Replacement Pages 147,156,157 & mark-up Pages to Proposed TS Change 190,removing Ref to Documents Outside of TS That Define Components to Which Program AppliesML20199K850 |
Person / Time |
---|
Site: |
Vermont Yankee ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
---|
Issue date: |
11/21/1997 |
---|
From: |
VERMONT YANKEE NUCLEAR POWER CORP. |
---|
To: |
|
---|
Shared Package |
---|
ML20199K844 |
List: |
---|
References |
---|
NUDOCS 9712010218 |
Download: ML20199K850 (6) |
|
|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217N3001999-10-21021 October 1999 Proposed Tech Specs,Correcting Two Textual Errors & Changing Designation of Referenced Figure ML20217K8731999-10-18018 October 1999 Proposed Tech Specs Revising Activated Charcoal Testing Methodology IAW Guidance Provided in GL 99-02 ML20212F6941999-09-21021 September 1999 Proposed Tech Specs,Increasing Required Vol of Stored Fuel in Diesel Fuel Oil Storage Tank ML20211J0211999-08-31031 August 1999 Proposed Tech Specs Bases Page 91,allowing Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line (Predicted) Uncorrected Solution & on-line (Measured) 3D-Monicore Exposure Corrected Solution ML20211B7051999-08-18018 August 1999 Proposed Tech Specs Revising Reactor Core Spiral Reloading Pattern to Begin Around SRM ML20211B6781999-08-18018 August 1999 Proposed Tech Specs Revising Definition of Surveillance Frequency to Incorporate Provisions That Apply Upon Discovery of Missed TS Surveillance ML20210D2481999-07-20020 July 1999 Proposed Tech Specs Revising & Clarifying Operability & SRs of High Pressure Core Cooling Systems ML20210D3371999-07-20020 July 1999 Proposed Tech Specs Re Enhancements to Support Implementation of Increased Core Flow ML20209G1671999-07-12012 July 1999 Proposed Tech Specs Revising Value for SLMCPR & Deleting Wording Which Specifies These as Cycle 20 Values ML20196K2951999-06-29029 June 1999 Proposed Tech Specs Pages for Proposed Change 220,revising Leak Rate Requirements of TS 3.7.A.4 & 4.7.A.4 for Main Steam Line Isolation Valves ML20196H2881999-06-24024 June 1999 Proposed Tech Specs Revising & Clarifying Terminology Re Certain RPS Scram Bypass Permissives ML20195J8691999-06-15015 June 1999 Proposed Tech Specs Increasing Stis,Adding Allowable OOS Times,Replacing Generic ECCS Actions for Inoperable Instrument Channels with function-specific Actions & Relocating Selected Trip Functions from TS ML20195F9531999-06-0909 June 1999 Proposed Tech Specs,Supplementing Proposed Change 213, Allowing Use of ASME Code Case N-560,per GL 88-01 ML20195C8841999-05-26026 May 1999 Proposed Tech Specs Clarifying Suppression Chamber Water Temp SR 4.7.A, Primary Containment & Modifying Associated TS Bases ML20206H3771999-05-0606 May 1999 Proposed Tech Specs Pages ,Eleting Specific Leak Rate Requirements of TS 3.7.A.4 & 4.7.A.4 ML20206J7231999-05-0505 May 1999 Proposed Tech Specs Pages for Proposed Change 212,modifying TS to Enhance Limiting Conditions for Operation & Surveillance Requirements Relating to SLC Sys ML20205S9431999-04-20020 April 1999 Proposed Tech Specs,Revising Reactor Core Spiral Reloading Pattern Such That It Begins Around Source Range Monitor ML20205T4721999-04-19019 April 1999 Marked-up Tech Specs Pages Re Suppl to 990201 Request for Amend to License DPR-28,revising Portions of Proposed Change 208 ML20205S4081999-04-16016 April 1999 Proposed Tech Specs Modifying Inservice Insp Requirements