ML20052F491
| ML20052F491 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/04/1982 |
| From: | Schroeder C COMMONWEALTH EDISON CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.C.7, TASK-TM 4042N, NUDOCS 8205130076 | |
| Download: ML20052F491 (71) | |
Text
__ . .
/ x Commonwealth Edison
) one First Nationzl Pirra. Chicigo. Ilknois
[
l \ v ~J Address R: ply to: Post Offics Box 767
\ ,/ Chicago. Illinois 60690 May 4, 1982 C.)
E RECElVED g,
MAY121982> b '
Mr. A. Schwencer, Chie f a ustat umam anum s Licensing Branch #2 b
"gammma /f Division of Licensing U. S. Nuclear Regulatory Commission g Washington,-DC 20555 -
Subject:
LaSalle County Station Units 1 and 2 Completion o f Vendo r Review of Emergency Procedures NRC Docket Nos. 50-373 and 50-374 References (a): NUREG 0737, Item I.C.7 (b): NUREG 0519, SER For LaSalle County Station Chapter 22, Item I.C.7 (c): C. Schroeder letter to A. Schwencer dated April 5, 1982, " Completion o f Vendor Review o f Emergency Procedures"
Dear Mr. Schwencer:
The purpose o f this letter is to transmit to you additional information regarding Reference (a), Vendor Review o f Emergency Procedures.
In Reference (b), the staf f stated: "The nuclear steam supply system vendor, General Electric Company, is reviewing the power-ascension test procedures and emergency procedures. The applicant has committed to ensuring the review is completed and vendor recommendations addressed prior to the beginning of low-power testing. The staf f must review the final draf t procedures to determine if the vendor review has been completed acceptably. We will condition the operating license such that our review must be c.omp,lete before full power."
Commonwealth Edison Company has ensured that the vendor review has been completed. This was documented in Reference (c).
Although not specifically required by Reference (b), during a telecon on April 28, 1982, Dr. A. Bournia and Mr. R. Urban of your staf f requested that the detailed comments from the vendor review also be submitted to the staf f for review. Enclosed please find the additional information, as requested.
0I
$01 QS$$ho$N A
May 4, 1982 A. Schwencer : If'there are any further questions in this matter, please contact this office.
One signed original and thirty-nine (39) copies of this .
letter and the enclosure are provided for your use.
Very truly yours, W./cl~ub~ s/,/ s C. W. Schroeder Nuclear Licensing Administrator 1m Enclosure cc: NRC Resident Inspector - LSCS 4042N
_ _ _ _ -__ ___- _ -- -_ J
g NUCLEAR ENERGY GERER AL g ELECTRIC BUSINESS GROUP GENERAL ELECTRIC CO.. LASALLE COUNTY NUCLEAR STATION, P O BOX 240 Nuclear Services Department M ARSEILLES. ILLINO!S 61341 Prione (215) 357-6807 _g g February 8, 1982 l
Mr. R. H. Holyoak "
Station Superintendent Commonwealth Edison Company LaSalle County Nuclear Station Subj ect: LaSalle Site Emergency Procedure (LGA) Review Ref er ence: (1) NUREG 0737, Section 1.C.7
Dear Mr. Holyoak,
In accordance with the requirements of Ref erence (1), a General Electric review of the LaSalle Emergency Procedures has been completed.
A copy of the specific revision of procedures that were reviewed is included as Enclosure 1. Emergency Procedure Guidelines (Revision IB) were used as the primary ref erence document in conducting this review.
The LaSalle procedures have been found to be in general compliance with the Emergency Procedure Guidelines (Revision IB) with specific General Electric comments included as Enclosure 2. '
h LN W
[. E . Ellis F.Y. Brown Operations Superintendent Operations Manager LaSalle County Kuclear Station LaSalle County Nuclear Station
/
/
! A V /2?fLW (
l J. F. Schilder Senior Program Manager H. R. Pef f er Proj ect Manager '
[
Training & Technical Services LaSalle Site JEE:=jg Enclosures cc: E. F. Karner - M/C 884 D. R. Pankratz - M/C 884 S. T. Rogers - M/C 73E J. J. Sheehan - M/C 884 R. E. Spencer - GE, LaSalle R[F .
e ,
~
1 l
l ENCLOSURE 1 _
LEH-819 LGA -T1 Revision 1 January 10, 1982 1
GENERAL PRECAUTIONS NOIf The following precautions are generall y appl icable at all times. Conformance to these cautions ensures that the LGA's will be most ef ficientl y executed.
- 1. Inform the Shift Supervisor i f an abnormal increase in Drywell radiation level s is observed.
- 2. Monitor the general state of the plant. If an entry condition for either LGA-01 or LGA-03 occurs, enter that LGA. When it is determined that an emergency no longer exists, enter an LGP or LOA.
h-- 3. Monitor RPV water level and pressure and primary containment temperature, pressure, and level from l
mul t i pl e indications. Be aware that all indicators
- of these parameters have not been tested to verify that they will meet new environmental standards.
- 4. If a safety function is initiated automatically, l
assume a true initiating event has occurred unl ess otherwise confirmed by at least two independent indications.
S. Whenever RHR is in the LPCI Hode, inject through I
the heat exhangers as soon as possible.
- 6. Do not secure or place an ECCS component in MANUAL mode, unless by at least two independent indications, misoperation in AUTOMATIC mode is confirmed, or adequate core cooling is assured.
- a. If an ECCS component is placed in MANUAL mode, it will not ini tiate automaticall y.
D. Make frequent checks of tne Initiating or controlling parameter.
- c. When manual operation i s no longer required, f restore the system to AUTOMATIC / STANDBY mode t
if pos s i bl e. -
l
LGA-T1 Revision 1 January 10, 1982 2 !finatf
- 8. Under unl ikely, oegraded temperature' conditions in the drywell an onscale level reading mby occur when l evel i s actuall y below the lower i nstrument tap.
This phenomenon is only conceivable in the Upset Range and Shutdown Range. If the Shutdown Range indicates a level above 31 inches, then this phenomenon is not postul ated to occur.
If the Drywell Temperature is less than 175 F then this phenomenon is not postulated i n the Upset Range.
-r-m - ., - - , - ,- - , g ,,,r- ye- se----, ----,,-m w-- n- - , , - - - - - , - > + . _ . r .w, - ,, .,.--g -gr.-v e-,- - ~ - - -
C LGA-01 Revision 4 January 7, 1982 1
LEVEL CONTROL -
A. PURPOSE The purpose of this procedure is to restore and staoi.lize RPV water l evel .
B. ENTRY CONDITIONS The entry conditions for this procedure are any of the f oll owi ng:
- 1. RPV water l evel less than 12.5"
- 2. Drywell pressure greater than 1.69 psig H
I.
- 3. An isol at ion condition exi sts which requires or initiates reactor scram
, C. OPER AT_OR_ ACT_ IONS l - _--- _ - - - - - - - _ _
CAUTION l
NOTIFY SHIFT SUPERVISOR TO CLASSIFY THE EVENT I AND INITIATE GSEP IF APPROPRIATE
f ___
- 2. VERIFY system isolations consistent with plant -
l parameters (LOP-PC-03).
- 3. VERIFY automatic initiation of ECCS systems ano Sb6T system consistent with plant parameters.
- 4. VERIFY oiesel genGrators start consistent wi th pl ant parameters.
