|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212B5741999-09-0505 September 1999 Rev 11 to 2000-ADM-4532.04, Oyster Creek Emergency Offsite Dose Calculation Manual ML20209H5051999-07-14014 July 1999 Proposed Tech Specs Pages 3.1-15 & 3.1-17 of Table 3.1.1 ML20209E0951999-07-0707 July 1999 Proposed Tech Specs,Changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20212H5441999-06-18018 June 1999 Proposed Tech Specs Reflecting Installation of Addl SFP Storage Racks That Will Accommodate Increase in Spent Fuel Assemblies Beyond Existing Storage Capacity of SFP as Described in Licensing Rept ML20195D0761999-06-0303 June 1999 Proposed Tech Specs,Permitting Plant Operation with Three Operable Recirculation Loops ML20205P8531999-04-15015 April 1999 Proposed Tech Specs,Modifying Number of Items in Sections 2 & 3 of Tss,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4 ML20198K0671998-12-23023 December 1998 Proposed Tech Specs Pages 3.8-2 & 4.8-1,changed to Specify Surveillance Frequency of Once Per Three Months ML20195C6561998-11-10010 November 1998 Proposed Tech Specs Section 5.1.A,removing Restriction on Sale or Lease of Property within Exclusion Area ML20155J7501998-11-0505 November 1998 Proposed Tech Specs,Modifying Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & to Verify Channel Operability ML20151V5091998-09-0303 September 1998 Proposed Tech Specs 3.4.A.10.e & 3.5.A.2.e Re Condensate Storage Tank Level ML20237D9591998-08-21021 August 1998 Proposed Tech Specs Removing Requirement for ADS Function of EMRV to Be Operable During Rv Pressure Testing & Correcting Note H of Table 3.1.1 ML20237B2221998-08-0606 August 1998 Proposed Revised Tech Specs Pages for Change Request 205,dtd 961031,correcting Minor & Inadvertent Editorial Changes in Locations Where Changes Have Not Been Proposed ML20236T1211998-07-23023 July 1998 Proposed Tech Specs Pages for Amend to License DPR-16,to Establish That Existing SLMCPR Contained in TS 2.1.A Is Applicable for Next Operating Cycle (Cycle 17) ML20236T4811998-07-21021 July 1998 Proposed Tech Specs Re Changes to Administrative Controls ML20236T4981998-07-21021 July 1998 Proposed Tech Specs Re Reactivity Control ML20236J1431998-06-30030 June 1998 Proposed Tech Specs,Consisting of Revised Page 3-5 Re RPV Pressure/Temp Limits ML20236H2181998-06-29029 June 1998 Proposed Tech Specs,Modifying EDG Insp Requirement Previously Submitted in Entirety ML20248K2851998-05-28028 May 1998 Proposed Tech Specs Re That Such First Type a Test Required by Primary Containment Leakage Rate Testing Program Be Performed During Refueling Outage 18R ML20197G2771997-12-23023 December 1997 Proposed Tech Specs Reflecting Change in Trade Name of Owner & Operator of Oyster Creek Nuclear Generating Station ML20197J2561997-12-10010 December 1997 Proposed Tech Specs Changing Pages 2.3-6,2.3-7,3.1-11, 3.1-14,3.1-16,3.4-8,3.8-2,3.8-3,4.3-1,4.5-13 & 6-1 ML20210L3311997-08-15015 August 1997 Proposed Tech Specs,Incorporating Note Which Indicates That Proposed Change to SL Mcrp Applicable for Current Operating Cycle (Cycle 16) Only ML20135C2001996-11-27027 November 1996 Proposed Tech Specs Pages 4.7-1,4.7-2,4.7-3 & 4.7-4 Re Surveillances for Station Batteries ML20129K3401996-11-12012 November 1996 Proposed Tech Specs,Consisting of Change Request 224, Implementing Revised 10CFR20, Stds for Protection Against Radiation Effective 910620 ML20134H0541996-10-31031 October 1996 Proposed Tech Spec,Requesting Deletion of Table 3.5.2 ML20129C0691996-10-10010 October 1996 Proposed Tech Specs,Clarifying