|
---|
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 ML20006C0571990-01-18018 January 1990 Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. ML20006A4211990-01-17017 January 1990 Proposed Tech Specs,Removing Certain cycle-specific Parameter for Relocation to Core Operating Limits Rept ML15264A1571990-01-0202 January 1990 Revised Crisis Mgt Implementing Procedures,Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9,Rev 1 to CMIP-14 & Rev 30 to CMIP-21 ML16152A8951990-01-0202 January 1990 Rev 33 to Public Version of Crisis Mgt Plan for Nuclear Stations. ML20012A3801990-01-0101 January 1990 Rev 28 to, Offsite Dose Calculation Manual,Oconee,Mcguire & Catawba Nuclear Stations. ML20012A3791990-01-0101 January 1990 Rev 27 to, Offsite Dose Calculation Manual,Oconee Nuclear Station. ML20012A3771990-01-0101 January 1990 Rev 26 to, Offsite Dose Calculation Manual McGuire Nuclear Station. ML20012A3751990-01-0101 January 1990 Rev 25 to, Offsite Dose Calculation Manual,Cawtaba Nuclear Station. ML20011D3141989-12-21021 December 1989 Proposed Tech Specs Re Intervals for Surveillances ML20012A3691989-12-0505 December 1989 Rev 8 to, Process Control Program,Mcguire Nuclear Station. ML20011D2441989-12-0101 December 1989 Crisis Mgt Implementing Procedures. ML20012A3721989-11-27027 November 1989 Rev 4 to, Process Control Program,Cawtaba Nuclear Station. ML20059E0241989-11-22022 November 1989 Rev 3 to Environ Monitoring & Emergency Preparedness ML20005G4221989-11-17017 November 1989 Proposed Tech Specs Re RCS Heatup Limitations ML20012A3731989-11-15015 November 1989 Rev 4 to, Process Control Program Oconee Nuclear Station. ML19325F1931989-11-0101 November 1989 Public Version of Rev 32 to, Crisis Mgt Plan for Nuclear Stations. ML19332C8451989-11-0101 November 1989 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 31 to CMIP-1,Rev 28 to CMIP-4,Rev 32 to CMIP-5,Rev 37 to CMIP-6,Rev 36 to CMIP-7,Rev 25 to CMIP-8,Rev 31 to CMIP-9 & Rev 19 to CMIP-13 ML19327B4051989-10-19019 October 1989 Proposed Tech Specs,Authorizing Use of Vantage 5 Fuel & Combination of Vantage 5 Fuel & Present Optimized Fuel Assembly Core at Plant ML19325C6071989-10-0303 October 1989 Proposed Tech Specs Re Onsite Power Distribution ML20247H3371989-09-15015 September 1989 Revised Corporate Organization for Nuclear Incidents (Coni) Procedure Manual Including Rev 15 to CONI-1.01, Preparation,Issuance & Control Procedures, Rev 30 to CONI-1.02, Coni & Rev 19 to CONI-1.03, Alerting .. ML20246A4081989-08-16016 August 1989 Rev 5 to Inservice Testing Program Plan ML20245L7651989-08-0707 August 1989 Rev 0 to Offsite Dose Calculation Manual ML20247M7921989-07-31031 July 1989 Rev 6 to PWR Operations Guideline Number 12 Simulator Testing Program. Simulator Transient Test Review Data Encl ML20247M9151989-07-27027 July 1989 Procedure Generation Package ML18153B8371989-07-24024 July 1989 Proposed Tech Specs Reflecting Composition of Station Nuclear Safety & Operating Committee Following Recent Assignment of superintendent-engineering Position at Stations.Tech Spec Pages Include 6.1-6,6-5 & 6-6 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 B13221, Proposed Tech Specs Re Inservice Insp of Steam Generator Tubes & Acceptance Criteria for Tubes1989-06-29029 June 1989 Proposed Tech Specs Re Inservice Insp of Steam Generator