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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211M6651999-09-0101 September 1999 Errata Page 4-45,reflecting Proposed Changes Requested in ML20211D1551999-08-20020 August 1999 Proposed Tech Specs Pages,Revising Degraded Voltage Relay as-left Setpoint Tolerances ML20210J1261999-07-29029 July 1999 Proposed Tech Specs Revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance TSs ML20195E6201999-06-0404 June 1999 Proposed Tech Specs,Modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20206R1171999-05-13013 May 1999 Proposed Tech Specs Section 3.1.1,incorporating Administrative Updating & Changing Bases Statement ML20205H0781999-04-0101 April 1999 Proposed Tech Specs Adding LCO Action Statements,Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20203B0511999-02-0202 February 1999 Proposed Tech Specs Expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems Outside of Containment ML20196H5361998-12-0303 December 1998 Proposed Tech Specs Reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196G4861998-12-0303 December 1998 Non-proprietary Proposed Tech Specs,Consenting to Transfer & Authorization for Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License ML20196F8661998-11-25025 November 1998 Proposed Tech Specs Revised Pages for TS Change 277 Changing Surveillances Specs for OTSG ISI for TMI Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only. with Certificate of Svc ML20154Q6271998-10-19019 October 1998 Proposed Tech Specs Adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18 ML20154P8661998-10-19019 October 1998 Proposed Tech Specs,Providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage ML20249B2421998-06-11011 June 1998 Proposed Tech Specs Re Alternate High Radiation Area Control ML20217J8201998-03-25025 March 1998 Proposed Tech Specs Page 6-1,reflecting Change in Trade Name of Owners & Operator of TMI-1 & Correcting Typo ML20217E5311998-03-23023 March 1998 Proposed Tech Specs Pages for Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 EFPY ML20217G0201997-10-0303 October 1997 Proposed Tech Specs Re Revised Pages 4-80 & 4-81 Previously Submitted ML20211F3781997-09-24024 September 1997 Proposed Tech Specs Revising Steam Line Break Accident Dose Consequence ML20211C3421997-09-19019 September 1997 Proposed Tech Specs Pages 3.8-3.9b to TS Section 3.1.4 Providing More Restrictive Limit of 0.35 Uci/Gram Dose Equivalent I-131 & Clarifying UFSAR Analysis ML20211C2431997-09-19019 September 1997 Proposed Tech Specs Re Decay Heat Removal Sys Leakage ML20210K0011997-08-14014 August 1997 Proposed Tech Specs Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J4051997-08-12012 August 1997 Proposed Tech Specs Revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operation ML20198E7941997-07-30030 July 1997 Proposed Tech Specs Incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 Nor Considered in TMI-1 UFSAR DBA Analysis Dose Calculations for 2568 Mwt ML20151K2071997-07-25025 July 1997 Revised TS Page 6-19 Replacing Corresponding Page Contained in 970508 Transmittal of TS Change Request 264 ML20141E1491997-05-0808 May 1997 Proposed Tech Specs,Consisting of Change Request 264, Incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2471997-04-21021 April 1997 Proposed Tech Specs 3.3.1.2,changing Required Borated Water in Each Core Flood Tank to 940 ft,4.5.2.1.b,lowering Surveillance Acceptance Criteria for ECCS HPI Flow to 431 Gpm & 3.3.1.1.f Re Operability of Decay Heat Valves ML20134M1211997-02-0707 February 1997 Proposed Tech Specs,Incorporating Certain Improvements from Revised STS for B&W plants,NUREG-1430 ML20133D2821996-12-24024 December 1996 Proposed Tech Specs 3.15.3 Re Auxiliary & Fuel Handling Bldg Air Treatment Sys ML20132F3301996-12-16016 December 1996 Proposed Tech Specs,Reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135D0991996-12-0303 December 1996 Proposed Tech Specs Incorporating Certain Requirements from Revised B&W Std TS,NUREG-1430 ML20135C5321996-12-0202 December 1996 Proposed Tech Specs Re Relocation of Audit Frequency Requirements ML20128H4121996-10-0303 October 1996 Errata to Proposed Ts,Adding Revised Table of Contents & Making Minor Editorial Corrections ML20117H0451996-08-29029 August 1996 Proposed Tech Specs,Consisting of Change Request 257, Incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1971996-06-28028 June 1996 Proposed Tech Specs,Consisting of Change Request 259, Allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8791996-05-24024 May 1996 Proposed Tech Specs Re Pages for App A.Certificate of Svc Encl ML20101R1571996-04-10010 April 1996 Proposed Tech Specs,Revising Addl Group of Surveillances in Which Justification Has Been Completed ML20100J6931996-02-22022 February 1996 Proposed Tech Specs,Consisting of Change Request 254, Revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Battery Cell Parameters Not Met ML20095J2311995-12-21021 December 1995 Proposed Tech Specs,Raising Low Voltage Action Level to 105 Volts DC ML20092K5471995-09-20020 September 1995 Revised Tech Spec Pages 4-31,4-32 & 4-33,incorporating Change in TS Section 4.4.1.5 ML20091L2911995-08-23023 August 1995 Proposed Tech Specs Page 6-11a,incorporating Ref to 10CFR20.1302 ML20087F4921995-08-11011 August 1995 Proposed TS Section 3.2 Re Makeup,Purification & Chemical Addition Sys Requirements ML20085N1601995-06-22022 June 1995 Proposed Tech Specs Revising Replacement Pages in Package & Remove Outdated Pages,In Response to NRC Request for Addl Info ML20084L4351995-06-0101 June 1995 Proposed TS 5.3.1.1,describing Use of Advanced Clad Assemblies ML20084N3501995-06-0101 June 1995 Proposed Tech Specs,Deleting RETS & Relocating TSs Per Guidance in GL 89-01 & NUREG-1430 ML20084B3361995-05-24024 May 1995 Proposed Tech Specs Re Change in Surveillance Test Requirements for source-range Nuclear Instrumentation ML20083N7841995-05-17017 May 1995 Proposed Tech Specs,Consisting of Change Requests 252, Removing Chemical Addition Sys Requirements from TS to COLR ML20079A7811994-12-23023 December 1994 Proposed Tech Specs Page 3-32a ML20069A6781994-05-20020 May 1994 Proposed Tech Specs,Supporting Cycle 10 Control Rod Trip Insertion Time Testing ML20065M6831994-04-19019 April 1994 Proposed Tech Specs,Reflecting Deletion of Audit Program Frequency Requirements ML20065K0451994-04-11011 April 1994 Proposed Tech Specs Reflecting Relocation of Detailed Insp Criteria,Methods & Frequencies of Containment Tendon Surveillance Program to FSAR & Providing Direct Ref to Existing Tendon Surveillance Program ML20073C7731994-03-22022 March 1994 Proposed Tech Specs Re Control Rod Trip Insertion Time Testing 1999-09-01
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211M6651999-09-0101 September 1999 Errata Page 4-45,reflecting Proposed Changes Requested in ML20211D1551999-08-20020 August 1999 Proposed Tech Specs Pages,Revising Degraded Voltage Relay as-left Setpoint Tolerances ML20210S7691999-08-12012 August 1999 Rev 10 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20210J1261999-07-29029 July 1999 Proposed Tech Specs Revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance TSs ML20195E6201999-06-0404 June 1999 Proposed Tech Specs,Modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20206R1171999-05-13013 May 1999 Proposed Tech Specs Section 3.1.1,incorporating Administrative Updating & Changing Bases Statement ML20206R6531999-05-13013 May 1999 Rev 39 to TMI Modified Amended Physical Security Plan ML20205H0781999-04-0101 April 1999 Proposed Tech Specs Adding LCO Action Statements,Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20204B5291999-03-12012 March 1999 Rev 9 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual (Edcm) ML20203B0511999-02-0202 February 1999 Proposed Tech Specs Expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems Outside of Containment ML20196G4861998-12-0303 December 1998 Non-proprietary Proposed Tech Specs,Consenting to Transfer & Authorization for Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License ML20196H5361998-12-0303 December 1998 Proposed Tech Specs Reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196F8661998-11-25025 November 1998 Proposed Tech Specs Revised Pages for TS Change 277 Changing Surveillances Specs for OTSG ISI for TMI Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only. with Certificate of Svc ML20154P8661998-10-19019 October 1998 Proposed Tech Specs,Providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage ML20154Q6271998-10-19019 October 1998 Proposed Tech Specs Adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18 ML20154D5491998-10-0101 October 1998 