I l
~- , - , , - . - - . , _ , ,. _ . , ,, ,_ , ,-. ,,,_ , , --_ -- ,s _ , .-- ,
LGA-01 Revision 4 January 7, 1962 2
CAUTIOr4 AVOIO RPV HIGH WATER LEVEL TRIP (*S4.5") OF FW PUMPS, RCIC AND CLOSURE OF THE HPCS INJECTION VALVE.
C.S. RESTORE and MAINTAIN RPV water l evel between +12.5" and +S4.5" with one or more of the following systems:
- a. Condensate /Feedwater . . 1076 to O psig
- b. CRC . . . . . . . . . . 1076 to O psig
___ 1) INCRE ASE flowrate to maximum, OPERATE two pumps if possiDie (LOA-RD-07).
- c. RCIC . . . . . . . . . . 1076 to 57 psig
- d. HPCS . . . . . . . . . . 1076 to O psig 1550 to 6350 gpm
- e. LPCS . . . . . . . . . . 440 to O psig O to 6350 gpm
- f. LPCI . . . . . . . . . . 260 to O psig 0 to 7450 gpm
- 6. If RPV water level can be restored anc maintainea above +12.5"
! ME l
it is determined that an emergency does not exist Then ENTER appropriate LGP as determinea by the Shift Supervisor.
1 l .
1 1 -
l 1
l
[ >
LGA-01 '
Revision 4 January 7, 1982 3
C.7. If RPV water level cannct be maintainea aoove +12.5" Then PAINTAIN RPV water level above T.A.F.
(-161" on Fuel Zone Indicator)..
- 8. If RPV water level cannct be maintained aoove T.A.F. (-161" on Fuel Zone Indicator) 95 RPV water level cannot be determined Then ENTER LGA-04, Level Restoration 3ND EVACUATE nonessential personnel from the reactor building.
=-- 9. ghgn RPV water level has stabilized Then ENTER LGA-02, Cooldown. ,
D. REFERENCES .
1 LGP 3-2, Reactor Scram
- 2. LGA-04, Level Restoration
- 3. LGA-02, Cool down
- 4. LOA-RD-07, Simultaneous Operation of Botn CRD Pumps
- 5. LOP-PC-03, Primary Containment Isol ation Status
- Panel
e. - r. - - , , - - . = ,. o ,---es - . - - - - - - -,.m, . ~ . - - . . _ -. -.. -.-- - ,,
LGA-02 Revision 4 January 10, 1982 1
COOLDOWN A. PURPOSE The purpose of this procedure i s to depressurize and cool down the RPV to cold shutdown conditions while maintaining RPV water level within a satisfactory range.
B. gtqRY CONDITIONS This procedure is entered from LGA-01, Level C ont r ol ,
af ter the RPV water level has been stabilized.
C. OPERATOR ACTIONS i
CAUTION v- IF HIGH DRYWELL PRESSURE (1 69 PSIG) IS PRESEN1 WHILE DEPRESSURIZING THE RPV AND ADEQUATE CORE COOLING IS ASSURED.
-THEN PREVENT INJECTION FROM THE LPCS AND LPCI SYSTEMS PRIOR TO REACHING THE RPV PRESSURE AT WHICH THEY WILL INJECT. WHEN THE HIGH DRYWELL PRESSURE CONDITION CLEARS, DEPRESS INITIATION LOGIC RESET PUSH 8UTTON AND RESTORE LPCS AND LPCI TO THE ST ANDBY r
CONDITION (LOP-RH-11, LOP-LP-02). _
I 1
. - , - - - , , -- _ _ . . _ _ . , - - - - _ , , . - _ . . . , - - _ . _ _ - _.-- ,n, ,,,,,,y ,, --y,,,--,-_,.,-,-,n,.,,_~,,,---g-nn.--nn-,n , p.-,,w. -
7 - . ,
l LGA-02 Revision 4 January 10, 1982 2
~
C.l. Continue maintaining RPV water level between T.A.F. (
(-161" on Fuel Zone Indicator) and +54 5" with one or more of the following systems:
- a. Condensate /Feedwater . . 1076 to O'psig
- o. CRO . . . . .. . . . . 1076 to O psig
- 1) INCRE ASE flowrate to maximum, OPERATE two pumps if possible (LOA-RD-07).
- c. RCIC . . . . . . . . . . 1076 to 57 psig
- d. HPCS . . . . . . . . . . 1076 to O psig 1550 to 6350 gpm
- e. LPCS . . . . . . . . . . 440 to O psig 0 to 6350 gpm
~~~
- f. LPCI . . . . . . . . . $ 260 to O psig 0 to 7450 gpm
- 2. If high suppression pool water l evel , 26'10",
-- (+3") occurs 95 low CY tank level (3'1") occurs
, Then VERIFY HPCS and RCIC suctions transfer from CY tank to the suppression pool.
- 3. If RPV water level cannot be maintained above T.A.F. (-161" on Fuel Zone Indicator) 9a .
RPV water l evel can not be determined Then ENTER LGA-04, Level Restoration.
- 0
--*~.--r._-_,_.,m. ---. _ . _ _ -.
~
LGA-02 Revision 4 January 10, 1982 3
C.4. DEPRESSURIZE and COOLDOWN the RPV at less than 100 F/hr (LG A-C1,9RPV Pr essure Reducti on - Pref er red --
Method). The 100 F/hr cooldown rate ma.y be exceeded to conserve RPV inventory, protect primary or secondary containment integrity, or limit radioactive release to the environment.
5 .- When the RHR Shutdown Cooling interlocks clear Then INITIATE the Shutdown Cooling mode of RHR (LOP-RH-07, Shutoown Cooling System Startup and Operation).
\
- 6. If the RHR Shutdown Cool ing mode cannot be established and further cooldown is required Then continue to cooldown using one or more of the systems used for depressurization (LGA-Cl). MAINTAIN RPV water temperature above 80 F for Unit 1 on 86 F for Unit 2.
- 7. If RPV cooldown is required but cannot be accompl i shed Then PERFORM the f ollowing:
- a. INITIATE suppression pool cool i ng.
- b. CLOSE the following val ves:
- 1) MSIv's 1B21-F022 A/B/C/D - (2821-F022A/B/C/D) and 1B21-F028A/B/C/C (2821-F028A/B/C/D).
l
- 2) Main Steam Line Drains 1821-F016 (2B21-l F016) and 1B21-F019 (2821-FOl9)
- 3) RCIC i sol ation val ves IESI-F063 (2ESI-l F063) lE51-F076 (2ESl-F076) and 1ESl-1 F008 (2E51-F008)
- 4) RHR Steam Concensing isolation valve l
l .
.- -. .. . __ _ -_- z. L .-
LGA-02 Revision 4 January 10, 1982 4
C.7. c. OPEN two SRV's.
- d. SLOWLY RAISE RPV water level to establ i sh water flow through the open'SRV's back to the suppression pool.
- i. CONTROL suppression pool temperature to maintain ~
RPV water temperatures above 80 F for Unit 1 or 86 F for Unit 2.
- 8. When pl ant conditions permite Then Proceed to Cold Shutcown in accordance with LGP 2-1, Normal Unit Shutdown.
O
LGA-02 Revision 4 January 10, 1982 5
D. REFERENCES
- 1. LGA-Ol, Level Control
- 2. LGA-04, Level Restoration 3 LGA-Cl, RPV Pressure Reduction.