of Section 4.6.E to Allow NRC-approved Alternatives to GL 88-01 ML20205S3121999-04-15015 April 1999 Proposed Tech Specs Revised Bases Pages 90,227,164 & 221a, Accounting for Change in Reload Analysis,Reflecting Change in Condensation Stability Design Criteria & Accounting for More Conservative Calculation ML20202E5451999-01-25025 January 1999 Proposed Tech Specs Re Technical Requirements Manual Content ML20206S0661999-01-22022 January 1999 Proposed TS to Change Number 189,proposing Relocation of Fire Protection Requirements from TSs to TRM ML20198D5381998-12-15015 December 1998 Proposed Tech Specs Page 142,correcting Wording to Reflect Previously Approved Wording,Last Revised in Amend 160 ML20198B7421998-12-11011 December 1998 Proposed Tech Specs Changing Wording of Primary Containment Integrity Definition to State That Manual PCIVs Which Are Required to Be Closed During Accident Conditions May Be Opened Intermittently Under ACs ML20197J4631998-12-10010 December 1998 Proposed Tech Specs Section 4.9.2,revising Info Re Calibr of Augmented Offgas Sys Hydrogen Monitors ML20197H0031998-12-0707 December 1998 Proposed Tech Specs Change 209,resolving Emergency Concern Re Potential Operation Outside of LCO Contained in Current TS & Potential USQ with Respect to Opening of Manual PCIVs During Plant Operation ML20155F7421998-11-0303 November 1998 Proposed Tech Specs Incorporating Minor Corrections or Clarifications Which Enhance Clarity of TSs Without Materially Changing Meaning or Application ML20155G5061998-11-0202 November 1998 Proposed Tech Specs Re ECCS Actuation Instrumentation - LPCI A/B RHR Pump Start Time Delay Requirements & CS Sys A/B Pump Start Delay Requirements ML20151U0131998-09-0404 September 1998 Proposed Tech Specs,Increasing Spent Fuel Storage Capacity of Util Spent Fuel Pool from 2,870 to 3,355 Fuel Assemblies ML20236H4551998-06-30030 June 1998 Proposed Tech Specs Modifying Table 4.2.1 to Delete ECC Actuation Instrumentation Re Core Spray Sys & LPCI Sys Auxiliary Power Monitor Calibr Requirement ML20247E5671998-05-0808 May 1998 Proposed Tech Specs Page 270,containing Wording Inadvertently Deleted from TS Proposed Change 202 ML20247J8121998-05-0808 May 1998 Proposed Tech Specs Reducing Normal Operating Suppression Pool Water Temp Limit & Adding Time Restriction for Higher Temp Allowed During Surveillances That Add Heat to Suppression Pool ML20217P4171998-05-0101 May 1998 Proposed Tech Specs Re Administrative Controls Section ML20217G7131998-04-23023 April 1998 Proposed Tech Specs Change 200 Revising Station SW & Alternate Cooling Sys Requirements ML20217C4591998-03-20020 March 1998 Proposed Tech Specs Re Containment Purge & Vent ML20217A1271998-03-13013 March 1998 Proposed Tech Specs Bases Section 3.10.B,updated to Require That Station Battery,Eccs Instrumentation Battery,Or Uninterruptable Power Sys Battery Be Considered Inoperable If Any One Cell Is Below Specification Cell Voltage ML20202H2611998-02-0606 February 1998 Revised TS Pages Re Change 190,w/typos Corrected ML20197E8481997-12-22022 December 1997 Replacement Pages 160 & 279 & mark-up Pages to Proposed TS Change 190 Containing Editorial Changes ML20203F0131997-12-11011 December 1997 Proposed Tech Specs Revising Current Value for SLMCPR for Cycle 20,next Operating Cycle ML20199K8501997-11-21021 November 1997 Replacement Pages 147,156,157 & mark-up Pages to Proposed TS Change 190,removing Ref to Documents