Letter Sequence Other |
|---|
|
|
MONTHYEARML20135H8071985-04-12012 April 1985
Procedure CP.104 Re Transient Occurrence That Leaves RCS Being Cooled by HPI Cooling
Project stage: Other
ML20135H8001985-04-12012 April 1985
Procedure CP.102 Re Normal Cooldown
Project stage: Other
ML20127D9261985-05-10010 May 1985
Requests Fee Re 850412 Application for Permanent Exemption from Installation of Reactor Vessel Head Vent
Project stage: Approval
ML20135H8091985-05-29029 May 1985
Rev 1 to Procedure CP.105 Re Transient Termination Following Occurrence That May Require Pressurizer Recovery Solid Plant Cooldown w/once-through Steam Generator Removing Heat & RCS Subcooled
Project stage: Other
ML20135H8031985-05-29029 May 1985
Rev 1 to Procedure CP.103 Re Transient Termination Following Occurrence That Leaves RCS Saturated w/once-through Steam Generators Removing Heat
Project stage: Other
ML20135H7971985-05-29029 May 1985
Rev 1 to Procedure E.07 Re Operator Action
Project stage: Other
ML20126K2251985-06-17017 June 1985
Submits Fee for 850412 Exemption Request Re Vessel Head Vents (10CFR50.44(c)(3)iii),per 850510 Request
Project stage: Other
ML20135H8121985-08-12012 August 1985
Rev 33 to Procedure B.4 Re Plant Shutdown & Cooldown
Project stage: Other
ML20135H7931985-09-19019 September 1985
Forwards Operating Procedures,Per Miner Request,To Aid in NRC Review of 850412 Request for Permanent Exemption from Requirements of 10CFR50.44(c) Re Installation of Reactor Vessel Head Vent
Project stage: Request
ML20138K6991985-12-11011 December 1985
Environ Assessment & Finding of No Significant Impact Re Util 850412 Application for Exemption from 10CFR50.44(c)(3)(iii) Requirements Re Installation of Reactor Vessel Head Vent
Project stage: Approval
ML20138K6751985-12-11011 December 1985
Forwards Environ Assessment & Finding of No Significant Impact,Re Util 850412 Application for Exemption from 10CFR50.44(c)(3)(iii) Requirements.Notice Forwarded for Fr Publication
Project stage: Approval
ML20137B5421985-12-24024 December 1985
Safety Evaluation Supporting 850412 Exemption Request from Reactor Vessel Head Vent Requirement of 10CFR50.44(c)(3) (III)
Project stage: Approval
ML20137B5311985-12-24024 December 1985
Exemption from Requirements of 10CFR50.44(c)(3)(iii) Re Installation of Reactor Vessel Head Vent & Other Sys Required to Maintain Adequate Core Cooling If Accumulation of Noncondensible Gases Causes Loss of Function of Sys
Project stage: Approval
ML20137B5151985-12-24024 December 1985
Forwards Exemption from Requirements of 10CFR50.44(c)(3) (Iii),Re Installation of Reactor Vessel Head Vent Based on Verification That Noncondensible Gas Bubble Can Be Safely Removed Via Hot Leg High Point Vents,Per 850412 Request
Project stage: Approval
1985-05-10
[Table View] |
|
|---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20203H7501997-08-19019 August 1997
Rev 10 to Radiological Environ Monitoring Program Manual
ML20203H7351997-02-10010 February 1997
Rev 9 to CAP-0002, Off-Site Dose Calculation Manual
ML20203H7231997-01-21021 January 1997
Rev 9 to Radiological Environ Monitoring Program Manual
ML20059C1861993-12-22022 December 1993
