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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] |
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- .15 FIRE PROTECTION 3.15.1 FIRE PROTECTION INSTRDIENTATICS Applicability: At all times when equipment in that fire detectior. zone is required to be operable. Fire detection instruments located within the Reactor Building are not required to be operable during the performance cf Type A Containment Leakage Rate Test.
Objective: To insure adequate fire detection capability.
Specification:
i 3.18.1.1 The minimum fire detection instrumentation for each fire detection zone shown in Table 3.18-1 shall be operable or action shall be taken as described in specificatior. 3.18.1.2.
l 3.18.1.2 With the number of OPERABLE fire detection instruments less than required by Table 3.18-1.
- a. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, establish a fire watch patrol to inspect the zone with the inoperable instrument (s) at least once
^
per hour unless the instrument (s) is located inside the containment, then inspect the containment at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor containment air temperature at least once per hour at the locations listed in Specification 3.17.3.
- b. Restore the inoperable instrument (s) to OPERABLE status within 14 days or,in lieu of any other report required by specification 6.9.2, prepare and submit a special report to the Commission within the next 30 days outlining the actions taken, the cause of the inoperability and the plans and schedules for restoring the instrument (s) to OPERABLE status.
Bases OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early
_ stages. Prompt detection of fires will reduce the potential for damage to
( safety related equipment and is an integral eler;nt in the overall facility i fire protection program.
In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to operability.
1 0 ' ': 90 (p(r(6 3-5s
TAELE 3.19-1 FIRE DETECTIO:: I :S3D'E::TS Total : umber Instrument Location of Detectors Minimum Instruments Operable Heat Smoke Heat Smoke
- 1. Control Building Elev. 355' :
Control Room 0 8 NA 4 Computer Room 0 6 NA 3 HCV Panel 0 2 NA 1 CC & CR Panel 0 3 NA 2 PC & PCR Panel 0 3 NA 2 PL Panel 0 1 NA 1 ,
- 2. Control Building Elev. 338' 1D 4160 V SWGR 0 1 NA 1 1E 4160 V SWGR 0 1 NA 1 ESAS Cabinets (CB-3C) 0 3 NA 2 Cable Spreading 4 1 2 1
- 3. Control Building Elev. 322' 1P 480 V SWGR 0 1 NA 1 1S 480 V SWGR 0 1 NA 1 Battery Room A 0 1 NA 1 Battery Room B 0 1 NA 1 Inverter Room A 0 1 NA 1 Inverter Room B 0 1 NA 1 Remote Shutdown Panel 0 1 NA 1
- 4. Diesel Generators Diesel A 1 0 1 NA Diesel B 1 0 1 NA
- 5. Screen House 2 0 1 NA
- 6. Fuel Handling Bldg. Elev. 281' Ceneral Cable Area (Zone 1) 0 9 NA 5 Lubricant & Storage Area (Zone 2) 0 3 NA 2 I
3-87
) TABLE 3.18-1 Cont'd i
Instrument Location Total Su-ber of Detecters Minimum Instruments Operable Heat Smoke Heat Smoke
- 7. Auxiliary Building Elev. 261' Decay Heat Removal Pump A (Zone 6) 0 3 NA 2 j Decay Heat Re= oval Pump B (Zone 7) 0 4 NA 2 2 8. Auxiliary Building Elev. 281' Pipe Penetration Area (Zone 1) C 5 NA 3 Makeup & Purification Pumps (Zone 2)0 3 NA 2 Valve Gallery (Zone 3) 0 1 NA 1 j Cable Gallery (Zone 4) 0 4 NA 2 i
4
- 9. Auxiliary Building Elev. 305'
, Decay Heat & Nucl. Service Pumps and MCC 1A, 1B (Zone 5) 0 7 NA 4 Ventilation Room 1 1 1 1 i
l
- 10. Intermediate Building Elev. 295' EF-P-24B Rooms (Zone 1) 0 6 NA 3 Cable Area (Zone 2) 0 2 NA 1 i 1 EF-P-1 Room (Zone 3) 0 2 NA
- Valve Gallery (Zone 4) 0 2 NA 1
- 11. Intermediate Building Elev. 305' Tank Room (Zone 5) 0 1 NA 1
- 12. Reactor Building Elev. 281'
- Exhaust Ducts (Zone 1) 0 3 NA 2 Decay Heat Valve 1 (Zone 2) 0 1 NA 1 l
Decay Heat Valve 2 (Zone 2) 0 1 NA 1
- Cable Tray at Let Down Cooler 3
(Zone 3) 0 1. NA 1 1
- 13. Reactor Building Elev. 305' l Exhaust Ducts (Zone 4) 0 5 NA 3 Purge Exhaust (Zone 5) 0 1 NA 1 i Cable Tray at Personnel Hatch ,
l- (Zone 6) 0 2 NA 1 l
- 14. Reactor Building Elev. 346' D-Ring ld (Zone 7) 0 6 NA 4 1- D-Ring le (Zone 8) 0 6- NA 4
- 15. Reactor _ Building Elev. 382' p- Cable Tray (Zone 9) 0 2 NA 1 i- 16. Reactor Building Elev. 382'
, Elevator Room-(Zone 10) 0 1 NA. 1 i
L 3-87a
- = _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ , , _ . , _ _ _ _ _ _ _ , _ _ . _m_______ mm__ ___,,.____________mm__.m_ _ _ _ _ _ _ , _ , _ _ _ _ _ _
l 3.15.3 DELUCE/ SPRINKLER SYSTEMS I
Applicability: At all times when equipment in the area is required to be operable, pbjective: To assure adequate fire suppression capability.
