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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20212C0961999-09-16016 September 1999 Proposed ITS & Bases Changes Strikeout & Shadowed Text & Revision Bar Format,Increasing Licensed Capacity for Spent Fuel Assembly Storage in SFP & Revising Configuration for Storage of Fresh Fuel ML20211L1011999-09-0202 September 1999 Proposed Tech Specs Re Once Though SG Tube Surveillance Program,Alternate Repair Criteria (ARC) for Axial Tube End Crack (Tec) Indications ML20209D2971999-07-0808 July 1999 Proposed Tech Specs,Changing ITS for CREVS & VFTP & Correcting Typo in ITS Section 5.6.2.12 ML20195B8091999-05-26026 May 1999 Proposed Tech Specs,Revising ITS Bases That Will Update NRC Copies of ITS ML20195B7081999-05-17017 May 1999 Proposed ITS Section 3.3.8, EDG Lops, SR 3.3.8.1,revising Note for Surveillance & Deleting Note for Frequency ML20206S7691999-05-12012 May 1999 Proposed Improved Tech Specs Pages 3.4-21 Through 3.4-21D ML20206N1401999-05-10010 May 1999 Proposed ITS Administrative Controls Section 5.8, High Radiation Area ML20206M0961999-05-0707 May 1999 Proposed Tech Specs,Revising Wording for SR 3.5.2.5 to Be More Consistent with NUREG-1430,Rev 1 & Clarifying Process of Valve Position Verification ML20206H6541999-05-0505 May 1999 Proposed Tech Specs,Proposing Alternate Repair Criteria for Axial Tube End crack-like Indications in Upper & Lower Tubesheets of CR-3 OTSGs ML20204D9211999-03-18018 March 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Tube Repair Roll Process ML20202E6551999-01-27027 January 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Insp Interval Extension ML20196D6761998-11-30030 November 1998 Proposed Tech Specs LCO 3.9.3,allowing Both Doors in Personnel Air Locks & Single Door in Oeh to Be Open During Refueling Operations ML20195K4551998-11-24024 November 1998 Proposed Tech Specs,Installing diesel-driven EFW Pump to Remove Interim ITS & Provide Resolution to EDG Capacity Limitations ML20195K0031998-11-23023 November 1998 Proposed Tech Specs Re LAR Number 241,rev 0 for High Pressure Injection Sys Mods ML20195H6581998-11-17017 November 1998 Proposed Improved Tech Specs (Its),Revising 5.7.2 by Changing Type of Structural Integrity Assessment Required from Probabilistic to Deterministic ML20155F4501998-10-30030 October 1998 Proposed Revised Improved Tech Specs (ITS) Deleting Note Re Number of Required Channels for Degrees of Subcooling Function & Subdividing Core Exit Temp Function Into Two New Functions in ITS Table 3.3.17-1 ML20155F4021998-10-30030 October 1998 Proposed Revised Improved Tech Specs (ITS) Section 5.6.2.19, ITS Section 3.4.11,Bases 3.4.11 & 3.4.3 Re PTLR & LTOP Limits ML20155F9551998-10-30030 October 1998 Proposed Tech Specs Pages to LAR 245,changing Methodology for Sf Pool B Criticality Analysis ML20154P3101998-10-16016 October 1998 Proposed Tech Specs Resolving USQ by Leaving Valves DHV-34 & DHV-35 Normally Closed ML20154C1581998-09-30030 September 1998 Proposed Tech Specs Pages Re LAR 238,to Correct RCS Leakage Detection Capability of RB Atmosphere Gaseous Radioactivity Monitor Described in ITS Bases & FSAR ML20238F4761998-08-31031 August 1998 Proposed Tech Specs,Proposing New Repair Process for Plant OTSGs ML20151X0431998-08-31031 August 1998 Proposed Tech Specs Adding Three Addl Reg Guide 1.97 Type a Category 1 Pami Variables & One Type B Category 1 Pami Variable to ITS Table 3.3.17-1, Pami ML20236V8831998-07-30030 July 1998 Proposed Tech Specs Pages Re CREVS & Ventilation Filter Test Program ML20236E9851998-06-30030 June 1998 Proposed Tech Specs Re Exigent License Amend Request 228,rev 1 for Once Through SG Tube Surveillance Program ML20249B2671998-06-18018 June 1998 Proposed Tech Specs Pages Re one-time