Functional Requirement to Provide Interlock Permissive Which Ensures Source of Cooling Water Available Via Core Spray Sys Prior to Depressurization ML20129A5731996-10-10010 October 1996 Proposed Tech Specs,Revising Addl Group of Surveillances Where Justification Completed Following Receipt of Amend 144 ML20134F4101996-10-0404 October 1996 Proposed Tech Specs 2.1.A & 3.10.C to Reflect Change in SLMCPR & Revise Operating CPR Limit for Stability, Respectively ML20117E7061996-08-23023 August 1996 Proposed Tech Specs,Proposing New pressure-temp Limits Up to 22,27 & 32 EFPY Based on Predicted Nilductility Adjusted Ref Temp for Corrresponding EFPY of Operation ML20115G2101996-07-17017 July 1996 Proposed Tech Specs,Allowing Implementation of 10CFR,App J, Option B ML20113A8641996-06-19019 June 1996 Proposed Tech Specs Table of Contents,1.24 Re Footnote to definition,1.25 Re Definition,Section 3.5.A.3b Re Containment,Section 4.5 Re Containment,Bases for Section 4.5 & Section 6.9.3.b Re Reporting Requirements ML20111A3841996-05-0707 May 1996 Proposed Tech Specs,Adopting Provisions of STS NUREG-1433, Rev 1,dtd 950407,Sections SR 3.0.1,3.0.3 & Associated Bases ML20107E7751996-04-15015 April 1996 Proposed Tech Specs 5.3.1 Re Handling Heavy Loads Over Irradiated Fuel ML20101P1561996-03-31031 March 1996 Rev 9 to Oyster Creek Nuclear Generating Station Pump & Valve IST Program ML20101J7681996-03-28028 March 1996 Proposed Tech Specs,Modifying Statements in TS & Bases to Correctly Reflect Ref Parameter for Anticipatory Scram Signal Bypass ML20101J6091996-03-25025 March 1996 Proposed Tech Specs,Deleting Spec Which Requires Thorough Insp of EDG Every 24 Months During Shutdown ML20100J9151996-02-23023 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20100H9971996-02-22022 February 1996 Proposed Tech Specs 3.7-1,3.7-2,4.7-1 & 4.7-2 Re Deletion of TS Requirement to bi-annually Inspect EDG & Mod of Spec Re AOT ML20095C1031995-12-0505 December 1995 Proposed Tech Specs Re Rev of Submittal Date for Annual Exposure Data Rept Bringing Plant Into Conformance w/10CFR20.2206 & Relaxing Overly Restrictive Administrative Requirement ML20086A7161995-06-26026 June 1995 Proposed Tech Specs Re Performance of Reactor Shutdown & Drywell to Inspect Snubbers in Svc for Only 12 Months ML20080P6501995-02-28028 February 1995 Proposed Tech Specs Change Request 225 Re Change to Page 6-4 of Tech Spec Section 6.5.1.12.Change Consistent w/NUREG-1433,STSs General Electric Plants,BWR/4,Rev 0,dtd 920928 ML20078N3791995-02-0808 February 1995 Proposed Tech Specs Re Oyster Creek Spent Fuel Pool Expansion ML20078Q6481994-12-15015 December 1994 Revised TS & Bases Pages to Section 3.1 of TS Change Request 191 ML20078M1431994-11-25025 November 1994 Proposed TS 5.3.1.E,allowing 2,645 Fuel Assemblies to Be Stored in Fuel Pool ML20073F9501994-09-26026 September 1994 Revised Plan for Long Range Planning Program for Oyster Creek Nuclear Generating Station ML20073F9411994-09-26026 September 1994 Revised Plan for Long Range Planning Program for TMI Nuclear Station Unit 1 ML20072S2921994-09-0202 September 1994 Proposed Tech Specs Supporting Rev of APRM Channel Calibr Interval from Weekly to Quarterly ML20072Q4251994-08-20020 August 1994 Rev 0 to Oyster Creek Nuclear Generating Station Sea Turtle Surveillance,Handling & Reporting Instructions for Operations Personnel ML20072L4741994-08-19019 August 1994 Proposed Tech Specs Control Rod Exercising & Standby Liquid Control Pump Operability Testing ML20070J7971994-07-31031 July 1994 Rev 8 to Oyster Creek Nuclear Generating Station Pump & Valve Inservice Testing Program ML20070E3411994-07-0808 July 1994 Proposed Tech Specs Re Improved Protection to Safety Related Electrical Equipment from Loss of Capability 1999-09-05