Specification:
3.18.3.1 The Deluge and/or Sprinkler Systems located in the following areas shall be operable or action shall be taken as described in specification 3.18.3.2.
- a. Diesel Generator and Radiator Rooms
- b. Diesel Generator Combustion Air Intakes
- c. Diesel Generator Cooling Air Intake j d. Control Building Filter (AH-F3A, AH-F3B) Rooms s e. Air Intake Tunnel (3 zones)
- f. Charcoal Filter (AH-F10, AH-Fil) l g. Intake Screen Pump House
- h. Diesel driven fire pump areas
- 1. Control Building at elevation 306'
- j. Control Building Engineered Safeguards - switch gear room at elevation 338' 6"
- k. Fuel Handling Building at elevation 281' 0"
- 1. Auxiliary Building containment penetration area at elevation 4 281' 0" 3.18.3.2 With any of the above deluge and/or sprinkler systems in any room or zone inoperable:
- a. Establish a once-per-hour fire patrol with backup fire suppression equipment for the unprotected area (s), within one hour except that no fire watch is required in the air intake tunnel.
- b. Restore the system to OPERABLE status within 14 days or,in lieu of any other report required by specification 6.9.2, prepare and submit a Special Report to the Commission within the next 30 days outlining the actions taken, the cause of inoperability and the plans and schedule for restoring the system to OPERABLE i- status.
d 3-89 -
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- . - , ,- ,-,,-,.w ,e , ww.,.m.-,,m,%,. ,, ,-,w.c,.r. .,-~w #.,. .nrw-m-.m-w.--,. --,----r ---..cm,-- , y--,% u.---, - -
3.16.5 HALON SYSTEMS Applicability: The Air Intake Tunnel Halon System shall be functional at all times except when the Control Building ventilation is on recirculation. The Computer Room Halon System shall be functional at all times except when the halon-protected computer equipment in the Control Room is not energized.
Objective: To assure adequate fire suppression capability.
S?pcification:
3.18.5.la. The Halon System shall be operable having at least 90% of full charge pressure and 95% full charge weight or action shall be taken as described in specification 3.18.1.2.
3.18.5.lb. The Air Intake Tunnel Halon System may be removed from service for periods up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> when the air tunnel must be occupied for testing or maintenance.
3.18.5.2 If the Halon system in any zone is inoperable:
- a. Establish a continuous fire watch with backup fire suppression equipment for the Computer Room Halon System.
- b. Restore the system to OPERABLE status within 14 days or,in lieu of any other report required by Specification l
6.9.2, prepare and submit a Special Report to the Commission l
within the next 30 days outlining the action taken, the
! cause of the inoperability and the plans and schedule
- l. for restoring the system to operable status, i
i i
I N
+
a 3-91 i
Table 3.l?-2 HOSE STA!!O':S Internediate Building
- 1. Fire hose near northeast piping chamber stairway ct elev. 309' (2 stations)
Auniliarv Buildint
- 1. -Fire Hose near stairway at northeast end of building near valve room at elev. 285'.
- 2. Fire hose near waste evaporator condensate tank and auxiliary steam
] condensate return unit elev. 285'.
- 3. Fire hose near stairway at northeast end of auxiliary building and engineered safeguards control center, alev. 309'.
i
- 4. Fire hose near radioactive waste control center, elev. 309'.
l
- 5. Fire hose in heat exchanger vault, elev. 386'. i Turbine Building
. 1. Fire hose along vest side of building near 12th stage extraction feed-4 water heaters, elev. 326'.
- 2. Fire hose along west side of building near 10th stage extraction feed- i water heaters, elev. 359'.
i i Fuel Handling Building
- 1. Fire hose along west wall north end, elev. 326'.
- 2. Fire hose along west wall south end, elev. 326'.
, 3. Fire hose along west wall north end, elev. 342'.
- 4. Fire hose along west wall north end, elev. 342'.
, 5. Fire hose along cast wall north end, elev. 359'.
- 6. Fire hose along cast wall south end, elev. 359'.
- 7. Fire hose middle west wall, elev. 384'.
