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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20206B9211999-04-23023 April 1999 Proposed Defueled Tech Specs Stating That Characterization of Revised Review & Audit Function Remain in Plant TS Rather than Be Transferred to Plant QA Plan ML20205N1821999-03-24024 March 1999 Proposed Tech Specs Deleting Condition 2.C(10) from Plant License ML20204E5701999-03-17017 March 1999 Proposed Tech Specs,Removing Section 6.7, Procedures & Programs & Section 6.9, Record Retention, from TS & Transferring to Yankee Decommissioning QA Program ML20204E5241999-03-17017 March 1999 Revised Tech Specs,Consolidating Mgt Positions & Transferring Review & Audit Functions to Yankee Decommissioning QA Program ML20204D9031999-03-17017 March 1999 Proposed Tech Specs Section 6.2.2,deleting Overtime Restrictions Currently Incorporated in Ynps TS ML20155A2561998-10-15015 October 1998 Proposed Defueled Tech Specs Re Required Frequency of Submittal of Radioactive Effluent Release Rept ML20237E3631998-08-20020 August 1998 Proposed Tech Specs,Removing Definition of Site Boundary from Subsection 1.10 of Definitions & Modifying Subsection 5.1 of Design Features ML20216E2101997-09-0505 September 1997 Proposed Tech Specs,Modifying Defueled TS 3.1.3 to Allow Util to Continue W/Implementation of Ynps Decommissioning Plan Which Has Been Incorporated Into Ynps FSAR ML20126E7601992-12-21021 December 1992 Permanently Defueled Tech Specs ML20055D4031990-06-25025 June 1990 Proposed Tech Specs Re Changes in Safety Injection Tank Min Water Inventory ML20247L3581989-09-14014 September 1989 Proposed Tech Specs Re Limiting Condition for Operation & Surveillance Requirements for Control Rod Insertion Limits, Boron Control,Peak LHGR & Xenon Redistribution Multiplier ML20246M0541989-08-31031 August 1989 Proposed Tech Specs,Modifying Pages 3/4 3-19,Table 3.3-4 & 3/4 3-21,Table 4.3-3,to Add Steam Line Monitors & Primary Vent Stack Noble Gas Monitor to Listing of Radiation Monitoring Instrumentation & Surveillance Requirements ML20247M6321989-07-24024 July 1989 Proposed Tech Specs Re Power Distribution Limits ML20246M0221989-07-12012 July 1989 Proposed Tech Spec Tables 3.3-4, Radiation Monitoring Instrumentation & 4.3-3, Radiation Monitoring Instrumentation Surveillance Requirements ML20244D3841989-04-14014 April 1989 Proposed Tech Specs Re Steam Generator Pressure/Temp Limits, Primary Pump Seal Water Sys,Control Room Emergency Air Cleaning Sys & Sealed Source Contamination ML20246P1401989-03-21021 March 1989 Proposed Tech Specs Adding Snubber DRH-SNB-1 to Table 3.7-4 ML20196B0771988-11-22022 November 1988 Tech Spec Page 3/4 3-2 Inadvertently Omitted from Util 881021 Proposed Change 222 to Tech Specs ML20205L1691988-10-21021 October 1988 Proposed Tech Specs,Removing Description of High Pressurizer Water Level & Modifying Description of Main Coolant Sys High Pressure ML20151Z1871988-08-11011 August 1988 Proposed Tech Spec Changes to Remove Ref to Specific Value of 2,200 Ppm & Provide Generalized Boron Concentration Value & Remove Requirement for Inverse Count Rate Multiplication Measurement After Insertion of Each Five Fuel Assemblies ML20150B0371988-06-27027 June 1988 Proposed Tech Specs,Allowing Installation of Two Piping Mods Necessary for Installation of Enhanced Water Cleanup Sys ML20196K7361988-06-27027 June 1988 Proposed Tech Spec Table 3.6.1, Containment Barriers, Deleting Valve VD-V-752 & Tech Spec 3.4.5.1, Main Coolant Leakage Detection Sys, Adding Operability,Action & Surveillance Requirements for Telltale Level Switch ML20196K1391988-06-27027 June 1988 Proposed Tech Specs Table 3.6-1 ML20196J2831988-06-27027 June 1988 Proposed Tech Specs 3.5.1.e,increasing Nitrogen Supply Pressure to Safety Injection