Exigent License Amend to Allow Operation W/Number of Indications Previously Identified as Tube End Anomalies & Multiple Tube End Anomalies in OTSG Tubes ML20247P8931998-05-22022 May 1998 Proposed Improved Tech Specs 5.2.1 Re Onsite & Offsite Organizations ML20217P5181998-04-28028 April 1998 Proposed Tech Specs Re Reactor Coolant Pump Motor Flywheel Insp ML20217G0121998-04-23023 April 1998 Proposed Improved Tech Specs Section 5.7.2, Special Repts, Clarifying That Complete Results of OTSG Tube Inservice Insp Shall Be Submitted to NRC 90 Days After Startup (Breaker Closure) ML20217C6341998-03-20020 March 1998 Proposed Tech Specs Re Editorial Changes to Improved TS Saftey Limits & Administrative Controls to Replace Titles of Senior Vice President,Nuclear Operations & Vice President, Nuclear Production W/Position of Chief Nuclear Officer ML20217C4931998-03-20020 March 1998 Proposed Improved Tech Specs 5.6.2.8.c Re Reactor Coolant Pump Motor Flywheel Insp ML20203D1611998-02-20020 February 1998 Proposed Tech Specs,Providing Revs to CR-3 Improved TS Bases That Update NRC Copies of Improved TS ML20198S9151998-01-22022 January 1998 Proposed Tech Specs Consisting of Rev 1 to TS Change Request 210,correction of Typo & Addition of Footnotes ML20202G8511997-12-0505 December 1997 Proposed Tech Specs Establishing New Improved TSs (ITS) Surveillance Requirement for Performance of Periodic Integrated Leak Test of Cche Boundary & Revising ITS Bases 3.7.12 to Define Operability of Cche ML20202G7991997-12-0505 December 1997 Proposed Tech Specs Revising Description of Starting Logic for RB Recirculation Sys Fan Coolers to Ensure That Only One RB Fan Starts on Es RB Isolation & Cooling Signal ML20199G8461997-11-21021 November 1997 Proposed Tech Specs Pages Involving Additional Restrictions, Editorial Clarifications & Typos ML20212F2741997-10-31031 October 1997 Proposed Tech Specs Pages Re Decay Heat Removal Requirements in Mode 4 ML20212C9801997-10-25025 October 1997 Proposed Tech Specs Re Power Operated Relief Valve Lift Setpoint TS Limit That Has Been Revised for Instrument Uncertainty ML20217F5231997-10-0404 October 1997 Proposed Tech Specs Pages Addressing Revision to Description of Electrical Controls for Operating Reactor Building (RB) Recirculation Sys fan/cooler,AHF-IC,as Discussed in FSAR & Improved TS ML20217D2741997-10-0101 October 1997 Proposed Tech Specs Adding Methodology to Monitor first-span Intergranular Attack (Iga) Indications & Disposition Growth During Future B OTSG Eddy Current Exams ML20210T9771997-09-12012 September 1997 Proposed Tech Specs Replacement Pages Re New Improved TS 3.4.11 Re Low Temp Overpressure Protection Sys ML20216F8481997-09-0909 September 1997 Proposed Tech Specs Re Analysis Rev for Makeup Sys Letdown Line Failure Accident as Discussed in FSAR ML20217Q2121997-08-26026 August 1997 Proposed Tech Specs Changing Design Basis of EDG Air Handling Sys ML20217N2501997-08-20020 August 1997 Proposed Improved Tech Specs 5.6.2.10 Re Tube Surveillance ML20210K8921997-08-16016 August 1997 Proposed Tech Specs 3.8.1.3,requesting one-time Outage on Each EDG to Perform Necessary Mod & Maint ML20151L7541997-08-0404 August 1997 Proposed Tech Specs Extending Frequency of EDG Surveillances During Period of Time CR-3 EDGs Are Being Modified ML20196J1431997-07-29029 July 1997 Proposed Tech Specs Adding EDG Kilowatt Indication to post- Accident Monitoring Instrumentation to Support CR-3 Restart Issue of EDG Load Mgt ML20196H0281997-07-18018 July 1997 Proposed Tech Specs Changes Establishing Requirements for Low Temperature Overpressure Protection Sys ML20148K7811997-06-14014 June 1997 Proposed Tech Specs Re Efw,Hpi,Emergency Feedwater Initiation & Control Sys ML20138H8781997-05-0101 May 1997 Proposed Tech Specs Replacing Prescriptive Requirements of 10CFR50,App J,Option a w/performance-based Approach to Leakage Testing Contained in 10CFR50,App J,Option B ML20137X5361997-04-18018 April 1997 Proposed Tech Specs,Providing Revs to CR-3 Improved TS Bases That Update NRC Copies of Improved TS 1999-09-02