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20212B5741999-09-0505 September 1999 Rev 11 to 2000-ADM-4532.04, Oyster Creek Emergency Offsite Dose Calculation Manual ML20101P1561996-03-31031 March 1996 Rev 9 to Oyster Creek Nuclear Generating Station Pump & Valve IST Program ML20073F9501994-09-26026 September 1994 Revised Plan for Long Range Planning Program for Oyster Creek Nuclear Generating Station ML20073F9411994-09-26026 September 1994 Revised Plan for Long Range Planning Program for TMI Nuclear Station Unit 1 ML20072Q4251994-08-20020 August 1994 Rev 0 to Oyster Creek Nuclear Generating Station Sea Turtle Surveillance,Handling & Reporting Instructions for Operations Personnel ML20070J7971994-07-31031 July 1994 Rev 8 to Oyster Creek Nuclear Generating Station Pump & Valve Inservice Testing Program ML20078A7821994-06-24024 June 1994 Purge & Vent Containment Isolation Valves Resilient Seal Maintenance/Surveillance Program & Technical Basis ML20064G5391994-01-14014 January 1994 Rev 0 to Div I Mod Design Description MDD-OC-622-C Div I, Replacement of Recirculation Flow Monitoring Electronics ML20046B5271993-07-29029 July 1993 Emergency Operating Procedures for Oyster Creek,Including Rev 1 to 2000-EMG-3200.01A,.01B,.04A,.04B,.08A,.08B,Rev 2 to 2000-EMG-3200.12,Rev 4 to 2000-EMG-3200.05,Rev 5 to 2000-EMG-3200.10,.11 & Rev 9 to 2000-EMG-3200.02 ML20045E6931993-06-28028 June 1993 Rev 52 to Procedure 2000-RAP-3024.01, NSSS Annunciator Response Procedure. ML20056C3151993-05-0707 May 1993 Rev 1 to Vol IV of Gpun ISI & NDT Manual ML20085L4141991-10-31031 October 1991 Rev 7 to Pump & Valve Testing Program ML20086B5131991-07-16016 July 1991 Rev 5 to Radiological Controls Policy & Procedure Manual 9300-ADM-4010.03, Oyster Creek Emergency Dose Calculation Manual ML20062G8641990-10-0404 October 1990 Rev 0 to Functional Requirements for Augmented Drywell Insp ML20062B9401990-09-17017 September 1990 Rev 2 to TR-050, Gpun Response to Generic Ltr 88-01 & NUREG-0313,Rev 2 ML20043C2511990-05-25025 May 1990 Rev 4 to Radiological Controls Policy & Procedure Manual 9300-ADM-4010.03, Emergency Dose Calculation Manual. ML20245K7441989-06-0606 June 1989 Rev 3 to 9300-ADM-4010.03, Oyster Creek Emergency Dose Calculation Manual ML20246B6221989-03-25025 March 1989 Rev 2 to 9300-ADM-4010.03, Oyster Creek Emergency Dose Calculation Manual ML20195K0511988-05-26026 May 1988 Oyster Creek,12R Outage,Igscc Insp/Stress Improvement Plans ML20147F9331987-08-25025 August 1987 Rev 3 to Procedure 1000-ADM-1291.01, Procedure for Nuclear Safety & Environ Impact Review & Approval of Documents ML20204B4131987-03-12012 March 1987 Rev 5 to Pump & Valve Inservice Testing Program ML20062G8521987-02-19019 February 1987 Rev 8 to Functional Requirements for Drywell Containment Vessel Thickness Exam ML20205E7891986-08-0707 August 1986 Rev 0-03 to Corporate Procedure 1000-ADM-1291.01, Safety Review & Approval Procedure ML20214S6621986-04-0909 April 1986 Rev 0 to Emergency Preparedness Exercise Scenario 6. W/Four Oversize Maps ML20205E7051986-03-0909 March 1986 Rev 2 to Oyster Creek Nuclear Generating Station Procedure 105.3, Maint of Oyster Creek Environ Qualified Equipment ML20205E6731986-02-21021 February 1986 Rev 1-01 to Procedure 5000-ADM-7311.03, Project Reviews ML20209H3111985-10-31031 October 1985 Emergency Operating Procedure Writer'S Guide