- 4. LGP 2-1, Normal Unit Snutdown
- 5. LOA-RD-07, Simultaneous Operation of Both CRD Pumps
- 6. LOP-RH-07, Shutdown Cool ing System Startup and Operation.
- 7. LOP-RH-ll, Preparation for Standby Operation of the Low Pressure Coolant Injection System
- 8. LOP-LP-02, Preparation for Standby Operation of the Low Pressure Core Spray System.
~
. r L G A-03 Revision 3 January 10, 1982 1
' ~
CONTAINMENT CONTROL A. PURPO_ES The purpose of this procedure is to control primary containment temperatures, pressure and level . This procedure i s per f ormed concur rently wi th the procedure from which it is entered.
B. ENTRY CONDITIONS The entry conditions for this procedure are any of the following:
- 1. Suppression Pool Water Temperature . above 100 F Drywell Atmosphere Temperature . . . above 135 F 2.
__ above 1 69 psig
- 3. Drywell Pressure . . . . . . . . . .
Suppression Pool Water Level . . . . aoove 26' 10" .
4.
(+3")
Suppression Pool Water Level . . . . below 26' 2.5" 5.
(-4.5")
C. OPERATOR ACTIONS -
CR ION IRRESPECTIVE OF THE ENTRY CONDITION, ENTER THIS PROCEDURE AT STEPS C.1, C.2, C.3 and C.4 AND PERFORM THESE STEPS CONCURRENTLY WITH ONE ANOTHER.
LGA-03 Revision 3 )
January 10, 1982 2
{AUIION NOTIFY SHIFT SUPERVISOR TO CLASSIFY l THE EVENT AND INITIATE GSEP IF APPROPRIATE -
C.l. MONITOR and CONTROL Su2Bression Pool water temperature
- a. CLOSE any SRV's that are stuck open per LOA-NB-02, Stuck Open Safety Relief Valve.
CAUTION IF CONTINUOUS LPCI OPERATION 15 REQUIRED TO ASSURE ADEOUATE CORE COOLING, 00 NOT DIVERT RHR PUMPS FROM THE LPCI MODE. --
- b. If Suppression Pool water temperature reaches 100 F .
Then START Suppression Pool cool i ng.
/
- c. If Suppression Pool water temperature reaches 110 F Then SCRAM the reactor and PERFORM LGP 3-2, Reactor Scram, concurrentl y with this procedure.
O
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- i 9 i i
6 Il O
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. LGA-03 Revision 3 January 10, 1982 3
r LGA-03-G1 Heat Capacity Temperature Limit I .
LGA-03 Revision 3 January 10, 1982 4
CAUTION 00 NOT DEPRESSURIZE THE RPV BELOW 57 PSIG UNLESS MOTOR ORIVEN PUMPS SUFFICIENT TO HAINThlN RPV WATER LEVEL ARE RUNNING AND AVAILABLE FOR INJECTION.
- - - - = _
CAUTION COOLOOWN RATES ABOVE 100 F/HR MAY BE REQUIREO TO ACCOMPLISH THIS STEP.
= - _
C. 1. d. If Suppression Pool water temperature cannot be maintained below the Heat Capacity Temperature Limit, LGA-03-G1
~
Then MAINTAIN RPV pressure below the.Ilmit e- using the. methods in LGA-C1, RPV Pressure Reduction - Preferred Method. .
- e. If Suppression Pool water temperature and RPV pressure cannot ce maintained or restored below the Heat Capacity Temperature Limit, LGA-03-GI.
Then OPEN all ADS val ves.
.LGA-C2, RPV Pressure Reduction -
ADS Failure.
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LGA-03 Revision 3 January 10, 1982 1 5 I l
\
0-i LGA-03-G2 RPV Saturation Limit
LGA-03 Revision 3 January 10, 1982 6
(
C.2. MONITOR and CONTROL drrwell temperature
- a. If DRYWELL TEMPERATURE exceeds 135 F Then VERIFY that a Pr imary Containment Cool i ng Loop is operating.
- b. If the oper ating loop is determined to provide insufficient cooling Then ST ART the standby loop. (LOP-VP-02, Startup and Operation of Primary Containment Chill Water System).
- c. If DRYWELL TEMPERATURE reaches t'he RPV Saturation Limit, LGA-03-G2 Then ENTER LGA-05, RPV Flooding.
= _ = . _
IF CDNTINUDUS LPCI OPERATION 15 REQUIRED TO ASSURE ADEQUATE CORE COOLING, DO NOT DIVERT RHR PUMPS FROM -
THE LPCI MODE.
- d. If DRYWELL TEMPERATURE approaches 340 F Then SHUTDOWN Reactor Recirculation Pumps and Drywell Fans AND INITIATE Drywell Sprays.
o
LGA-03 Revision 3 January 10, 1982 7
C.2. e. If DRYWELL TEMPERATURE can not be maintained '
below 340 F
~
Then OPEN all ADS val ves.
- 2) If less than 3 SRV's can be opened Then RAPIDLY DEPRESSURIZE the RPV per LGA-C2, RPV Pressure Reduction
- ADS Failure.
s
--- ,-e- - - , , - , - e , -,n,e,-mn- - , ,- - - - - y, ,,,,--, ------- .,y. ~ - , - ~,,----m- -,,e-- ,,,,w- - --__--,--w ~--- - , , - - - - -
LGA-03 Revision 3 January 10, 1982 )
8 C.3. MONITOR and CONTROL P_Ebay C ont a i_ nme n t p_r,e r s s ur e with the followinJ systems, as reguired:
CAUTION IF, PRIMARY CONT AINMENT PRESSURE REACHES 1.69 PSIG THE VERIFY THAT-THE POST LOCA CONTAINMENT AIR MONITORING SYSTEM HAS INITI AT ED.
CAUTION START THE HYDROGEN RECOMBINER SYSTEM PRIOR TO PRIMARY CONTAINMENT HYDROGEN CONCENTRATION EXCEEDING 3.3 PERCENT BY VOLUME (LOP-HG-02 STARTUP AND SHUTDOWN OF POST LOCA COMBUSTIBLE GAS CONTROL SYSTEM).
_ = - - -
w l
CAUTION i
ELEVATED SUPPRESSION CHAMBER PRESSURE MAY TRIP THE RCIC TURBINE ON HIGH EXHAUST PRESSURE, 25 PSIG.
CAUTION DEFEATING ISOLATION INTERLOCKS MAY BE REQUIRED TO ACCOMPLISH THIS STEP __
- a. Primary Containment Cooling System (REFER to LOA-VP-02, Primary Containment Pressure Reduction
- Drywell Cooling).
- b. Venting through SBGTS (REFER to LOA-VQ-01, Primary Containment Pressure Reduction -
Venting).
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LGA-03 Revision 3 January 10, 1982 9
i l'
f 1
1 i LGA-03-G3 1
Pressure Suppression Limit O
e
LGA-03 Revision 3 January 10, 1982 10 CAUTION IF CONTINUOUS LPCI OPERATION IS REQUIR'ED TO ASSURE ADEQUATE CORE COOLING, 00 NOT OIVERT RHR PUMPS FROM THE LPCI MODE.
C.3. c. If Suppression Chamber pressure cannot be maintained below 22 psig 3ND Suppression Pool level i s below 49'8" Then INITIATE Suppression Pool Sprays.