Tubes & Acceptance Criteria for Tubes ML20245H5671989-06-23023 June 1989 Proposed Tech Specs Revising Tech Spec Page 3.4.6.1, RCS Leak Detection Sys ML20245H5781989-06-22022 June 1989 Proposed Tech Specs for Amend 109 to License DPR-54 ML20247N0421989-06-19019 June 1989 Rev 5 to SS-1, Braidwood Simulator Steady State Performance Test ML20247M7861989-05-26026 May 1989 Rev 0 to SV-1, Braidwood Simulator Surveillance Testing ML20247M7581989-05-26026 May 1989 Rev 0 to Test NO-1, Braidwood Simulator Normal Operations Testing B13256, Proposed Tech Specs,Revising Administrative Controls for Radiological Effluent Monitoring Manual1989-05-25025 May 1989 Proposed Tech Specs,Revising Administrative Controls for Radiological Effluent Monitoring Manual ML20247H2841989-05-22022 May 1989 Proposed Tech Specs Re Types of Absorber Matls in Control Rod Assemblies 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 ML20245F2581989-04-25025 April 1989 Proposed Tech Specs Re Administrative Controls in High Radiation Area ML20245C2541989-04-0505 April 1989 Public Version of Rev 29 to Duke Power Co Crisis Mgt Plan for Nuclear Stations ML20247M7801989-04-0404 April 1989 Rev 0 to ST-1 Re Simulators safety-related Valves Stroke W/ Acceptable Time Period Required by ANSI/ANS-3.5-1985 ML20248G0051989-04-0303 April 1989 Proposed Tech Specs,Changing Tables 3.3-1 & 4.3-1,per Generic Ltr 85-09 for Reactor Trip Sys Automatic Actuation Using Shunt Coil Trip Attachments 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 ML20006C0571990-01-18018 January 1990 Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. ML15264A1571990-01-0202 January 1990 Revised Crisis Mgt Implementing Procedures,Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9,Rev 1 to CMIP-14 & Rev 30 to CMIP-21 ML16152A8951990-01-0202 January 1990 Rev 33 to Public Version of Crisis Mgt Plan for Nuclear Stations. ML20012A3751990-01-0101 January 1990 Rev 25 to, Offsite Dose Calculation Manual,Cawtaba Nuclear Station. ML20012A3771990-01-0101 January 1990 Rev 26 to, Offsite Dose Calculation Manual McGuire Nuclear Station. ML20012A3791990-01-0101 January 1990 Rev 27 to, Offsite Dose Calculation Manual,Oconee Nuclear Station. ML20012A3801990-01-0101 January 1990 Rev 28 to, Offsite Dose Calculation Manual,Oconee,Mcguire & Catawba Nuclear Stations. ML20012A3691989-12-0505 December 1989 Rev 8 to, Process Control Program,Mcguire Nuclear Station. ML20011D2441989-12-0101 December 1989 Crisis Mgt Implementing Procedures. ML20012A3721989-11-27027 November 1989 Rev 4 to, Process Control Program,Cawtaba Nuclear Station. ML20059E0241989-11-22022 November 1989 Rev 3 to Environ Monitoring & Emergency Preparedness ML20012A3731989-11-15015 November 1989 Rev 4 to, Process Control Program Oconee Nuclear Station. ML19325F1931989-11-0101 November 1989 Public Version of Rev 32 to, Crisis Mgt Plan for Nuclear Stations. ML19332C8451989-11-0101 November 1989 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 31 to CMIP-1,Rev 28 to CMIP-4,Rev 32 to CMIP-5,Rev 37 to CMIP-6,Rev 36 to CMIP-7,Rev 25 to CMIP-8,Rev 31 to CMIP-9 & Rev 19 to CMIP-13 ML20247H3371989-09-15015 September 1989 Revised Corporate Organization for Nuclear Incidents (Coni) Procedure Manual Including Rev 15 to CONI-1.01, Preparation,Issuance & Control Procedures, Rev 30 to CONI-1.02, Coni & Rev 