Outside of TS That Define Components to Which Program Applies ML20199J7661997-11-20020 November 1997 Proposed Tech Specs Pages,Revising Requirements for Main Station Batteries ML20217H6931997-10-10010 October 1997 Proposed Tech Specs Revising & Clarifying Requirements for Offsite Power Sources ML20211A6461997-09-18018 September 1997 Proposed Tech Specs,Providing marked-up Pages for Proposed Changes 192 & 193 ML20217Q3311997-08-22022 August 1997 Proposed Tech Specs Pages 245 & 252,amending App a to Modify TS to More Clearly Describe Separation of Switchgear Room Into Two Fire Areas & Incorporate Specifications for New Low Pressure CO2 Suppression Sys ML20217N4111997-08-20020 August 1997 Proposed Tech Specs Pages 270 & 270a,updating Section 6 in Order to Add & Revise Ref to NRC Approved Methodologies Which Will Be Used to Generate cycle-specific Thermal Operating Limits to COLR ML20141H1171997-07-11011 July 1997 Proposed Tech Specs,Replacing Pages 147,156 Through 161,168 & 279 of Util TS W/Corrected Pages ML20148J1861997-06-0909 June 1997 Proposed Tech Specs Change 191,updating Section 6.0 Administrative Controls ML20132B5771996-12-10010 December 1996 Proposed Tech Specs 3.13 Re Fire Protection Sys ML20129C4521996-10-17017 October 1996 Proposed Tech Specs,Revising Pages 89,89a & 90 to Incorporate Changes from Amends 148 & 149 ML20128N6031996-10-11011 October 1996 Proposed Tech Specs,Revising Existing Requirements Re Amount of Foam Concentrate Required to Support Operability of Recirculation Motor Generator Set Foam Sys in TS 3.13.G.1 & 3.13.G.2 1999-09-21
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217N3001999-10-21021 October 1999 Proposed Tech Specs,Correcting Two Textual Errors & Changing Designation of Referenced Figure ML20217K8731999-10-18018 October 1999 Proposed Tech Specs Revising Activated Charcoal Testing Methodology IAW Guidance Provided in GL 99-02 ML20212F6941999-09-21021 September 1999 Proposed Tech Specs,Increasing Required Vol of Stored Fuel in Diesel Fuel Oil Storage Tank ML20211J0211999-08-31031 August 1999 Proposed Tech Specs Bases Page 91,allowing Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line (Predicted) Uncorrected Solution & on-line (Measured) 3D-Monicore Exposure Corrected Solution ML20211B6781999-08-18018 August 1999 Proposed Tech Specs Revising Definition of Surveillance Frequency to Incorporate Provisions That Apply Upon Discovery of Missed TS Surveillance ML20211B7051999-08-18018 August 1999 Proposed Tech Specs Revising Reactor Core Spiral Reloading Pattern to Begin Around SRM ML20210D2481999-07-20020 July 1999 Proposed Tech Specs Revising & Clarifying Operability & SRs of High Pressure Core Cooling Systems ML20210D3371999-07-20020 July 1999 Proposed Tech Specs Re Enhancements to Support Implementation of Increased Core Flow ML20209G1671999-07-12012 July 1999 Proposed Tech Specs Revising Value for SLMCPR & Deleting Wording Which Specifies These as Cycle 20 Values ML20196K2951999-06-29029 June 1999 Proposed Tech Specs Pages for Proposed Change 220,revising Leak Rate Requirements of TS 3.7.A.4 & 4.7.A.4 for Main Steam Line Isolation Valves ML20196H2881999-06-24024 June 1999 Proposed Tech Specs Revising & Clarifying Terminology Re Certain RPS Scram Bypass Permissives ML20195J8691999-06-15015 June 1999 Proposed Tech Specs Increasing Stis,Adding Allowable OOS Times,Replacing Generic ECCS Actions for Inoperable Instrument Channels