Emergency Operating Spec 69-1001168-01, Loss of Reactor Coolant/Rcs Pressure.ML20024C771 |
Person / Time |
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Site: |
Three Mile Island |
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Issue date: |
05/15/1978 |
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From: |
Hallman D, Tracy Scott, Spangler W BABCOCK & WILCOX CO. |
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To: |
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References |
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TASK-*, TASK-02, TASK-2, TASK-GB 620-0024, 620-24, 69-1001168-01, 69-1001168-1, EOS-0162, EOS-162, GPU-0543, GPU-543, NUDOCS 8307130267 |
Download: ML20024C771 (11) |
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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] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20210S7691999-08-12012 August 1999 Rev 10 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20206R6531999-05-13013 May 1999 Rev 39 to TMI Modified Amended Physical Security Plan ML20204B5291999-03-12012 March 1999 Rev 9 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual (Edcm) 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 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 ML20202B2061998-01-30030 January 1998 Rev 7,Temporary Change Notice 1-98-0013 to 6610-PLN-4200.02, Edcm ML20217M7251997-06-22022 June 1997 Rev 16 to Procedure 6610-PLN-4200.01, Odcm ML20138B4641996-05-0606 May 1996 Rev 14 to Procedure 6610-PLN-4200.01, Odcm ML20092M1941995-09-21021 September 1995 TMI-1 Pump & Valve IST Program ML20084N3541995-03-24024 March 1995 Rev 11 to 6610-PLN-4200.01, Odcm ML20137B5371995-03-22022 March 1995 Rev 11 to 6610-PLN-4200.01, Odcm ML20081C1281995-03-0808 March 1995 Svc Water Sys Operational Performance Insp Self-Assessment Plan ML20073F9411994-09-26026 September 1994 Revised Plan for Long Range Planning Program for TMI Nuclear Station Unit 1 ML20059M2301993-11-12012 November 1993 Rev 7 to 6610-PLN-4200.01, Odcm ML20057B3781993-09-0202 September 1993 Rev 6 of Solid Waste Staging Facility Sys Description ML20127A2181992-10-15015 October 1992 Rev 1 to 6615-PLN-4520.01, REMP - Plan ML20127A2301992-08-11011 August 1992 Rev 30 to Emergency Procedure 1202-32, Flood ML20090D4031991-10-0404 October 1991 Rev 16 to Waste Solidification Process Control Program ML20082M2991991-08-29029 August 1991 Rev 8 to Operating Procedure 1104-28I, Waste Solidification Process Control Program ML20127A1511991-07-0808 July 1991 Rev 4 to 1000-PLN-4010.01, Gpu Nuclear Corp Radiation Protection Plan ML20082M2951991-06-27027 June 1991 Rev 14 to Operating Procedure 1104-28I, Waste Sodification Process Control Program ML20198B9741991-06-17017 June 1991 Rev 2 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20070L3331991-03-15015 March 1991 Rev 1 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20070U9241991-03-0404 March 1991 Rev 0 to 6610-PLN-4200.01, Odcm ML20059H9031990-09-0707 September 1990 Rev 0 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20059C7931990-08-23023 August 1990 Rev 5 to Sys Description 3184-007, Solid Waste Staging Facility ML19351A4371989-11-30030 November 1989 Rev 9 to 9110.PLN-4200.02, Emergency Dose Calculation Manual. ML20248D4071989-09-27027 September 1989 Rev 8 to 9100-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20245K1211989-08-0202 August 1989 Rev 4 to SD 3184-007, Div Sys Description for Solid Waste Staging Facility ML20244C2961989-06-30030 June 1989 Rev 1 to Sys Description SD 3510-013, Div Sys Description for Reactor Bldg Sump Recirculation Sys ML20246M7931989-03-0909 March 1989 Rev 11 to Operating Procedure 1104-28I, Waste Solidification Process Control Program ML20154C7191988-06-0303 June 1988 Rev 10 to Operating Procedure 1104-28I, Waste Solidification Process Control Program ML20154Q6771988-05-27027 May 1988 Recovery Operations Plan ML20236M1621987-11-0909 November 1987 Radiological Environ Monitoring Program for TMI-1 ML20236M4281987-10-19019 October 1987 Vols 1 & 2 of 1987 TMI Annual Exercise Scenario ML20147F9331987-08-25025 August 1987 Rev 3 to Procedure 1000-ADM-1291.01, Procedure for Nuclear Safety & Environ Impact Review & Approval of Documents ML20238C6391987-08-21021 August 1987 Rev 2 to Design Criteria 3255-86-0004, TMI-2 Design Criteria for Pressurizer Defueling Sys. W/One Oversize Figure ML20236K9601987-07-24024 July 1987 Rev 3 to 3184-007, Solid Waste Staging Facility Sys Description ML20215M3261987-06-19019 June 1987 Rev 16 to Organization Plan ML20215H0301987-06-15015 June 1987 Revised Emergency Plan Implementing Procedures,Including Rev 2 to 6415-IMP-1300.06. Addl Assistance & Notification & Rev 1 to 6415-IMP-1300.16, Contaminated Injuries. Updated Table of Contents Encl ML20215M1291987-03-20020 March 1987 Corrected NCRP Commentary 4, Guidelines for Release of Waste - Water from Nuclear Facilities W/Special Ref to Public Health Significance of Proposed Release of Treated Waste Waters at Tmi ML20214S4481986-12-31031 December 1986 TMI-2 Cleanup Program,Post-Defueling Monitoring Storage ML20212N6711986-12-17017 December 1986 Rev 2 to Test Procedure SC-1302-323 Isolator - Fault Testing. Test Results Encl ML20212H7821986-10-10010 October 1986 Rev 7 to Operating Procedure 1104-28I, Waste Solidification Process Control Program ML20206U7611986-09-26026 September 1986 Rev 1 to SD 3520-010, Div Sys Description for Processed Water Storage & Recycled Sys ML20205E7891986-08-0707 August 1986 Rev 0-03 to Corporate Procedure 1000-ADM-1291.01, Safety Review & Approval Procedure ML20211Q8251986-06-0202 June 1986 Rev 4 to SDD-TI-614, Div I Sys Design Description for TMI-1 Remote Shutdown Sys ML20203N1761986-04-29029 April 1986 Rev 4 to Div Sys Description for Auxiliary Bldg Emergency Liquid Cleanup Sys (Epicor II) 1999-08-12
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TECHNICAL. DOCUMENT F
i ENERGBCY OPERATING SPECIFICATION
. 69 - 1001168 - 01 Doc. ID - Serial No., Revision No.