Accumulator to 488 Pounds Per Square Inch Gauge ML20154J5991988-05-19019 May 1988 Proposed Tech Spec 4.9.7.2, Spent Fuel Pit ML20148Q8911988-04-0404 April 1988 Proposed Tech Specs Defining Incore Detection Sys as Combination Sys of Both Fixed & Movable Detectors & Associated Equipment ML20151D0671988-04-0404 April 1988 Proposed Tech Spec Page 3/4 8-10 Re Battery Chargers ML20148J2991988-03-25025 March 1988 Proposed Tech Spec Table 3.3-2, ESF Instrumentation & Table 4.3-2, ESF Instrumentation Surveillance Requirements, Reflecting Deleted Modes 5(1) & 5*, Respectively ML20150E2381988-03-25025 March 1988 Proposed Tech Specs Modifying Containment Isolation Barriers ML20148J2701988-03-23023 March 1988 Proposed Tech Spec 3.1.1.1.2,reflecting Change in Shutdown Margin Switching Temp from 490 to 470 F ML20150C0171988-03-11011 March 1988 Proposed Tech Specs Modifying Section 6.2 & Moving Organization Charts (Figures 6.2-1 & 6.2-2) to Section 501 of FSAR ML20148K1671988-01-15015 January 1988 Proposed Tech Specs,Adding Shipping Cask Liners,Vol Reduction Equipment,Shipping Casks Not for Spent Fuel & Spent Fuel Assembly Nondestructive Test Equipment to Tech Spec 3.9.7 ML20149E8871988-01-0505 January 1988 Proposed Tech Specs,Modifying Tables 3.3-2,3.3-3 & 4.3-2 to Require 18-month Functional Test of First Level Undervoltage Protection for Each of Three 480-volt Emergency Buses ML20149E7271988-01-0505 January 1988 Proposed Tech Spec Figure 6.2.2, Facility Organization, Reflecting Elevated Mgt Concerns Re Security ML20210A5041987-01-29029 January 1987 Proposed Tech Specs Re Extension of Cycle 18 in-core Instrumentation Sys to Cycle 19 ML20213A4431987-01-22022 January 1987 Proposed Tech Specs,Providing Flexibility in Areas Governing Integrity Testing of Steam Generator Tubes ML20215N6281986-10-22022 October 1986 Proposed Tech Spec 4.5.2.b.4,increasing Allowable Open Time for LPSI Min Recirculation Line Valve CS-MOV-532 to 120 Minutes Per Wk ML20197A7611986-10-20020 October 1986 Proposed Tech Specs,Allowing for Performance of 10CFR50.59 Reviews for Future Core Reloads ML20211E8091986-10-0909 October 1986 Proposed Tech Spec Table 4.3-1, Reactor Protective Sys Instrumentation Surveillance Requirements ML20204F7191986-07-31031 July 1986 Proposed Changes to Tech Specs 3.3.3.2,4.2.1.2,4.2.2.1, 4.2.2.2 & 4.2.3.2 Re Operation of in-core Instrumentation Sys ML20211K7501986-06-24024 June 1986 Proposed Changes to Tech Specs to Allow Performance of 10CFR50.59 Reviews for Future Core Reloads ML20151U5571986-02-0505 February 1986 Proposed Tech Specs,Per Generic Ltr 84-43, Reporting Requirements of 10CFR50... & Generic Ltr 85-19, Reporting Requirements on Primary Coolant Iodine Spikes & Supporting LER Sys Mods ML20136J3981986-01-0808 January 1986 Proposed Changes to Tech Spec Table 3.6-1,replacing Manual Containment Isolation Valve W/Blank Flange ML20141G3461986-01-0606 January 1986 Proposed Tech Spec Changes,Permitting Filing of Supplemental Dose & Meteorological Summary Rept within 150 Days of Jan 1 Each Yr ML20138N3131985-10-31031 October 1985 Proposed Tech Spec Changes Per NUREG-0737,Item II.F.1.6, Containment Hydrogen Monitors ML20133K5061985-10-16016 October 1985 Proposed Tech Spec Table 4.3-2, Engineered Sys Instrumentation Surveillance Requirements, Requiring Monthly Functional Test of New Second Level Degraded Grid Voltage Protection for Each 480-volt Emergency Bus ML20133K4491985-10-15015 October 1985 Proposed Tech Spec Table 3.6-1,adding Two Containment Isolation Valves for Compliance W/Tech Spec 3/4.6.2 Which Requires Type C Tests for Valves ML20133K2041985-10-15015 October 1985 Proposed Tech Specs,Reflecting Mods to RCS Vent Sys Valve Power Supplies ML20133J8001985-10-15015 October 1985 Proposed Tech Spec Changes,Revising Table 3.3-4, Radiation Monitoring Instrumentation, Table 4.3-3, Radiation Monitoring Instrumentation Surveillance Requirements & Tech Spec 3.3.3.2, Instrumentation-In-Core Detection Sys ML20133C5801985-09-30030 September 1985 Proposed Tech Specs Re Radiological Environ Monitoring ML20133C3211985-09-30030 September 1985 Proposed Changes to Tech Spec 2.2.1 & Tables 2.2-1,3.3.2 & 3.3-3,increasing Required Setpoint for Main Steam Line Isolation Trip from 200 Psig to 262.5 Psig 1999-04-23