- ~
- d. If A Suppression Pool to Orywell vacuum breaker is STUCK OPEN Then Manuall y ISOLATE the vacuum breaker per LOA-PC-03, Stuck Open Suppression Pool to Drywell Vacuum Breaker.
- e. If Suppression Chamber pressure approacnes l
the Pressure Suppression Limit, LGA-l 03-G3 Then SHUTDOWN the Reactor Reci rculation Pumps and the Orywell Fans
( AND INITIATE Drywell Sprays and OPERATE as necessary to maintain Suppression Chamber pressure below the curve.
- f. If Suppression Chamber pressure cannot oe maintained Delow the Pressure Suppression Limit, L G A- 03-G 3 Then ENTER LGA-05, RPV Flooding.
LGA-03-GL I d i; m rc n m u m qungjig n n rnyjiim n Amin 19 i m e' H 1mm EElj
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i LGA-03 Revision 3 January 10, 1982 11 F r i 1 I LGA-03-G4 1 Heat Capacity Level Limit l l
l
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. l LGA-03 Revision 3 January 10, 1982 12 C.4. MONITOR and CONTROL su2 Dress i on 2001 water level
- a. MAINTAIN Suppression Pool water level betveen 26'2.5" (-4.5") and 26' 10" ( + 3") (LOP-RH-16, Lowering of Suppression Pool Level or LOP-HP-05, Raising of Suppression Pool Level).
- b. If Suppression Pool water level cannot be mai ntai ned above -4.5" fhen MONITOR Suppression Pool Temperature from the Process Computer, point L124 or from the Remote Shutdown Panel.
3ND MAINT AIN the /L T above the Heat Capacity Level Limit, LGA"b3-G4, by 5- 1) Raising Suppression Pool Level
- 2) Reducing Supprer.sion Pool Temperature .
- 3) Reducing RPV Pressure using the methods in LGA-C1, RPV Pressure i
Reduction - Preferred Method.
- c. If AT cannct ne maintained above the
~~
He$k Capacity Level Limit, LGA G4, Then OPEN all ADS val ves.
- 1) If all ADS valves can nol be opened Then OPEN otner SRV's until a total of 7 valves are open.
- 2) If less than 3 SRV's can be opened Then Rapidl y DEPRESSURIZE the RPV per LGA-C2, RPV Pressure Reduction -
ADS Failure. e
LGA-03 Revision 3 January 10, 1982 13
- d. If high -suppression pool level 26'10" (+3") occurs na
. low CY tank level (3' 1") occurs Tgn VERIFY HPCS and RCIC suctions transfer from CY tank to Suppression Pool.
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LGA-03 Revision 3 January 10, 1982 14 r i I l l 4 LGA-03-G5 Suppression Pool Load Limit I l l l [ . . _ _ . __ __ _____ _ _ _ _
LGA-03 Revision 3 January 10, 1982 15 __C.4. c. If the Suppression Pool water level can not be maintained bel ow 26'10" (+3")
^ND adequate core cooling is assured Then TERMINATE injection into the reactor.
vessel from sources external to the Primary Containment.
=
CAUT_I__QN COOLDOWN RATES ABOVE 100 F/HR MAY BE REOUIRED TO ACCOMPLISH THIS STEP.
- - - - - - -- -- --- ;= .
- f. If Suppression Pool water level cannot be
"- maintained bel ow the Suppression Pool Load Limit, LGA-03-G5 Then MAINTAIN RPV pressure below the 1 Imit using methods in LGA-C1, RPV Pressure Reduction - Preferred Method.
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LGA-03 Revision 3 January 10, 1982 16 I I l LGA-03-G5 Suppression Pool Load Limit l l
LGA-03 Revision 3 January 10, 1982 17 CAUTION DO NOT DEPRESSURIZE THE RPV BELOW 57 PSIG UNLESS
, MOTOR DRIVEN PUMPS SUFFICIENT TO MAINTAIN RPV W AT ER LEVEL ARE RUNNING AND AVAILABLE FOR INJECTION
__C.4. 9 If Suppression Pool water level and RPV pressure cannot be restored or maintained below the Suppression Pool
~ Load Limit, LGA-03-GS, Then OPEN all ADS val ves.
- 1) If all ADS val ves can not be opened Then
~~~~
OPEN other SRV's until a total
#- of 7 valves are open.
- 2) If less than 3 SRV's can be opened Then RAPIDLY DEPRESSURIZE the RPV per LGA-C2, RPV Pressure Reduction -
ADS Failure.
- h. If Pri mary Contai nment water level i
reaches level corresponding to 809' above sea level (REFER to LOA-i PC-04, Primary Containment Level Determination, for a method to determi ne l evel ) Then TERMINATE injection into the RPV from sources external to the Primary Containment whether or not adequate core cooling is assured.
LGA-03 Revision 3 January 10, 1982 18 D. REFERENCES
- 1. LOA-NB-02, Stuck Open Safety Relief Valve
- 2. LGP 3-2, Reactor Scram.
3. LOP-VP-02, Startup and Operation of Primary Containment Chill Water System.
- 4. LGA-OS, RPV Flooding.
S. LGA-C1, RPV Pressure Reduction - Preferred Method
- 6. LGA-C2, RPV Pressure Reduction - ADS Failure
- 7. LOP-HG-02, Startup and Shutdown of Post LOCA Combustible Gas Control System.
- 8. LOP-RH-16, Lowering of Suppression Pool Level.
- 9. LOP-HP-05, Raising of Su>pression Pool Level. .
- 10. LOA-VP-02, Primary Concainment Pressure Reduction
-Drywell Cooling.
l 11. LOA-VO-01, Primary Containment Pressure Reduction
-Venting 12.
LOA-PC-03, Stuck Open Suppression Pool to Drywell vacuum Breaker.
- 13. LOA-PC-04, Primary Containemtn Level Determination
LGA-04 Revision 4 January 10, 1982 1 LEVEL RESTORATION A. PURPOSE The purpose of this procedure is to restore RPV water level. B. ENTRY CONDITIONS This procedure is entered from LGA-01 (Level Cont r ol ) or LGA-02 (Cooldown) when RPV water level cannot be maintained above T.A.F. (-161" on the Fuel Zone Indicator) or whenever level cannot be determined. C. O P ER AT_QR ACTIONS
- 1. LINE UP for injection and START pumps in 2 or more of the following Normal Injection Systems:
D' a. Condensate /Feedwater
- b. HPCS
- c. A RHR (LPCI Mode)
- d. B RHR (LPCI Mode)
- e. C RHR (LPCI Mode)
- f. LPCS
LGA-04 Revision 4 January 10, 1982 2 C.2. If less than 2 of the Normal Injection Systems can be lined up , . __ Then COMMENCE L INING_UP as many of the following Al ternate Injection Systems as possible:
- a. Fuel Pool Emergency Make Up to Reactor, LOA-FC-03.