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212C1121999-09-16016 September 1999 Criticality Safety Analysis of W Spent Fuel Storage Racks in Pool B of Crystal River Unit 3 ML20212C0961999-09-16016 September 1999 Proposed ITS & Bases Changes Strikeout & Shadowed Text & Revision Bar Format,Increasing Licensed Capacity for Spent Fuel Assembly Storage in SFP & Revising Configuration for Storage of Fresh Fuel ML20211L1011999-09-0202 September 1999 Proposed Tech Specs Re Once Though SG Tube Surveillance Program,Alternate Repair Criteria (ARC) for Axial Tube End Crack (Tec) Indications ML20212C0991999-08-31031 August 1999 Criticality Safety Analysis of Crystal River Unit 3 Pool a for Storage of 5% Enriched Mark B-11 Fuel in Checkerboard Arrangement with Water Holes ML20209D2971999-07-0808 July 1999 Proposed Tech Specs,Changing ITS for CREVS & VFTP & Correcting Typo in ITS Section 5.6.2.12 ML20195B8091999-05-26026 May 1999 Proposed Tech Specs,Revising ITS Bases That Will Update NRC Copies of ITS ML20195B7081999-05-17017 May 1999 Proposed ITS Section 3.3.8, EDG Lops, SR 3.3.8.1,revising Note for Surveillance & Deleting Note for Frequency ML20206S7691999-05-12012 May 1999 Proposed Improved Tech Specs Pages 3.4-21 Through 3.4-21D ML20206N1401999-05-10010 May 1999 Proposed ITS Administrative Controls Section 5.8, High Radiation Area ML20206M0961999-05-0707 May 1999 Proposed Tech Specs,Revising Wording for SR 3.5.2.5 to Be More Consistent with NUREG-1430,Rev 1 & Clarifying Process of Valve Position Verification ML20206H6541999-05-0505 May 1999 Proposed Tech Specs,Proposing Alternate Repair Criteria for Axial Tube End crack-like Indications in Upper & Lower Tubesheets of CR-3 OTSGs ML20204D9211999-03-18018 March 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Tube Repair Roll Process ML20205A7651999-03-18018 March 1999 Rev 29 to AR-305, Es E Annunciator Response ML20205A7961999-03-15015 March 1999 Rev 22 to AR-301, ESA Annunciator Response ML20205A8051999-03-15015 March 1999 Rev 33 to AR-303, ESC Annunciator Response ML20205A8211999-03-15015 March 1999 Rev 35 to AR-403, PSA H Annunciator Response ML20205A3441999-03-12012 March 1999 Rev 25 to AR-402, PSA G Annunciator Response ML20204D5781999-03-0909 March 1999 Rev 10 to AP-513, Toxic Gas ML20204D5821999-03-0808 March 1999 Rev 22 to AR-603, Tgf O Annunciator Response ML20207H7741999-03-0303 March 1999 Rev 15 to AR-602, Tgf N Annunciator Response ML20207J6591999-03-0202 March 1999 Rev 18 to AR-504, ICS L Annunciator Response ML20207J6461999-03-0202 March 1999 Rev 21 to AR-301, ESA Annunciator Response ML20206S7561999-02-28028 February 1999 Rev 2 to Pressure/Temp Limits Rept, Dtd Feb 1999 ML20203C7461999-02-0303 February 1999 Rev 2 to AR-801, FSA Annunciator Response ML20202E6551999-01-27027 January 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Insp Interval Extension ML20202B1411999-01-22022 January 1999 Rev 22 to AR-401, PSA F Annunciator Response ML20199G5201999-01-15015 January 1999 Rev 11 to AP-961, Earthquake ML20199G5581999-01-12012 January 1999 Rev 4 to AP-404, Loss of Decay Heat Removal ML20199G5691999-01-12012 January 1999 Rev 4 to AP-604, Waterbox Tube Failure ML20198T2411999-01-0606 January 1999 Rev 19 to AR-701, Ssf P Annunciator Response ML20196G6771998-12-0101 December 1998 Rev 17 to Annunciator Response AR-702, Ssf Q Annunciator Response ML20196D6761998-11-30030 November 1998 Proposed Tech Specs LCO 3.9.3,allowing Both Doors in Personnel Air Locks & Single Door in Oeh to Be Open During Refueling Operations ML20196G5851998-11-25025 November 1998 Rev 32 to AR-303, ESC Annunciator Response ML20196G3371998-11-25025 November 1998 Reissued Rev 15 to AR-702, Ssf Q Annunciator Response ML20195K4551998-11-24024 November 1998 Proposed Tech Specs,Installing diesel-driven EFW Pump to Remove Interim ITS & Provide Resolution to EDG Capacity Limitations ML20196F6691998-11-24024 November 1998 Rev 11 to AP-330, Loss of Nuclear Svc Cooling ML20195K0031998-11-23023 November 1998 Proposed Tech Specs Re LAR Number 241,rev 0 for High Pressure Injection Sys Mods ML20196F7721998-11-23023 November 1998 Rev 3 to EOP-12, Station Blackout ML20196F7031998-11-23023 November 1998 Rev 3 to AP-404, Loss of Decay Heat Removal ML20196F7541998-11-23023 November 1998 Rev 7 to EOP-08, LOCA Cooldown ML20196F7461998-11-23023 November 1998 Rev 6 to EOP-07, Inadequate Core Cooling ML20196F7241998-11-23023 November 1998 Rev 2 to AP-510, Rapid Power Reduction ML20196F7161998-11-23023 November 1998 Rev 9 to AP-470, Loss of Instrument Air ML20196F8711998-11-23023 November 1998 Rev 28 to AR-305, Es E Annunciator Response ML20196F9451998-11-19019 November 1998 Rev 7 to AP-1080, Refueling Canal Level Lowering ML20196F9381998-11-19019 November 1998 Rev 27 to AP-770, Emergency Diesel Generator Actuation ML20195H6581998-11-17017 November 1998 Proposed Improved Tech Specs (Its),Revising 5.7.2 by Changing Type of Structural Integrity Assessment Required from Probabilistic to Deterministic ML20196D8321998-11-13013 November 1998 Rev 1 to Crystal River Unit 3 ASME Section Xi,Isi Program Interval 3 & Ten Yr NDE Program ML20195H8761998-11-0505 November 1998 Rev 23 to AR-302, Esb Annunciator Response ML20155F4021998-10-30030 October 1998 Proposed Revised Improved Tech Specs (ITS) Section 5.6.2.19, ITS Section 3.4.11,Bases 3.4.11 & 3.4.3 Re PTLR & LTOP Limits 1999-09-02
[Table view] |
Text
.w .
- O pJ '
Technical Specification Change Reouest No. 24 (Appendix A)
Replace pages 3/4 6- 5,16,17,18,19, 20 and 21 with the attached revised pages 3/4 6-1;, 16, 17, 18, 19, 20 and 21.
Proposed Change Change Specification 3/4.6.3.1 to apply to containment automatic isolation valves.
Delete the wording "during the COLD SHUTDOWN or REFUELING MODE" in Specification 4.6.3.1.2.
Add asterisks to the valves in Table 3.6-1 that perform a containment automatic isolation function upon receipt of a contair. ment isolation or radiation-high signal and add a footnote to that effect.
Reason for Proposed Change Specification 3/4.5.3.1. applies only to containment automatic isolation valves as is reflected by the surveillance requirements and this change is to clarify that point.
The requirement to demonstrate the OPERABILITY of the containment auto-matic isolation valves only during COLD SHUTDOWN or REFUELING is overly restrictive. The ACTION statement of Specification 3.6.3.1 adequately protects the health and safety of the plant personnel and the public in the event that any of the containment automatic isolation valves is found to be inoperable. In addition, this Specification could force the
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shutdown of Crystal River - Unit 3 to perform a surveillance that can be performed in the other OPERATIONAL MODES as well as COLD SHUTDOWN and REFUELING.
The addition of asterisks and footnote in Table 3.6-1 clarifies which valves should be surveilled per Specifications 4.6.3.1.2.a and b.
Of the 103 valves listed in Sections A and B of Table 3.6-1, sixteen are check valves, fifteen do not receive a containment isolation or radiation-high signal and eight open on a containment isolation signal. The remaining sixty-four close on a containment isolation or radiation-high signal and are asterisked.