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20206B9211999-04-23023 April 1999 Proposed Defueled Tech Specs Stating That Characterization of Revised Review & Audit Function Remain in Plant TS Rather than Be Transferred to Plant QA Plan ML20205N1821999-03-24024 March 1999 Proposed Tech Specs Deleting Condition 2.C(10) from Plant License ML20204E5241999-03-17017 March 1999 Revised Tech Specs,Consolidating Mgt Positions & Transferring Review & Audit Functions to Yankee Decommissioning QA Program ML20204E5701999-03-17017 March 1999 Proposed Tech Specs,Removing Section 6.7, Procedures & Programs & Section 6.9, Record Retention, from TS & Transferring to Yankee Decommissioning QA Program ML20204D9031999-03-17017 March 1999 Proposed Tech Specs Section 6.2.2,deleting Overtime Restrictions Currently Incorporated in Ynps TS ML20155A2561998-10-15015 October 1998 Proposed Defueled Tech Specs Re Required Frequency of Submittal of Radioactive Effluent Release Rept ML20237E3631998-08-20020 August 1998 Proposed Tech Specs,Removing Definition of Site Boundary from Subsection 1.10 of Definitions & Modifying Subsection 5.1 of Design Features ML20197D4341997-12-31031 December 1997 Rev 1 to Ynps License Termination Plan ML20216E2101997-09-0505 September 1997 Proposed Tech Specs,Modifying Defueled TS 3.1.3 to Allow Util to Continue W/Implementation of Ynps Decommissioning Plan Which Has Been Incorporated Into Ynps FSAR ML20141F6391997-05-15015 May 1997 License Termination Plan for Yankee Nuclear Power Station ML20198G6381997-02-0707 February 1997 Rev 12 to Ynps Off-Site Dose Calculation Manual ML20138Q5301996-10-31031 October 1996 Rev 11 to Off-Site Dose Calculation Manual ML20198S6131993-12-31031 December 1993 Partially Deleted Rev 9 to Edcr 93-303, Vessel Internals Segmentation Component Removal Program 1995 ML20198S5681993-08-0202 August 1993 Partially Deleted Rev 6 to Edcr 93-303, Reactor Vessel Internals Segmentation Component Removal Program 1993 ML20126E7601992-12-21021 December 1992 Permanently Defueled Tech Specs ML20058D8451990-10-29029 October 1990 Separate Rept Re Local Leak Rate Test Results from Core 19/20 Refueling Outage ML20058D8421990-06-30030 June 1990 June 1990 Reactor Containment Bldg Integrated Leak Rate Test & Periodic Local Leak Rate Tests ML20055D4031990-06-25025 June 1990 Proposed Tech Specs Re Changes in Safety Injection Tank Min Water Inventory ML20247L3581989-09-14014 September 1989 Proposed Tech Specs Re Limiting Condition for Operation & Surveillance Requirements for Control Rod Insertion Limits, Boron Control,Peak LHGR & Xenon Redistribution Multiplier ML20246M0541989-08-31031 August 1989 Proposed Tech Specs,Modifying Pages 3/4 3-19,Table 3.3-4 & 3/4 3-21,Table 4.3-3,to Add Steam Line Monitors & Primary Vent Stack Noble Gas Monitor to Listing of Radiation Monitoring Instrumentation & Surveillance Requirements ML20247M6321989-07-24024 July 1989 Proposed Tech Specs Re Power Distribution Limits ML20246M0221989-07-12012 July 1989 Proposed Tech Spec Tables 3.3-4, Radiation Monitoring Instrumentation & 4.3-3, Radiation Monitoring Instrumentation Surveillance Requirements ML20244D3841989-04-14014 April 1989 Proposed Tech Specs Re Steam Generator Pressure/Temp Limits, Primary Pump Seal Water Sys,Control Room Emergency Air Cleaning