with function-specific Actions & Relocating Selected Trip Functions from TS ML20195F9531999-06-0909 June 1999 Proposed Tech Specs,Supplementing Proposed Change 213, Allowing Use of ASME Code Case N-560,per GL 88-01 ML20195C8841999-05-26026 May 1999 Proposed Tech Specs Clarifying Suppression Chamber Water Temp SR 4.7.A, Primary Containment & Modifying Associated TS Bases ML20206H3771999-05-0606 May 1999 Proposed Tech Specs Pages ,Eleting Specific Leak Rate Requirements of TS 3.7.A.4 & 4.7.A.4 ML20206J7231999-05-0505 May 1999 Proposed Tech Specs Pages for Proposed Change 212,modifying TS to Enhance Limiting Conditions for Operation & Surveillance Requirements Relating to SLC Sys ML20205S9431999-04-20020 April 1999 Proposed Tech Specs,Revising Reactor Core Spiral Reloading Pattern Such That It Begins Around Source Range Monitor ML20205T4721999-04-19019 April 1999 Marked-up Tech Specs Pages Re Suppl to 990201 Request for Amend to License DPR-28,revising Portions of Proposed Change 208 ML20205S4081999-04-16016 April 1999 Proposed Tech Specs Modifying Inservice Insp Requirements of Section 4.6.E to Allow NRC-approved Alternatives to GL 88-01 ML20205S3121999-04-15015 April 1999 Proposed Tech Specs Revised Bases Pages 90,227,164 & 221a, Accounting for Change in Reload Analysis,Reflecting Change in Condensation Stability Design Criteria & Accounting for More Conservative Calculation ML20202E5451999-01-25025 January 1999 Proposed Tech Specs Re Technical Requirements Manual Content ML20206S0661999-01-22022 January 1999 Proposed TS to Change Number 189,proposing Relocation of Fire Protection Requirements from TSs to TRM ML20198D5381998-12-15015 December 1998 Proposed Tech Specs Page 142,correcting Wording to Reflect Previously Approved Wording,Last Revised in Amend 160 ML20198B7421998-12-11011 December 1998 Proposed Tech Specs Changing Wording of Primary Containment Integrity Definition to State That Manual PCIVs Which Are Required to Be Closed During Accident Conditions May Be Opened Intermittently Under ACs ML20197J4631998-12-10010 December 1998 Proposed Tech Specs Section 4.9.2,revising Info Re Calibr of Augmented Offgas Sys Hydrogen Monitors ML20197H0031998-12-0707 December 1998 Proposed Tech Specs Change 209,resolving Emergency Concern Re Potential Operation Outside of LCO Contained in Current TS & Potential USQ with Respect to Opening of Manual PCIVs During Plant Operation ML20155F7421998-11-0303 November 1998 Proposed Tech Specs Incorporating Minor Corrections or Clarifications Which Enhance Clarity of TSs Without Materially Changing Meaning or Application ML20155G5061998-11-0202 November 1998 Proposed Tech Specs Re ECCS Actuation Instrumentation - LPCI A/B RHR Pump Start Time Delay Requirements & CS Sys A/B Pump Start Delay Requirements ML20196A7851998-10-0909 October 1998 Rev 19 to Vynp IST Program Plan ML20151U0131998-09-0404 September 1998 Proposed Tech Specs,Increasing Spent Fuel Storage Capacity of Util Spent Fuel Pool from 2,870 to 3,355 Fuel Assemblies ML20237E9571998-08-27027 August 1998 Start-Up Test Rept Vynp Cycle 20 ML20236H4551998-06-30030 June 1998 Proposed Tech Specs Modifying Table 4.2.1 to Delete ECC Actuation Instrumentation Re Core Spray Sys & LPCI Sys Auxiliary Power Monitor Calibr Requirement ML20247J8121998-05-0808 May 1998 Proposed Tech Specs Reducing Normal Operating Suppression Pool Water Temp Limit & Adding Time Restriction for Higher Temp Allowed