ML20138J3821985-10-22022 October 1985 Rev 2 to Standing Order 38, Reactor Low Level Alarm Response W/Yarways Out of Svc ML20138J1381985-10-0303 October 1985 Rev 16 to Procedure 116, Surveillance Test Program. W/ Cross-Ref of Surveillance Procedures & Tech Specs ML20205E6791985-09-13013 September 1985 Rev 1-01 to Technical Functions Div Procedure 5000-ADM-7313.01, Mod & Sys Design Descriptions ML20205E6551985-06-14014 June 1985 Rev 0-01 to Technical Functions Div Procedure 5000-ADM-7317.01, Equipment Environ Qualification ML20205E7261985-05-31031 May 1985 Rev 0-00 to Corporate Procedure 1000-POL-7317.01, Environ Qualification of Equipment ML20205E7951985-02-0101 February 1985 Safety Review Training Program Description. Related Info Encl ML20095C6831984-07-25025 July 1984 Rev 1 to Procedure 125, Engineering Calculations & Technical Evaluations ML20090J3291984-05-10010 May 1984 Annual Exercise Scenario,840510 ML20082G6221983-10-0101 October 1983 Offsite Dose Calculation Manual ML20077L6421983-07-29029 July 1983 Procedure Generation Package for Emergency Operating Procedures ML20076K3541983-06-30030 June 1983 Program Plan for Control Room Human Factors Review at Oyster Creek Nuclear Generating Station ML20085J0781983-05-20020 May 1983 Public Version of Revised Emergency Plan Implementing Procedures EPIP-1 Re Classification of Emergency Conditions, EPIP-4 Re Site Emergency & EPIP-5 Re General Emergency ML20071Q3831983-05-0505 May 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPIP-5 Re General Emergency, EPIP-1 Re Classification of Emergency Conditions & EPIP-3 Re Alert ML20028D7261982-12-22022 December 1982 Public Version of Revised Emergency Plan Implementing Procedures EPIP-07 Re Personnel injury,EPIP-09 Re Offsite Dose Projections & EPIP-22 Re Search & Rescue Operations ML20065A1521982-11-0202 November 1982 Public Version of Rev 1 to Emergency Plan Implementing Procedures EPIP-26 Re Activation of Technical Support Ctr & EPIP-27 Re Activation of Operations Support Ctr ML20023B0781982-09-23023 September 1982 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPIP-10 Re Emergency Radiological Surveys Onsite & EPIP-25 Re Nearsite Emergency Operations Facility (Neof) ML20069F2031982-08-17017 August 1982 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPIP-1 Re Classification of Emergency conditions,EPIP-2 Re Unusual Event & EPIP-3 Re Alert ML20063G1261982-07-0101 July 1982 to Tech Spec for Water Quality ML20050D3691982-03-12012 March 1982 Public Version of Emergency Plan Implementing Procedures, Including Procedures EPIP-01 Re Classification of Emergency conditions,EPIP-02 Re Unusual Event & EPIP-03 Re Alert ML20039A7221981-11-24024 November 1981 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPIP-1 Re Classification of Emergency conditions,EPIP-2 Re Unusual Event & EPIP-3 Re Alert ML20064N2731981-09-24024 September 1981 Inservice Insp-Plan B ML20009C2711981-07-0707 July 1981 Process Control Program for In-Container Solidification of Concentrated Liquid Waste & Filter Sludge. ML20080Q6171981-05-21021 May 1981 Rev 0 to Stress Analysis for Demonstration of Operability of Purge & Vent Valves During Dbas 1999-09-05
[Table view] |
Text
- s Number OYSTER CREEK NUCLEAR GENERATING (UCIGar STATION PROCEDURE Standing Order 38
Reactor Low Level Alarm Response with Yarways Out-of-Service 2 Applicabdity/ Scope Responsible Office Plant ations Applies to work at Oyster Creek This document is important to safety B Yes O No Effective Date ThisRevision2incorpoYligEyggygg{p]gn Temporary Changes: ,
TC-10/21/85-2 .