Sys & Sealed Source Contamination ML20244D3931989-04-11011 April 1989 Core 20 Startup Program for Yankee Nuclear Power Station ML20246P1401989-03-21021 March 1989 Proposed Tech Specs Adding Snubber DRH-SNB-1 to Table 3.7-4 ML20196B0771988-11-22022 November 1988 Tech Spec Page 3/4 3-2 Inadvertently Omitted from Util 881021 Proposed Change 222 to Tech Specs ML20205L1691988-10-21021 October 1988 Proposed Tech Specs,Removing Description of High Pressurizer Water Level & Modifying Description of Main Coolant Sys High Pressure ML20151Z1871988-08-11011 August 1988 Proposed Tech Spec Changes to Remove Ref to Specific Value of 2,200 Ppm & Provide Generalized Boron Concentration Value & Remove Requirement for Inverse Count Rate Multiplication Measurement After Insertion of Each Five Fuel Assemblies ML20196K1391988-06-27027 June 1988 Proposed Tech Specs Table 3.6-1 ML20196J2831988-06-27027 June 1988 Proposed Tech Specs 3.5.1.e,increasing Nitrogen Supply Pressure to Safety Injection Accumulator to 488 Pounds Per Square Inch Gauge ML20150B0371988-06-27027 June 1988 Proposed Tech Specs,Allowing Installation of Two Piping Mods Necessary for Installation of Enhanced Water Cleanup Sys ML20196K7361988-06-27027 June 1988 Proposed Tech Spec Table 3.6.1, Containment Barriers, Deleting Valve VD-V-752 & Tech Spec 3.4.5.1, Main Coolant Leakage Detection Sys, Adding Operability,Action & Surveillance Requirements for Telltale Level Switch ML20154J5991988-05-19019 May 1988 Proposed Tech Spec 4.9.7.2, Spent Fuel Pit ML20148Q8911988-04-0404 April 1988 Proposed Tech Specs Defining Incore Detection Sys as Combination Sys of Both Fixed & Movable Detectors & Associated Equipment ML20151D0671988-04-0404 April 1988 Proposed Tech Spec Page 3/4 8-10 Re Battery Chargers ML20148Q4681988-03-31031 March 1988 Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45 ML20148J2991988-03-25025 March 1988 Proposed Tech Spec Table 3.3-2, ESF Instrumentation & Table 4.3-2, ESF Instrumentation Surveillance Requirements, Reflecting Deleted Modes 5(1) & 5*, Respectively ML20150E2381988-03-25025 March 1988 Proposed Tech Specs Modifying Containment Isolation Barriers ML20148J2701988-03-23023 March 1988 Proposed Tech Spec 3.1.1.1.2,reflecting Change in Shutdown Margin Switching Temp from 490 to 470 F ML20150C0171988-03-11011 March 1988 Proposed Tech Specs Modifying Section 6.2 & Moving Organization Charts (Figures 6.2-1 & 6.2-2) to Section 501 of FSAR ML20154L9791988-03-0606 March 1988 Rev 6 to Yankee Nuclear Power Station Offsite Dose Calculation Manual ML20148K1671988-01-15015 January 1988 Proposed Tech Specs,Adding Shipping Cask Liners,Vol Reduction Equipment,Shipping Casks Not for Spent Fuel & Spent Fuel Assembly Nondestructive Test Equipment to Tech Spec 3.9.7 ML20149E8871988-01-0505 January 1988 Proposed Tech Specs,Modifying Tables 3.3-2,3.3-3 & 4.3-2 to Require 18-month Functional Test of First Level Undervoltage Protection for Each of Three 480-volt Emergency Buses ML20149E7271988-01-0505 January 1988 Proposed Tech Spec Figure 6.2.2, Facility Organization, Reflecting Elevated Mgt Concerns Re Security ML20235Q7771987-09-30030 September 1987 Core Xix Startup Program for Yankee Nuclear Power Station ML20237C7631987-06-30030 June 1987 Reactor Containment Bldg Integrated Leak Rate Test ML20237C7911987-05-31031 May 1987 Separate Accompanying Summary Rept of Type B & C Results.. ML20210B5551987-04-20020 April 1987 Rev 4 to Procedure DC-1, Seismic Reevaluation & Retrofit Criteria ML20206D3741987-03-31031 March 1987 Yankee Nuclear Power Station Graded Exercise,Exercise Manual ML20210A5041987-01-29029 January 1987 Proposed Tech Specs Re Extension of Cycle 18 in-core Instrumentation Sys to Cycle 19 1999-04-23
[Table view] |
Text
__ _ _ _ _ _ _ _ _ _ _ _ _ _
?. . .