During Surveillances That Add Heat to Suppression Pool ML20247E5671998-05-0808 May 1998 Proposed Tech Specs Page 270,containing Wording Inadvertently Deleted from TS Proposed Change 202 ML20217P4171998-05-0101 May 1998 Proposed Tech Specs Re Administrative Controls Section ML20217G7131998-04-23023 April 1998 Proposed Tech Specs Change 200 Revising Station SW & Alternate Cooling Sys Requirements ML20217C4591998-03-20020 March 1998 Proposed Tech Specs Re Containment Purge & Vent ML20217A1271998-03-13013 March 1998 Proposed Tech Specs Bases Section 3.10.B,updated to Require That Station Battery,Eccs Instrumentation Battery,Or Uninterruptable Power Sys Battery Be Considered Inoperable If Any One Cell Is Below Specification Cell Voltage ML20202H2611998-02-0606 February 1998 Revised TS Pages Re Change 190,w/typos Corrected ML20197E8481997-12-22022 December 1997 Replacement Pages 160 & 279 & mark-up Pages to Proposed TS Change 190 Containing Editorial Changes ML20203F0131997-12-11011 December 1997 Proposed Tech Specs Revising Current Value for SLMCPR for Cycle 20,next Operating Cycle ML20199K8501997-11-21021 November 1997 Replacement Pages 147,156,157 & mark-up Pages to Proposed TS Change 190,removing Ref to Documents Outside of TS That Define Components to Which Program Applies ML20199J7661997-11-20020 November 1997 Proposed Tech Specs Pages,Revising Requirements for Main Station Batteries ML20217H6931997-10-10010 October 1997 Proposed Tech Specs Revising & Clarifying Requirements for Offsite Power Sources ML20211A6461997-09-18018 September 1997 Proposed Tech Specs,Providing marked-up Pages for Proposed Changes 192 & 193 ML20217Q3311997-08-22022 August 1997 Proposed Tech Specs Pages 245 & 252,amending App a to Modify TS to More Clearly Describe Separation of Switchgear Room Into Two Fire Areas & Incorporate Specifications for New Low Pressure CO2 Suppression Sys ML20217N4111997-08-20020 August 1997 Proposed Tech Specs Pages 270 & 270a,updating Section 6 in Order to Add & Revise Ref to NRC Approved Methodologies Which Will Be Used to Generate cycle-specific Thermal Operating Limits to COLR ML20141H1171997-07-11011 July 1997 Proposed Tech Specs,Replacing Pages 147,156 Through 161,168 & 279 of Util TS W/Corrected Pages ML20148J1861997-06-0909 June 1997 Proposed Tech Specs Change 191,updating Section 6.0 Administrative Controls ML20149M7451997-01-24024 January 1997 Startup Test Rept,Vermont Yankee Cycle 19 1999-09-21
[Table view] |
Text
. - ~ . - . - . . . - - - . - - - _ . . - - . -. . - . - _ _ - --- -
I VYNPS 3.7. LIPf1 TING' CONDITIONS FOR 4.7 SURVEILLANCE REQUIREMENTS OPERATION '
- e. Minimum Water ,
Volume .
- f. Maximum Water Volume -
70,000 cubic feet ' i
- 2. Primary containment 2. The primary containment integrity shall be . integrity shall be maintained at all times dt.aonstrated as required when the reactor is by the Primary .
critical or when the Containment Leak Rate I reactor water Testing Program temperature is above. (PCLRTP).
212'F and fuel is in the ,
reactor vessel except- ;
while performing 3ow i power physics tests at .
I atmospheric pressure at power levels not to exceed 5 Mw(t). ,
- 3. -If a portion of a system 3. (Blank) l that is considered to be an extension of primary ,
containn. ant is to be opened, isolate the l affected penetration flow path by use of at i least one closed and '
deactivated automatic '
valve, closed manual valve or blind flange.
