Tech Spec Change Request 60 Supporting Licensee Request to Change App a of License DPR-50.Change Concerns Emergency Power Systems Per NRC 770603 Request for Comparison of Current Design W/Nrc Positions.Certificate of Svc EnclML19260A135 |
Person / Time |
---|
Site: |
Three Mile Island ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
---|
Issue date: |
08/19/1977 |
---|
From: |
Arnold R METROPOLITAN EDISON CO. |
---|
To: |
|
---|
Shared Package |
---|
ML19260A133 |
List: |
---|
References |
---|
GQL-1145, NUDOCS 7910290750 |
Download: ML19260A135 (11) |
|
|
---|
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
'
METROPOLITMi EDISCII COMPANY JERSEY CENTRAL PO'n'ER & LIGHT COMPMIY AND PENNSYLVMIIA ELECTRIC COMPMIY
, THREE MILE ISLAND NUCLEAR STATION UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Scecification Change Recuest No. 60 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating License No. DPR-50 for Three Mile Island :Iuclear Station Unit 1. As a part of this request, proposed replacement pages for Appendix A are also included.
METROPOLITMI EDISON COMPANY f .
By! /
/ Vice President
/
J Sworn and subscribed to me this $! day of , 1977 Notary Public e.gTARY D'j N .
Reacmg. Sera? O r~v i My Comm ssien baats
1480 165 3 910 2907f0
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMiISSION IN THE MATTER OF DOCKIT NO. 50-289 LICENSE NO. DFR-50 METROPOLITAN EDISON COMPANY This is to certify that a copy of Technical Specification Change Request No. 60 t,e Appendix A of the Operating License for Three Mile Island Nuclear Station i! nit 1, has, en the date given belov, bee' filed with the U. S. Nuclear Regulatory Cc: mission and been served on the chief executives of Lcndonderry Township, Dauphin County, Pennsylvania and Dauphin County, Pennsylvania by deposit in the United States mail, addressed as follows:
Mr. Weldon B. Arehart Mr. Harry B. Reese, Jr.
Board of Supervisors of Board of County Commissioners Londenderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Court House Middletown, Pennsylvania 17057 Harrisburg, Pennsylvania 17120 METROPOLI"'AN EDISON CCIGANY l
By , ' / h /
'Vi'ce President Dated: Aum:st 10 lo77 1480 166
Three Mile Island Nuclear Station, Unit 1 Operating License No. DFB-50 Docket No. 50-289 Technical Specifiestion Change Recuest No. 60 The licensee requests that the attached revised pages replace pages 3-32, 3-37, h-h6, and h-h7 of the existing Technical Specifications, Appendix A.
Reasons Por Change Reauest -
This change request is to comply with the Co==ission's June 3,1977 letter requesting a comparison of our current design of the emergency power systems at TMI-l with the Staff Positions.
Safety Analysis Justifying Chance Position 1:
As requested in your letter of June 3,197', below is our analysis to show TMI-l has eqaivalent capabilities and protective fes'. ares to the Staff Position on second level protection.
The Cen=ission required a second level of voltage protection fcr the onsite power system be provided in order to prevent a sustained degradation of the offsite power syste='s voltage from causing the failure of redundant safety-related electrical equipment.
Metropolitan Idison has determined that this requirement is not necessary for TMI-1 based on the following:
The Class 1E electrical systes at TMI-l has undervoltage trip relaying protection on all safety-related electrical buses (the h160 volt E.S.
buses ID and 1E, the h80 volt buses IP, 1R, 1S and 1T). The undervoltage trip setpoints are:
Bus Setnoints b kv. 3534 volts h80 v. h10 volts The original and present basis for the undervoltage trip setpoints is to maintain the bus voltage above the =inimus motor starting voltage for safety equipment. These setpoints were deter =ined after reviewing the various bus voltage levels and the required mini =u= motor starting voltage. The 353h volt trip setting on the h kv bus corresponds to a 206 kv value for the off-site power system. Therefore, any degraded voltage level below a 206 kv grid vo]tage vould result in the automatic transfer to the onsite power source.
1480 167
The Cc==ission vas concerned with the operation of electrical safety equipment between this trip value and the nominal grid voltage level of 232 kv. This second level of undervoltage relaying would be set somewhere in this range, such that, if the grid voltage vould degrade to a value below nominal (232 kv) but above the existing undervoltage, (206 kv), after a preset time period, the second level relay would be activated and automatically transfer to the on-site power source. This is not necessary at TMI-1 because the safety-related electrical equipment was designed to operate within this degraded condition.