i l 3/4.6 CONTAINMENT SYSTEM _S_
3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: MODES 1, 2, 3 and 4 ACTION:
Without primary CONTAINMENT INTEGP.ITY, restore CONTAINMENT INTEGRITY within one hour or 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 REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
- a. At least once per 31 days by verifying that:
- 1. All penetrations not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed be vslves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-1 of Specification 3.6.2 and
- 2. All equipment hatches are closed ar.d sealed,
- b. By calculating and plotting the containment ui mass as determined by the containment continuous Icek monitoring system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c. By verifying at least once per 3 months that all penetration test, vent and drain connections and '
instrumentation ports providing a direct path to the containment are isolated with a minimum of one cap, plug, closed valve, instrument or appropriate seal, except as ,
provided in Table 3.6-1 of Specification 3.6.2. I
- d. Any threaded pipe cap or threaded plug used to provide CONTAINMENT INTEGRITY will be torque tested on installation.
YANKEE ROWE 3/4 6-1 Amendment No. ,46(AdI 8803300169 880325 PDR ADOCK0500gg9 P
TABLE 3.6-1 CONTAINMENT BARRIERS TESTABLE DURING ISOLATION PLANT OPER.ATION TIME (Yes or No) (Seconos)
VALVE NUMBER FUNCTION A.1 AUTow.ATIC ISOLATION VALVE 5 (Subject to Type C Testing)
Yes 30 V0-TV-202 Main Coolant Orain Yet 30 V0-T V-203 Main Coolant Vent Yes 30 VD TV-204 Valve Stem Leakoff Yes 30 SA-TV-206 Pain Coolant Sample 30 Neutron Shield Tank Sae.ple Yes SA-TV-207 Yes 30 VO-TV-209 - Containment Orain Yes 30 SW-T V-408 Containe.ent Cooling Water Return 30 Containment Cooling Vater Inlet Yes SW TV-412 Yes 30 HC-TV-409 (14) Containment lleating Condensate Return 30 HC-TV-413 (14) Containment Heating Steam Supply Yes No 30 PR-TV-214 Safety Discharge Header 30 Yes CH LCV-222 Main Coolant Bleed A.2 AUTOWATIC ISOLATION VALVES (Net Subject to Type C Testing)
B.1 KANUAL VALVES (Subject to Type C Testing)
NA C5-y-601 Shield Tank Cavity Fill NA NA NA CA-V-746(3) Containment Air Charge KA kA HV-V-5 Containe.ent H 2 Y'"* I#5*'"
RA NA HV-V-6(8) Containeent H Vent System 2
NA HV-V-34(8) Containeent H Vent System RA 2 j NA CA-V-688 Containment Service Air Supply MA NA CA-V-834 Containeent H Vent System Air supply RA 2
gg gg ,
VD-V-1107(10) g ,ng,q3,,ng 3,,p),
VD-V-110B(10) Containeent Sample NA NA H Recoe.biner Inlet Tap NA NA CA V 1275(I) l 2
KA l CA-Y 1276(8) H2 Recombiner Inlet Tap NA RA CA-V-1277 53) Containment Air Charge KA BA-V-61 Containnent Breathing Air M NA BA-V-63 Containtnent Breathing Air -
NA NA YANKEE ROVE 3/4 6-11 A,end,ent No.p,56, H,,#
I
}..-
l _ TABLE 3.6-1 (continued)
CONTAINSENT BARRIERS TESTABLE DURING ISOLATION PLANT OPERATION TIME VALVE NUW.BER FUNCTION (Yes or ho) (Seconcs) l VD-V-752(4) Neutron Shield Tank-Outer Test NA NA VD-V-754(4} Neutron Shield Tank-Inner Test NA NA l
l HC-V-602 Air Purge Bypass RA NA C A-V-755( 6) VCPH Pressure Relief NA NA PU-V-651 Containment Sump to Charging NA NA VD-V-917 LPST 5.V. Discharge Header NA NA B.2 PANUAL VA'VES
. (Net Subject to Type C Testing)
C. CHECK VALVES (Not Subject to Type C Testing)