Reactor Building
- 1. Fire hose near personnel access hatch, elev. 312'.
- 2. Fire hose near southeast stairway, elev. 285'.
- 3. Fire hose near southeast stairway, elev. 350'.
- 4. Fire hose at top east D-Ring, elev. 369'.
- 5. Fire hose at door to D-Ring, elev. 285'.
i
- 6. Fire hose near west stairway, elev. 285'.
- 7. Fire hose near equipment access hatch, elev. 312'.
- 8. Fire hose near west stairway, elev. 350'.
- 9. Fire hose at top west D-Ring, elev. 369'.
a i
3-93
~. ._. . - . .
3.1E.7 FIRE BARP,IER PENETRATIO::5 i Applicab ilit:, : All fire barrier penetration seals (including cable and pipe penetration barriers, fire doors and fire dampers) in fire zone boundaries protecting safety related areas shall be functional at all times when equipment on either side of the j barrier is required to be operable.
Objective: To assure the effectiveness of fire barriers.
j Specification:
3.18.7.1 All fire barrier penetration seals protecting safety related areas shall be functional or action shall be taken as described
, it 3.18.7.2.
3.16.7.2a. With one or more of the above required fire barrier penetration
' seals non-functional, establish a fire patrol to inspect at least one side of the affected penetration once per hour during refueling shutdown, cold shutdown, heatup/cooldown, and hot shutdown. At all other times a continuous fire watch shall be posted on one side of tha affected penetration within one hour.
3.18.7.2b. Restore the penetration seal to an OPERABLE status with 14 days or, in lieu of any other report required by Specification 6.9.2, prepare and submit a Special Report to the Commission within the next 30 days outlining the action to be taken, the cause of the inoperability and the plans and schedule for restarting
- the system to an OPERABLE status.
Bases: The functional integrity of the fire barrier penetration seals ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment. The fire barrier penetration seals are a passive element in the facility fire protection program and are subject to periodic inspections.
During periods of time when the seals are not functional, a roving or continuous fire watch is required to be maintained
- in the vicinity of the affected seal until the seal is restored
' to functional status as described in specifcation 3.18.7.2.
h E*
I I
3-94
'.: 2 F!RE PROTECTIC:: SYSTEMS
.19.1 FIRE PROTECTIO:: I! STEDE::TS A nlicability: Instruments listed in Table 3.1S-1 Obj e ct ive : To insure operability of fire detettien instruments.
Snecification:
4.18.1.1 Each of the fire detection instrum +- . are, in Table 3.18-1 which are accessible during plant cr'entico is.ll be demonstrated operable at least once per 6 cent t b* oer::crince of a Channel Functional Test. Instruments linte on inole 3.18-1 which are not accessible during plant operation shall be demonstrated operable by the performance of a Channel Functional Test during each cold shutdown exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.
4.18.1.2 The non-supervised circuits b. tween the instrument and the control room shall be demonstrated operable at least once per month for the instruments listed in Table 3.18-1.
4.18.1.3 The NFPA Standard 72 D supervised circuits associated with the detector alar =s for Table 3.18-1 instrunents shall be demonstrated operable at least once per 6 months.
4-72
.l?.3 H.ALO" SYSTO:S A-'11:2bilit:: Halon Systems described in Specificarica 3.15.5.
Obiective: To insure system operabilit:. .
E ecification:
'.15.5.1 The Halon System shall be verified cperable:
- a. At least once per 6 conths by verifying each Halon storage tank weight and pressure.
- b. At least once per 18 months by:
- 1. Verifying that the systen, including associated ventilation da pers, actuates automatically to a simulated test signal.
- 2. Functional test of the ultraviolet detectors, test ,
of the pressure wave detectors, and replacement of the explosives actuators for the Air Intake Tunnel Halon System. l 4-75
4.1s.7 FIRE BARRIER PENETRATIONS Applicability: All fire barrier penetration seals (including cable and pipe penetration barriers, fire doors and fire dampers) ;
in fire zone boundaries protecting safety related areas shall ;
be functional at all times when ecuipment either side of ;
the barrier is required to be operable. !
Objective: To assure that the effectiveness of fire barriers protecting safety-related areas is maintained.
Specification:
4.18.7.1 Fire barrier penetration seals and fire da=pers shall be verified to be functional by a visual inspection:
- a. At least once each refueling interval; and
- b. Prior to declaring a fire barrier penetration seal or fire damper functional following repairs, maintenance, or initial installation.
4.18.7.2 Fire doors shall be verified to- be functional by a visual inspection:
- a. At least weekly for doors that are locked. closed to verify that they are locked closed and free cf obstructions.
- b. At least daily for doors held open by. automatic release mechanisms to verify that the doorway is free of obstructions.
- c. At least daily for doors neither locked nor supervised to verify that they are in a closed position.
- d. Prior to declaring a fire door functional following repairs, maintenance, or initial installation.
4-76a
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