Tects conducted by IMI-l personnel on starters /contactors supplying power to three phase h80 v. ES equipment have confirmed that they operate satisfactorily to a voltage of 3Sh volts. The h kv equipment (E.S. motors) are controlled by circuitry utilizing 125 V.D.C. and therefore, would not be affected by any sustained degraded voltage level.
An analysis of plant operation and equipment failure during a degraded grid voltage was performed. This analysis pointed out that no proble=s von'.d be encountered during a degraded grid voltage condition, and the degradation of grid voltage to that corresponding to the undervoltage trip setpoint was an extre=ely unlikely situation. As a continuation of this analysis, a study was done to deter =ine the probability of occurrence of a degraded grid voltage below 215 kv. The probability of the contingencies that could result in this condition are in the 10 7 to 10 10 range. Therefore, it is concluded that no modifications to the Class lE distribution system at TMI-l is required.
Position 2:
The current undervoltage relaying scheme for all E.S. buses have the Cotsissiun'c t position incorporated. The E.S. buses undervoltage relays initiate the ? cad shedding. As soca as the diesel generator breaker closes in, an auxiliary contact opens preventing the undervoltage relaying from initiating the load shedding. If the diesel generator breaker should trip, the auxiliary contact vill close, reinstating the load shedding feature. Therefore, no modifications are necessary for Position 2.
~
Position 3:
TMI-l surveillance procedures currently perform portions of the Commission requirements. Metropolitan Edison vill rewrite the surveillance procedure which delineates this testing to fulfill the requirements of demonstrating the diesel generator operable while simulating a loss of off-site power in conjunction with a safe +y injection actuation test signal.
This vill verify that on interruption of the onsite source (diesel generator) the loa 7.4 are shed from the emergency buses, in accordance with design requirenents and that subsequent loading of the onsite source is through the load sequencer.
This vill be accomplished by:
1480 168
- 1. Opening the offsite power source breaker to.the emergency bus si=ulating loss of offsite power. It vill be verified that the proper loads are shed from the emergency buses.
- 2. Concurrently, an ES signal vill be activated. It will then be verified that the diesel generator starts and the emergency buses are loaded in their proper sequence. .
3 After operating for 5 minutes, the diesel generator breaker vill be tripped, verifying that the leads are again shed,
- b. The diesel generator breaker vill again close. There vill be verification that the auto-connected e=ergency loads are energized through the load sequencer and the diesel operates loaded for 5 minutes.
r 1480 169 4
TABLE 3.5-1 Continued .
INSTRUMENTS OPERATION CONDITIONS Functional Unit (A) (B) (C)
Engineered Safeguards Minimum Operable Minimum Degree of Operator Action if Conditions Analog Channels Hedundancy of Column A and B cannot be met (a)
- 3. Reactor Building Isolation.
and Reactor Building Cooling System g
- a. Reactor Building 14 puig Instrument Channel 2 1 llot Shutdown
- b. Manual Pushbutton 2 1 llot Shutdown
(") If minimum conditions are not met within 2fs hours, the unit shall then be placed in a cold shutdown condition.
(b) Also initiates Low Pressure injection.
14 . Reactor Building Spray System
- a. Henetor Building 30 psig Instrument Channel 2(b) 1 !!ot Shutdown
- b. Spray Pump Manual '
Switches (c) 2 1 Ilot Shutdown (3) If minimum conditions are not met within 214 hours0.00248 days <br />0.0594 hours <br />3.53836e-4 weeks <br />8.1427e-5 months <br />, the unit shall then be placed in a cold shutdown condition.
C (b) Two out of three switches in each actuation channel operable.
(c) Spray valves opened by manual pushbutton listed in item 3 above.
O
TABLE 3.5-1 Continued INSTHUMENTS OPEllATION CONDITIONS Functional Uiit (A) (B) (C) 5 4.16 Kv Emergency Buy Undervoltage Relays (d) 2/ Bus - 1/ Bus (e)
(d) Total no. of channels - 3/ Bus g (e) With the number of Operable Channels one less than the total number of channels operation may proceed until performance of the next required Channel Functional Test provided the inoperable channel is placed in the trip condition within 2h hours.