Proposed Tech Specs Amend 186,rev 1 Re Nuclear Organizational Changes
ML20058L4371993-12-0909 December 1993
Proposed Tech Specs Amend 187 Including Changes Making PDTS Consistent W/New 10CFR20 Regulations
ML20127N3671993-01-19019 January 1993
Proposed Tech Specs Section D6.0,administrative Controls for Proposed Amend 186
ML20059E0191990-08-0303 August 1990
Rev 0 to CAP-0002, Odcm
ML20059E0141990-01-31031 January 1990
Rev 0,App a to CAP-0002, Odcm
ML20059E0241989-11-22022 November 1989
Rev 3 to Environ Monitoring & Emergency Preparedness
ML20246A4081989-08-16016 August 1989
Rev 5 to Inservice Testing Program Plan
ML20245L7281989-07-18018 July 1989
Rev 5 to Administrative Procedure RSAP-0101, Nuclear Organization Responsibilities & Authorities
ML20246F1241989-07-0505 July 1989
Proposed Tech Specs,Deleting App B in Entirety
ML20246A5221989-06-30030 June 1989
Closure Plan
ML20245H5781989-06-22022 June 1989
Proposed Tech Specs for Amend 109 to License DPR-54
ML20246E8551989-04-30030 April 1989
Analysis of Capsule RS1-F Smud Reactor Vessel Matl Surveillance Program
ML20245L0461989-04-27027 April 1989
Proposed Tech Specs for Proposed Suppl 1 to Amend 134 Re Application for Amend to License DPR-54,clarifying Unacceptability of Analysis Allowing Imperfections Greater than 40% of Nominal Tube or Sleeve Wall Thickness
ML20235Y6071989-03-0606 March 1989
Proposed Tech Spec Page 4-17,including one-time Extension for Certain Surveillances Required to Be Performed by 890329
ML20245G1941989-02-28028 February 1989
Procurement Engineering Assessment Plan Final Rept
ML20245H8911989-02-28028 February 1989
Revised Proposed Tech Specs,Including Pages 3-30a,3-30b, 3-40a,3-45,3-46,4-18a & 4-75 Re Addition of Operating Requirements Designed to Provide Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations
ML20195F7701988-11-18018 November 1988
Proposed Tech Spec Section 3.4, Steam & Power Conversion Sys
ML20206F2881988-11-15015 November 1988
Proposed Tech Specs 4.6.4.f (Page 4-34i) Re Surveillance of Equipment Required to Verify Vital 120 Volt Ac Bus Operability
ML20205R8681988-11-0404 November 1988
Proposed Tech Specs Re Local Leakage Rate Tests & Reactor Bldg Containment Integrity
ML20205M8971988-10-28028 October 1988
Proposed Tech Specs Re Nuclear Svc Battery Operability & Surveillance Requirements
ML20205L2661988-10-25025 October 1988
Proposed Tech Spec Table 3.14-3, Carbon Dioxide Suppression Zones
ML20155G2201988-10-0707 October 1988
Proposed Tech Specs Clarifying Operational Mode Applicability of Tech Spec 3.4 & Definition of Auxiliary Feedwater Sys Train
ML20155B8481988-09-30030 September 1988
Proposed Tech Specs Re Reactor Protection Sys Trip Setting Limits,Rcs High Point Vents,Leakage & Leak Detection,Reactor Coolant Inventory & Auxiliary Electric Sys
ML20155B4591988-09-30030 September 1988
Proposed Tech Spec Sections 1,3,4,5 & 6,reflecting Numerous Editorial Corrections & Administrative Changes
ML20206A8151988-09-28028 September 1988
Rev 0 to, Effluents & Water Mgt Project Action Plan
ML20154J5611988-09-19019 September 1988
Proposed Tech Specs,Changing Local Leak Rate Test Requirements for Containment Penetrations