19 to CONI-1.03, Alerting .. ML20246A4081989-08-16016 August 1989 Rev 5 to Inservice Testing Program Plan ML20245L7651989-08-0707 August 1989 Rev 0 to Offsite Dose Calculation Manual ML20247M7921989-07-31031 July 1989 Rev 6 to PWR Operations Guideline Number 12 Simulator Testing Program. Simulator Transient Test Review Data Encl ML20247M9151989-07-27027 July 1989 Procedure Generation Package ML20245L7281989-07-18018 July 1989 Rev 5 to Administrative Procedure RSAP-0101, Nuclear Organization Responsibilities & Authorities ML20246A5221989-06-30030 June 1989 Closure Plan ML20247N0421989-06-19019 June 1989 Rev 5 to SS-1, Braidwood Simulator Steady State Performance Test ML20247M7581989-05-26026 May 1989 Rev 0 to Test NO-1, Braidwood Simulator Normal Operations Testing ML20247M7861989-05-26026 May 1989 Rev 0 to SV-1, Braidwood Simulator Surveillance Testing ML20245C2541989-04-0505 April 1989 Public Version of Rev 29 to Duke Power Co Crisis Mgt Plan for Nuclear Stations ML20247M7801989-04-0404 April 1989 Rev 0 to ST-1 Re Simulators safety-related Valves Stroke W/ Acceptable Time Period Required by ANSI/ANS-3.5-1985 ML20245G1941989-02-28028 February 1989 Procurement Engineering Assessment Plan Final Rept ML20247M8011989-02-0101 February 1989 Rev 1 to 1BWEP-0, Reactor Trip or Safety Injection Unit 1 ML20247M8201989-02-0101 February 1989 Rev 1 to 2BWEP-0, Reactor Trip or Safety Injection Unit 2 ML20247M8661989-02-0101 February 1989 Rev to 1BEP-0, Reactor Trip or Safety Injection Unit 1 ML20247M8741989-02-0101 February 1989 Rev 1 to 2BEP-0, Reactor Trip or Injection Unit 2 ML20206A8151988-09-28028 September 1988 Rev 0 to, Effluents & Water Mgt Project Action Plan ML20204J1391988-09-0707 September 1988 Temporary Procedure Change 88-504 to Rev 4 to Procedure E-0, Reactor Trip or Safety Injection ML20204J0391988-08-23023 August 1988 Rev 4 to Emergency Operating Procedure EOP 3.1-28, Turbine Overspeed ML20205A3671988-08-0303 August 1988 Rev 4 to Emergency Operating Procedure EOP 2532, Loss of Primary Coolant ML20205A6281988-08-0303 August 1988 Rev 3 to Emergency Operating Procedure EOP 2540C, Functional Recovery of RCS Inventory & Pressure ML20205A6111988-08-0303 August 1988 Rev 2 to Emergency Operating Procedure EOP 2540B, Functional Recovery of Vital Auxiliaries (AC & DC Power) ML20205A4191988-08-0303 August 1988 Rev 2 to Emergency Operating Procedure EOP 2540A, Functional Recovery of Reactivity Control ML20205A6651988-08-0303 August 1988 Rev 3 to Emergency Operating Procedure EOP 2540D, Functional Recovery of Heat Removal ML20205A4011988-08-0303 August 1988 Rev 4 to Emergency Operating Procedure EOP 2537, Loss of All Feedwater ML20205A3941988-08-0303 August 1988 Rev 4 to Emergency Operating Procedure EOP 2536, Excess Steam Demand ML20205A3831988-08-0303 August 1988 Rev 5 to Emergency Operating Procedure EOP 2534, Steam Generator Tube Rupture ML20205A3521988-08-0303 August 1988 Rev 2 to Emergency Operating Procedure EOP 2528, Electrical Emergency ML20205A3181988-08-0303 August 1988 Rev 3 to Emergency Operating Procedure EOP 2525, Std Post-Trip Actions ML20205A3341988-08-0303 August 1988 Rev 2 to Emergency Operating Procedure EOP 2526, Reactor Trip Recovery 1997-08-19
[Table view] |
Text
_ _ _ __ _ _ .
l}, -
t -
j gt, i e '
EFFECTIVE DATE
$'- 07-12-85 Rev. 1 i
WP0002F
, D-0058P l .