Cancellation Notification of Temporary Change Notice 1-98-0066 to Procedure 6610-PLN-4200.02 ML20206C0911998-09-0101 September 1998 Rev 17 to Odcm ML20249B2421998-06-11011 June 1998 Proposed Tech Specs Re Alternate High Radiation Area Control ML20216E9751998-04-13013 April 1998 Emergency Dose Assessment Users Manual, for Insertion Into Rev 7 of Edcm ML20216E9491998-04-0909 April 1998 Rev 7,Temporary Change Notice 1-98-003 to 6610-PLN-4200.02, Edcm, Changing Pages 2 & 57 & Adding New Emergency Dose Assessment Users Manual ML20217J8201998-03-25025 March 1998 Proposed Tech Specs Page 6-1,reflecting Change in Trade Name of Owners & Operator of TMI-1 & Correcting Typo ML20217E5311998-03-23023 March 1998 Proposed Tech Specs Pages for Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 EFPY ML20202B2061998-01-30030 January 1998 Rev 7,Temporary Change Notice 1-98-0013 to 6610-PLN-4200.02, Edcm ML20198T4721997-12-31031 December 1997 TMI-1 Cycle 12 Startup Rept ML20217G0201997-10-0303 October 1997 Proposed Tech Specs Re Revised Pages 4-80 & 4-81 Previously Submitted ML20211F3781997-09-24024 September 1997 Proposed Tech Specs Revising Steam Line Break Accident Dose Consequence ML20211C2431997-09-19019 September 1997 Proposed Tech Specs Re Decay Heat Removal Sys Leakage ML20211C3421997-09-19019 September 1997 Proposed Tech Specs Pages 3.8-3.9b to TS Section 3.1.4 Providing More Restrictive Limit of 0.35 Uci/Gram Dose Equivalent I-131 & Clarifying UFSAR Analysis ML20210K0011997-08-14014 August 1997 Proposed Tech Specs Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J4051997-08-12012 August 1997 Proposed Tech Specs Revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operation ML20198E7941997-07-30030 July 1997 Proposed Tech Specs Incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 Nor Considered in TMI-1 UFSAR DBA Analysis Dose Calculations for 2568 Mwt ML20151K2071997-07-25025 July 1997 Revised TS Page 6-19 Replacing Corresponding Page Contained in 970508 Transmittal of TS Change Request 264 ML20217M7251997-06-22022 June 1997 Rev 16 to Procedure 6610-PLN-4200.01, Odcm ML20141E1491997-05-0808 May 1997 Proposed Tech Specs,Consisting of Change Request 264, Incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2471997-04-21021 April 1997 Proposed Tech Specs 3.3.1.2,changing Required Borated Water in Each Core Flood Tank to 940 ft,4.5.2.1.b,lowering Surveillance Acceptance Criteria for ECCS HPI Flow to 431 Gpm & 3.3.1.1.f Re Operability of Decay Heat Valves ML20134M1211997-02-0707 February 1997 Proposed Tech Specs,Incorporating Certain Improvements from Revised STS for B&W plants,NUREG-1430 ML20133D2821996-12-24024 December 1996 Proposed Tech Specs 3.15.3 Re Auxiliary & Fuel Handling Bldg Air Treatment Sys ML20132F3301996-12-16016 December 1996 Proposed Tech Specs,Reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135D0991996-12-0303 December 1996 Proposed Tech Specs Incorporating Certain Requirements from Revised B&W Std TS,NUREG-1430 ML20135C5321996-12-0202 December 1996 Proposed Tech Specs Re Relocation of Audit Frequency Requirements ML20128H4121996-10-0303 October 1996 Errata to Proposed Ts,Adding Revised Table of Contents & Making Minor Editorial Corrections ML20117H0451996-08-29029 August 1996 Proposed Tech Specs,Consisting of Change Request 257, Incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1971996-06-28028 June 1996 Proposed Tech Specs,Consisting of Change Request 259, Allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8791996-05-24024 May 1996 Proposed Tech Specs Re Pages for App A.Certificate of Svc Encl ML20138B4641996-05-0606 May 1996 Rev 14 to Procedure 6610-PLN-4200.01, Odcm ML20101R1571996-04-10010 April 1996 Proposed Tech Specs,Revising Addl Group of Surveillances in Which Justification Has Been Completed ML20100J6931996-02-22022 February 1996 Proposed Tech Specs,Consisting of Change Request 254, Revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Battery Cell Parameters Not Met ML20096F0521995-12-31031 December 1995 TMI-1 Cycle 11,Startup Rept ML20095J2311995-12-21021 December 1995 Proposed Tech Specs,Raising Low Voltage Action Level to 105 Volts DC ML20092M1941995-09-21021 September 1995 TMI-1 Pump & Valve IST Program 1999-09-01
[Table view] |
Text
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TABLE 3.5-1 (Continued) *[
N .