Page Revision 1.0 2 2.0 0 3.0 2 4.0 ,
I 5.0 0 6.0 0 7.0 1 8.0 1 El-1 1 E2-1 1 NON-CONTPOLLU.
Thg r,r;.cacnont Yv, . NOt a ;(opt Up To Date h,D $Ntot Ct00k Signature Concurring Organization Element Date Originator h h [ [ h 9 eve /-ss Operations Control /o. 22 W Concurred by bh[L. Plant Operations Director /8[Il[g[
INM ~
h PRG Chairman /0
(/ (;
v 5
=
B510290'3r 85 jg9
- PDR ADOCK 0 PDR .
j P Q
Approved by Vice President and Director, O.C. / &[NI
~
A00oloS1 2 84 (12048) 10
Number OYSTER CREEK NUCLEAR GENERATING NUCIGar STATION PROCEDURE Standing Order 38
- Reactor Low Level Alarm Response Revision No.
with Yarways Out-of-Service o 1.0 APPLICAE,ILITY 1.1 This Standing Order provides direction for response to Reactor Vessel Low Level Alarms (H-7-e, H-8-e) and/or unexpected changes in reactor vessel water level greater than 10" during reactor .
shutdown with the Yarway reactor vessel water level instrumentation disabled.
1.2 This Standing Order provides for Standby Gas Treatment System Initiation, if normal Reactor Building ventilation becomes inoperable while the Yarway reactor water level instrumentation is disabled.
1.3 This Standing Order provides direction for assuring that the Core Spray System remains filled, if power to MCC IB21A, MCC 1821B or to the core spray fill pumps is lost.
CAUTION:
HHEN THE YARWAY LEVEL INSTRUMENTS ARE DISABLED, AUTOMATIC INITIATION OF THE SAFETY SYSTEMS AT THE 'LOH-LOW' LEVEL IS NOT OPERABLE. BY THIS STANDING ORDER MANUAL INITIATION OF THE 'LOH-LOW' LEVEL SAFETY FUNCTIONS IS REQUIRED AT THE
' LOW' LEVEL AS AN ADDITIONAL MARGIN OF SAFETY.
S 5
o 3
2 i
a i
A i s ii.82
. 2.0
4MC.SarI OYSTER CREEK NUCLEAR GENERATING STATION PROCEDURE Standing Order 38
"* Reactor Low Level Alarm Response ReWsion No.
with Yarways Out-of-Service 2 2.0 PREREQUISITES 2.1 Reactor is in cold shutdown condition and primary containment integrity is no longer required, AND The requirements of note gg to Technical Specification Table 3.1.1 are met.
gg) "These functions.are not required to be operable when secondary containment is not required to be maintained or when the conditions of Section 3.5.B.I.a. b, c, and d are met, and reactor water level is closely monitored and logged hourly. The Standby Gas Treatment System will be manually initiated if reactor water level drops to the low level tr{p setpoint".
2.2 Both core spray systems must, as a minimum, meet the requirements for reduced availability as specified in Technical Specification 3.4.A.7, 3.4.A.8, or 3.4.A.10.
2.3 Annunciator H-8-e, "B GEMAC LO LVL", has been temporarily connected to the "B" GEMAC level instrument. The alarm setpoint 1
1 146" TAF.
5 2.4 Reactor level select switch is positioned to "A" GEMAC level
@ instrument. Annunciator H-7-e, "RX LVL HI/LO", will alarm when 5
"A" GEMAC 1 146" TAF or 1 175" TAF.
2.5 "A" GEMAC, "B" GEMAC and the wide range GEMAC level instrument h readings are logged every 30 2 10 minutes.
i m m n 82
<,2o..> 3.0
Number Nuclear YSTER CREEK NUCLEAR GENERATING STATION PROCEDURE Standing Order 38
- Reactor Low Level Alarm Response Revision No.
with Yarways Out-of-Service 1 2.6 All licensed Control Room personnel shall have read this Standing Order prior to assuming shift responsibilities under the plant conditions to which the Standing Order applies. .