- b. Reactor Fill from SBLC, LOA-SC-03
- c. ECCS Water Leg Pumps
- d. Cycled Condensate Makeup to the Reactor, LOA-CY-02
- e. Suppression Pool Makeup to the Reactor, LOA-SF-01 P- f. Diesel Fire Pump Makeup to the Reactor, LOA-FP-03
-- e
e LGA-04 Revision 4 January 10, 1982 3 If at any time RPV water level cannot be __C.3 determined ANQ is no system or Normal Injection System least one lined up for injection with at pump running START pumps in Al ternate Injection Systems Then injection. that are lined up for no system, Normal Injection System, or If i s l i ned up
- a. Alternate Injection System least one pump for injection with at running ENTER LGA-04, Le vel Restoration at Step Then and PERFORM the Steam Cooling y_ C.9.d.
operation. If at any time RPV water level cannot be C.4. octermined add at least one system, Normal Injection System, is lined up or Al te rnate Injection System at least one pump for injection with running Then ENTER LGA-05, RPV Flooding. O
LGA-04 Revision 4 January 10, 1982 4 TABLE 1 . RPV Pressure Region 4t8 , 440 to 57 57 HIGH INTERMEDIATE LOW RPV LVL. INC. C.6 C.7 C.8 - RPV LVL. DEC. C.9 C.10 a
>=
9 l l l l l e e
- _s, y-_ _ _ , _ _
LGA-04 Revision 4 January 10, 1982 S C.S. MONITOR RPV water level and pressure
- a. REFER to Table 1 to determine the step to enter for existing RPV level and,pressur'e conditions.
D. If RPV water l evel trend reverses E RPV pressure trend reverses O RPV pressure changes region (in Table 1) Then RETURN to Step C.5 of this procedure. e { l a
. -- - - - , ~ . _ - . , , _ , _ ,
LGA-04 Revision 4 January 10, 1982 6 C.6. RPJ level i ncreasinJ and RPV pressure gr, eater than
~~~
i 9 211S I!!igh R e_g_i on]
- a. ENTER LGA-01, Level Control ~ at Ste.p-C.S.
e l l l i
+
e o G
i LGA-04 Revision 4 January 10, 1982 7 __C.7 RPV level increasing and RPV pressure between 440 and 57 osig. 1 Intermediate Regioni CAUTION 00 NOT DEPRESSURIZE THE RPV BELOW 57 PSIG UNLESS MOTOR DRIVEN PUMPS SUFFICIENT TO MAINTAIN RPV WATER LEVEL ARE RUNNING AND AVAILABLE FOR INJECTION. RCIC is not available
- a. _If 3ND RPV pressure is increasing Then OPEN all ADS val ves.
- 1) If all ADS val ves can no$ be opened
#~
Thgn OPEN other SRV's until a total of 7 valves are open.
- 2) If less than 3 SRV's can be opened Thgn RAPIDLY DEPRESSURIZE the RPV per LGA-C2, RPV Pressure Reduction
- ADS Failure.
- b. If RCIC is not av a i l abl e hND RPV pressure is ag[ increasing ,
_Then ENTER LGA-Ol, Level Control at Step C.S.
- c. When RPV water l evel reaches +12.5" Then ENTER LGA-Ol, Level Control at Step C.5.
i 1 l
LGA-04 Revision 4 January 10, 1982 8 C.8. RPV l evel i ncreas i ng and RPV pressure below 57 PLsig 13w r eg i_on ) .
- a. If PV pressure is increasing Then OPEN all ADS Val ves.
- 1) If all ADS val ves can not De opened Then OPEN other SRV's until a total of 7 valves are open.
- 2) If less than 3 SRV's can be opened Thgn RAPIDLY DEPRESSURIZE the RPV per LGA-C2, RPV Pressure Reduction
- ADS Failure.
- b. When RPV level exceeds T.A.F. (-161" on the Fuel Zone Indicator) m-Then ENTER LGA-01, Level Control at Step -
C.S. i h e l .
LGA-04 Revision 4 January 10, 1982 9 C.9. RPV level decreasing and RPV pgessure gigatgL than 21 psig 11 ntle med i at e/H_ i,gh regionj.
- a. If RCIC is ngt operating Then RESTART RCIC.
f
- b. If CRD is not operating gul at least 2 Normal Injection Systems are lined up for injection with pumps running Then OPEN al1 ADS val ves.
- 1) If all ADS val ves can not be opened Thgn OPEN other SRV's until a total of 7 SRV's are open.
- 2) If less than 3 SRV's can be openec Then RAPIDLY DEPRESSURIZE the RPV per LGA-C2, RPV Pressure reduction
- ADS Failure.
- c. If CRD i s not operating ANp No Normal Injection System is linec up for injection with at least one pump running Then ST ART pumps in Alternate Injection Systems that are lined up for injection.
4
t
)
LGA-04 f Revision 4 January 10, 1982 ' 10 C.9. d. If the RPV water level drops to T.A.F. (-161" on the Fuel Zone Indicator) ANE . CRD not operating, AM2 RCIC not operating Ago No Normal Injection System is lined up for injection with a pump running, AME - No Alternate Injection System is lined W-- up for injection with a pump running Then PERFORM the following steps: .
- 1) W h e_n RPV water level drops to the minimum zero injection RPV water level (-236" on the Fuel Zone Indicator)
OE l ' RPV water l evel cannot be determined (Do not Enter LGA-05, RPV Flooding) Then OPEN one SRV.
- 2) When RPV pressure drops Delow 500 psig Then OPEN 6 additional SRV's.
e
LGA-04 Revision 4 January 10, 1982 11 _C.9. e. I f, the RPV water level drops to -161" on the Fuel Zone Indicator d D., CRD is operating, QR a Normal Injection System OR, an Alternate Injection System is lined up for injection with a pump running Then OPEN all ADS valves.
- 1) If all ADS val ves can not be opened Ben OPEN other SRV's until a total of 7 valves are open.
- 2) M less than 3 SRV's can be opened D,e n RAPIDLY DEPRESSURIZE the RPV per LGA-C2, RPV Pressure Reduction,
- ADS Failure.
4
- , r=,
l - LGA-04 Revision 4 January 10, 1982 12-C.10. RPV level . decreasing and RPV pressure less than 57 psig flow nggi,on1
- a. If No for Normal injectionInjection with atSystem.
least is l ined up running one pump Ihen START pumps in the Alternate Injecti,on Systems that are lined up for i nj ecti on
- b. If RPV pressure is increasing Ihen OPEN all ADS valves.
- 1) If all AOS valves can not ce opened Then
~~~~
OPEN other SRV's until a total of 7 valves are open.
- 2) lf less than 3 SRV's can be opened m-Then RAPIOLY DEPRESSURIZE the RPV per LGA-C2, RPV Pressure Reductions
- ADS Fail ure.
- c. If RPV pressure is ngt increasing AND RPV water level drops to T.A.F.
(-161" on the Fuel Zone Indicator) lhen OPEN all ADS val ves. ___ 1) if all ADS val ves can ngt De opened Then OPEN 7 valvesother SRV's until a total of are open. 2) OPERATE the LPCS and'HPCS suppression pool. with suction from 4 l
LGA-04 Revis ion 4 January 10, 1982 13 __C.lO. c. 3) When either LPCS or HPCS is operating with suction from the suppression pool hND The differential pressure between the suppression pool and the RPV is less than 122 psi Then TERMINATE injection into the RPV from sources external to the Primary Containment. D. REFERENCES
- 1. LGA-Ol. Level Control
- 2. LGA-02. Shutdown
- 3. LGA-05, RPV Flooding
- 4. LOA-FC-03, Fuel Pool Emergency Make Up to Reactor S. LOA-5C-03, Reactor Fill from SBLC
- 6. LGA-C2, RPV Pressure Reduction - ADS Failure
- 7. LOA-CY-02, Cycled Condensate Makeup to the Reactor
- 8. LOA-5F-Ol, Suppression Pool Makeup to the Reactor
- 9. LOA-FP-03, Diesel Fire Pump Makeup to the Reactor D
LGA-OS Revision 4 Janu6ry 7, 1982 1 RPV FLOODING A. PURPCSE The purpose of this procedure is to assure adequate core cooling and containment integrity by floodi ng tne RPV. S. ENTRY CONDITIONS This procedure is entered from LGA-03 (Containment Contr ol ) , or'LGA-04 (Level Restoration) when: RPV water level cannot be determined O3 DRYhELL TEMPERATUAE reacnes the RPV Saturation Limit 0.S m-SUPPRESSION CHAMBER PRESSURE cannot ne maintained Delow the Pressure Suppression Limit, , __ _ _ _ - - - _ _ = = _ _ _ CAUTION DO I40T DEPRESSURIZE THE RPV BELOW 57 PSIG UNLESS MOTOR DRIVEN PUMPS SUFFICIENT TO MAINTAIN RPV WATER LEVEL ARE RUNNING AND AVAILABLE FOR INJECTICN. J r D l O