ML20154D7591988-09-0808 September 1988
Proposed Tech Specs Re Administrative Controls,Onsite & Offsite Organizations & Facility Staff
ML20153E6481988-08-31031 August 1988
Proposed Tech Specs on Limiting Condition for Operation Re Containment Isolation Valves
ML20151K1041988-07-28028 July 1988
Rev 0 to Special Test Procedure STP.668, EFIC High/Medium Decay Heat Test
ML20207C0831988-07-27027 July 1988
Revised Proposed Tech Specs,Consisting of Rev 1 to Proposed Amend 102,deleting App B
ML20151H6131988-07-15015 July 1988
Rev 0 to Matl Control Dept Action Plan for Rancho Seco Nuclear Generating Station
ML20196A2281988-06-21021 June 1988
Proposed Tech Specs Providing Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations During Power Operation & Modifying Existing Purge Sys Operation Requirement
ML20155K0971988-06-14014 June 1988
Proposed Tech Specs Making Minor Corrections to Table 3.5.5-1, Accident Monitoring Instrumentation,Items 5 & 14 & Table 4.1-1 Items 65 & 92 & Adding Second Note to Table 4.1-1,Item 80
ML20195J4921988-06-10010 June 1988
Proposed Tech Spec Pages 4-69 Through 4-85a,modifying Radiological Effluent Tech Specs to Reduce Count Time Required for prebatch-release Sample Analysis
ML20151R0641988-04-15015 April 1988
Rev 0 to STP.1154, Remote Shutdown Panel Test
ML20151X3211988-04-0606 April 1988
Rev 1 to Procedure Development Project Action Plan for Temporary & Interim Procedure Change Incorporation as Procedure Rev
ML20151V5871988-04-0202 April 1988
Rev 1 to Sys Engineering Action Plan SYSTEM-012, CRD Breaker Action Plan
ML20151X2871988-03-31031 March 1988
Rev 0 to Sys Engineering Action Plan SYSTEM-009, Letdown Cooler Thermal & Hydraulic Shock Prevention
ML20150D1861988-03-17017 March 1988
Proposed Tech Specs,Correcting Typos & Making Further Editorial Changes to Proposed Amend 139,dtd 860129
ML20196G5131988-03-0101 March 1988
Proposed Tech Specs,Revising Tech Spec 4.1-1,Item 44.c & Tech Spec 4.10.1.E.2 Re Total Quantity of Gaseous Chlorine in Restricted Area
ML20147F0771988-02-25025 February 1988
Revised Proposed Tech Spec Table 4.1-1 & Tech Spec 4.10.1.E.2,requiring Performance of Surveillances Only When Gaseous Chlorine Onsite
ML20147B1761988-02-15015 February 1988
Rev 0 to RECM-6878, Radiological Effluent Control Manual
ML20148D9931988-02-12012 February 1988
Post-Trip Transient Investigation,Assessment & Reporting
ML20149K8621988-02-12012 February 1988
Proposed Tech Spec 6.5.1.6.d,identifying Items Not Requiring Plant Review Committee Review
ML20196D9091988-02-11011 February 1988
Proposed Tech Specs,Adding Term Dewatering to Process Control Program
ML20149G1781988-02-0808 February 1988
Proposed Page 3-19 to Tech Spec 3.3, Emergency Core Cooling,Reactor Bldg Emergency Cooling & Reactor Bldg Spray Sys
ML20196B8071988-02-0101 February 1988
Proposed Tech Spec Figure 6.2-2, Nuclear Organization Chart
1997-08-19
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20203H7501997-08-19019 August 1997
Rev 10 to Radiological Environ Monitoring Program Manual
ML20203H7351997-02-10010 February 1997
Rev 9 to CAP-0002, Off-Site Dose Calculation Manual