E.02 VITAL SYSTEM STATUS VERIFICATION c3 Verification Column Action Column, VERIFY THE FOLLOWING: IF VERIFICATION CANNOT BE MADE. PERFORM THE FOLLOWING:
1.0 ALL SAFETY AND . Borate to a 1% shutdown margin.
CONTROL RODS AT '
IN LIMIT
/
t' 2.0 REACTOR POWER a. Push Rx Trip button on H1RC.
j DECREASING ON b. At Panel H2ES deenergize bus 3B * ,
INTERMEDIATE " (52.-3B05) and 3C2 (52-3C23) at the ,
RANGE same time. T[EE af ter 10 sec delay, reenergize bus 3B and 3C2.
- c. Start HPI Pump taking suction from
~
BNST; stop makeup pump. .
- d. Maximize letdown flow to flash tank.
- e. Manually open CRD breakers in East 480V switchgear room.
a e
i 8605160280 860306 2 PDR ADOCK 0500 6 Rev. 1 E.02-1
. i
_ ~ . _ _ . _ ___ _ - . . - - ... . - . - - . . . , . _ _ . - . . , . - -
{ ,
V
. E.02 A
VITAL SYSTE STATUS VERIFICATION b ,
'T q .
Verification Column ' Action Column a s
VERIFY THE FOLLOWING: IF VERIFICATION CANNOT BE MADE. PERFORM
{ ,
THE FOLLOWING: !
.i !
l '
] I 1
} 3.0 AT LEAST.ONE RCP a. Verify Natural Circulation RUNNING 1. OTSG T,,g approximately the same as T,.
. 2. Lovering OTSG pressure causes a corresponding decrease in T, and T #i""***** ~
h .
- 3. Incore temp within 10*F of T
- b. Verify AFW flow. Rule 4 ,,
4.0 MAIN FEEDWATER a. Take manual control and shut main ,
. FLOW AND feedwater control valve.
FEEDPUMR SPEED b. Take manual control of startup i RUNNING BACK feedwater control. valve and attempt to control feedwater flow.
- c. At 82.5% on OP Range, run feedpumps j hack to minimum speed and ensure Main J
'i Block Valves are closed.
l .d. At 90% on OP Range, trip one Main Feed j Pump.
1 .
1 1 5.0 BOTH OTSG Trip both runnin'g MFW pumps 8HD. verify 1
LEVEL < 95%
i AFW Starts.
l ON OP RANGE AND Verify AFW valves shut to the affected ,
DECREASING . OTSG(s) until level returns to normal.
e
'k Rev. 1 E.02-2 O .
l! - -
I . . . . - - -
s 8 ,
i I
E.02 -
l
~
VITAL SYSTEM STATUS VERIFICATION . -
)
i
} (s .b .
Verification Column Action Column =
VERIFY'THE FOLLOWING: IF VERIFICATION CANNOT BE MADE. PERf_QRH THE FOLLOWING: l
_.J., !
i I
6.0 ALL MAIN. TURBINE Push Turbine Trip and Generator Trip button STOP VALVES SRUT on HISS. If,the turbine does not trip, *
, a. Run valve position limiter to zero and trip turbine from the front standard.
l'
- b. Trip EH oil pumps.
[ 7.0 OCBs AND GENERA- (QQ H9I open breakers if turbine is not 1- TOR EXCITER tripped.) Verify Turbine tripped 3232[
BREAKER TRIPPED push Generator Trip button. IE: breakers do not open, manually open the*generatoc OCBs &EQ generator exciter breaker.
8.0 SITE LOADS a. Verify auto start.of:the diesel'
, . TRANSFERRED TO- generators &HR loading of-the 4A and 3
STARTUP TRANS- 4B buses.
j FORMER WITH 4A AND 4B BUSES b. Verify auto start of AFW &MQ raise SG
] ENERGIZED level to 50% on the OP Range, with'AFW I
properly throttled. (See Specific 1 q Rule 3.) ,
- c. Ensure Seal Supply Isolation Valve.