The fifteen valves that don't receive a containment isolation or radiation-high signal are:
-DHV-4 MSV-414 DHV-41 SWV-35 DHV-42 SWV-37 DHV-43 SWV-39 DHV-91 SWV-41 MSV-411 SWV-43 M SWV-45 8003050 h These valves are verified OPERABLE per Specification 4.6.1.1. Valve
'DHV-4 is included in this group, even though FSAR Table R-4 (page 5-85,
m, s
Penetration No. 344) identifies both valves on the Decay Heat Coolant letdown line inside the containment (DHV-3 and 4) as valves receiving an Engineered Safeguards signal. The valves, as originally designed, do not receive a containment isolation signal. This was reflected in the original version of Table 5-4. The " Signal" column of the table for DHV-3 and 4 was changed from " Remote Manual" to "ES" in FSAR amendment 48 in order to reflect the fact that the Automatic Closure and Interlock System logic for closing DHV-3 and4 at an RC pressure of > 284 osig comes from the ES cabinets. This System is described starting on FSAR page 9-15.
The eight valves that open on a containment isolation signal are:
BSV-3 MUV-23 BSV-4 MUV-24 DHV-5 MUV-25 DHV-6 MUV-26 These valves are verified OPERABLE per Specification 4.5.2.d.l.
Safety Analysis of Proposed Change None of the requirements applicable to the safety analysis are diminished by the proposed changes and no unreviewed safety question is involved.
This change is proposed only to bring the Technical Specifications for Crystal River Unit 3 into agreement with actual plant conditions.
s.
CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3.1 The containment automatic isolation valves specified in Table 3.6-1 shall be OPERABLE with isolation times as shown in Table 3.6-1.
APPLICABILITv- MODES 1, 2, 3 and 4.
ACTION:
With one or more of the containment automatic isolation valves (s) specified in Table 3.6-1 inoperable, either:
- a. Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or
- b. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated containment automatic isolation valve secured in the isolation position, or
- c. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange; or
- d. Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REOUIREMENTS 4.6.3.1.1 The containment automatic isolation valves specified in Table 3.6-1 shall be demonstrated. OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, contrcl or power circuit by performance of a cycling test and verification of isolation time.
CRYSTAL RIVER - UNIT 3 3/4 6-15
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CONTAINMENT SYSTEM.S SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.1.2 Each containment automatic isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE at least once per 18 months by:
4
- a. Verifying that on a containment isolation test signal, each containment isolation valve actuates to its isolation position.
- b. Verifying that on a containment radiation-high test signal, each containment purge and exhaust automatic isolation valve actuates to its isolation position.
l l
CRYSTAL RIVER - UNIT 3 3/4 6-16
TABLE 3.6-1 CONTAINMENT ISOLATION VALVES VALVE NUMBER FUNCTION ISOLATION TIME (seconds)
A. CONTAINMENT' ISOLATION
- 1. BSV-27 check # iso. dur. nor.. operation NA BSV-3 # and open dur. RB spray 60 BSV-26 check # NA BSV-4 # 60 %
- 2. CAV-126
- iso. CA sys. fr. RC letdn. 60 CAV-1
- iso. CA sys. fr. pzr. 60 CAV-3
- 60 CAV-2 iso. CA sys. 60 CAV-4 #
- isolate liquid sampling 60 3
CAV-6 #
- 3. CFV-20 check iso.- N2 supply fr. CFT-1A NA CFV-28
- 60 CFV-17 check iso. N2supply fr. CFT-1B NA CFV-27
- 60 CFV-18 check iso. MU system fr. CFT-1B NA CFV-26 60 CFV-19 check iso. MU system fr. CFT-1A NA i CFV-25
- 60 CFV-42 iso. liquid sampling fr. 60 CF system CFV-15 iso. WD sys. fr. CF tanks 60 CFV-16 60