ML20203H7231997-01-21021 January 1997
Rev 9 to Radiological Environ Monitoring Program Manual
ML20059E0191990-08-0303 August 1990
Rev 0 to CAP-0002, Odcm
ML20059E0141990-01-31031 January 1990
Rev 0,App a to CAP-0002, Odcm
ML20059E0241989-11-22022 November 1989
Rev 3 to Environ Monitoring & Emergency Preparedness
ML20246A4081989-08-16016 August 1989
Rev 5 to Inservice Testing Program Plan
ML20245L7281989-07-18018 July 1989
Rev 5 to Administrative Procedure RSAP-0101, Nuclear Organization Responsibilities & Authorities
ML20246A5221989-06-30030 June 1989
Closure Plan
ML20245G1941989-02-28028 February 1989
Procurement Engineering Assessment Plan Final Rept
ML20206A8151988-09-28028 September 1988
Rev 0 to, Effluents & Water Mgt Project Action Plan
ML20151K1041988-07-28028 July 1988
Rev 0 to Special Test Procedure STP.668, EFIC High/Medium Decay Heat Test
ML20151H6131988-07-15015 July 1988
Rev 0 to Matl Control Dept Action Plan for Rancho Seco Nuclear Generating Station
ML20151R0641988-04-15015 April 1988
Rev 0 to STP.1154, Remote Shutdown Panel Test
ML20151X3211988-04-0606 April 1988
Rev 1 to Procedure Development Project Action Plan for Temporary & Interim Procedure Change Incorporation as Procedure Rev
ML20151V5871988-04-0202 April 1988
Rev 1 to Sys Engineering Action Plan SYSTEM-012, CRD Breaker Action Plan
ML20151X2871988-03-31031 March 1988
Rev 0 to Sys Engineering Action Plan SYSTEM-009, Letdown Cooler Thermal & Hydraulic Shock Prevention
ML20147B1761988-02-15015 February 1988
Rev 0 to RECM-6878, Radiological Effluent Control Manual
ML20148D9931988-02-12012 February 1988
Post-Trip Transient Investigation,Assessment & Reporting
ML20196B6901988-01-31031 January 1988
Rev 0 to Radiological Effluents Action Plan
ML20149E2771988-01-29029 January 1988
Rev 4 to Inservice Testing Program Plan for Pumps & Valves
ML20196C8521988-01-27027 January 1988
Rev 2 to Procurement Engineering Assessment Plan
ML20148T0071988-01-20020 January 1988
Rev 1 to STP.961, Loss of Offsite Power
ML20147H9261988-01-13013 January 1988
Rev 2 to Monthly Surveillance Test of Control Room/ Technical Support Ctr Essential Ventilation Sys Loop A. W/One Oversize Drawing
ML20147H8771988-01-13013 January 1988
Rev 3 to Refueling Interval,Special Frequency Control Room/ Technical Support Ctr Essential HVAC Sys Actuation by Rad Monitors & Chlorine Detectors Train a
ML20234F4601987-12-21021 December 1987
Rev 5 to AP.310, Offsite Dose Calculation Manual
ML20236U1391987-11-20020 November 1987
Emergency Operating Procedure Technical Basis EOP POM-248
ML20236P5221987-11-13013 November 1987
Rev 0 to Special Test Procedure STP.961, Loss of Offsite Power Test
ML20236Q0601987-11-10010 November 1987
Rev 1 to Radiological Environ Monitoring Program Manual
ML20236X3591987-10-31031 October 1987
Rev 3 to Wire & Cable Program Rept
ML20236L1481987-10-30030 October 1987
Rev 4 to Procedure AP.310, Offsite Dose Calculation Manual
ML20236P1941987-10-14014 October 1987
Rev 1 to STP.660, Integrated Control Sys Tuning at Power
ML20236D3191987-10-0707 October 1987
Rev 0 to Radiological Environ Monitoring Program Manual
ML20236B7491987-09-23023 September 1987