Y M
P O
M CD CD
353 ENGINEERED SAFEGUARDS PROTECTI0h SYSTEM ACTUATION SETPOINTS Apulicability 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 engineered safeguards protection system actuation setpoints and permissible bypasses shall be as follows:
Initiating Sienal Function Setnoint High Beac+ Building Reactor Building Spray 1 30 psig Pressure (o1 High-Pressure Injection i h psig Low-Pressure Injection i k psig Start Reactor Building Cooling & Reactor Building Isolation i h psig Low Reactor Coolant High Pressure Injection >150 2) and E500 3) p31g System Pressure Lov Pressure Injection >150Q(2) and E500(3)psig h.16 kv E.S. Buses Switch to Onsite Power Undervoltage Source and Load Shedding 353h volts (h)
(Loss of Offsite Power or Voltage) egraded 5
(1) May be bypassed for reactor building leak rate test.
(2) May be bypassed below 1650 psig and is autome.tically reinstated above 1650 psig.
(3) May be bypassed belov 900 psig and is automatically reinstated above 900 psig.
( ) Allowable values - 353h is the nominal setpoint. 3h23 is the minimum allowed setting.
(3) The undervoltage relays (0.E. 12AV53K1A) have characteristic time -
Voltage Curves, when the voltage is reduced to 2995v, the relay will trip in
<T.15 sec.
1480 172 3-37
Bases High Reactor Building Pressure The baais for the 30 psig and h 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.
Lov 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 of break sizes and is far enough below nor=al operating pressure to prevent spurious initiation.
t 1480 173 3-37a
h.6 DERGENCY POWER SYSTDI PERIODIC TESTS Apolicability Applies to periodic testing and surveillance requirement of the e=ergency power system.
Objective To verify that the emergency power system vill respond pro =ptly and properly when required. -
Specification The following tests and surveillance shall te performed as stated:
h.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 nameplate rating (3000 kv). This test vill be conducted every month on each diesel generator. Normal plant operation vill not be affected.
- b. Automatic start of each diesel generator and restoration to operation of particular vital equipment, initiated by an actual loss of normal a-c station service power supply together with a simulated engineered safeguards actuation signal. This test vill be conducted during reactor shutdown for refueling to assure that the diesel-generator vill start assuming load in ten seconds and assume the load of all safeguards equipment listed in 4.51.lb within 60 seconds after the initial starting signal.
This test vill be conducted to verify the followind -
(1) Upon loss of normal a-c station service power supply the de-energization of the emergency buses and load shedding occurs.
(2) The diesel starts from ambient conditions on the auto-start signal, energizes the emergency buses with permanently connected loads, energizes the auto-connected emergency loads through the load sequencer and operates for 5 minutes.
(3) On interruption of the onsite source, the loads are shed from the emergency buses in accordance with design requirements.
That on reconnection with the onsite source, the emergency buses are energized with permanently connected loads, the auto-connected emergency loads are energized through the load sequencer and the diesel generator operates for 5 minutes.
1480 174 h-L6
- 2. Each diesel generator shall be given an inspection at least annually in accordance with the manufacturer's reco==endations for this class of stand-by service.
h.6.2 Station Batteries
- a. The voltage, specific gravity, and liquid level of each cell' vill be =easured and recorded monthly.
- b. The voltage and specific gravity of a pilot cell vill be =easured and recorded weekly. .
- c. Each ti=e data are recorded, new data shall be compared with old to detect signs of abuse or deterioration.
- d. The battery will be subjected to a load test at a frequency not to exceed refueling periods. The battery voltage as a function of time vill be monitored to establish that the battery performs as expected during this load test.
Bases The tests specified are designed to de=onstrate that one diesel-generator vill provide power for operation of safeguards equipment. They also assure that the e=crgency generator control syste= and the control syste=s for the safeguards equipment vill function automatically in the event of a loss of normal a-c station service power or upon the receipt of an engineered safeguards actuation signal. The testing frequency specified is intended to identify and permit correction of any =echanical or electrical deficiency before it can result in a syste= failure. The fuel oil supply, starting circuits, and controls are continuously monitored and any faults are alarmed and indicated. An abnormal condition in these systems would be signaled without having to place the diesel generators on test.
Precipitous failure of the station battery is extremely unlikely. The surveillance specified is that thich has been de=onstrated over the years to provide an indication of a cell becoming unserviceable long before it fails.
R EFERENCE (1) FSAP, Section 8.2 1480 175 h h7