for LOSS OF REACTOR COOLAhT/ REACTOR COOLANT SYS17.H PRESSURE EOS 0162 m-T26800 CONFiii.:hiIAl PAGE 1 COUNSEL ONLY
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. TABLE OF CONTENTS / EFFECTIVE PAGE LIST 68-2001168-01' i
! stc7 ton Titti nst one. no.
l 1. 0 , PURPOSE 4 69-1001168-01 2.0 SYMPTOMS 4 69-1001168-01 5 69-1001168-01 j 3.0 AUTOMATIC ACTION 5 69-1001168-01
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! 4.0 IMEDIATE OPERATOR ACTION 5 69-1001168-01 5-1 69-1001168-01 5.0 SUB5EQUENT OPERATOR ACTION 6 69-1001168-01
. 7 69-1001168-01 6.0 RE."RENCES . 7 69-1001168-C1 7-1 69-1001168-01 I
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COUNSEL ONLY DATE: 2 24-78 PAGE 3
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69 1001168-01
- TECHNICAL DOCUMENT i a ;
4 1
1.0 PURPCSE
.I , s
.i This specification describ.s the recanaended actions in the .vant j of an abnormal. decrease in Reactor Coolant System (RC3) pressure
- or pressurizer level. The symptoms and actions are considered according to the severity of the accident.
1.1 Small leak - within the capability of one makeup pump to maintain
. RCS prassure.
' ~
1.2 Intermediate leak - wi.hin the capability of the High Pressure Injection 017I) System to maintain RCS pressure.
j 1.3- Large leak - exceeds the capability of the HPI system to maintain
- RCS pressure.
2.0 SYMPTOMS 2.1 Small Leak 2.1.1 Hakeup rank inventery decreasing during steady s. ate operation grea:e than the normal rate but less than the capacity of one makeup pump. ,
2.1.2 Makeup flow increasing with stable T,y,.
[ :
! 2.1.2 Possible.radistics alar = in reae:cr building (R!) or other locatics that could indicate a RCS leak.
2.1J Possible R8 sump level increase. '
i 2.1.5 Greater than normal leakage during the routine performance of Reference 6.2.
2.2 Intermediate Leak 2.2.1 Pressurizer level and RCS pressure decreasing with stable T,y, and makeup flow increasing to an4==.
2.2.2 Makeup tank inventory decreasing greater than capacity of one
- askeup pump but less than capacity of HPI system.
t .
I 2.2.3 Radiation alarm in R3 or other location that could indicate a I RCS leak.
2.2.4 Increasing level in RB sump with possible high level alars.
2.2.5 Possible increase in RB pressure and temperature.
2.2.6 Possible makeup flow high alarm. bb 7, COUNSE!.OF 2 24 78 PAGE 4
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"'2 **l TECHNICAL DOCUMENT j 2.3 tarre Leak
! 2.3.1 Ra'id p decrease in press u i:er level and RCS press w e.
. - 2.3.2 Reactor and tubine trips accompanied by Engineered Safety Featwes Actuation System (ESFAS) actuation.
2.3.3 High radia-ion ala:n in R5 or other location that could indicate a RCS leak.
, 2.3.4 High reactor bu.ilding presswe .and temperature. -
^ ,! 2.3.5 High RB sump level with a high level ala:n. (01) 3.0 AUTOMATIC ACTION 3.1 Small Leak
, . Flow increases through pressuri:e level con =ol valve.
3.2 Intermediate Leak i
3.2.1 Flow increases through pressw i:e level control valve. (01)
- 3.2.2 Possible reactor trip (Low RCS pressure or low presswi:e level). (01) 3.2.3 Possible tu bine trip. (01) 3.2.4 Possible ESFAS actuation (Low RCS presswe). (01) 3.3 Larre Leak .