Rev 1 to D-0050, Engineering Action Plan
ML20235Q7561987-09-0303 September 1987
Twelve Sys Expanded Assessment of Expanded Augmented Sys Review & Test Program Rept
ML20234C2331987-09-0101 September 1987
Motor-Operated Valves Program
ML20235Z5811987-08-31031 August 1987
Rev 2 to Wire & Cable Program Rept
ML20235N8631987-08-26026 August 1987
Rev 0 to Surveillance Procedure SP.486, Monthly Control Room/Technical Support Ctr Ventilation Gas Monitor Test
ML20238E2451987-08-24024 August 1987
Rev 1 to Maint Administrative Procedure MAP-0009, Preventive Maint Program
ML20235U0581987-08-18018 August 1987
Procedure AP.2.07, Verification of Emergency Operating Procedures
ML20235U0461987-08-18018 August 1987
Procedure AP.2.06, Validation of Emergency Operating Procedures
ML20237L6371987-08-12012 August 1987
Sys Review & Test Program Mgt Overview Manual
ML20238D5981987-08-0606 August 1987
Rev 0 to ADM-0037, Maint Administrative Procedures Manual
ML20235N5461987-08-0606 August 1987
Rev 1 to Surveillance Procedure SP.485A, Refueling Interval,Special Frequency Control Room/Technical Support Ctr Essential HVAC Sys Actuation by Rad Monitors & by Chlorine Detectors Train a
ML20236J7071987-07-15015 July 1987
Expanded Augmented Sys Review & Test Program (Easrtp) Evaluation Plan
ML20236J6921987-07-15015 July 1987
Expanded Augmented Sys Review & Test Program Methodology Guidelines
ML20216H8221987-06-25025 June 1987
Rev 3 to Inservice Testing Program Plan,Rancho Seco Nuclear Generating Station
ML20238E2501987-06-23023 June 1987
Rev 3 to Inservice Testing Program Plan for Pumps & Valves
ML20214K3051987-04-24024 April 1987
Nuclear Records Mgt
ML20214K2981987-04-24024 April 1987
QA Records
1997-08-19
[Table view] |
Text
-
,z. :-
04-12-85
. _ Original -
WF0012F .
(- .
. 0-0058P CP.104 .
TRANSIENT TERMINATION FOLLOWING AN OCCURRENCE THAT LEAVES T R i?J l THE RCS BEING COOLED BY HPI COOLING '
. i
!t 1.0 IF THE RCS IS SATURATED,, THEN ENSURE, MAXIMUM.HPI FLOW. ,
1.6 IE ILE It,
~c {;;
.1 Rule 1. ,e ,i / W i.
2.0 OPEN OR VERIFY OPEN EMOV (PSV-21511) AND EMOV 8 LOCK VALVE '(HV-21505): bra u ,. i l
1 3.0 (( FOR ANY REASON THE RCS BECOMES SUPERHEATED, .THEN GO TO ICC SECTION ;I[ TEi ,
E.07. i : rt . !
,It 4.0 WHEN THE RCS SU8C00 LED MARGIN IS ESTABLISHED.-THEN; ,
([C -[L 1: !'
.1 Start a RCP AND +
,, 1 ! ... t ,; , .
I
.2 Control HPI per Rule 2. *
. .? - Q t r cu i J
(-
t
~
5.0 If THE RCS IS SATURATED, THEN (NSURE THE CFTs VALVES REMAIN OPEN. - ' :j_
6.0 IF THE RCS SU8C00 LED MARGIN IS ESTABLISHED AND THE RCS DEPRESSURIZATION. ,
IS BEING CONTROLLED, THEN ISOLATE THE CORE FLOOD TANKS. *
~
L
.1 WHEN the RC system pressure reaches 675 to 700 psig, THEN rack in ,t ;c breakers 20228 and 20229 AND close the core flood isolation valve : , ,
(HV-26513 and HV-26514). : ,. c-: t '
.2 Rack out breakers 20228 and 20229 and tag in accordance with OP A.4.; - - ,
~
7.0 IF,AT ANY TIME: .
.1 THE INCORE T/Cs INDICATE THAT THE RCS SU8C00 LING MARGIN IS REESTABLISHED ,
WITH FW AND SGs STILL AVAILABLE BUT VOIDS ARE TRAPPED IN ,HIGH POINTS OF (
LOOPS, ,
OR
.2 FW TO OTSGs IS RESTORED AFTER ENTERING CP.104 WITHOUT FW, THEN FOLLOW STEPS 9.0 THROUGH 14.0.