.. I LGA-05 Revision 4 January 7, 1982 2
__C.l. OPEN all ADS val ves.
- a. If all ADS valves can not De opened Then OPEN other SRV's until a total of 7 valves are open.
D. If less tnan 3 SRV's can be opened Then RAPIDLY DEPRES5URIZE tne RPV per LGA-C2, RPV Pressure Recuttion - ADS Failure.
- 2. If at least 3 SRV's are open og .
HPCS Pump is availaDie for injection with high level trip bypassed (LOA-HP-01, RPV U ~' Floooing - High Level HPCS I s ol at i on Bypass). OS Motor Driven Feedsater Pump is ava il aDl e for injection with nigh l evel trip bypasseo (LO4-FW-02, RPV Flooding - High level MDRFP Pump Trip Bypass) Then CLOSE the f ol l owi ng val ves:
- a. MSIV's IB21-F022A/B/C/C (2B21-F022A/E/C/C) and 1821-FC2 8 A/B/C/ D (2B21-F028A/B/C/D).
G o. Pain Steam Line crains lE21-F016 (2B21-F016) and 1821-F019 (2B21-F019).
- c. RCIC isolation val ves IE51-F063, (2E51-FC63),
1E51-F076 (2E51-F07o), and IE51-FOC8 (2E51-FOOB).
- c. P Hk Steam condensing isolation valves lE51-F066 (2E51-F064).
(. RWCU i sol ati on val ves 1G33-F001 (2G33-FOCl) ano 1G33-F004 .(2633-F004).
LGA-05 Revision 4 January 7, 1922 3 C.3. If RPV water level cannot De determinec Then Perforn. the f ollowing steps:
- a. COMMENCE and INCREASE injection i nto the RPV with the f oll owi ng systems until:
RPV pressure is staole or increasing AED RPV pressure is greater than 90 psig above Suppressi on Pool Pressure
- 1) HPCS (with hi gn l evel trip bypassed - LOA-HP-01 RPV Flooding - High Level HPCS I s ol at i on Bypass)
- 2) Motor Driven Reactor Feed Pump (with high level trip bypassed - LOA-FW-02, RPV
"- Floocing - Hign Level MDRFP Trip Bypass)
- 3) LPCS ,
- 4) LPCI
- 5) Condensate / Condensate Sooster Pumps
- 6) CRD ,
- 7) Reactor Vessel Fill from SBLC, LOA-SC-03 l
\ ECCS Water Leg Pumps 8)
- 9) Cycled Condensate Makeup to the Reactor, LOA-CY-02
- 10) Suppression Pool Makeup to tne Reactor, LOA-SF-Ol
- 11) Olesel Fire Pump Makeup to tne Reector, LOA-FP-03
- 12) Fuel Pool Emergency Maxeup to the Reactor, LOA-FC-03 e
6 e
LCA-05 Revision 4 January 7, 1982 4 __C.3. o. hhen RPV pressure is greater.than 90 psig l above Suppression Pool Pressure - Then Injection may De reduced so long as RPV pressure is maintained aoove 90 psio. C.4. If RPV water level can be determined Then COMMENCE ano INCREASE injection into the RPV witn the following systems until RPV water level is increasing:
- a. HPCS
- o. Motor Driven Reactor Feed Pump
- c. LPCS
- d. LPCI e- e. Condensate / Condensate Booster Pumps
- f. CRC ECCS Water Leg Pumps !
g.
- h. Cycled Concensate Makeup to the Reactor, LOA- g i
CY-02 l
- i. Suppression Pool Makeup to the Reactor, LOA- l SF-Cl
- j. Reactor Vessel Fill from SBLC, LOA-SC-03 l-
- k. Diesel Fire Pump Makeup to the Reactor, LOA- [
FP-03 l f f 1. Fuel Pool Emergency Makeup to the Reactor, LOA-FC-03 1 I i I f 1
LGA-C5 Revision 4 January 7, 1952 5 C.S. If Drywell Pressure exceeds 45 psig . AgD Containment Radiation Levels indicate 10CFR100 l i mi ts will not be exceeded Then VENT the Drywell througn val ve 1(2)V0035, Drywell Vent / Purge Outlet Downstream I sol a t i on, to SBGTS in accordance with LOA-VP-03, l Emergency Primary Containment Pressure Relief. C.6. If Drywell Pressure cannot be maintained Del ow 132 psig (Primary Containment Pressure Limit) Then INITIATE the foll owing systems irrespective of whether acequate core cooling is assured:
- a. Drywell Sprays
- o. Suppression Pool Sprays (ONLY wnen Suppression Pool Water l evel i s Del ow 49 ft. 8 in. - LOA- .
PC-04). CAUTION DEFEATING ISOLATION IrvT ERLOCKS M AY SE REQUIRED TO ACCOMPLISH THIS STEP
- 7. If Orywell Pressure exceeds 132 psig (Primary l Containment Pressure Limit)
T he_n VENT the Primary Containment in accorcance i with LOA-VP-03. Emergency Primary Containment Pressure Rel ief, to reduce pressure belo. the limit. l 8. CONTINUE injecting water into thg RPV until DRYwELL TEMPERATURE i s pel o. 212 F AlJD RPV
.ater level instrumentation i s avaiIaole.
l l - e l I L
LGA-05-G3 . ._ MAXIMUM ACCEPTABLE CORE UNCOVERY TIME
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e LGA-C5 Revision 4 January 7, 1952 6 LGA-OS-G3 Maximum Acceptaole Core Uncovdry Time w-I e l 1
LGA 'JS Gevision 4 January 7, 1952 7 C.9. If it can be determi ned that tne RPV is filleo 9E RPV pressure is at least 90 psig above Suppression Pool pressure Then -T ERMIN AT E all injection into the RPV
$29 REDUCE RPV water level
- a. If RPV water level indication is not restorea witnin the Maximum AcceptaDie Core Uncover y T ime, LGA-05-G3, after commenci ng .termi nati on cf injection into tne RPV Then RETURN to Step C.3 of this procedure.
v-
- o. If RPV -ater level indication 11 restored -
within the Maximun Acceptacle Core Uncovery Time, LGA-05-G3, of commensing termination of injection h19 Drywell Pressure is less than 45 psig Then Er.TER LGA-Oi, Level Control at Step C.S. 4
LGA-CS Revision 4 J6nuery 7, IcB2 8 D. FEFERENCES 1 LGA-01, Level Control
- 2. LGA-C2, RPV Pressure Reduction - ADS Failure.