- 4. Whenever primary ;
containment is required, 4. The leakage from any one l .
- l. the leakage from any one main steam line ,
main steam line isolation valve shall isolation valve shall not exceed 11.5 scf/hr not exceed 15.5 scf/hr at 24 psig (Pt) . Repadr -
at 44 psig (P.) . and retest shall be conducted to insure compliance.
l l
l-1
' Amendment No,' M ,- 147'
VYNPS 3.9 . LIMITING CONDITIONS FOR 4.7 SURVEILLANCE REQUIREMENTS OPERATION
- 5. Core spray and LPCI pump 5. The core spray and LPCI lower compartment door lower compartment openings shall be closed openings shall be '
at all times except checked closed daily.
during passage or when reactor coolant temperature is less than 212'F.
D. Primary Containment D. Primary Containment Isolation Valves lpolation Valves
- 1. During reactor power
- 1. Surveillance of the operating conditions all primary containment l containment isolation isolation valves should valves and all be performed as follows:
instrument line flow l check valves shall be a. The operable operable except as isolation valves specified in that are power Specification 3.7.D.2. operated and automatically initiated shall be tested for automatic initiation and the closure times specified in Table 4.7.2 at least once per operating cycle.
- b. Operability testing of the primary containment isolation valves shall be performed in accordance with Specification 4.6.E.
- c. At least once per quarter, with the reactor power less than 75 percent of rated, trip all main steam isolation valves (one at a time) and verify closure time,
- d. At least twice per week, the main steam line isolation valves shall be exercised by partial closure and subsequent
- reopening.
l i
Amendment No. W , 84, Me, M4, 444, 156
. - . - - - . _ _ . _ . ..._.-.. -.-.._-.--. - ._.__ ...-_~. _ . _ _ . _ . - - . . -
i I
VYNPS ,
l 4.7 3 /7 LIMITING CONDITIONS FOR SURVEILLANCE REQUIREMENTS O($ RATION
- 2. In the event any 2. Whenever a containment l ,
containment isolation isolation valve is valve becomes inoperable, the position inoperable, reactor of at least one other i power operation may valve in each line j continue provided at having an inoperable least one containment valve shall be logged isolation valve in each daily. l' 1 line having an inoperable valve is in the mode corresponding to the isolated
- condition.
- 3. If' Specifications s 4 3.7.D.1 and 3.7.D.2 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the cold shutdown condition i within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I A
f f
i l
t 1
l.-- Amendment No. 157
. . _ . . . _ _ _ _ _ . . - .._,_...m- _ . _ , _ _ . . _ . _ , , _ _ _ _ _ _ , _ _ , _ - . . , , . . . _ . _ - . , . _ . _ _.
VYNPS 3.7 LIMITING C0!ElITICNS FCR 4.7 StJRVEILI.ANCE RIQUIREMCrtS
.
- e. Minimum Water g - 1 3
Volume . g p,% j 58,000 cubic feet u, dg. y -
g, gagg m y,g,, Pses~ C kat49)
Volume .
l 70,000 cubic feet
- 2. Primary contair:nont 2. The primary containment integrity shall be integrity shall be maintained at all times demonstrated as required when the reactor is critical or when the pe 1x t 5. to w e prgaar cr -p /
reactor water ont nae shall et toscarature is above th cony 41amedt '
212?S and fuel is in the ap6eptance ese a reactor vessel except get eth n t while performing low ap nd power physics tests at 6
atmospheric pressure at . ene ati s ;
power levels not to exceed 5 Hw(t).
se s1 ted T le .7.1 halV
/
1 kt ed 't
- 3. Wlydnevep'prianrv / 44' sig fa).