( CP.104-1 8509240249 850919 ,
PDR ADOCK 0%g2 P ,
l
1, .
8.0 GO TO CP.103, STEP. 8 0. - -
(
9.0 ESTABLISH CONDITIONS NEEDED TO RE' STORE HEAT TRANSFER. .' ,
- i
, .1 E the RCS is NOT subcooled using core exist T/Cs OR_ hot leg RTDs, THEN i i
ensure maximum HPI flow. v >
r
-.2 IF NO RCPs are running, THEN try to get 'at least one RCP ready for bump.': i
- Ensure that SG 1evels are being maintained at.95 percent on the operate'
~
.3 (' t.
range. ,
* ' m i
l
~ '
10.0 E A 'ANY TIME, WHILE PERFORMING STEPS 11.0 THROUGH 14.0, NATURAL >.9 i CIRCULATION IS REGAINED, THEN ~C> 1'
.1 E the RCS is subcooled as indicated by both incore T/Cs and hot leg . !
RTDs THEN go to CP.105. ,' .
(
.2 E the RCS remains . saturated, THEN go to CP.103. ,
j . T '
. i
.1 ' Natural circulation is verified by: O '
'a
.1. Th ot and IC T/Cs (average of 5 highest) indicate subcooling .
}.
- and decreasing.
.2 ' ' Primary IC T/C temperature decreases when secondary pressure is decreased. .
(.' .c i
11.0 LOWER OTSG PRESSURE TO INDUCE HEAT TRANSFER. il
.1 Lower OTSG pressure by adjusting TBVs or ADVs, while maintaining OTSG t'
, t:
level, until secondary Tsat is 40* to 60*F lower than core exit
,. thermocouple temperature. Maintain this OTSG pressure. -
t 12.0 E RCPs CANNOT BE BUMPED, THEN CONTINUE COOLDOWN WITH STEP 1.0 THROUGH f 8.0 0F THIS SECTION. i 13.0 USE PUMP BUMPS TO INDUCE HEAT TRANSFER. '
.1 Determine RCP operability per OP A.2. .
.2 Bump a RCP, which is capable of being started, in a loop with OTSG level i at the low level limit or greater. t
.3 Allow RCS pressure to stabilize within !20 psig.
9 CP.104-2 ,
.f I
i
,c!' i
- 4 .- l I
13.4 Repeat Steps 13.2 through 13.3 for operable RCPs that have not been : - ..
I bumped. Allow 15 minutes between pump bumps. E all operable RCPs have been bumped and heat transfer HAS. N.O.T. been reestablished, THEN continue '. ' s a'
; with Step 14.0. : P, '
4 f t 14.0 FURTHER LOWER OTSG PRESSURE T0 INDUCE HEAT TRANSFER. < 5 .. t - e e. . . e - s eL t, ,
}
l- .1 E at least one hour has passed since",reactorltrip and 'any RCPs are .i 2L 2 h i
capable of being started, THEN start'and run one RCP, preferably in a sax: *
! t:
-loop with OTSG level greater than 24".r ~s -
A~ .
W. (,
g
-~ w 2, . .:
g
^
15.0 E RCS MAINTAINS SUBC00 LING MARGIN,~ HEN 'GO TO CP.105.' IF RCS REMAINS' iSCS i SATURATED, THEN CONTINUE C00LDOWN PER STEPS 1.0 THROUGH 8.0. 9.!D:6 t i j.
e 9
[:
e
- . , f-t 1
i il i
t
~.1 '
}
, i
('
l l
1
~
l i
?
i
} i'
! l I i r
i 1
4
- END i
e
( ,, CP.104-3 i
I,
.-_ _ _ _ - _ . - _ __ _ _ _ . . _ . _ . _ _ _ . . . _ _ . _ _ , _ . _ _ _ . . _ . __ e.}}