INSTRUMENTS OPERATION CONDITIONS FUNCTIONAL UNIT (A) (B) (C)
Minimum Operable Minimum degree Operator Action if Conditions Channels of redundancy of Column A and B Cannot be Met
.5. 4.16KV ES Bus Undervoltage y Relays _
'N g 1. Degraded Grid Voltage 2 1 (a)
.g relays C
- 2. Loss of Voltage relay 2 1 (a)
(a) .If a relay fails in the untripped state, it shall be placed in a tripped state within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to obtain a degree of redundancy of 1. The relay may be removed from the tripped state for up l%
s to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for functional tecting pursuant to Table 4.1-1.
W W
4
3.5.3 ENGINEERED SAFECUARDS PROTECTION SYSTEM ACTUATION SETPOINTS Applicability:
This specification applies to the engineered safeguards protection system actuation setpoints.
Objective:
To provide for automatic initiation of the engineered safeguards protection system in the event of a breach of Reactor Coolant System integrity.
Specification:
3.5.3.1 The enginected safeguards protection system actuation setpoints and permissible bypasses shall be as follows:
Initiating Signal Function Setpoint High Reactor Building Reactor Building Spray < 30 psig Pressure (1)
High-Pressure Injection j[ 4 psig Low-Pressure Injection j[ 4 psig Start Reactor Building Cooling & Reactor Building Isolation < 4 psig Low Reactor Coolant High Pressure Injection > 1500(2) and
?_ 500(3) psig System Pressure Low Pressure Injection 3,1500(2) and
> 500(3) psig 4.16 kv E.S. Buses Undervoltage Relays Degraded Voltage (5) Switch to Onsite Power Source and load shedding 3595 volts (4)
Degraded grid timer 10 sec (5)
Loss of voltage Switch to Onsite Power Source and load shedding 2400 Volts (6)
Loss of voltage timer 1.5 see (7)
(1) May be bypassed for reactor building leak rate test.
(2) May be bypassed.below 1650 psig and is automatically reinstated above 1650 psig.
3-37
e :. -
(3) May be bypassed below 900 psig and is automatically reinstated above 900 psig.
(4) Minimum. allowed setting is 3560 v. Maximum allowed setting is 3650 v.
(5) Minimum allowed time is 8 sec. muimum allowed time is 12 sec.
(6) Minimum allowed setting is 2200 volts, maximum allowed setting is 2860 volts.
(7) Minimum allowed time is (1.0) second, maximum allowed time is (2.0) seconds.
Bases High Reactor Building Pressure The basis for the 30 psig and 4 psig setpoints for~the high pressure signal is to establish a setting which would be reached in adequate time such that protection is provided for the entire spectrum of break sizes and is far enough above normal containment internal pressures to prevent spurious initiation.
Low Reactor Coolant System Pressure The basis for the 1500 and 500 psig low reactor coolant pressure setpoint for high and low pressure injection initiation is to establish a value which is high enough such that protection is provided for the entire spectrum to break sizes and is far enough below normal operating pressure to prevent spurious initiation.
4.16 KV ES Bus Undervoltage Relays The basis for the degraded grid voltage relay setpoint is to protect the safety related electrical equipment from loss of function in the event of a sustained degraded voltage condition en the offsite power system. The 61mer setting prevents spurious transfer to the onsite source for transient conditions.
The loss of voltage relay and timers detect loss of offsite power condition and initiate tranufer to the onsite source with minimal time delay.
p i
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TABLE 4.1-1 (Continued)
CIIANNEL DESCRIPTION CHECK TEST CALIBRATE REMARKS
- 38. Steam Generator Water Level W NA R
- 39. Turbine Overspeed Trip NA R NA
- 40. Sodium Thiosulfate Tank Level NA NA R
- 41. Sodium Hydroxide Tank Level NA NA R Indicator
- 42. Diesel Generator Protective NA NA R Relaying
- 43. 4 KV ES Bus Undervoltage Relays (Diesel Start)
- a. Degraded Grid NA M(1) R (1) Relay operation will be checked i
by local test pushbuttons
- b. Loss of Voltage NA M(1) R (1) Relay operation will be checked by local test pushbuttons
- 44. Reactor Coolant Pressure S(1) M R (1) When reactor coolant system is Dil Valve Interlock Bistable pressurized above 300 psig or Taves is greater than 200 F.