SI-V-34 (13) Safety Injection (HP) NA NA C5-V-621 (13) Safety Injection (LP) NA NA CH-V-611 M* Feed to Loop #4 NA NA D.1 REMOTE FANUAL VALVES (Subjec.t to Type C Testing)
CC-TV-205(5) Co penent Ccoling Return No NA CC-TV-20B(5) Component Cooling Inlet No NA HV-50V-39 Hydrogen Monitering Yes NA HV-50V-42 Hydrogen Monitoring Yes NA D.2 REMOTE PANUAL VALVES (Net Subject to Type C Testing)
SC-MOV-551/ Shutdown Cooling In No NA 553 (1,2)
SC-MOV-552/ Shutdown Cooling Out No NA 554 (1,2)
CH-MOV-522(7) MC Feed-to-Loop Fill Header No NA 51-MOV-516 ECCS Recirculation No NA SI-MOV-517 'ECCS Recirculation No NA YANKEE ROVE 3/4 6-12 Amendment No. 69, k.[
l l
TABLE 3.6-1 (continued)
CONTAINMENT BARRIERS TESTABLE DURING ISOLATION TIME VALVE FUMBER FUNCTIOU PLANT OPERATION (Yes or Wo) (Seconds)
E.1 BAPRIERS (Subject to Type B Testing)
NA NA Demineralized Water Supply (Blank Flange) NA NA Cavity Purification (Blank Flange) NA NA L.P. Vent Header (Blank Flange) NA NA Personnel Airlock WA NA Electrical Penetrations NA NA Fuel Chute (Blank Flange)(9) NA NA Air Purge Inlet (Blank Flange) NA NA Air Purge Outlet (Blank Flange) NA NA l LPST Safety Valve Discharge Header 5 Blank Flanges (9) NA Fuel Chute Dewctering Pump Discharge (Blank Flange) NA E.2 BARRIERS (Not Subject to Type B Testing)
NA NA 18" Bolted Manway NA Containment Leg Expansion Joints NA NA NA Fuel Chute Eyjansion Joints (9) NA NA Equipment Hatch NA Containment Top Manhole Cover NA NA NA Containment Bottom Manhole Cover NA Pressurizer Heise Gauge Line NA NA NA Containment Pressure Sensing Lines (two)
F. SAFETY VALVES (Subject to Type C Testing)
LPST Safety Valve (9) NA NA 37-215 NA FA.223 Valve Stem Leakoff Safety Valve NA NA NA Si-227 CCST Safety Valve 9
TABLE 3.6-1 (Continued)
TABLE NOTATION (1) T.S. 4.6.1.1.a.1 not applicable while in Modes 1 or 2, due to ALARA considerations.
(2) Valves may oe open under administrative control while in Mode 4.
(3) Valves may be open under administrative control while in Modes 1, 2, 3, or 4 for containment air charge.
(41 Valves may be open under administrative control while in Modes 1, 2, 3, or 4 for neutron shield tank leakage test.
(5) Normally open and closed by administrative controls.
(6) CA-V-755 may be unlocked when personnel are in the Vapor container. Valve may be open while in Modes 1, 2, 3, or 4 for depressurization of the V.C. personnel hatch during containment access or for testing.
(7) CH-MOV-522 may be energized under administrative controls.
(8) Valves may be open under administrative control while in Modes 1, 2, 3, or 4 for surveillance testing.
(9) T.S. 4.6.1.1.a.1 and 4.6.1.1.c not applicable while in Modes 1, 2, 3, or 4, due to ALARA considerations.
(10) Containment sample valves (VD-V-1107 and VD-V-1108) and their test taps (VD-V-902 and VD-V-909) may be open under administrative control in order to sample containment air.
(11) The ACTION statements of T.S. 3.6.2, 3.0.3 and 3.0.4 do not apply.
(12) Secondary isolation valves may be open under adminsitrative controls. j (13) Test taps SI-V-94 and SI-V-98 may be open under administra- !
tive control to relieve safety injection discharge header !
pressure following surveillance testing.
)
(14) Strainer Blowdown Valves may be open under administrative control during system startup or for strainer cleanout.
YANKEE-ROWE 3/4 6-15 Amendment No. ps' 1
. _ _ -. , - . .- - : -. -.-_l