2.7 At least one SGTS Train must be available at all times.
2.8 The Emergency Diesel (s) providing power to the Core Spray Pumps and the SGTS Train used to meet the requirements of this Standing Order must be operable and available.
2.9 Any Primary Containment Isolation Valve defined in Table 38-1 that y is irioperable must be listed in Table 38-2 with a backup isolation valve listed.
s 2
5 1
8 A i s n 82
<izo.,> 4.0
Number
-gIII lIIIII OYSTER CREEK NUCLEAR GENERATING STATION PROCEDURE Standing Order 38 d'
Reactor Low Level Alarm Response Revision No.
with Yarways Out-of-Service o 3.0 INSTRUCTIONS FOR REACTOR RATER LOH LEVEL Upon receiving a reactor low level alarm, or if an unexpected change in vessel level of 10" or greater is observed on cny narrow or wide range GEMAC level instrument, then take the following actions.
3.1 Confirmatory Action Check the narrow and wide range GEMAC level instruments for rea.ctor water level below 146" TAF.
CAUTION:
AUTOMATIC INITIATION OF SAFETY FUNCTIONS AT THE 'LOH-LOH' LEVEL IS DISABLED HITH YARHAY LEVEL INSTRUMENTS INOPERABLE.
THE FOLLOHING ACTIONS MUST BE PERFORHED MANUALLY.
3.2 Manual Corrective Actions 3.2.1 For Reactor Hater Level Less Than 146" TAF on Any One Level Instrument (Low Hater Alarm Setpoint) or For Unexpected Changes in Vessel Level of 10" or Greater 3.2.1.1 Notify Rad Con to evacuate the drywell.
- 3. 2.1. 2 Check drywell equipment drain tank and sump for indications of leakage. If leakage is indicated and if conditions permit, dispatch an operator 5 to the drywell to visually identify leakage.
? 3.2.1.3 Restore reactor water level to the normal range.
5 3.2.1.4 Continuously monitor water level until it stabilizes in normal range.
a
^**" 5 " .82 tiaa.,> 5.0
Number (UCIGar OYSTER CREEK NUCLEAR GENERATING STATION PROCEDURE Standing Order 38
- Reactor Low Level Alarm Response Revision No.
with Yarways Out-of-Service o 3.2.2 For Reactor Water Level Less Than 138" TAF on Any One Level Instrument (Low Hater Scram Setpoint)
_ NOTE: .
Reactor level less than 138" TAF constitutes an entry condition for EMG-3200.01, "RPV Control". The below steps should be followed concurrently with EMG-3200.01.
However, EMG-3200.01 takes precedence, if conflicts arise.
CAUTION:
j AUTOMATIC INITIATION OF THE AB0VE SAFETY FUNCTI0flS IS DISABLED HITH YARWAY LEVEL INSTRUMENTATION INOPEP.ABLE.
THE ABOVE ACTIONS MUST BE PERFORMED MANUALLY.
3.2.2.1 Isolate the reactor vessel (MSIV's Isolation Condenser Vent Valves, MSIV drain line valves, V-24-30, Instrument and Nitrogen Supply to Drywell).
3.2.2.2 Start core spray pumps and begin injection into the RPV until it can be determined that RPV level is > 146" TAF.
3.2.2.3 Start diesel generators.
S
- 3.2.2.4 Initiate Standby Gas Treatment System and 5
g confirm Rx Building isolation.
?
O 3.2.2.5 Trip the recirc pump breakers.
T 3.2.2.6 Isolate the Reactor Cleanup System.
O i 3.2.2.7 Isolate the Shutdown Cooling System.
e GUClear OYSTER CREEK NUCLEAR GENERATING STATION PROCEDURE Standing Order 38
- Reactor Low Level Alarm Response ReWsion No.
with Yarways Out-of-Service 1 3.2.2.8 Isolate each Primary Containment Penetration listed in Table 38-1 by closing at least 1 one (1) valve in each penetration. Refer to Table 38-2 when any isolation valve in :
Table 38-1, or any valve specified in 1
Steps 3.2.2.1, 3.2.2.4, 3.2.2.6, and 3.2.2.7, is inoperable.