,atan ta en s - etuir .
the ota rima . e tes a s 11 co ai nt 1 go ate be rfo ed t y 11 ot e eed is at nv ve
.8 eight ereo pe Jdst.e in /
da (L 44 p.) g (F ta oss e / /'Pab t. .2. . /
. / /
- 3. p ior ov- la n he e I 4. Whenever primary rint ri of a em containment is required. ou sid he r ry cpe lee. ave com y e nta , w ich a
/ isolation lv sha co et to y lve[
no xce 5 cce of (%.nk-) li ed n le .7 b, t ==v' "- 11 le e ola on lv ak te .) t pe j u in the pen g acc ont res re ,) / , s 11 ve e to s anW/the leakage from any erf If he one main steam line op in aan be isolation valve shall i la fr t not exceed 15.5 sef/hr ont two at 44 psig (P,). iso atip va es i:./
= c t). a ope c. /
ritefia and J v (1 rt ), bl k y . p,c4.n of a sp% +1n.g f g sha be gs c..otdartA w bc ** *OSaM** ofing/
,,,,-. , e.+...-- .
ts 4 4* *Ps'**A s 4, , a g gr,6m i ; g g.3 % aff.s.4.4 Ps***"*h*^ O* i e va)he 11 p.A %) us,. 94 taa n ont aI* M e ed E% o Lt /
..a 4s. W W4 amba Vic v=W5, The leakage from any one
- g. M e.a -\ vatv e .c 'et * *J fL-3* .
s ne
,g A A not exceed 11.5 scf/hr at 24 psig (Pt). Repair and retest shall be conducted to insure compliance.
Amendment No. 50 147
WNP S 3.7 :,:xn::*3 CONDI? 0NS FCR ~
4.7 SURVULLANCE RICU:RENDrt$
O P DtATION-
. r --
l 5. Core spray sad LPC: pump 5. The core spray and LPc: l lower compartment door lower compart:nent openings shall be closed openings shall be at all times except checked closed daily, during passage or when reactor coolant canoerature is less than 213*F.
D. Primar-/ containment D. Primare centainrnent .
I Isolation Valygg, Isolatten valves
- 1. During reactor power 1. surveillance of the eparating conditions alt primar/ containment e.*M'**a+ isolation velves tMst ed isolation valves should IIh7a41e/li7,M and all be perfor:ned as follows:
instr.anent line flow chec)c valves shall bs a. The operable operable exedpc as isolation valves specified in j that are power Specification 3.7.D.2. i operated and I automatically initiated shall be tested for automatic initiation and the closure times specified in 7able 4.7.2 at least once per operating cycle.
- b. Operability testing of the primary contaLnment isolation valves shall be performed in accordance with specification 4.6.E.
- c. At least once per quarter, with the reactor power less than 75 percent of raced, trip all main steam isolation valves (one at a time) and verify closure ti=e,
- d. At least twice per week. the main steam line
' isolation valves shall be exercised by partial closure and subsequent reopening.
Amendment No. 54, M, u4, H4,147 156
_ _ _ _ . ~ .
, . VYNPS 3.7 LIMITI!C CONDITIONS LtR 4.7 SURVEIILANCE REQUIRD4Ctr2 OPERATION p e wif a e n m e n t p.6 %.n mw
- 2. In the event any 2. Whenever ad iso 14eton isolation' valve .
valveLMitid/ Mv 7/:Lis
' grAg5/W Adbl<{,'[]?$ inoperaale, the pos& tion e inoperaaAO, of at least one other reactor power operacion valve in each line may conciaue provided at having an inoperable least one galve in each . valve shall be logged an daily.
line havingDalva inoperable is in the mode corr'esposding to the isolated condition. c OMbi 4 M M d
\' - - h otste e s
- 3. If specifications 3.7.D.1 and 3.7.D.2 k
cannot; be met, an orderly shutdom. shall be iniciar.ed and the reactor shall be in the cold shut. lown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
e 1
157
, .. ,, . , - . . - - ,