- 3. LGA-03, Containment Control
- 4. LGA-04. Level Restoration S. LOA-FC-03, Fuel Pool Emer5ency Make up to Reactor
- 6. LOA-SC-03, Reactor Vessel Fill from SBLC
- 7. LOA-CY-02, Cycled Condensate Makeup to the Reactor S. LOA-5F-Ol, Suppression Pool Makeup to the Reactor
- 9. LOA-VP-03, Emcrgency Primary Containment Pressure Relief w-10 LOA-FF-03, Diesel Fire Pump Makeup to the Reactor.
11 LOA-HP-01, RPV Fl oooing - Hi gh Level HPCS Isolation Bypass
- 12. LOA-FW-02, RPV Fl ooding - High Level MDRFP Trip Byoass i
e e
- , . , . , . . , . m ,, _ _, ..y. . _ , , m-- - . , . -_ - _ . _ , , , -
LGA-C1 Revision 1 January 7, Ic82 1 RPV PRESSURE REDUCTION - (PREFERRED METHODS) A. PURPOSE Tne purpose of the procedure is to list preferred rr.ethod& to reduce RPV pressure at a controlled rate. B. OPERATOR ACTIONS CAUTION DO NOT DEPRESSURIZE BELOW 57 PSIG UNLESS MOTOR DRIVER; PUMPS SUFFICIENT TO MAINT AIN RPV WATER LEVEL ARE Rut:NING AND AVAILABLE FOR INJECTION L_______________________-_____------__- I. _Ma _in Condenser Avail abl e : r
- a. Use Main Turbine Bypass Valves to DEPRESSURIZE U j
~~
and COCLCOWN the RPV at less than LOC F per hour.
- b. Pressure reduction may oe augmented twith one cr more of the foll owing systems.
- 1) RCIC (LOP-RI-02)
=
CAUTION
. DC f;OT USE THE RHR STEAM CONDENSING MODE UNLESS:
1 THE SUPPRESSION POOL TEMPERATURE CAN BE MAINT AltsED BELOW 120 F ddiE
- 2. bog. A Af4D B RHr< LOO PS ARE AVAILABLE.
- 2) RHR steaci conoensing mooe (LOP-RH-09).
e
- ~
LGA-Cl Revision 1 January 7. 1952 4 B.l. D. 3) Other steam driven equipment a) Steam Jet Air Ejectors b) Steam to Turoine Oriven Reactor Feed Pumps c) Steam to Radwaste ReDoiler d) Steam to Offgas Preheater e) Steam to Gland Seal Steam ReDoiler f) Main Condenser Deaerating Steam
- 4) RWCU recirculation mode (LOP-RT-02)
S) Main Steam Line Drains
- 6) RhCU coolant rejection (LOP-RT-09) y 5 e 5
1 p ! e Y ! i ? l ; 6 . N y (
LGA-C2 Revision 1 Jar.uary 7, 1%2 1 1 RPV PRESSURE REDUCTION - ADS FAILURE A. PURPOSE The purpose of this procedure is to list the systems avail able to reduce RPV pressure when an ADS actuation is requireo and less than 3 SRV's can De openeo.
~
B. OPERATOR ACTIONS
- 1. RAPIDLY REDUCE RPV pressure using one or more of 3
the f olloaing systems (use in order which will minimize r adi oacti ve r el ease ) : . QQI ON DEFEATING ISOLATION INTERLOCKS MAY BE RECUIRED TO ACCOr4PLISH THIS STEP (LCA-MS-C1, MAIN STEAM I SOL AT ION BYPASS FOR EMERGENCY DEPR ESSURI Z AT I ON ) .
- a. Main Turcine bypass Valves e
+ ' * - e
LGA-Cl Revision 1 January 7, 1982 3 B.2. Main Concenser noj avail able
- a. DEPRESSURIZE and COOLDOWN RPV at less tnan ~
' 100 F/Hr using or e or more of the following systems:
- 1) RCIC (LOP-RI-02)
CAUTION 00 NOT USE THE RHR STEAM CONDENSING MODE UNLESS:
- 1. THE SUPPRESSION POOL TEMPERATURE CAN BE MAINTAINED BELOW 120 F
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- 2. 303 A AND B RHR LOOPS ARE AVAILABLE.
e- _________________________________
- 2) RHR steam condens ing rnode (LOP-RH-09)
- 3) RhCU recirculation mode (LOP-RT-02)
__ __ _ _._ ___ _ _ _ _ _____- = _ _ = CAUTIO*: 1F CRYWELL PNEUM AT IC SUPPLY TO THE SRV'S IS LOST (DRYWELL PNEUMATIC BOTTLE HEADER LOh PRESSURE ALARM) _H_E_DEPRESSURIZE _ _ _ _ _ _ _ _ THE _ _ _RPV _ _WITH _ _ _SUSTAINED _ _ _ _ _ - SRV CP EtJI NG
- 4) Pressure reouction may be augmented -f:
a) SRV's (in alphabetical sequence) i c) RwCO ( cool ant rejection). (LOP-RT-09) l [
LGA-C2 Revision 1 J6nuary 7, 1952 2
- b. Steam Driven Equipment .
- 1) Steam Jet Air Ejectors.
- 2) Turbine Driven Reactor Feed Pumps
- 3) Rad Waste Recoiler
- 4) Off Gas Preheater
. 5) Gland Seal Steam Reboiler
- 6) Main Condenser Deaerating Steam
- c. RCIC Main Steam Line Crains d.
- c. RWCU ( c ool ant rejection) w-
- f. RCIC Steam Line
- g. RPV Head Vent
- n. RHR Steam Condensing Mode
'1 l
4 I I .
ENCLOSURE 2 LEH-819 CATAGORIES OF COMMENTS I. An opinion offered for inforr:ation purposes only; the utility should consider taking action consistent with the reviewer's recommendation if such action is not inconsistent with the general practices followed by the utility. Generally, these comments have little or no implication as to the procedure's technical compliance with the BWR Emergency Procedure Guidelines (EPG). II. Comments which bear (directly or indirectly) on the procedure's technical compliance with the EPGs, or identify an unnecessarily restrictive interpretation of the EPGs, G.E. recommends that action should be taken consistent with the recommendatien; however, f ailure to incorporate the reviewer's reconnendations would not adversly affect safety of operation. III. Comments which identify questionable implementation of the EPGs which could result in inadequate guidance being given to the operator. Tailure to incorporate the comment / recommendation could, in the opinion of the reviewer, diminish the associated procedure's technical adequacy. 9 m -
, LEVEL CONTROL -LGA-01 PAGE 1,2 - CAUTIONS CATAGORY I 1.
These are not used in the EPG because it is a general EPG intention to avoid using cautions in Level Control. Consideration could be given to removing these cautions. . Additionally, the caution relating to the +54.5" trip on Page 2 is unnecessary and redundant because the number 54.5'.' is specifically mentioned in Step C.S. PAGE 2, STEP C.6 CATAGORY II 2. This step is redundant and unnecessary. It is true that the EPG* may be exited whenever, in the opinion of operating personnel, an emergency condition no longer exists. However, the EPG do not require level to be above +12.5". " Stable" vater level can be anywher e between TAF and +54.5" . This step, as written, is an unnecessarily conservative interpretation of the EPG. PAGE 3, STEP C.7 CATAGORY I
- 3. .