3.2.2.9 Clear the OW of all personnel and shut at least (1) one drywell airlock door.
3.2.2.10 Ensure all penetrations to Primary Containment are closed, including manways and penetration flanges.
5 n
5 N
5 i
k e
cizo.,, 7.0
Number OYSTER CREEK NUCLEAR GENERATING NUCIGar STATION PROCEDURE Standing Order 38
"* Reactor Low Level Alarm Response Revision No.
with Yarways Out-of-Service 1 4.0 INSTRUCTIONS FOR LOSS OF REACTOR BUILDING VENTILATION Upon loss of Reactor Building ventilation (L-4-c, L-5-c), then:
4.1 Confirmatory Actions a.
4.1.1 Check for trip of Reactor Building ventilation. .
4.1.2 Check for auto-initiation of Standby Gas Treatment System.
4.2 Manual Corrective Actions 4.2.1 Attempt restart of Reactor Building vedtllation system.
4.2.2 If Reactor Building ventilation cannot be restored, initiate Standby Gas Treatment System.
4.2.3 If Standby Gas Treatment cannot be initiated, comply with Technical Specification 3.5.b.la, b, c, d, and e.
5.0 INSTRUCTIONS FOR LOSS OF POWER TO MCC IB21A, 1821B or CORE SPRAY FILL PUMPS Upon loss of power to motor control centers IB21A, 1821B or loss of any Core Spray Fill Pump, then:
5.1 Manual Corrective Actions 5.1.1 If the Core Spray fill Pump (s) is not restarted within 5 minutes, start a Core Spray Main Pump in any system that does not have a fill pump operating. DO NOT INJECT INTO THE RPV UNLESS REQUIRED BY THIS STANDING ORDER OR g EMERGENCY OPERATING PROCEDURES.
@ 5.1.2 Continue to operate the Core Spray Main Pump until power 5
= is restored to the Core Spray Fill Pump.
2 k
A i s n 82 c ,2 a u ) 8.0
(UCl88r YSTER CREEK NUCLEAR GENERATING STATION PROCEDURE Standing Order 38
- Reactor Low Level Alarm Response ReWsi n No.
with Yarways Out-of-Service 1 TABLE 38-1 CONTAINMENT PENETRATIONS AND ISOLATION VALVES Penetration Isolation Valve (s) .,
RBCCH Inlet V-5-147 RBCCH Outlet V-5-166, -167 Reacto.- Head Cooling V-31-2 DHEDT . V-22-1, -2 PASS Liquid Poison Sample Valve V-40-6 DH Sump V-22-28 -29 Torus to Reactor Building V-26-16, V-26-15' Vacuum Breakers V-26-18, V-26-17' TIP System TIP Machine Ball Valves TIP N2 Purge V-23-70 H2 Sensing Line V-38-37, -38, -39, -40, -44, -46 Recirc Loop Sample Line V-24-29, -30 Torus 02 Sample Line V-38-22. -23 DH 02 Sample Line V-38-9, -10 DH Vent V-27-1, -2, V-23-21, -22 DH Purge V-27-3, -4, V-23-13, -14, -17. -18 Torus Vent V-28-17, -18, -47 2_
g Torus Purge V-23-15, -16. 20 9
g Torus Particulate Monitor V-38-16 -17 h
$ ' NOTE: Tied open for ventilation. Untie and close if V-26-16 (-18) cannot be isolated, if required.
(120*P> A000105011 82 El-1
""*D" Nuclear OYSTER CREEK NUCLEAR GENERATING STATION PROCEDURE Standing Order 38
- Reactor Low Level Alarm Response Revision No.
with Yarways Out-of-Service 1 TABLE 38-2 CONTAINMENT ISOLATION VALVES NOT IN SERVICE AND RESPECTIVE REDUNDANT ISOLATION VALVE VALVE 005 PENETRATION REDUNDANT VALVE DATE/ TIME RETURNED s
5 cizo A i s n.82 l >
E2-j
_ _ .