, SFV-23616 is closed. Restart an HPI *
, 3 . or Makeup Pump. Recover RCP Seal
<? .. Injection per OP A.2, Section 7.0.
Rev. 1 E.02-3
.i
, r
. E.02 -
~
VITAL SYSTEM STATUS VERIFICATION .
.e
, r. ,e h s
h Verification Column Action Column . .-
VERIFY THE FOLLOWING: IF VERIFICATION CANNOT BE MADE. PERPORN THE FOLLOWING: *
- j .
d .
8.0 (Continued)_ d. Verify SAS and IAS in service, if not, start diesel air compressor and refer l
, to C.23, Loss of Plant Air System as i
, necessary.
o l
] e. Verify Nuclear Service Raw Water pumps j
i start.
Verify OTSG pressure control with ADVs.
^
f.
9.0 LETDOWN FLOW AT Close letdown bypass and orifice block 40 GPN '
valves (HV-22010 and HV-220ll) at Panel
, H1RC.
- i 10.0 PRESSURIZER. Start HPI Pump lined up to BWST and open i LEVEL Loop A HPI injection valve (SFV-23811).
, 100 INCHES i
a l
4 11.0 RCS PRESSURE . a) Verify HPI, LPI, and RB isolation and
] GREATER THAN cooling channels (lA and 18 &lE 2A and j . 1600 PSIG AHD, 2B) have actuated by noting the colors
! RB PRESSURE of components' indicating lamps on the LESS THAN H2SF panel. !
4 PSIG -
, , , b) Close the EMOV block valve (HV-21505).
. . Rev. 0 7
Rev. 1 y .
E.02-4 Y l i
l-I .
.. )
3 . . . -
E.02 VITAL SYSTEM STATUS VERIFICATION i
f.}.
u-j .
Verification Column Action Column '
i:
VERIFY THE FOLLOWING: IF VERIFICATION CANNOT BE MADE. PERFORM THE FOLLOWING:
11.0 (Continued) c) Verify AFW starts M maintain appropriate OTSG level. (See' Specific Rules 3 and 4.)
n U
d) Close AFW Bypass Valves SFV-20577 and SFV-20578. Verify AFW flow on
. FI-31802 and FI-31902 on H2PS. R AFW
$ . flow is not observed, control flow by
[ . throttling AFW. Bypass Valves SFV-20577 s
and SFV-20578. E AFW control valves FV-20527 and FV-20528 operate, M q close AFW bypass valves SFV-20577 and 20578 83, control AFW flow with the (l
rt AFW control valves. OTHERWISE throttle l1 , AFW bypass valves to. control AFW flow. -
4
'N 1
e) Verify RCP seal injection flow at ElRC.
li
} 12.0 RB PRESSURE a) Verify that RB spray pumps M , spray
] LESS THAN 30 PSIG '
valves-(Channels 3A'and 3B & B,4A and, d
4B) have actuated.
b) Verify'RB spray flow subsequent to the li . 5 min time delay.
?!
O Rev. 1
~
E.02-5 i
f I:
- l - , - - , , - - m-~~~-, -----,------w','-~v-- o~~*~'* " ' ~ ' " ~ ' ~ ~ ' " * ^ ^ ~
3 , _
l j.
l E.02 l i
VITAL SYSTkN STATUS VERIFICATION '
j tb
.-2 i l
. I 3
Action Column Verification Column ;
., VERIFY THE FOLLOWING: IF VERIFICATION CANNOT BE MADE.' PERFORM THE FOLLOWING: l l
13.0 OTSG "A" AND Verify: l "B" PRESSURE GREATER THAN "A" SIDE LOW PRESSURE 435 PSIG !
j .a) Verify MFW Block Valve ,(FV-20529) l l closed. I b) Stop any AFW flow to "A" OT3G. l c) Verif.y no MFW flow at H1RI.
f "B" SIDE LOW PRESSURE -
i I
l' a) Verify MFW Block Valve (FV-20530) i c1'osed: -
b) Stop any AFW flow to "B" OTSG. l 3 c) Verify no MFW flow at H1RI.
i i'
- 1* 14.0 ALL NNI Refer to C Procedures for Loss of NNI j POWER ON power. . _.
r 15.0 ADEQUATE Go to Loss of Subcooling E.03.