S - Each Shift T/W - Twice per week R - Each Refueling Period D - Daily B/M - Every 2 months NA - Not Applicable W - Weekly Q - Quarterly B/W - Every two weeks M - Monthly P - Prior to each startup . ;,
if not done previous week
l
~
4;5 EMERGENCY LOADING SEOUENCE AND POWER TRANSFER, EMERGENCY CORE COOLING SYSTEM AND REACTOR BUILOING COOLING SYSTEM PERIODIC TESTING 4.5.1 Emergency Loading Sequence -
. Applicability:
" Applies to periodic testing requirements for safety actuation systems.-
t Obj ective:
T verify that the emergency loading sequence and automatic power transfer is "'
op;rable.
Sprcifications:
4.5.1.1 Sequence and Power Transfer Test
- a. During each refueling interval, a test shall be conducted to demonstrate that the emergency loading sequence and power transfer is operable.
- b. The test will be considered satisfactory if the following pumps and fans have been successfully started and the following valves have completed their travel on preferred power and transferred to the emergency power as evidenced by the control board component operating lights, and either the station computer or pressure / flow indication.
_1 '
-M. U. Pump
-D. H. Pump and D. H. Injection Valves and D. H. Supply Valves
-R. B. Cooling Pump
-R. B. Ventilators
-D. H. Closed Cycle Cooling Pump
-N. S.' Closed Cycle Cooling Pump
-D. H. River Cooling Pump
-N. S. River Cooling Pump
-D. H. and N. S. Pump Area Cooling Fan
-Screen House Area Cooling Fan
-Spray Pump. (Initiated in coincidence with a 2 out of 3 R. B. 30 psig Pressure Test Signal.)
- c. Following successful transfer to the emergency diesel, the diesel generator breaker will be opened to simulate trip of the generator then reclose to verify block load on the reclosure.
~ 4.5.1.2 Sequence Test
- a. At intervals not to exceed 3 months, a test shall be conducted to demon-strate that the emergency loading sequence is operable, this test shall be performed on either preferred power or emergency power.
- b. The test will be considered satisfactory if the pumps and fans listed in 4.5.1.lb have been successfully started and the valves listed in4,5.1.lb have completed their travel as evidenced by the control board component operating lights, and either the station computer or pressure / flow indi-
_ cation.
T Z~B :s 3BT The Emergency loading sequence and automatic power transfer test verifies the operation h.
TT 4-39 is
1 1
- of the pumps associated with the emergency core cooling system and reactor D .:. ~
building cooling system. In addition, it performs a functional verification of~ r -
}~ the loss of voltage relays, the block loading circuits, and the emergency diesel:"
generators. ..
,-~
.: - . ~ 2,- .
REFERENCES _
(1) FSAR Section 7 (2) FSAR Section 1.4-(3) Specification 4.6.lb 4
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4-40
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4.'6 EMERGENCY POWER SYSTEM PERIODIC TESTS
~:. Applicability:
2 -
Applies to periodic testing and surveillance requirement of the emergency ~
'+2 power system.
7_: gg -
~2 Obj ective:
To verify that the emergency power system will respond promptly and properly when required.
Specification:
The following tests and surveillance shall be performed as stated:
4.6.1 Diesel Generators __
- a. Manually-initiated start of the diesel generator, followed by manual synchronization with other power sources and assumption of load by the diesel generator up to the name-plate rating (3000 kw). This test will be conducted every month on each diesel generator. Normal plant operation will not be affected.
- b. Automatically start and loading the emergency diesel generator in accordance with specification 4.5.1.1.b/c including the following:
(1) Verify that the diesel generator starts from ambient condition upon receipt of the ES signal and is ready to load in i 10 seconds.
(2) Verify that the diesel block loads upon simulated loss of offsite power in 1 30 seconds.
(3) The diesel operates with the permanently connected and auto connected load for > 5 minutes.
(4) The diesel engine does not trip when the generator breaker is opened while carrying emergency loads.
(5) The diesel generator block loads and operates for > 5 minutes upon reclosure of the diesel generator breaker.
- c. Each diesel generator shall be given an inspection at least annually in accordance with the manufacturer's recommendations for this class of stand-by service.
4.6.2 Station Batteries
- a. The voltage, specific gravity, and liquid level of each cell will be measured and recorded mcathly.
_a b. The voltage and specific gravity of a pilot cell will be rgg, measured and recorded weekly.
nr hf c. Each time data are recorded, new data shall be compared with iff old to detect signs of abuse or deterioration.
jp 4-46