3.3.1 Reactor trip (Low RCS presswa or low pressuriser level)
( Turbine W.y
- 3.3.2 3.3.3 ESFAS Actuation (Low RCS presswe) f 4.0 IMMEDIATE CPERATOR ACTION i 4.1 Small Leak 4.1.1 Isolate letdown 4.1.2 Attempt to locate and isolate d e leak C0hFD&lTIAL T25804 0UNSEl. ONLY 2-24-78 PAGE 5 DATE:
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.mau ao-se semenaron owmen 69-1001168-01 TECHNICAL DOCUMENT l 4.2 Intermediate Leak 4.2.1 Tr'ip reactor and assure turbine trips 4.2.2 Isolate letdown
- 4. 2. 3 Initia o HPI 4.3 Large Leak 4.3.1 Verify automatic action has taken place.
4.3.2 Deleted. (01) 4.3.3 Trip all RC pumps if adequate suction pressure cannot be maintained. (01)
P CONFIDENT!AL T2see COUNSEL ONLY DATE: 2-24-78 PAG 3 5-1
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- TECHNICAL DOCUMENT 68-1"116s-01 t
5.0 SUBSEQUENT OPERATOR ACTION h
, If a steam generator (SG) tube leak is suspected as the casualty (radiation in secondary steam system or other indication) when RC (01) pressure has been reduced below secondary safety valve setpoint, ischte the affected SG and use r===hMg SG for cooldown as reqi. ired. Additional measures to reduce seconda.y system contami-
. natian and to reduce or prevent the release of radioactive elements to the atmosphers should be taken.
5.1 Small Leak (01) 9 3.1.1 If leakage cannot be redu:ed to less than the limits of Reference 6.1 follow the actions required by Reference 6.1.
5.1.2 Maintain makeup tank level per Reference 6.3.
. 5.1.3 Te==inate RB purge if i= progress.
l 3.2 Inter:sediate Leak (01)
, 5.2.1 Operate third makeup pump to aid HPI as needed to maintain pressuri:er level.
i NOTE: It will be necessa.y to take water from the makeup tank periodically to prevent overfilling due to the return flow from RC pump seals.
5.2.2 Reduce the number of operatin2 RC pumps to one in each loop.
5.2.3 Te==inate R8 purge if in progress.
5.2.4 Cooldown the plant to cold shutdown.
5.2.5 Attempt to find and isolate the leak.
5.2.6 Prior to rizining out of water for HPI, or if HPI flow is below 900 GPM and pressure is above the ==*== allowed for the Decay Heat Removal System (DHRS), use the DHR pump to transfer water from the RS sump to HPI per References 6.3 and 6.8.
5.2.7 When RCS pressure allows, use DHR system in the RB st.. p recirculation mode per Reference 6.8.
NOTE: Insure refill and repressurisation of the RCS does not cause dead head of DHR pumps.
nssos ?NFIDENTTAT 3]Ur.' p m n y PAGE 6 DATE: 2-2a.73
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3 =wca a co-se se=sweOX .omsom I TECHNICAL DOCUMENT 69-100116s-01 9
! 5.3 Large Leak (01)
- 5. 3.1 Verify proper operation of ESFAS, including initiation of low pressure injection when the setpoint is reached per Reference 6.4.
?
5.3.2 Cooldown the plant in as near normal a manner as possible per Reference 6.6.
5.3.3 While still using water from the borated water storage tank (BWST),
assure adequate fluid supply to the high or low press =e injection -
systens will be available from the R1 sump prior to the BWST low level alarm per Reference 6.8.
/
5.3.4 Esablish normal or RB sump recirculation decay heat removal as .
appropriate when the SW57 low level alarm setpoint is resched per Reference 6.g.
5.3.5 Sample RR hydrogen and initiate hydrogen removal procedures if required.
5.3.6 Secure 157AS components as necessary.
- NOTE: HPI may only be secured if the following conditions are .
met.
~.
- (1) The low pressure injection system is in operation and the' flow is equal to or greater than that required to reseve the decay heat load or (2) HPI has been in operation for greater thsn 10 minutes, the pressurizer level is above the normal operating level and the system pressure is at least 50 PSIG (plus instrument error) above saturation pressure for the reactor outlet water temperature.
5.3. 7 Initiate long term cooling with the decay heat removal system per References 6.4 and 6.8.
6.0 REFERENCE 5
, 6 .1 Plant Technical Specifications .
6.2 RCS Leak Detection, 05 501 (01) 6.3 Makeup and Purification System Operation, 05 3521 nas<n CONFIDENTIAL COUNSEL ONLY DA71: 2*2'*78 PAGE
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. j 6.4 - ESFAS Operation, 05 2621 1
,.l 6.5 Reactor Trip, 505 0172 6.6 Plant Shutdown, OS 0135 6.7 Plant Limits and Precautions, OS 1101 6.8 Decay Heat Removal System Operation, OS 3621 I
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nssos CONFiDENTIA!.
COUNSEL ONL,Y DATE: 2-24-78 PAGE 7-1
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