Position Indicator M NA R
55. Safety Valve Position Indicator (Acoustic Flow l Monitor) M NA R I Propo.ed l Amendment No. 7, II, 54, 60, 93, 97, 98, 159 4-7b I

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RANCHO SECO LMIT 1 TECHNICAL SPECIFICATIONS ,

Surveillance Standards TABLE 4.1-1 (Continued)

INSTRUMENT SURVEILLANCE REQUIREMENTS Channel Description Check Test Calibrate Remarks _

56. Deleted
57. Voltage Protection (1) Test using unde <. cage relay's (Definite and Inverte "TRIP TEST." No quantitative Time Delay Relays) measurements.
a. Undervoltage Relay M(1) N/A R Voltage Setpoint
b. Undervoltage Relay M(1) N/A R Time Delay 58, Containment Area High S(2) M(1)(2) R(2) (1) Test using i:::talled source Range Monitor (2) Includes SPDS
59. Wide Range Containment M(1) N/A R(1) (1) Includes SPDS Water Level

,60. Containment Hydrogen S(1) M(1) Q(1) (1) Includes SPDS Analyzer

61. Emergency Sump Level M N/A R Narrow Range
62. Containment Wide range M(1) N/A R(1) (1) Includes SPDS Pressure
63. High Range Noble Gas S M R (1) See Table 4.20-1 for additional Effluent Monitors (1) Surveillance requirements for

- RB Exhaust Stack effluent monitors.

- Aux. Building Stack

- Aux. Building Grade Level Vent

64. Main Steam Line Radiation S M(1) R (1) Test using installed source Monitors
65. Subcooling Margin Monitors M N/A R
66. Incore Thermocouples(2) M(1) N/A R(1) (1) Includes SPDS (2) 16 Class 1 thermocouples 1 67. Low Temperature Over N/A (1) R (1) Prior to cooldown Pressure Protection Proposed
  • Amendment No. 48, 88, 8Z, 87, 97, 94, 159 4-7c  ;

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l RANCHO SECO UNIT 1 TECHNICAL SPECfsICATIONS Survellaance Standards - -

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TABLE 4.1-1 (Continued) *,

INSTRUMENT SURVEILLANCE REQUIREMENTS 1

Channel Description Check Test Calibrate Remarks

77. Reactor Coolant Hot Leg M(1) N/A R(1) (1) Includes SPDS Temperature Wide Range
78. Reactor Coolant System M(1) N/A R(1) (1) Includes SPDS
  • Pressure - Wide Range
79. Steam Generator Water M(1) N/A R(1) (1) Includes SPDS and Control Level High Range Room indicators
80. Hot Leg Level
  • M(1)(2) N/A R(1) (1) Includes SPDS (2) With RC forced flow, only the verification of channel output is required.
81. Steam Generator M(1) N/A R(1) (1) Includes SPDS and Control Room '

Pressure indicators ,

' Reactor Coolant Hot Leg Level portion of the Reactor Coolant Inventory Tracking System.

Proposed Amendment No. 97, 159 4-7f

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S RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards .

Table 4.1-1 (Continued) ~

INSTRUMENT SURVEILLANCE REOUIREMENTS Channel Description Check Test Calibrate Remarks

82. Spray Pond Water Temperature O NA R
83. Spray Pond Water Level D NA R Dneroency Shutdown Instrumentation
84. Wide Range OSTG Level M NA R
85. Wide Range OSTG Pressure Pressurizer Level M NA R
86. Wide Range Reactar Coolant Hot Leg Temperature M NA R
87. Wide Range Reactor Coolant Cold Leg Temperature M NA R
88. Wide Range Reactor Coolant Pressure M NA R
89. Source Range Neutron Flux Indicator
  • NA NA R
90. Makeup Tank Level M NA R
91. ReservM Other Instrumentation
92. Condensate Storage M(1) N/A R(1) (1) Includes SPDS Tank Level 5 - Each Shift M - Monthly P = Prior to each startup if not done previous week 0 = Daily Q - Quarterly R = Once during the refueling interval W = Weekly SY = Semiannual "Deenergized and disconnected except when control room habitability is lost.

Proposed Amendment No. 97, 159 4-79

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