- l. SUBCOOLING MARGIN' EXISTS .
- REFER GUIDELINE 1 1
. ;;^
?b . l Rev. 1 '" " 1 E.02-6 l i
j ,
. E.02 lu ,
VITAL SYSTEM STATUS VERIFICATION
, Ds -
' .u -
Verification Column- Action Column
, VERIFY THE FOLLOWING: IF VERIFICATION CANNOT BE MADE. PERFORM l
\
THE FOLLOWING:
E 16.0 ADEQUATE PRIMARY Go to Loss of Heat Transf*er E.04.
'TO SECONDARY
) HEAT TRANSFER EXISTS REFER GUIDELINE 2 I
l 17.0 PRIMARY TO Go to Excessive Heat Transfer E.05. .
SECONDARY HEAT TRANSFER IS l
[' '
\'
NOT EXCESSIVE .
l REFER GUIDELINE 3 '
18.0 NO~ INDICATION Go to SGTR E.06.
j OF A SGTR ON MAIN STEAM LINE OR AIR
- EJECTOR OFF GAS OR GLAND STEAM i RADIATION j MONITOR 19.0 THE PLANT IS STABLE IN A, SAFE SUBCOOLED CONDITION WITH $ ROPER
- PRIMARY TO SECONDARY HEAT TRANSFER AND NO MAJOR PRIMARY
) BOUNDARY FAILURES. FURTHER ACTION AT THIS POINT WILL BE AT THE' DISCRETION OF STATION MANAG$, MENT.
Rev. 1 E.02-7 i -
E.02 4
SUBC00 LING MARGIN J . - -
GUIDELINE No. 1 -
'u
- 1. Adequate Subcooling Margin exists when the SPDS T #
l hot Incore Thermocouple data point is above and to the left of the i variable subcoo' ling margin curve.
OR v
- a. If both SPDS displays are not_available and at least one RCP is_. sunning: Subcooling monitors indicate gre'ater than
., 50* subcooling.
- b. If both SPDS displays are not available and no RCPs are running: RCS pressure and incore thermocouple temperature (average of five highest) plot >50* subcooling or above and to the left,of th'e variable subcooling margin curve. -
. ~ ~
e en e
J e
I i
k.
)
4
,n I
Rev. 1 .
l E.02-8 l a
[
L
il . .
.. l y:
y .e .
- 4. E.02 I INADEQUATE PRIMARY TO SECONDARY HEAT TRANSFER GUIDELINE No. 2 l
. 2. Inadequate Primary to Secondary Heat Transfer
- a. Primary Method j SPDS: RCS temperature is increasing, not stable f inside the Post Trip Nindow t and t
[ - -
T, and OTSG T,,g are not coupled.
T, and CTSG T,,g should be k>
approximately equal and tracking together j . (coupled).
6 P.
I
- b. Secondary Method (both SPDS displays are not available) i -
Use plant instrumentation to determine the following: .
~
j-RCS temperature increasing '
i 3
] , and
! T, and oTSG T,,, are not coupled. !
?
i l 1
7.
l$ -
l i
) '
g .
3 Rev. 1 E.02-9
b -
E.02 1
-EXCESSIVE PRIMARY TO SECONDARY HEAT TRANSFER f GUIDELINE No. 3 ;F
~,
4 . .
- 3. Excessive Primary to Secondary Heat Transfer
- a. Primary Method SPDS': , RCS temperature and pressure decreasing,
- not stable in the Post Trip Window c I j and
- l. .
- j. OTSG pressure decreasing (<960 psig) or
{ OTSG T,,g decreasing (<540*F).
fa 3
f b. Secondary Method (both SPDS displays are not available) i i Use' plant indication to determine the following:
'RCS temperature and pressure decreasing
~
l .
j and' .
OTSG pressure decreasing (<960 psig). '
1 i
i i
}
1 t __ .
I I
l..
I i
1 ENO p
D Rev. 1 .
E.02-10 J .
1
'l
. . .