In the "g" portion of this step, the EPG stated "H RPV vater level cannot be restored and maintained above +12.5" ". ~ CATAGORY II
- 4. PAGE 3 LaSalle has deleted EPG Step LC-2.5 which references cycling SRVs.
LaSalle has the Low Level Set (LLS) function installed and therefore considers the step unnecessary. However, LaSalle cust re= ember that even if LLS is working properly,1 SRV vill preferentially cycle and it may be necessary to take manual control of SRVs to prevent excessive localized heating in the S/P. O 9
COOLDOWN - LCA-02
- 5. PAGE 3 CATAGORY II Comment #4 is also applicable here (between Steps C.3 and C.4),
concerning cycling SRVs.
- 6. PAGE 4, STEP C.7 CATAGORY-I While the EPG say to open 1 SRV at this point (EPG Step C.7.c),
Sargent & Lundy has supporting calculations that demonstrate that 2 SKVs will be required to pass the necessary shutdown cooling flow. . This should be entirely satisfactory and should pose no problem with respect to EPG conformance. The intent of the EPG is met by the LaSalle approach.
- 7. PAGE 4, STEP C.7 CATAGORY II l
EPG Step C5-6 specifies increasing flow "to the maximum" in Step C.7.f. EPG Step C5-6.3 also ref ers to throttling injection flow if a 100 F/hr cooldown rate were exceeded. 4 b f i l L
. CONTAINMENT CONTROL - LGt-03
- 8. PAGE 6, STEP C.2.c CATAGORY II The EPG reco= mends a more detailed method of determining D/W temperature - i.e. noting the temperature near each cold reference leg vertical run. CECO currently intends to use bulk D/W -
temperature and this approach should be satisfactory for temporary use, but the f easability of adding additional temperature elements (with each channel of temperature indication referenced to the appropriate channel of water level indication) should be considered. Furthermore, the existing channels of temperature indication in the L/W should be identified with respect to proximity to the cold reference leg vertical runs.
- 9. PAGE 10, STEP C.3.c CATAGORY I The numbers 22 psig and 49'8" replace the EPG SPSL. This approach is entirely satisfactory and fully meets the intent of the EPG.
- 10. PAGE 10, STEP C.3.d CATAGORY I This step is not per the EPG, but reflects LaSalle Tech. Spec. -
article 3.6.4.a which requires a stuck open vacuum breaker to be manually isolated within 4 hours. Therefore this step should not
- __ constitute a problem with respect to the EPG.
r LEVEL RESTORATION - LGA-04
- 11. PAGE 10, STEP C.9.d.1) And C.9.d.2) CATAGORY II The minimus zero inj ection RPV vater level used here is the middle of the active fuel. This is a conservative estimate that may be -
used until final EPG calculations are completed and released by the BWR Owner's Group Emergency Procedures Committee. Similarly the minimum single SRV steam cooling pressure used here is also a preliminary conservative value, satisfactory for use now, but one that may change when final EPG calculations are completed.
- 12. PAGE 11, STEP C.9.e CATAGORY III RCIC is not strictly covered by the existing step. EPG Step Cl-7.2 (second box) directs the operator to the Rapid Depressurization Procedure if RCIC (even if only RCIC) were running. LaSalle has not mentioned RCIC here because opening ADS valves is the next step and they feel that this will, negate the usefullness of RCIC.
Retaining this step, per the EPG, should be considered because - pressure should be reduced at this point, consistent with EPG Caution #14, to enhance the operability of low pressure injection g_ systems by reducing brake flow. This can be done without compromising the operability of RCIC. l I t l I
. RPV FLOODI?;G - LGA-05
- 13. PAGE 3, STEP C.3 CATAGORY I
" Perform the following steps" is unnecessary and could be removed from the "Then" part of this step.
- 14. PAGE 3, STEP C.3.a. CATAGORY II The minimum RPV flooding pressure used here (90 psig) is for 3 open SRVs. Since this procedure will most likely be performed with 7 SRVs open and since the pressures are known for the cases where 3,4,5,6 or 7 SRVs are open, this additional inf ormation should also be given to the operator.
- 15. PAGE 5 CATAGORY II The EPG includes a step (between existing Steps C.7 and C.8) that directs filling RPV level instrument ref erence columns. My understanding is that: (1) CECO will delete the ref erence to filling instrument reference legs because there is presently no means of providing a source of high pressure water to acco=plish the back fill, and (2) the f easibility of adding a means of force filling the reference legs with a high pressure source such as CRD will be examined with possible haplementation as a long term
,__ solution.
Consideration should be given to retaining this step, per the EPG, , in case this situation should be encountered during low pressure conditions, where the standard low pressure backfill technique will work. The high pressure backfill technique should also be pursued and implemented when and if possible. Furthermore, since the minimum RPV flooding pressure for the case where 7 SRVs are open is only 26.4 psig, and since this is well within the pressure range for normal low pressure backfill methods, there may be situations where high pressure backfill would not be necessary. Without this i step in the procedure the operator will not be reminded to attempt the backfill and this is not what the EPG intended.
- 16. PAGE 7 CATAGORY II The EPG includes Step C6-6.3 between the existing Steps C.8 and C.9.
Consideration should be given to using this step per the EPG: (1) to ensure maximum consistency with the EPG, (2) to ensure that the reference to the PCPL (in EPG Step C6-7) is considered before returning to Level Control, and (3) to ensure that the chances are minimized of inadvertantly terminating RPV inj ection and reducing RPV vater level as directed by LaSalle's Steps C.9 and C.9.a. It is LaSa11e's belief that EPG Caution #1 and the present Step C.9 adequately cover this point.
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c CENERAL COMMENTS
- 17. .CATAGORY lI As noted earlier f or D/W te=perature (Comment #8) and high pressure l backfilling of ref erence legs (Comment f15), the f easability of adding instrumentation to measure containment water level up to the containment vent elevation (809' above Sea Level) is also being evaluated be CECO.
It is recommended that this item (containment- level indication) be given high priority and be implemented as soon as ' practicable because alternate methods of determining this level (such as approximating containment level by multiplying injection flow rate tines ' time of injection) are of questionable accuracy.
- 18. CATAGORY III
- The calculations supporting all EPG Appendix B curves were based on draf t revisions of the Appendix. While satisf actory for implementation at this point, these calculations should be double checked to be in accordance with the final revision of the Appendix when it is issued by the BVR Owner's Group Emergency Procedure Co =ittee.
Si=ilarly, the text of the procedures should be reviewed and revised as necessary to ensure compliance with the final revision of the EPG. (_
- 19. CATAGORY II EPG Caution #16 does not appear to have been incorporated into the LaSalle procedures.
- 20. CATAGORY l With respect to the tr.plementation of EPG Cautions; LaSalle's approach of incorporating the majority of the cautions directly into the procedures, upgrading control roo= panels to facilitate i=plementation of items such as Caution #6 and #12, the inclusion of all EPG Cautions as an addendum to the LGA package, and the detailed nature of their training program appears to be a very satisfactcry nethod.
- 21. CATAGORY II LGA-Tl " General Precautions" it e f3 includes a ref erence to environ-nental standards. This ite: will cost likely confuse the operator and nake hin unsure of which, if any, indications should be used.
This cenfuses the operater by cuestioning the relichility cf same instruments anE thereby indirectly cuestions all indications. Censideration should theref ore be given to rc=oving this statement.
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