CFV-29 60 CFV-ll iso. CF tanks fr. liquid 60
, CFV-12 sampling system 60
- 4. CIV-41 150. CI sys. fr. RB 60 CIV-40
- 60 CRYSTAL RIVER - UNIT 3 3/4 6-17
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. TABLE 3.6-1 (Continurd)
CONTAINMENT ISOLATION VALVES VALVE NUMBER FUNCTION ISOLATION TIME
"'(seconds)'~~~
- 5. DHV-93 check iso. DH system fr. pzr. NA SHV-91 60 DHV-43 # iso. DH sys. fr. RB sump 120 DHV-42 # 120 DHV-4# & 41# iso. DH sys. fr. RC 120 DHV-6 # iso. DH system from 60 DHV-5 # Reactor Vessel 60
- 6. DWV-162 check iso. system NT, DWV-160 60
- 7. FWV-44 check e iso. feedwater NA FWV-45 check
- from RCSG-1A NA FWV-43 check d iso. feedwater NA FWV-45 check = from RCSG-1B NA
- 8. MSV-130 #
- from RCSG-1A 60 MSV-148 #
from RCSG-1A MSV-413 # iso. main steam lines 60 from RCSG-1B l
-MSV-414 # iso, main steam lines 60 from RCSG-1B
- 9. MUV-40
- iso. MU system from RC 60 l MUV-41
- 60 MUV-261 * . iso. MU system from 60 control bleed-off MUV-260
MUV-258
- 60 CRYSTAL RIVER - UNIT 3 3/4 6-18 l
l AULL 3.6-1 (Continuggl C0lTAXNMENT XSCLATION VALVES VALVE NUMBER FUNCTION ISOLATI0" TIME (seconds )
- 9. (Continued)
MUV-163 check # open during HPI and NA MUV-25 # iso. dur. nor. operation 60 MUV-164 check # NA MUV-26 # 60 MUV 160 check # open'during HPI and NA MUV-23 # iso. dur. nor, operation 60 MUV-161 check # open during HPI and NA MUV-24 # iso, dur. nor operation 50 MUV-27 5
- open dur. nor. operation 60 and closed during HPI
- 10. SWV-39 # iso. NSCCC from AHF-lO SO SWV-45 # 60 SWV-35 # iso. NSCCC from AHF-1A 60 m SWV-41 # 60 SWV-37
- iso. NSCCC from AHF-1B 60 SWV-43 # 60 SWV-48 !* to isolate NSCCC from 60 SWV-47 d* MUHE-1A & 1B and WDT-5 60 SW-49 s* 60 SW-50 #
- 60 SW-80 #* iso. NSCCC frcm RCP-1A 60 SWV-84 #* , 60 SWV-82 #* iso. NSCCC frc~m RCP-lC 60 SWV-86 #* 60 SWV-81 f* iso. NSCCC from RCP-lO 60 SWV-85 4* 60 SW-79 e* iso. NSCCC from RCP-1B 60 4 SWV-65 J* 60 SWV-109F NSCCC to DRRD-1 60 SW-110#* 60 m
CRYSTAL RIVER - UNIT 3 3/4 6-19 Amendment No. 11
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lAttLF. 3.6-1 :Lontinued)-
CONTAINMENT ISOLATION VALVES VALVE NUMBER FUNCTION ISOL A, TION, TIME (seconds)
- 11. WDV-1
- iso. WDT-4 from RB sump 60 WDV-3
- iso. WDT-4 from WDT-5 60 WOV-94*& 62
. WDV-406
- iso. gas waste disposal 60 WDV-405
- from vents in RC system 60
- 12. WSV-3 iso, containment monitoring 60 WSV-4 system from RS 60 WSV-5
- 60 WSV-6 60 B. CONTAINMENT Pt;RGE AND EXHAUST -
- 1. AHV-1C'6 ID* iso. pur, sup. system 60 AHV-1B *& 1 A* iso. pur. exhaust system 60 -
C. MANUAL
- 1. iAV-23 iso. IA from RS NA IAV-29 NA
- 2. LkV-50 iso. leak rate test system NA LRV-36 from RB NA LRV-51 iso. atmos. vent and RB NA LRV-35 & 47 purge exhaust system NA from RB LRV-49 iso, atmos. vent from RB NA LRV-38 & 52 NA LRV-45 iso. LR test _ panel from RB NA LRV-44
--- NA
- 3. MSV-146# iso. misc. waste storage NA
, tank from RCSG-1B d
- 4. NGV-62 iso. NG system from NA NGV-81 # steam generators NA NGV-82 iso. NG system from pzr. NA CRYSTAL RIVER - UNIT 3 3/4 6-20
+
s
- ~ .'
TABL,E_;1.6-1 (Continued)
L_0N1AlfiMENT ISOLATION VALVES-VALVE NUMBER FUNCTION ISOLATION TIME (seconds)
- 5. SAV-24 iso. SA from RB NA
-6. SFV-18 iso. SF system NA SFV-19 NA SFV-il9# iso. Fuel Transfer tubes NA SFV-120# from F.T. Canal NA
- 7. WSV-1 contaimnent monitoring NA WSV-2 system from RB UA D. PENETRATIONS REQUIRING TYPE B TESTS Blind Flange 119 iso. RB NA Blind Flange 120 NA Blind Flange 116 NA Blind Flange 202 fiA Blind Flange 348 iso. fuel transfer ~ tube from NA Blind Flange 436 Transfer Canal NA Equipment Hatch iso. RB NA Personnel Hatch iso. RB NA e Not subject to Type C Leakage Test Containment automatic isolation valve s
CRYSTAL RIVER - UNIT 3- 3/4 6-21
.